IAEA activities in the field of research reactors safety

International Nuclear Information System (INIS)

Ciuculescu, C.; Boado Magan, H.J.

2004-01-01

IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities will be presented: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOC's); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors adopted by the Board of Governors on 8 March 2004, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors published on the IAEA website on February 2003 and the results obtained. (author)

Nuclear safety activities in the SR of Slovenia in 1986

Energy Technology Data Exchange (ETDEWEB)

Susnik, J [Inst. Jozef Stefan, Ljubljana (Slovenia)

1987-06-15

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1986. (author)

Nuclear safety activities in the SR of Slovenia in 1986

International Nuclear Information System (INIS)

Susnik, J.

1987-06-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1986. (author)

General principles of nuclear safety management related to research reactor decommissioning

International Nuclear Information System (INIS)

Banciu, Ortenzia; Vladescu, Gabriela

2003-01-01

The paper contents the general principles applicable to the decommissioning of research reactors to ensure a proper nuclear safety management, during both decommissioning activities and post decommissioning period. The main objective of decommissioning is to ensure the protection of workers, population and environment against all radiological and non-radiological hazards that could result after a reactor shutdown and dismantling. In the same time, it is necessary, by some proper provisions, to limit the effect of decommissioning for the future generation, according to the new Romanian, IAEA and EU Norms and Regulations. Assurance of nuclear safety during decommissioning process involves, in the first step, to establish of some safety principles and requirements to be taken into account during whole process. In the same time, it is necessary to perform a series of analyses to ensure that the whole process is conducted in a planned and safe manner. The general principles proposed for a proper management of safety during research reactor decommissioning are as follows: - Set-up of all operations included in a Decommissioning Plan; - Set-up and qualitative evaluation of safety problems, which could appear during normal decommissioning process, both radiological and nonradiological risks for workers and public; - Set-up of accident list related to decommissioning process the events that could appear both due to some abnormal working conditions and to some on-site and off-site events like fires, explosions, flooding, earthquake, etc.); - Development and qualitative/ quantitative evaluation of scenarios for each incidents; - Development (and evaluation) of safety indicator system. The safety indicators are the most important tools used to assess the level of nuclear safety during decommissioning process, to discover the weak points and to establish safety measures. The paper contains also, a safety case evaluation (description of facility according to the decommissioning

Leadership and Management for Safety. General Safety Requirements (Arabic Edition)

International Nuclear Information System (INIS)

2016-01-01

This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

Leadership and Management for Safety. General Safety Requirements (Chinese Edition)

International Nuclear Information System (INIS)

2016-01-01

This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

Leadership and Management for Safety. General Safety Requirements (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

Leadership and Management for Safety. General Safety Requirements (Spanish Edition)

International Nuclear Information System (INIS)

2017-01-01

his Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

International Nuclear Information System (INIS)

Zull, Lawrence M.; Yeniscavich, William

2008-01-01

The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites

General safety orientations of the Jules Horowitz Reactor Project (JHRP)

International Nuclear Information System (INIS)

Tremodeux, P.; Fiorini, G.L.

2000-01-01

After a brief reminder of the JHR purpose, the document outlines the General Safety related Orientations/Recommendations used for the design and the safety assessment of the facility. As far as the JHR design is new, the safety philosophy adopted for this reactor will be as consistent as possible with that recommended for future (power...) reactors. The general recommendations developed in the paper are: the general nuclear safety approach for the design, operation and analysis with, in particular, the adoption of the Defence In Depth principle; the general safety objectives in terms of radiological consequences; the use of Probabilistic Safety Studies; quality assurance. The 'Defence in Depth' concept using amongst others the 'Barrier' principle remains the basis of the JHR safety. 'Defence In Depth' is applied both to design and operation. Its adequacy is checked during the safety assessment and the paper gives the technical recommendations that should allow the designer to implement this concept into the final design. Built mainly for experimental irradiation the JHR facilities will be handled according to conventional or new operation rules which could put materials under stress and entail handling errors. Specific recommendations are defined to take into account the corresponding peculiarities; they are discussed in the paper. The safety design of the JHR takes into account the experience accumulated through the CEA experimental irradiation programmes, which represents several dozen reactor years; the consultation of CEA reactor facilities operators is ongoing. The corresponding feedback is shortly described. Recommendations related to maintenance and associated operation are indicated as well as those regarding the human factor. Details are given on the JHR safety practical implementation through the CEA/DRN Safety approach. Details of the corresponding Safety Objectives are also discussed. Finally the designer position on the role of probabilistic safety

A Review of General Aviation Safety (1984-2017).

Science.gov (United States)

Boyd, Douglas D

2017-07-01

General aviation includes all civilian aviation apart from operations involving paid passenger transport. Unfortunately, this category of aviation holds a lackluster safety record, accounting for 94% of civil aviation fatalities. In 2014, of 1143 general aviation accidents, 20% were fatal compared with 0 of 29 airline mishaps in the United States. Herein, research findings over the past 30 yr will be reviewed. Accident risk factors (e.g., adverse weather, geographical region, post-impact fire, gender differences) will be discussed. The review will also summarize the development and implementation of stringent crashworthiness designs with multi-axis dynamic testing and head-injury protection and its impact on mitigating occupant injury severity. The benefits and drawbacks of new technology and human factor considerations associated with increased general aviation automation will be debated. Data on the safety of the aging general aviation population and increased drug usage will also be described. Finally, areas in which general aviation occupant survival could be improved and injury severity mitigated will be discussed with the view of equipping aircraft with 1) crash-resistant fuel tanks to reduce post-impact conflagration; 2) after-market ballistic parachutes for older aircraft; and 3) current generation electronic locator beacons to hasten site access by first responders.Boyd DD. A review of general aviation safety (1984-2017). Aerosp Med Hum Perform. 2017; 88(7):657-664.

Safety activities in small businesses

Science.gov (United States)

Sinclair, Raymond C.; Cunningham, Thomas R.

2015-01-01

Background Workplace injuries occur at higher rates in smaller firms than in larger firms, and the number of workplace safety activities appear to be inversely associated with those rates. Predictors of safety activities are rarely studied. Methods This study uses data from a national random survey of firms (n = 722) with less than 250 employees conducted in 2002. Results We found that, regardless of firm size or industry, safety activities were more common in 2002 than they were in a similar 1983 study. Having had an OSHA inspection in the last five years and firm size were stronger predictors of safety activities than industry hazardousness and manager’s perceptions of hazardousness. All four variables were significant predictors (β range .19 to .28; R2 = .27). Conclusions Further progress in the prevention of injuries in small firms will require attention to factors likely subsumed within the firm size variable, especially the relative lack of slack resources that might be devoted to safety activities. PMID:26339124

Relationship between general safety requirements and safety culture in the improvement of safe operation of I.N.R. TRIGA reactor facilities

International Nuclear Information System (INIS)

Ciocanescu, M.; Preda, M.; Chiritescu, M.; Dumitru, M.

1996-01-01

Acquiring of the basic principles of ''safety culture'' by a large number of profesionals in the nuclear field drew the attention of the decision factors in the INR managerial structure, who decided to promote certain practical actions at each level in order to improve nuclear safety. Starting from the ''Republican Standards for Nuclear Safety'' issued by CSEN in 1975, where general safety criteria are defined for nuclear reactors and NPPs, the specialists at the TRIGA reactor originated and implemented a coherent and secure system to ensure nuclear safety over all steps of nuclear activities: research, conception, execution, commissioning and operation. This system has been continuosly corrected so that now it is completely integrated in a modern safety system. The paper presents the way in which a modern system for nuclear safety at the TRIGA reactor has been implemented and developed, in accordance to specific criteria and requirements imposed by related National Regulations and with the principles of safety culture. Starting from the definition of specific responsabilities, there are presented the internal stipulations and practical actions at all levels in order to enhance nuclear safety. (orig.)

Activities on safety for the cross-cutting issue of research reactors in the IAEA

International Nuclear Information System (INIS)

Perrotta, J.A.; Boado Magan, H.J.

2003-01-01

IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety and implemented by the Engineering Safety Section through its Research Reactor Safety Unit. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities are discussed in this paper: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOCs); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the (Integrated Safety Assessment of Research Reactors) INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors developed, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors conducted in the year 2002 and the results obtained. (author)

Safety Culture Activities of HANARO in 2007

Energy Technology Data Exchange (ETDEWEB)

Wu, Jong Sup [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-05-15

One of the important aims of a management system for nuclear facilities is to foster a strong safety culture. The safety culture activities in HANARO have been continuously conducted to enhance its safe operation. The following activities and events on a safety culture were performed last year; - Seminars and lectures on safety for the 'Nuclear Safety Check Day' every month - Development of safety culture indicators - Development of operational SPIs (Safety Performance Indicators) - Preparation of an e-Learning program for safety education. In this paper, the safety culture activities in HANARO of KAERI are described, and the efforts necessary for a safety improvement are presented.

General safety considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

General safety considerations

International Nuclear Information System (INIS)

2001-01-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness

General safety considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

General safety considerations

International Nuclear Information System (INIS)

1998-01-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness

EDA activities related to safety

International Nuclear Information System (INIS)

Gordon, C.; Raeder, J.

2001-01-01

This article reviews the accomplishments in ITER safety analysis during the course of the Engineering Design Activities (EDA). The key aspects of ITER safety analysis are: effluents and emissions from normal operation, including planned maintenance activities; occupational safety for workers at the facility; radioactive materials and wastes generated during operation and from decommissioning ; potential incidents and accidents and the resulting transients. As a result of the work during the EDA it is concluded that ITER is safe

EDF - The Inspector General's report on Nuclear Safety and Radiation Protection 2009

International Nuclear Information System (INIS)

2010-01-01

After a first chapter in which the Inspector General states his own vision of facts and results regarding nuclear safety and radiation protection for 2009, the relationship with the ASN (Nuclear safety authority), and also gives his own impression on the whole EDF nuclear system, the next chapters more particularly address the following topics: safety management, radiation protection of interveners, abilities and education for new challenges, the exploitation quality, the implementation of new regulatory arrangements, the extension of exploitation duration, the EPR project, the doctors as actors of safety management, service providing or subcontracting companies and fleet performance, prevention and struggle against fire, the activity of British Energy which is part of the EDF group, events which occurred within the EDF group (exposure of an intervener, incidents involving fuel components, biases in work monitoring, a fire on a turbo generator, an incident in Dungeness), lessons drawn from other industrial events (in a Russian hydroelectric station and in a refinery in Texas), and visits in China and in Japan

Patient safety culture measurement in general care: clinimetric properties of 'SCOPE'.

NARCIS (Netherlands)

Zwart, D.L.M.; Langelaan, M.; Vooren, R.C. van de; Kuyvenhoven, M.M.; Kalkman, C.J.; Verheij, T.J.M.; Wagner, C.

2011-01-01

BACKGROUND: A supportive patient safety culture is considered to be an essential condition for improving patient safety. Assessing the current safety culture in general practice may be a first step to target improvements. To that end, we studied internal consistency and construct validity of a

General administrative activities

International Nuclear Information System (INIS)

Cottrell, W.B.

1982-01-01

Significant safety-related activities reported during May and June, which are not covered elsewhere in this issue, are summarized. The Advisory Committee on Reactor Safeguards (ACRS) issued several reports on a variety of topics of current concern to the Nuclear Regulatory Commission (NRC). Both the ACRS and Scientists and Engineers for Secure Energy (SE 2 ) comments on safety goals are excerpted. Five speeches by various NRC Commissioners are summarized. A House Committee conducted a hearing on the pressure-vessel thermal shock question. Proposed regulations dealing with Licensee Event Reports (LERs) and mandatory property insurance are reviewed. Last is a listing of a variety of safety-related topics

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-09-15

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered.

General administrative activities

International Nuclear Information System (INIS)

Cottrell, W.B.

1982-01-01

Significant safety-related activities reported during March and April, which are not covered elsewhere in this issue, are summarized here. The Advisory Committee on Reactor Safeguards (ACRS) issued several reports on a variety of topics of current concern to the Nuclear Regulatory Commission (NRC). A recent NRC draft report identifies preliminary ranking of safety issues. The NRC is establishing a new Office of Investigations. The NRC also released a list of plants now under construction which it suspects will be canceled or indefinitely deferred. Four speeches by NRC Commissioners are summarized, as is the only Research Information Letter issued during the report period. Last is a listing of a variety of safety-related topics

77 FR 33777 - General Aviation Safety Forum: Climbing to the Next Level

Science.gov (United States)

2012-06-07

... NATIONAL TRANSPORTATION SAFETY BOARD General Aviation Safety Forum: Climbing to the Next Level The National Transportation Safety Board (NTSB) will convene a 2- day forum focused on safety issues related to... the Next Level,'' will be chaired by NTSB Chairman Deborah A. P. Hersman and all five Board Members...

Planned activities to improve safety

International Nuclear Information System (INIS)

1998-01-01

This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 6 of the document contains some details about the planed activities to safety improvements

Generally Recognized as Safe: Uncertainty Surrounding E-Cigarette Flavoring Safety

OpenAIRE

Sears, Clara G.; Hart, Joy L.; Walker, Kandi L.; Robertson, Rose Marie

2017-01-01

Despite scientific uncertainty regarding the relative safety of inhaling e-cigarette aerosol and flavorings, some consumers regard the U.S. Food and Drug Administration’s “generally recognized as safe” (GRAS) designation as evidence of flavoring safety. In this study, we assessed how college students’ perceptions of e-cigarette flavoring safety are related to understanding of the GRAS designation. During spring 2017, an online questionnaire was administered to college students. Chi-square p-v...

Safety from Crime and Physical Activity among Older Adults: A Population-Based Study in Brazil

International Nuclear Information System (INIS)

Corseuil, M.W.; Schneider, I.J.C.; Orsi, E.; Hallal, P.C.; Corseuil, H.X.

2012-01-01

Objective. To evaluate the association between safety from crime and physical activity among older adults. Methods. A population-based survey including 1,656 older adults (60+ years) took place in Florianopolis, Brazil, in 2009-2010. Commuting and leisure time physical activity were assessed through the long version of the International Physical Activity Questionnaire. Perception of safety from crime was assessed using the Neighbourhood Environment Walk ability Scale. Results. Perceiving the neighbourhood as safe during the day was related to a 25% increased likelihood of being active in leisure time (95% CI 1.02-1.53); general perception of safety was also associated with a 25% increase in the likelihood of being active in leisure time (95% CI 1.01-1.54). Street lighting was related to higher levels of commuting physical activity (prevalence ratio: 1.89; 95% CI 1.28-2.80). Conclusions. Safety investments are essential for promoting physical activity among older adults in Brazil

Radiation Safety (General) Regulations 1983 (Western Australia)

International Nuclear Information System (INIS)

1983-01-01

The provisions of the Regulations cover, inter alia, the general precautions and requirements relating to radiation safety of the public and radiation workers and registration of irradiating apparatus or premises on which such apparatus is operated. In addition, the Regulations set forth requirements for the operation of such apparatus and for the premises involved. (NEA) [fr

Recommended general safety requirements for nuclear power plants

International Nuclear Information System (INIS)

1983-06-01

This report presents recommendations for a set of general safety requirements that could form the basis for the licensing of nuclear power plants by the Atomic Energy Control Board. In addition to a number of recommended deterministic requirements the report includes criteria for the acceptability of the design of such plants based upon the calculated probability and consequence (in terms of predicted radiation dose to members of the public) of potential fault sequences. The report also contains a historical review of nuclear safety principles and practices in Canada

General safety aspects

International Nuclear Information System (INIS)

1998-01-01

In this part next aspects are described: (1) Priority to safety; (2) Financial and human resources;; (3) Human factor; (4) Operator's quality assurance system; (5) Safety assessment and Verification; (6) Radiation protection and (7) Emergency preparedness

Attitude and awareness of general dental practitioners toward radiation hazards and safety.

Science.gov (United States)

Aravind, B S; Joy, E Tatu; Kiran, M Shashi; Sherubin, J Eugenia; Sajesh, S; Manchil, P Redwin Dhas

2016-10-01

The aim and objective is to evaluate the level of awareness and attitude about radiation hazards and safety practices among general dental practitioners in Trivandrum District, Kerala, India. A questionnaire-based cross-sectional study was conducted among 300 general dental practitioners in Trivandrum District, Kerala, India. Postanswering the questions, a handout regarding radiation safety and related preventive measures was distributed to encourage radiation understanding and protection. Statistical analysis were done by assessing the results using Chi-square statistical test, t -test, and other software (Microsoft excel + SPSS 20.0 trail version). Among 300 general practitioners (247 females and 53 males), 80.3% of the practitioners were found to have a separate section for radiographic examination in their clinics. Intraoral radiographic machines were found to be the most commonly (63.3%) used radiographic equipment while osteoprotegerin was the least (2%). Regarding the practitioner's safety measures, only 11.7% of them were following all the necessary steps while 6.7% clinicians were not using any safety measure in their clinic, and with respect to patient safety, only 9.7% of practitioners were following the protocol. The level of awareness of practitioners regarding radiation hazards and safety was found to be acceptable. However, implementation of their knowledge with respect to patient and personnel safety was found wanting. Insisting that they follow the protocols and take necessary safety measures by means of continuing medical education programs, pamphlets, articles, and workshops is strongly recommended.

Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

International Nuclear Information System (INIS)

2010-01-01

There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

International Nuclear Information System (INIS)

2009-01-01

There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

Effects of a team-based assessment and intervention on patient safety culture in general practice

DEFF Research Database (Denmark)

Hoffmann, B; Müller, V; Rochon, J

2014-01-01

Background: The measurement of safety culture in healthcare is generally regarded as a first step towards improvement. Based on a self-assessment of safety culture, the Frankfurt Patient Safety Matrix (FraTrix) aims to enable healthcare teams to improve safety culture in their organisations....... In this study we assessed the effects of FraTrix on safety culture in general practice. Methods: We conducted an open randomised controlled trial in 60 general practices. FraTrix was applied over a period of 9 months during three facilitated team sessions in intervention practices. At baseline and after 12...... months, scores were allocated for safety culture as expressed in practice structure and processes (indicators), in safety climate and in patient safety incident reporting. The primary outcome was the indicator error management. Results: During the team sessions, practice teams reflected on their safety...

Regulatory Activities for Licensee's Safety Culture

International Nuclear Information System (INIS)

Choi, Young Sung; Choi, Kwang Sik

2008-01-01

Weaknesses in safety culture have contributed to a number of incidents/accidents in the nuclear and other high hazard sectors worldwide in the past. These events have fostered an increasing awareness of the need for licensees to develop a strong safety culture to support successful and sustainable nuclear safety performance. Regulatory bodies are taking a growing interest in this issue, and several are actively working to develop and implement approaches to maintaining regulatory oversight of licensee safety culture. However, these approaches are not yet well-established, and it was considered prudent to share experiences and developing methodologies in order to disseminate good practices and avoid potential pitfalls. This paper presents the findings, conclusions and recommendations of international meetings and other countries' activities on safety culture and gives some suggestions for regulators to consider when planning regulatory oversight for licensee's safety culture

Nuclear safety philosophy and its general application to fuel management and handling - a regulator's viewpoint

International Nuclear Information System (INIS)

Petty, I.C.

1995-01-01

The Nuclear Safety Division (NSD) of the Health and Safety Executive (HSE) informs the UK Nuclear Industry of the principles that it applies in assessing whether licensees have demonstrated that their nuclear plants are as safe as is reasonably practicable. The paper commences with a discussion of the non-prescriptive approach to health and safety regulation which is the basis of the regulatory activities of NSD's operating arm -the Nuclear Installations Inspectorate (NII). It then describes in broad terms the overall approach used by NII for analysing the safety of nuclear plant, including fuel, which will cover both deterministic and probabilistic methodologies. The paper then introduces the sections of the Safety Assessment Principles which apply to nuclear fuel safety (both fuel handling and management). Most of these principles are of a general nature and do not just apply to fuel. The paper explains how safety cases might relate to the SAPs and offers some views on how a licensee might interpret them in developing his safety case. Particular emphasis is placed on the importance of submitting a high quality safety case and the type of information that should be in it. The advantages of the approach proposed, to the licensee as well as to the regulator, are identified. (author)

Risk communication activities toward nuclear safety in Tokai: your safety is our safety

International Nuclear Information System (INIS)

Tsuchiya, T.

2007-01-01

As several decades have passed since the construction of nuclear power plants began, residents have become gradually less interested in nuclear safety. The Tokai criticality accident in 1909, however, had roused residents in Tokai-Mura to realize that they live with nuclear technology risks. To prepare a field of risk communication, the Tokai-Mura C 3 project began as a pilot research project supported by NISA. Alter the project ended, we are continuing risk. communication activities as a non-profit organisation. The most important activity of C 3 project is the citizen's inspection programme for nuclear related facilities. This programme was decided by participants who voluntarily applied to the project. The concept of the citizen's inspection programme is 'not the usual facility tours'. Participants are involved from the planning stage and continue to communicate with workers of the inspected nuclear facility. Since 2003, we have conducted six programmes for five nuclear related organisations. Participants evaluated that radiation protection measures were near good but there were some problems concerning the worker's safety and safety culture, and proposed a mixture of advice based on personal experience. Some advice was accepted and it did improve the facility's safety measures. Other suggestions were not agreed upon by nuclear organisations. The reason lies in the difference of concept between the nuclear expert's 'safety' and the citizen's 'safety'. Residents do not worry about radiation only, but also about the facility's safety as a whole including the worker's safety. They say, 'If the workers are not safe, you also are unable to protect us'. Although the disagreement remained, the participants and the nuclear industry learned much about each other. Participating citizens received a substantial amount of knowledge about the nuclear industry and its safety measures, and feel the credibility and openness of the nuclear industry. On the other hand, the nuclear

Feasibility and safety of general anesthesia for bronchial thermoplasty: a description of early 10 treatments.

Science.gov (United States)

Aizawa, Mariko; Ishihara, Satoshi; Yokoyama, Takeshi; Katayama, Katsuyuki

2018-03-20

Bronchial thermoplasty (BT) is a recently introduced bronchoscopic treatment for patients with asthma refractory to pharmacotherapy. Intraprocedural sedation management is important for successful performance of BT. However, the results of general anesthesia in patients undergoing BT have not been well described. The aim of this study was to evaluate the feasibility and safety of general anesthesia in patients undergoing BT. We retrospectively reviewed the records of 10 consecutive BT treatments performed under general anesthesia in 4 patients. The feasibility outcomes were coughing and body movement during the procedure, procedure abandonment, and the relative frequency of thermal activation failure. The safety outcomes were bronchospasm and hypoxemia during the procedure, respiratory symptoms, and the need for oxygen after the procedure. Coughing occurred in two treatments. Neither body movement nor procedure abandonment occurred in any treatments. Neither intraprocedural bronchospasm nor hypoxemia occurred in any treatments. Respiratory symptoms occurred in 7 of 10 treatments within 1 day after the procedure and resolved within 4 days, which is comparable with a previous report. These results indicate that general anesthesia is feasible and safe for patients undergoing BT.

General administrative activities

International Nuclear Information System (INIS)

Cottrell, W.B.

1980-01-01

Significant safety-related activities reported during September and October, which are not covered elsewhere in this issue, are summarized here. The Nuclear Regulatory Commission (NRC) has adopted an interim statement of policy on the licensing of nuclear power plants. Four speeches by NRC Commissioners are summarized. The Advisory Committee on Reactor Safeguards (ACRS) issued a review of the NRC Systematic Evaluation Program (SEP). The NRC also issued a policy statement on emergency planning guidance. Two Research Informantion Letters (RILs) issued during the report period are summarized. Last is a listing of developments on a variety os safety-related topics

General aviation crash safety program at Langley Research Center

Science.gov (United States)

Thomson, R. G.

1976-01-01

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

Safety culture activities in HANARO

International Nuclear Information System (INIS)

Lim, I. C.; Park, C.; Hwang, S. R.; Choi, H. Y.; Jeon, B. J.

2002-01-01

The yearly operation time and the number of users in HANARO are increasing since its initial criticality has been achieved in 1995. This achievement is partly in debt to the spread of safety culture to operators and reactor users. In this paper, the activities done by the reactor operation organization on safety culture are described, and their further efforts identified to be necessary for the improvement and dissemination of safety culture and are presented

General re-evaluation of the safety on the nuclear ship 'Mutsu' and its repair work

International Nuclear Information System (INIS)

1980-01-01

According to the proposition by the Committee for Investigation Radiation Leak on Mutsu, the works of the general re-evaluation of safety were started after the approval by the Committee for Investigating General Re-evaluation and Repair Techniques for Mutsu. The contents of the general re-evaluation of safety are the inspection of the machines and equipments in the nuclear reactor plant, the review of the design of the nuclear reactor plant, the analysis of the nuclear reactor plant behavior in accidents, and the related experimental researches. These works have been carried out for five years, and problem did not arise at all regarding the nuclear reactor so far, but from the viewpoint of improving the safety and reliability further, it was decided to carry out the repair work based on the general re-evaluation of safety. The contents of the repair work are the improvement of the emergency core-cooling system, the improvement of the safety protection system, the improvement of the radiation monitoring equipments, the improvement of the containment vessel boundary, the improvement of the actuators for technological safety facilities, the improvement of the method controlling secondary water quality, and other repair works. The progress of the general re-evaluation of safety is reported. (Kako, I.)

Generalized railway tank car safety design optimization for hazardous materials transport: Addressing the trade-off between transportation efficiency and safety

International Nuclear Information System (INIS)

Saat, Mohd Rapik; Barkan, Christopher P.L.

2011-01-01

North America railways offer safe and generally the most economical means of long distance transport of hazardous materials. Nevertheless, in the event of a train accident releases of these materials can pose substantial risk to human health, property or the environment. The majority of railway shipments of hazardous materials are in tank cars. Improving the safety design of these cars to make them more robust in accidents generally increases their weight thereby reducing their capacity and consequent transportation efficiency. This paper presents a generalized tank car safety design optimization model that addresses this tradeoff. The optimization model enables evaluation of each element of tank car safety design, independently and in combination with one another. We present the optimization model by identifying a set of Pareto-optimal solutions for a baseline tank car design in a bicriteria decision problem. This model provides a quantitative framework for a rational decision-making process involving tank car safety design enhancements to reduce the risk of transporting hazardous materials.

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (French Edition)

International Nuclear Information System (INIS)

2010-01-01

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (Chinese Edition)

International Nuclear Information System (INIS)

2010-01-01

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (Arabic Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-09-15

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered.

Patient safety in primary care: a survey of general practitioners in The Netherlands.

NARCIS (Netherlands)

Gaal, S.; Verstappen, W.H.J.M.; Wensing, M.J.P.

2010-01-01

BACKGROUND: Primary care encompasses many different clinical domains and patient groups, which means that patient safety in primary care may be equally broad. Previous research on safety in primary care has focused on medication safety and incident reporting. In this study, the views of general

Evaluation of the League General Insurance Company child safety seat distribution program

Science.gov (United States)

1982-05-01

This report presents an evaluation of the child safety seat distribution initiated by the League General Insurance Company in June 1979. The program provides child safety seats as a benefit under the company's auto insurance policies to policy-holder...

General safety basis development guidance for environmental restoration decontamination and decommissioning

International Nuclear Information System (INIS)

Ellingson, D.R.; Kerr, N.; Bohlander, K.; Hansen, J.; Crowley, W.

1994-02-01

Safety analyses have the objective of contributing to two essential ingredients of a successful operation. The first is promoting the safety of the operation through worker involvement in information development (safety basis). The second is obtaining approval to conduct the operation (authorization). Typically these ingredients are assembled under separate programs covered by separate DOE requirements. DOE authorization relies on successful development of a document containing up to 21 topics written in terms and language suited to reviewers and approvers. Safety relies on successful training and procedures that convert the technical documented information into terms and language understandable to the worker. This separation can lead to successful incorporation of one ingredient independent of the other. At best, this separation may result in a safe but unauthorized operation; at worst, the separation may result in an unsafe operation authorized to proceed. This guide is based on experiences gained by contractors who have integrated rather than separated the safety and authorization. The short duration of ER/D ampersand D activities, the uncertainties of hazards, and the publicly expressed desire for demonstrable progress in cleanup activities add emphasis to the need to integrate rather than separate and develop new programs. Experience-based information has been useful to workers, safety analysis practitioners, and reviewers in the following ways: (1) Acquiring or developing the needed information in a useful form; (2) Managing the uncertainties during activity development and operation; (3) Identifying the subset of applicable requirements for an activity; (4) Developing the appropriate level of documentation detail for a specific activity; and (5) Increasing the usefulness and use of safety analysis (ownership)

Safety objectives for nuclear activities in Canada

International Nuclear Information System (INIS)

1982-04-01

This report by the Advisory Committee on Nuclear Safety presents a concise statement of the basic safety objectives which the Committee considers underlie, or should underlie, the regulations and the licensing and compliance practices of the Atomic Energy Control Board. The report also includes a number of general criteria for achieving these objectives

Survey and evaluation of inherent safety characteristics and passive safety systems for use in probabilistic safety analyses

International Nuclear Information System (INIS)

Wetzel, N.; Scharfe, A.

1998-01-01

The present report examines the possibilities and limits of a probabilistic safety analysis to evaluate passive safety systems and inherent safety characteristics. The inherent safety characteristics are based on physical principles, that together with the safety system lead to no damage. A probabilistic evaluation of the inherent safety characteristic is not made. An inventory of passive safety systems of accomplished nuclear power plant types in the Federal Republic of Germany was drawn up. The evaluation of the passive safety system in the analysis of the accomplished nuclear power plant types was examined. The analysis showed that the passive manner of working was always assumed to be successful. A probabilistic evaluation was not performed. The unavailability of the passive safety system was determined by the failure of active components which are necessary in order to activate the passive safety system. To evaluate the passive safety features in new concepts of nuclear power plants the AP600 from Westinghouse, the SBWR from General Electric and the SWR 600 from Siemens, were selected. Under these three reactor concepts, the SWR 600 is specially attractive because the safety features need no energy sources and instrumentation in this concept. First approaches for the assessment of the reliability of passively operating systems are summarized. Generally it can be established that the core melt frequency for the passive concepts AP600 and SBWR is advantageous in comparison to the probabilistic objectives from the European Pressurized Water Reactor (EPR). Under the passive concepts is the SWR 600 particularly interesting. In this concept the passive systems need no energy sources and instrumentation, and has active operational systems and active safety equipment. Siemens argues that with this concept the frequency of a core melt will be two orders of magnitude lower than for the conventional reactors. (orig.) [de

Implementation of the safety culture for HANARO Safety Management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

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

EDF - The Inspector General's report on Nuclear Safety and Radiation Protection

International Nuclear Information System (INIS)

Tandonnet, Jean

2012-01-01

This report is destined for the President of EDF with the purpose of informing him of the judgement the Inspector General has about the nuclear safety and radiation protection within the EDF Group. It is also intended for all who, in any way, play a role at EDF in improving nuclear safety. It may also prove useful to those outside the company who work in the nuclear field or indeed any branch of industry where there are risks to be managed and who wish to participate in the debate. It also contributes to the pool of information shared with the other nuclear operators under the auspices of WANO. The continuous improvement of nuclear safety results is a fundamental commitment of the EDF Group. This is notably reflected in a policy of transparency, whether in France, Britain, America or China. This document constitutes an example of this, offering an independent view of the operational situation. It is based on facts and findings derived in EDF's contacts with field staff and meetings with the decision makers, managers, medical personnel and players on both sides of this industry as well as outside stakeholders, especially contractor companies. The resulting snapshot of the situation in the field is particularly instructive. This report therefore concentrates more on problems and weaknesses rather than strengths and progress, except as concerns happenings outside France, where the focus is more on good practices than difficulties. Contents: 1 - The view from the Inspector General of EDF about the nuclear safety in the EDF group; 2 - A panorama of 2011: The management, The state of the installations, Maintenance of the French nuclear power plants, Relations with the French nuclear safety authority (ASN), The EPR projects, The players in the fields of health and safety, Radiation protection, Fire prevention and fire fighting, Increasing nuclear power plant security, Decommissioning; 3 - Nuclear safety management; 4 - The Fukushima Daiichi accident; 5 - Training to

2015 annual report of the managing director of the CEA general and nuclear inspection for nuclear safety and radiation protection

International Nuclear Information System (INIS)

2016-08-01

After an introduction by the managing director of the CEA general and nuclear inspection about activities and events of 2015, this report proposes some key figures and indicators to illustrate these activities and events. The next parts discuss, present and comment how a culture of safety is at the heart of the continuous progress approach by the CEA. The next chapters propose overviews and comments of lessons learned from nuclear inspections within the frame of audit programme or within the frame of centres' safety audits, and from reactive inspections. The last parts address the follow-up of recommendations, and progress orientations and perspectives

Research reactor management. Safety improvement activities in HANARO

International Nuclear Information System (INIS)

Wu, Jong-Sup; Jung, Hoan-Sung; Hong, Sung Taek; Ahn, Guk-Hoon

2012-01-01

Safety activities in HANARO have been continuously conducted to enhance its safe operation. Great effort has been placed on a normalization and improvement of the safety attitude of the regular staff and other employees working at the reactor and other experimental facilities. This paper introduces the activities on safety improvement that were performed over the last few years. (author)

Defining safety culture and the nexus between safety goals and safety culture. 1. An Investigation Study on Practical Points of Safety Management

International Nuclear Information System (INIS)

Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

2001-01-01

In a report after the Chernobyl accident, the International Atomic Energy Agency indicated the definition and the importance of safety culture and the ideal organizational state where safety culture pervades. However, the report did not mention practical approaches to enhance safety culture. In Japan, although there had been investigations that clarified the consciousness of employees and the organizational climate in the nuclear power and railway industries, organizational factors that clarified the level of organization safety and practical methods that spread safety culture in an organization had not been studied. The Central Research Institute of the Electric Power Industry conducted surveys of organizational culture for the construction, chemical, and manufacturing industries. The aim of our study was to clarify the organizational factors that influence safety in an organization expressed in employee safety consciousness, commitment to safety activities, rate of accidents, etc. If these areas were clarified, the level of organization safety might be evaluated, and practical ways could be suggested to enhance the safety culture. Consequently, a series of investigations was conducted to clarify relationships among organizational climate, employee consciousness, safety management and activities, and rate of accidents. The questionnaire surveys were conducted in 1998-1999. The subjects were (a) managers of the safety management sections in the head offices of the construction, chemical, and manufacturing industries; (b) responsible persons in factories of the chemical and manufacturing industries; and (c) general workers in factories of the chemical and manufacturing industries. The number of collected data was (a) managers in the head office: 48 from the construction industry and 58 from the chemical and manufacturing industries, (b) responsible persons in factories: 567, and (c) general workers: from 29 factories. Items in the questionnaires were selected from

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

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

2008-11-15

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

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

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

Assessment of IAEA safety series no. 75-INSAG-3 - ''basic safety principles for nuclear power plants''

International Nuclear Information System (INIS)

1989-01-01

The International Atomic Energy Agency Safety Series No. 75-INSAG--3, 'Basic Safety Principles for Nuclear Power Plants' is reviewed in the light of the Advisory Committee on Nuclear Safety reports ACNS--2, 'Safety Objectives for Nuclear Activities in Canada', and ACNS--4, 'Recommended General Safety Requirements for Nuclear Power Plants'. The INSAG safety objectives are consistent with the safety objectives stated in ACNS--2 but are less general, applying only to nuclear power plants. The INSAG safety principles are, in general, consistent with the requirements stated in ACNS--4 but put more emphasis on 'safety culture'. They give little attention to reactor plant effluents, waste management, or decommissioning. (fig., 5 refs.)

Generalized Safety and Efficacy of Simplified Intravenous Thrombolysis Treatment (SMART) Criteria in Acute Ischemic Stroke

DEFF Research Database (Denmark)

Sørensen, Sigrid B; Barazangi, Nobl; Chen, Charlene

2016-01-01

BACKGROUND: Common intravenous recombinant tissue plasminogen activator (IV rt-PA) exclusion criteria may substantially limit the use of thrombolysis. Preliminary data have shown that the SMART (Simplified Management of Acute stroke using Revised Treatment) criteria greatly expand patient...... eligibility by reducing thrombolysis exclusions, but they have not been assessed on a large scale. We evaluated the safety and efficacy of general adoption of SMART thrombolysis criteria to a large regional stroke network. METHODS: Retrospective analysis of consecutive patients who received IV thrombolysis...... within a regional stroke network was performed. Patients were divided into those receiving thrombolysis locally versus at an outside hospital. The primary outcome was modified Rankin Scale score (≤1) at discharge and the main safety outcome was symptomatic intracranial hemorrhage (sICH) rate. RESULTS...

JRC/IE support activities to PHARE nuclear safety programmes. Dissemination of PHARE project results

International Nuclear Information System (INIS)

Ranguelova, V.; Pla, P.; Rieg, C.; Bieth, M.

2005-01-01

Nuclear safety in Europe is one of European Union's primary concerns, therefore the European Union decided to take a prominent role to help the New Independent States and countries of Central and Eastern Europe to ensure the safety of their nuclear reactors. The European Union TACIS and PHARE programmes in nuclear safety have been undertaken since 1990. The European Commission's Directorate General External Relations (EC DG RELEX) and, Directorate General Europe Aid Co-operation Office (EC DG AIDCO), are responsible for programming and management of implementation of TACIS projects. Directorate General Enlargement (EC DG ELARG) is responsible for programming PHARE programmes, but implementation of most projects has been decentralised since 1999 budget year to the Beneficiary countries. DG ELARG acts as backstopping for the relevant EC Delegations. In these activities, the TSSTP Unit at the JRC/IE in Petten, The Netherlands, is a technical and scientific adviser of DG RELEX and DG AIDCO and provides support to DG ELARG for very specific technical issues. Several PHARE projects aiming at improving nuclear safety have been successfully implemented for a number of plants from Central and Eastern Europe. In some cases major safety issues have been addressed by means of multi-country projects and results have been disseminated to the rest of the nuclear community. Although a lot of information has been exchanged at a bilateral level, further effort is needed to collect the project results in a systematic way and make them available by means of the internet. At present the TSSTP Unit is implementing two projects for dissemination of PHARE project results. This activity will take a better advantage of today's communication technologies and ensure the management of the acquired knowledge through preservation and user-friendly access and retrieval of the project results. The paper provides an outline of the TSSTP Unit relevant knowledge preservation initiative, a description

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

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

2008-11-15

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

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

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

2008-01-01

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

Safety evaluation by living probabilistic safety assessment. Procedures and applications for planning of operational activities and analysis of operating experience

International Nuclear Information System (INIS)

Johanson, Gunnar; Holmberg, J.

1994-01-01

Living Probabilistic Safety Assessment (PSA) is a daily safety management system and it is based on a plant-specific PSA and supporting information systems. In the living use of PSA, plant status knowledge is used to represent actual plant safety status in monitoring or follow-up perspective. The PSA model must be able to express the risk at a given time and plant configuration. The process, to update the PSA model to represent the current or planned configuration and to use the model to evaluate and direct the changes in the configuration, is called living PSA programme. The main purposes to develop and increase the usefulness of living PSA are: Long term safety planning: To continue the risk assessment process started with the basic PSA by extending and improving the basic models and data to provide a general risk evaluation tool for analyzing the safety effects of changes in plant design and procedures. Risk planning of operational activities: To support the operational management by providing means for searching optimal operational maintenance and testing strategies from the safety point of view. The results provide support for risk decision making in the short term or in a planning mode. The operational limits and conditions given by technical specifications can be analyzed by evaluating the risk effects of alternative requirements in order to balance the requirements with respect to operational flexibility and plant economy. Risk analysis of operating experience: To provide a general risk evaluation tool for analyzing the safety effects of incidents and plant status changes. The analyses are used to: identify possible high risk situations, rank the occurred events from safety point of view, and get feedback from operational events for the identification of risk contributors. This report describes the methods, models and applications required to continue the process towards a living use of PSA. 19 tabs, 20 figs

IAEA activities on education and training in radiation and waste safety: Strategic approach for a sustainable system

International Nuclear Information System (INIS)

Mrabit, Khammar; Sadagopan; Geetha

2003-01-01

The statutory safety functions of the International Atomic Energy Agency (IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place enabling the Government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. The IAEA education and training activities follows the resolutions of its General Conferences and reflects the latest IAEA standards and guidance. In response to GC(44)/RES/13, the IAEA prepared a 'Strategic Approach to Education and Training in Radiation and Waste Safety' aiming at establishing, by 2010, sustainable education a training programmes in Member States. This Strategy was endorsed by General Conference resolution GC(45)/RES/10C that, inter alia, urged the Secretariat to implement the Strategy on Education and Training and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States' national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. In the last General Conference 2002, the IAEA was urged to continue to implement the Strategy, including the convening of the Steering Committee. The first Technical Committee meeting took place during the week 25-29 November 2002. (author)

Methods of checking general safety criteria in UML statechart specifications

International Nuclear Information System (INIS)

Pap, Zsigmond; Majzik, Istvan; Pataricza, Andras; Szegi, Andras

2005-01-01

This paper describes methods and tools for safety analysis of UML statechart specifications. A comprehensive set of general safety criteria including completeness and consistency is applied in automated analysis. Analysis techniques are based on OCL expressions, graph transformations and reachability analysis. Two canonical intermediate representations of the statechart specification are introduced. They are suitable for straightforward implementation of checker methods and for the support of the proof of the correctness and soundness of the applied analysis. One of them also serves as a basis of the metamodel of a variant of UML statecharts proposed for the specification of safety-critical control systems. The analysis is extended to object-oriented specifications. Examples illustrate the application of the checker methods implemented by an automated tool-set

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

International Nuclear Information System (INIS)

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

1998-01-01

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

IAEA Safety Standards

International Nuclear Information System (INIS)

2016-09-01

The IAEA Safety Standards Series comprises publications of a regulatory nature covering nuclear safety, radiation protection, radioactive waste management, the transport of radioactive material, the safety of nuclear fuel cycle facilities and management systems. These publications are issued under the terms of Article III of the IAEA’s Statute, which authorizes the IAEA to establish “standards of safety for protection of health and minimization of danger to life and property”. Safety standards are categorized into: • Safety Fundamentals, stating the basic objective, concepts and principles of safety; • Safety Requirements, establishing the requirements that must be fulfilled to ensure safety; and • Safety Guides, recommending measures for complying with these requirements for safety. For numbering purposes, the IAEA Safety Standards Series is subdivided into General Safety Requirements and General Safety Guides (GSR and GSG), which are applicable to all types of facilities and activities, and Specific Safety Requirements and Specific Safety Guides (SSR and SSG), which are for application in particular thematic areas. This booklet lists all current IAEA Safety Standards, including those forthcoming

EDF - The Inspector General's report on Nuclear Safety and Radiation Protection 2012

International Nuclear Information System (INIS)

2013-01-01

After a first chapter in which the Inspector General states his own vision of facts and results regarding nuclear safety and radiation protection for 2012, the next chapters address the following topics: the contrasted results of nuclear operating safety, the need to remain vigilant in nuclear safety management, the challenge of occupational safety, the need of new ambitious goals for radiation protection, an updated training which must be better led by line management, maintenance as a strategic issue, the long road ahead for nuclear technical information system (SDIN), the need of better attention to chemistry in operations, the new impetus of EPRs, plant life extension conditioned by nuclear safety, the mobilization of nuclear operators after Fukushima, and noteworthy operating events

National legislative and regulatory activities

International Nuclear Information System (INIS)

2012-01-01

This section gathers the following national legislative and regulatory activities sorted by country: Bulgaria: General legislation; Czech Republic: General legislation; France: General legislation, Regulatory infrastructure and activity; Germany: General legislation; India: Liability and compensation, Organisation and structure; Ireland: Radiation protection, General legislation; Korea (Republic of): Organisation and structure; Lithuania: Regulatory infrastructure and activity, Radioactive waste management, Radiation protection, international cooperation, Nuclear safety; Poland: General legislation; Romania: Environmental protection; Russian Federation: Radioactive waste management; Slovenia: Nuclear safety; Spain: Liability and compensation, Nuclear security; Sweden: Nuclear safety; Turkey: Radiation protection, Regulatory infrastructure and activity, Nuclear safety, Liability and compensation; United States: General legislation

Periodic safety review of the experimental fast reactor JOYO. Review of the activity for safety

International Nuclear Information System (INIS)

Maeda, Yukimoto; Kashimura, Youichi; Suzuki, Toshiaki; Isozaki, Kazunori; Hoshiba, Hideaki; Kitamura, Ryoichi; Nakano, Tomoyuki; Takamatsu, Misao; Sekine, Takashi

2005-02-01

Periodic safety review (Review of the activity for safety) which consisted of 'Comprehensive evaluation of operation experience' and Incorporation of the latest technical knowledge' was carried out up to January 2005. 1. Comprehensive evaluation of operation experience. It was confirmed that the effectual activities for safety through the operation of JOYO were carried out in terms of (1) Operation management, (2) Maintenance management, (3) Fuel management, (4) Radiation management, (5) Radioactive waste management, (6) Emergency planning and (7) Feedback of incidents and failures. 2. Reflection of the latest technical knowledge. It was confirmed that the latest technical knowledge including regulation and guide line established by Nuclear Safety Commission of Japan until March 31st. 2003 were properly reflected in impressing the safety of the reactor. As a result, it was evaluated that the activity for safety was carried out effectually, and no additional measure was identified continual safe operation of the reactor. (author)

Comprehensive target populations for current active safety systems using national crash databases.

Science.gov (United States)

Kusano, Kristofer D; Gabler, Hampton C

2014-01-01

The objective of active safety systems is to prevent or mitigate collisions. A critical component in the design of active safety systems is the identification of the target population for a proposed system. The target population for an active safety system is that set of crashes that a proposed system could prevent or mitigate. Target crashes have scenarios in which the sensors and algorithms would likely activate. For example, the rear-end crash scenario, where the front of one vehicle contacts another vehicle traveling in the same direction and in the same lane as the striking vehicle, is one scenario for which forward collision warning (FCW) would be most effective in mitigating or preventing. This article presents a novel set of precrash scenarios based on coded variables from NHTSA's nationally representative crash databases in the United States. Using 4 databases (National Automotive Sampling System-General Estimates System [NASS-GES], NASS Crashworthiness Data System [NASS-CDS], Fatality Analysis Reporting System [FARS], and National Motor Vehicle Crash Causation Survey [NMVCCS]) the scenarios developed in this study can be used to quantify the number of police-reported crashes, seriously injured occupants, and fatalities that are applicable to proposed active safety systems. In this article, we use the precrash scenarios to identify the target populations for FCW, pedestrian crash avoidance systems (PCAS), lane departure warning (LDW), and vehicle-to-vehicle (V2V) or vehicle-to-infrastructure (V2I) systems. Crash scenarios were derived using precrash variables (critical event, accident type, precrash movement) present in all 4 data sources. This study found that these active safety systems could potentially mitigate approximately 1 in 5 of all severity and serious injury crashes in the United States and 26 percent of fatal crashes. Annually, this corresponds to 1.2 million all severity, 14,353 serious injury (MAIS 3+), and 7412 fatal crashes. In addition

21 CFR 170.20 - General principles for evaluating the safety of food additives.

Science.gov (United States)

2010-04-01

... food additives. 170.20 Section 170.20 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) FOOD FOR HUMAN CONSUMPTION (CONTINUED) FOOD ADDITIVES Food Additive Safety § 170.20 General principles for evaluating the safety of food additives. (a) In reaching a...

NEA activities in safety and regulation

International Nuclear Information System (INIS)

Stadie, K.B.

1983-01-01

The NEA programme on Safety and Regulations is briefly reviewed. It encompasses four main areas - nuclear safety technology; nuclear licensing; radiation protection; and waste management - with three principal objectives: to promote exchanges of technical information in order to enlarge the data base for national decision making; to improve co-ordination of national R and D activities with emphasis on international standard problem exercises, and to promote international projects; to develop common technical, administrative and legal approaches to improve compatibility of safety and regulatory practices

Generally Recognized as Safe: Uncertainty Surrounding E-Cigarette Flavoring Safety

Directory of Open Access Journals (Sweden)

Clara G. Sears

2017-10-01

Full Text Available Despite scientific uncertainty regarding the relative safety of inhaling e-cigarette aerosol and flavorings, some consumers regard the U.S. Food and Drug Administration’s “generally recognized as safe” (GRAS designation as evidence of flavoring safety. In this study, we assessed how college students’ perceptions of e-cigarette flavoring safety are related to understanding of the GRAS designation. During spring 2017, an online questionnaire was administered to college students. Chi-square p-values and multivariable logistic regression were employed to compare perceptions among participants considering e-cigarette flavorings as safe and those considering e-cigarette flavorings to be unsafe. The total sample size was 567 participants. Only 22% knew that GRAS designation meant that a product is safe to ingest, not inhale, inject, or use topically. Of participants who considered flavorings to be GRAS, the majority recognized that the designation meant a product is safe to ingest but also considered it safe to inhale. Although scientific uncertainty on the overall safety of flavorings in e-cigarettes remains, health messaging can educate the public about the GRAS designation and its irrelevance to e-cigarette safety.

General overview of the ASSET activities in Ukraine

Energy Technology Data Exchange (ETDEWEB)

Ruday, C G [Ministry for Environmental Protection and Nuclear Safety of Ukraine, Kiev (Ukraine)

1997-12-31

Brief retrospective summary of the ASSET experience in Ukraine since first mission held in June 1992. Analysis of the positive influence of the ASSET approaches to the general safety culture status. Specific problems of the current situation. Difference in attitude to ASSET missions of plant managers and plant safety experts reveals global safety culture drawbacks on the organizational level. Analysis of the direct and root causes of the situation. Lessons learned. Ideas for corrective measures to be implemented. (author). 7 tabs.

General overview of the ASSET activities in Ukraine

International Nuclear Information System (INIS)

Ruday, C.G.

1996-01-01

Brief retrospective summary of the ASSET experience in Ukraine since first mission held in June 1992. Analysis of the positive influence of the ASSET approaches to the general safety culture status. Specific problems of the current situation. Difference in attitude to ASSET missions of plant managers and plant safety experts reveals global safety culture drawbacks on the organizational level. Analysis of the direct and root causes of the situation. Lessons learned. Ideas for corrective measures to be implemented. (author). 7 tabs

Research activities of MPA, Stuttgart University, for enhanced safety and reliability of components under complex load

International Nuclear Information System (INIS)

Herter, K.H.; Roos, E.; Schuler, X.; Maile, K.

2004-01-01

MPA research activities focus on fracture prevention and on the development of a generally applicable method of component integrity testing which, independent of the safety relevance of the components involved, is also part of ageing management. (orig.) [de

21 CFR 570.20 - General principles for evaluating the safety of food additives.

Science.gov (United States)

2010-04-01

... food additives. 570.20 Section 570.20 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS FOOD ADDITIVES Food Additive Safety § 570.20 General principles for evaluating the safety of food additives. (a) In reaching a...

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

Safety Cultures in Water-Based Outdoor Activities in Denmark

DEFF Research Database (Denmark)

Andkjær, Søren; Arvidsen, Jan

2015-01-01

In this paper, we report on the study Safe in Nature (Tryg i naturen) in which the aim was to analyze and discuss risk and safety related to outdoor recreation in the coastal regions of Denmark. A cultural perspective is applied to risk management and the safety cultures related to three selected...... water-based outdoor activities: small boat fishing, sea kayaking, and kite surfing. The theoretical framework used was cultural analysis and the methodological approach was mixed methods using case studies with survey and qualitative interviews. The study indicates that safety is a complex matter...... and that safety culture can be understood as the sum and interaction among six categories. The safety culture is closely related to the activity and differs widely among activities. We suggest a broad perspective be taken on risk management wherein risk and safety can be managed at different levels. Small boat...

Steel Erection Safety. Module SH-39. Safety and Health.

Science.gov (United States)

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

This student module on steel erection safety is one of 50 modules concerned with job safety and health. This module identifies typical jobsite hazards encountered by steel erectors, as well as providing safe job procedures for general and specific construction activities. Following the introduction, 11 objectives (each keyed to a page in the text)…

How do general practitioners use 'safety netting' in acutely ill children?

Science.gov (United States)

Bertheloot, Karen; Deraeve, Pieterjan; Vermandere, Mieke; Aertgeerts, Bert; Lemiengre, Marieke; De Sutter, An; Buntinx, Frank; Verbakel, Jan Y

2016-01-01

'Safety netting' advice allows general practitioners (GPs) to cope with diagnostic uncertainty in primary care. It informs patients on 'red flag' features and when and how to seek further help. There is, however, insufficient evidence to support useful choices regarding 'safety netting' procedures. To explore how GPs apply 'safety netting' in acutely ill children in Flanders. We designed a qualitative study consisting of semi-structured interviews with 37 GPs across Flanders. Two researchers performed qualitative analysis based on grounded theory components. Although unfamiliar with the term, GPs perform 'safety netting' in every acutely ill child, guided by their intuition without the use of specific guidelines. They communicate 'red flag' features, expected time course of illness and how and when to re-consult and try to tailor their advice to the context, patient and specific illness. Overall, GPs perceive 'safety netting' as an important element of the consultation, acknowledging personal and parental limitations, such as parents' interpretation of their advice. GPs do not feel a need for any form of support in the near future. GPs apply 'safety netting' intuitively and tailor the content. Further research should focus on the impact of 'safety netting' on morbidity and how the advice is conveyed to parents.

Status of safety in nuclear facilities - 2012. AREVA General Inspectorate Annual report

International Nuclear Information System (INIS)

2013-05-01

After a message from the Areva's Chief Executive Officer and a message from the senior Vice President of safety, health, security, sustainable development, a text by the inspector general comments the key safety results (events, dose levels, radiological impacts), the inspection findings, the areas of vigilance (relationship with the ASN, the management of the criticality risk, and facility compliance), some significant topics after the Fukushima accident. Then this report addresses the status of nuclear safety and radiation protection in the group's facilities and operations. It more specifically addresses the context and findings (lessons learned from the inspections, operating experience from event, employee radiation monitoring, environmental monitoring), crosscutting processes (safety management, controlling facility compliance, subcontractor guidance and management, crisis management), specific risks (criticality risk, fire hazards, transportation safety, radioactive waste management, pollution prevention, liability mitigation and dismantling), and areas for improvement and outlook

AREVA General Inspectorate 2010 Annual Report. Status of safety in nuclear facilities

International Nuclear Information System (INIS)

2010-01-01

After messages by different managers, this report proposes a description of the context for nuclear safety: group's policy in matters of nuclear safety and radiation protection, regulatory changes (in France, with respect to information, changes in administrative organization, overhaul of general technical regulations, international context). It describes the organizational changes which occurred within the company. It reports actions regarding transparency, briefly describes actions and principles aimed at improving safety, indicates and comments noteworthy nuclear events, discusses their assessment from a HOF (human and organizational factors) perspective, comments lessons learned from inspections, comments data regarding radiation protection and actions aimed at improving radiation protection. It discusses environmental impact issues. It addresses the different processes and factors which transversely appear in nuclear safety: safety management, human and organizational factors, safety in design, project management, and emergency management. Several specific risks are discussed: criticality control, nuclear materials safeguards, fire, spill prevention, transportation, radioactive waste, shutdown and dismantling, service operations, mining, and environmental liabilities. Document in French and in English

CEC activities in the field of LMFBR safety

International Nuclear Information System (INIS)

Balz, W.; Finzi, S.; Klersy, R.

1976-01-01

The aim of the ECC is to reach a common LMFBR Safety strategy in Europe. To this end the Commission promotes collaboration between the different fast reactor projects in the Community through working groups and collaborative arrangements and contributes with a research activity executed in its Joint Research Centre Ispra. A short description is given of the activity in the working groups and of the Ispra programme on LMFBR Safety. This programme covers: LMFBR thermohydraulics, fuel coolant interactions, dynamic structure loading and response, safety related material properties and whole core accident code development

[Fundamental role of the workers' representative in preventive safety activity].

Science.gov (United States)

Ossicini, A; Bindi, L; Casale, M C

2003-01-01

With the arrival of Legislative Decree 626/94 which brought into Italian law the EU directives on workers' health and safety at the workplace, our country has also introduced rules that make a break with the past in this area, with the creation of new professional roles. The workers' safety representative takes on a fundamentally important role in the management of prevention, safety and health for workers in their place of employment in accordance with article 19. In fact, before the introduction of this Legislative Decree, the "protection" of workers' health was essentially based on rules and regulations the application of which was left to the exclusive and direct responsibility of the relationship between the employer and doctor, leaving out any participation by the worker. Whereas in the past workers could only be considered the final receivers of instructions about the security measures to apply, with Law 626 the workers themselves became active participants in the assessment of risks at work and consequently in the implementing of all the safety and hygiene measures contributing to the reduction of risk levels. The new regulations now in force assign important tasks to the workers' safety representative; all tasks and responsibilities associated with that role are examined and discussed, especially those relating to rights to information and training, consultation and participation in the process of designing and promoting safety measures. The job of workers' representative today takes on a fundamentally important meaning and role in a self-regulating system of work safety, where he or she has a proper area responsibility, so becoming a reference point for the workers generally.

The Inspector General's report on Nuclear Safety and Radiation Protection 2013

International Nuclear Information System (INIS)

2014-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2013 2 - Safety in operation: good standing of results; 3 - Management of safety priority; 4 - Occupational safety: managers mobilization is necessary in France; 5 - Radiation protection: a new dynamics to initiate; 6 - Maintenance: regaining the essentials for the great careening; 7 - Fostering occupations to improve safety; 8 - A new momentum to the EPRs; 9 - Nuclear fuel, a major contribution to safety; 10 - Research-development: a lever to anticipate; 11 - Japan: safety under reconstruction; 12 - Noteworthy operational events; 13- Appendices: Results for the nuclear fleets (EDF SA, EDF Energy; Maps of the nuclear power plants(EDF SA, EDF Energy); Key dates for the nuclear units (EDF SA, EDF Energy); Abbreviations

Managing preventive occupational health and safety activities in Danish enterprises during a period of financial crisis

DEFF Research Database (Denmark)

Andersen, Hans H. K.; Bach, Elsa

2017-01-01

The onset of the financial crisis in 2008 has put pressure on enterprises that in turn have downsized and reorganized. Research has shown that economic recession has an effect on psychological and behavioral health that is attributed to working environment problems. The objective of this study is...... focus on the management of preventive workplace health and safety activities in enterprises during a period of economic recession....... is to unravel whether the onset of a general economic recession has had an impact on companies’ and public institutions’ preventive occupational health and safety activities. Hypotheses of the role of pro-cyclical and countercyclical effects are presented. This study is based on a survey of enterprise...... preventive occupational health safety activities. The baseline for the survey was established, in 2006 before the onset of the recession, with a follow up in 2011. Findings are discussed that support both the pro-cyclical and the countercyclical hypotheses. It is concluded that there is a need for a special...

SAFETY

CERN Multimedia

Niels Dupont

2013-01-01

CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

Design of an Active Automotive Safety System

Directory of Open Access Journals (Sweden)

Y. Wang

2013-07-01

Full Text Available With the development of the national economy, the people's standard of living got corresponding improvement, cars has been one of the indispensable traffic tools in many families. An active safety system is proposed, which can real-time detect the vehicle's running status and judge the security status of the vehicle. The system, which takes single-chip microcomputer as the controlling core and combines with millimeter-wave and ultrasonic distance measurement technology, can detect the distance from vehicle to vehicle and judge the security status of the vehicle. The hardware composition of the system and the data acquiring circuit are proposed, the mathematic model for different situation is established, and the controlling algorithm is completed. This system can accurately measure speed and distance between vehicles; the active safety control system can meet the relevant data measurement and transmission requirement; and can meet the functional requirement of the active safety control system

Assessing the general safety and tolerability of vildagliptin: value of pooled analyses from a large safety database versus evaluation of individual studies

Science.gov (United States)

Schweizer, Anja; Dejager, Sylvie; Foley, James E; Kothny, Wolfgang

2011-01-01

Aim: Analyzing safety aspects of a drug from individual studies can lead to difficult-to-interpret results. The aim of this paper is therefore to assess the general safety and tolerability, including incidences of the most common adverse events (AEs), of vildagliptin based on a large pooled database of Phase II and III clinical trials. Methods: Safety data were pooled from 38 studies of ≥12 to ≥104 weeks’ duration. AE profiles of vildagliptin (50 mg bid; N = 6116) were evaluated relative to a pool of comparators (placebo and active comparators; N = 6210). Absolute incidence rates were calculated for all AEs, serious AEs (SAEs), discontinuations due to AEs, and deaths. Results: Overall AEs, SAEs, discontinuations due to AEs, and deaths were all reported with a similar frequency in patients receiving vildagliptin (69.1%, 8.9%, 5.7%, and 0.4%, respectively) and patients receiving comparators (69.0%, 9.0%, 6.4%, and 0.4%, respectively), whereas drug-related AEs were seen with a lower frequency in vildagliptin-treated patients (15.7% vs 21.7% with comparators). The incidences of the most commonly reported specific AEs were also similar between vildagliptin and comparators, except for increased incidences of hypoglycemia, tremor, and hyperhidrosis in the comparator group related to the use of sulfonylureas. Conclusions: The present pooled analysis shows that vildagliptin was overall well tolerated in clinical trials of up to >2 years in duration. The data further emphasize the value of a pooled analysis from a large safety database versus assessing safety and tolerability from individual studies. PMID:21415917

Nuclear safety regulation on nuclear safety equipment activities in relation to human and organizational factors

International Nuclear Information System (INIS)

Li Tianshu

2013-01-01

Based on years of knowledge in nuclear safety supervision and experience of investigating and dealing with violation events in repair welding of DFHM, this paper analyzes major faults in manufacturing and maintaining activities of nuclear safety equipment in relation to human and organizational factors. It could be deducted that human and organizational factors has definitely become key features in the development of nuclear energy and technology. Some feasible measures to reinforce supervision on nuclear safety equipment activities have also been proposed. (author)

The mediating role of integration of safety by activity versus operator between organizational culture and safety climate.

Science.gov (United States)

Auzoult, Laurent; Gangloff, Bernard

2018-04-20

In this study, we analyse the impact of the organizational culture and introduce a new variable, the integration of safety, which relates to the modalities for the implementation and adoption of safety in the work process, either through the activity or by the operator. One hundred and eighty employees replied to a questionnaire measuring the organizational climate, the safety climate and the integration of safety. We expected that implementation centred on the activity or on the operator would mediate the relationship between the organizational culture and the safety climate. The results support our assumptions. A regression analysis highlights the positive impact on the safety climate of organizational values of the 'rule' and 'support' type, as well as of integration by the operator and activity. Moreover, integration mediates the relation between these variables. The results suggest to take into account organizational culture and to introduce different implementation modalities to improve the safety climate.

Active pedestrian safety by automatic braking and evasive steering

NARCIS (Netherlands)

Keller, C.; Dang, T.; Fritz, H.; Joos, A.; Rabe, C.; Gavrila, D.M.

2011-01-01

Active safety systems hold great potential for reducing accident frequency and severity by warning the driver and/or exerting automatic vehicle control ahead of crashes. This paper presents a novel active pedestrian safety system that combines sensing, situation analysis, decision making, and

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1, Revision 1 (Chinese Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication establishes requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

Identifying patient-centred recommendations for improving patient safety in General Practices in England: a qualitative content analysis of free-text responses using the Patient Reported Experiences and Outcomes of Safety in Primary Care (PREOS-PC) questionnaire.

Science.gov (United States)

Ricci-Cabello, Ignacio; Saletti-Cuesta, Lorena; Slight, Sarah P; Valderas, Jose M

2017-10-01

There is a growing interest in identifying strategies to achieve safer primary health-care provision. However, most of the research conducted so far in this area relies on information supplied by health-care providers, and limited attention has been paid to patients' perspectives. To explore patients' experiences and perceptions of patient safety in English general practices with the aim of eliciting patient-centred recommendations for improving patient safety. The Patient Reported Experiences and Outcomes of Safety in Primary Care questionnaire was sent to a random sample of 6736 primary care users registered in 45 English practices. We conducted a qualitative content analysis of responses to seven open-ended items addressing patients' experiences of safety problems, lessons learnt as a result of such experiences and recommendations for safer health care. A total of 1244 (18.4%) participants returned completed questionnaires. Of those, 678 (54.5%) responded to at least one open-ended question. Two main themes emerged as follows: (i) experiences of safety problems and (ii) good practices and recommendations to improve patient safety in primary care. Most frequent experiences of safety problems were related to appointments, coordination between providers, tests, medication and diagnosis. Patients' responses to these problems included increased patient activation (eg speaking up about concerns with their health care) and avoidance of unnecessary health care. Recommendations for safer health care included improvements in patient-centred communication, continuity of care, timely appointments, technical quality of care, active monitoring, teamwork, health records and practice environment. This study identified a number of patient-centred recommendations for improving patient safety in English general practices. © 2017 The Authors Health Expectations Published by John Wiley & Sons Ltd.

New set of Chemical Safety rules

CERN Multimedia

HSE Unit

2011-01-01

A new set of four Safety Rules was issued on 28 March 2011: Safety Regulation SR-C ver. 2, Chemical Agents (en); General Safety Instruction GSI-C1, Prevention and Protection Measures (en); General Safety Instruction GSI-C2, Explosive Atmospheres (en); General Safety Instruction GSI-C3, Monitoring of Exposure to Hazardous Chemical Agents in Workplace Atmospheres (en). These documents form part of the CERN Safety Rules and are issued in application of the “Staff Rules and Regulations” and of document SAPOCO 42. These documents set out the minimum requirements for the protection of persons from risks to their occupational safety and health arising, or likely to arise, from the effects of hazardous chemical agents that are present in the workplace or used in any CERN activity. Simultaneously, the HSE Unit has published seven Safety Guidelines and six Safety Forms. These documents are available from the dedicated Web page “Chemical, Cryogenic and Biological Safety&...

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

Nuclear safety in France: Extracts from 'Revue Generale Nucleaire'

International Nuclear Information System (INIS)

1979-07-01

Translations of 3 articles are included in this report. The first covers briefly the tasks and organisation of the Institute of Nuclear Protection and Safety (IPSN) in France. In the second article the principles of cost effectiveness are described and the applications of the general methodology to radiation protection is outlined. A study by the US Environmental Protection Agency is summarised. Methods for risk estimation in nuclear energy are presented in the final article

Safety of evolutionary and innovative nuclear reactors: IAEA activities and world efforts

International Nuclear Information System (INIS)

Saito, T.; Gasparini, M.

2004-01-01

'Defence in Depth' approach constitutes the basis of the IAEA safety standards for nuclear power plants. Lessons learned from the current generation of reactors suggest that, for the next generation of reactor designs, the Defence in Depth philosophy should be retained, and that its implementation should be guided by the probabilistic insights. Recent developments in the area of general safety requirements based on Defence in Depth approach are examined and summarized. Global efforts to harmonize safety requirements for evolutionary nuclear power plants have involved many countries and organizations such as IAEA, US EPRI and European Utility EUR Organization. In recent years, developments of innovative nuclear power plants are also being discussed. The IAEA is currently developing a safety approach specifically for innovative nuclear reactors. This approach will eventually lead to a proposal of safety requirements for innovative reactors. Such activities related to safety requirements of evolutionary and innovative reactors are introduced. Various evolutionary and innovative reactor designs are reported in the world. The safety design features of evolutionary large LWRs, innovative LWRs, Modular High Temperature Gas Reactors and Small Liquid Metal Cooled LMRs are also introduced. Enhanced safety features proposed in such reactors are discussed and summarized according to the levels of Defence in Depth. For future nuclear plants, international cooperation and harmonization, especially in the area of safety, appear to be inevitable. Based on the past experience with many member states, the IAEA believes itself to be the uniquely positioned international organization to play this key role. (authors)

Assessing the general safety and tolerability of vildagliptin: value of pooled analyses from a large safety database versus evaluation of individual studies

Directory of Open Access Journals (Sweden)

Schweizer A

2011-02-01

Full Text Available Anja Schweizer1, Sylvie Dejager2, James E Foley3, Wolfgang Kothny31Novartis Pharma AG, Basel, Switzerland; 2Novartis Pharma SAS, Rueil-Malmaison, France; 3Novartis Pharmaceuticals Corporation, East Hanover, NJ, USAAim: Analyzing safety aspects of a drug from individual studies can lead to difficult-to-interpret results. The aim of this paper is therefore to assess the general safety and tolerability, including incidences of the most common adverse events (AEs, of vildagliptin based on a large pooled database of Phase II and III clinical trials.Methods: Safety data were pooled from 38 studies of ≥12 to ≥104 weeks' duration. AE profiles of vildagliptin (50 mg bid; N = 6116 were evaluated relative to a pool of comparators (placebo and active comparators; N = 6210. Absolute incidence rates were calculated for all AEs, serious AEs (SAEs, discontinuations due to AEs, and deaths.Results: Overall AEs, SAEs, discontinuations due to AEs, and deaths were all reported with a similar frequency in patients receiving vildagliptin (69.1%, 8.9%, 5.7%, and 0.4%, respectively and patients receiving comparators (69.0%, 9.0%, 6.4%, and 0.4%, respectively, whereas drug-related AEs were seen with a lower frequency in vildagliptin-treated patients (15.7% vs 21.7% with comparators. The incidences of the most commonly reported specific AEs were also similar between vildagliptin and comparators, except for increased incidences of hypoglycemia, tremor, and hyperhidrosis in the comparator group related to the use of sulfonylureas.Conclusions: The present pooled analysis shows that vildagliptin was overall well tolerated in clinical trials of up to >2 years in duration. The data further emphasize the value of a pooled analysis from a large safety database versus assessing safety and tolerability from individual studies.Keywords: type 2 diabetes, dipeptidyl peptidase-4, edema, safety, vildagliptin

IAEA Activities on Education and training in Radiation and Waste Safety: Strategic approach for a sustainable system

International Nuclear Information System (INIS)

Marabit, K.; Sadagopan, G.

2003-01-01

The statutory safety functions of the International Atomic Energy(IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place, enabling the Government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. the IAEA education and training activities follow the resolutions of its General Conference and reflect the latest IAEA standards and guidance. Several General Conference resolutions have emphasized the importance of education and training (e. g. GC(XXXV)/RES/552 in 1991; GC(XXXVI)/RES/584 in 1992; GC(43)/RES/13 in 1999 and more recently GC(44)/RES/13 in 2000). In response to GC(44)/RES/13, the IAEA prepared a Strategic Approach to Education and Training in Radiation and Waste Safety (Strategy on Education and Training) aiming at establishing, by 2010, sustainable education and training programmes in its Member States. This Strategy was endorsed by the General Conference resolution GC(45)/RES/10C that, inter alia, urged the Secretariat to implement the Strategy on Education and Training, and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. A technical meeting was held in Vienna in March 2002 and concluded with an action plan for implementing the strategy up to 2010, the immediate action being the formation of a Steering Committee by the middle of 2002. This Steering Committee has the general remit to advise on the development and implementation of the strategy, as well as monitoring its progress. The first technical meeting of the Steering Committee took place on 25

Recent development in safety regulation of nuclear fuel cycle activities

International Nuclear Information System (INIS)

Kato, S.

2001-01-01

Through the effort of deliberation and legislation over five years, Japanese government structure was reformed this January, with the aim of realizing simple, efficient and transparent administration. Under the reform, the Agency for Nuclear and Industrial Safety (ANIS) was founded in the Ministry of Economy, Trade and Industry (METI) to be responsible for safety regulation of energy-related nuclear activities, including nuclear fuel cycle activities, and industrial activities, including explosives, high-pressure gasses and mining. As one of the lessons learned from the JCO criticality accident of September 1999, it was pointed out that the government's inspection function was not enough for fuel fabrication facilities. Accordingly, new statutory regulatory activities were introduced, namely, inspection of observance of safety rules and procedures for all kinds of nuclear operators and periodic inspection of fuel fabrication facilities. In addition, in order to cope with insufficient safety education and training of workers in nuclear facilities, licensees of nuclear facilities are required by law to specify safety education and training for their workers. ANIS is committed to enforce these new regulatory activities effectively and efficiently. In addition, it is going to be prepared, in its capacity as safety regulatory authority, for future development of Japanese fuel cycle activities, including commissioning of JNFL Rokkasho reprocessing plant and possible application for licenses for JNFL MOX fabrication plant and for spent fuel interim storage facilities. (author)

75 FR 53733 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2010-09-01

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

Role of in-house safety analysis and research activities in regulatory decision making

International Nuclear Information System (INIS)

Pradhan, Santosh K.; Nagrale, Dhanesh B.; Gaikwad, Avinash J.

2015-01-01

Achievement of an acceptable level of nuclear safety is an essential requirement for the peaceful utilization of nuclear energy. The success of Global Nuclear Safety Regime is built upon a foundation of research. Such research has been sponsored by Governments and industry and has led to improved designs, safer and more reliable plant operation, and improvements in operating plant efficiency. A key element of this research has been the nuclear safety research performed or sponsored by regulatory organizations. In part, it has been the safety research performed or sponsored by regulatory organizations that has contributed to improved safety and has laid the foundation for activities such as risk-informed regulation, plant life extension, improved plant performance (e.g. power uprates) and new plant designs. The regulatory research program is meant to improve the regulatory authority’s knowledge where uncertainty exists, where safety margins are not well-characterized, and where regulatory decisions need to be confirmed in existing or new designs and technologies. The regulatory body get research initiated either in-house or by the licensee or through technical support organizations (TSOs). Research and analysis carried out within the regulatory body is of immense value in this context. This could be in the form of analysis of safety significant events, analysis of severe accidents, review of operating experience, independent checks of critical designs and even review of operator responses under different situations towards arriving at modifications to training programmes and licensing procedures for operating personnel. A latent benefit of regulatory research carried out by the regulators themselves is that it improves their technical competence considerably which in turn leads to high quality safety reviews and improved regulation in general. The aim of the present paper is to provide an overview of role of regulatory research and the in-house regulatory safety

Exposure to ionizing radiations having a medical origin. Propositions for the implementation and the development of epidemiology surveillance activities in general population

International Nuclear Information System (INIS)

2002-09-01

This report gives propositions relative to the implementation and the development of epidemiology surveillance activities in general population in relation with medical exposure to ionizing radiations. It is intended for the General Direction of Health and General Direction of Nuclear Safety and Radiation Protection. These propositions have been elaborated by a work group coordinated and run by InVS and gathering the following organisms: French Agency of sanitary safety of health products (A.F.S.S.A.P.S.), Center of Quality Assurance of technological applications in the area of health (C.A.A.T.S.), Direction of Hospitals and Care organization (D.H.O.S.), General Direction of Health (D.G.S.), General Direction of Nuclear Safety and Radiation Protection (D.G.S.N.R.), National Federation of radiologists physicists (F.N.M.R.), institute of Radiation Protection and Nuclear Safety (I.R.S.N.), INSERM 'epidemiology of cancers', French Society of Biology and Nuclear Medicine (S.F.B.M.N.), French Society of Medical Physics (S.F.P.M.), French Society of Radiology (S.F.R.). (N.C.)

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

Safety Justification and Safety Case for Safety-critical Software in Digital Reactor Protection System

International Nuclear Information System (INIS)

Kwon, Kee-Choon; Lee, Jang-Soo; Jee, Eunkyoung

2016-01-01

Nuclear safety-critical software is under strict regulatory requirements and these regulatory requirements are essential for ensuring the safety of nuclear power plants. The verification & validation (V and V) and hazard analysis of the safety-critical software are required to follow regulatory requirements through the entire software life cycle. In order to obtain a license from the regulatory body through the development and validation of safety-critical software, it is essential to meet the standards which are required by the regulatory body throughout the software development process. Generally, large amounts of documents, which demonstrate safety justification including standard compliance, V and V, hazard analysis, and vulnerability assessment activities, are submitted to the regulatory body during the licensing process. It is not easy to accurately read and evaluate the whole documentation for the development activities, implementation technology, and validation activities. The safety case methodology has been kwon a promising approach to evaluate the level and depth of the development and validation results. A safety case is a structured argument, supported by a body of evidence that provides a compelling, comprehensible, and valid case that a system is safe for a given application in a given operating environment. It is suggested to evaluate the level and depth of the results of development and validation by applying safety case methodology to achieve software safety demonstration. A lot of documents provided as evidence are connected to claim that corresponds to the topic for safety demonstration. We demonstrated a case study in which more systematic safety demonstration for the target system software is performed via safety case construction than simply listing the documents

Safety Justification and Safety Case for Safety-critical Software in Digital Reactor Protection System

Energy Technology Data Exchange (ETDEWEB)

Kwon, Kee-Choon; Lee, Jang-Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Jee, Eunkyoung [KAIST, Daejeon (Korea, Republic of)

2016-10-15

Nuclear safety-critical software is under strict regulatory requirements and these regulatory requirements are essential for ensuring the safety of nuclear power plants. The verification & validation (V and V) and hazard analysis of the safety-critical software are required to follow regulatory requirements through the entire software life cycle. In order to obtain a license from the regulatory body through the development and validation of safety-critical software, it is essential to meet the standards which are required by the regulatory body throughout the software development process. Generally, large amounts of documents, which demonstrate safety justification including standard compliance, V and V, hazard analysis, and vulnerability assessment activities, are submitted to the regulatory body during the licensing process. It is not easy to accurately read and evaluate the whole documentation for the development activities, implementation technology, and validation activities. The safety case methodology has been kwon a promising approach to evaluate the level and depth of the development and validation results. A safety case is a structured argument, supported by a body of evidence that provides a compelling, comprehensible, and valid case that a system is safe for a given application in a given operating environment. It is suggested to evaluate the level and depth of the results of development and validation by applying safety case methodology to achieve software safety demonstration. A lot of documents provided as evidence are connected to claim that corresponds to the topic for safety demonstration. We demonstrated a case study in which more systematic safety demonstration for the target system software is performed via safety case construction than simply listing the documents.

Space reactor safety, 1985--1995 lessons learned

International Nuclear Information System (INIS)

Marshall, A.C.

1995-01-01

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

Space reactor safety, 1985--1995 lessons learned

Energy Technology Data Exchange (ETDEWEB)

Marshall, A.C.

1995-12-31

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

Predisposal management of radioactive waste. General safety requirements. Pt. 5

International Nuclear Information System (INIS)

2009-01-01

The objective of this Safety Requirements publication is to establish, the requirements that must be satisfied in the predisposal management of radioactive waste. This publication sets out the objectives, criteria and requirements for the protection of human health and the environment that apply to the siting, design, construction, commissioning, operation and shutdown of facilities for the predisposal management of radioactive waste, and the requirements that must be met to ensure the safety of such facilities and activities. This Safety Requirements publication applies to the predisposal management of radioactive waste of all types and covers all the steps in its management from its generation up to its disposal, including its processing (pretreatment, treatment and conditioning), storage and transport. Such waste may arise from the commissioning, operation and decommissioning of nuclear facilities; the use of radionuclides in medicine, industry, agriculture, research and education; the processing of materials that contain naturally occurring radionuclides; and the remediation of contaminated areas. The introduction of the document (Section 1) informs about its objective, scope and structure. The protection of human health and the environment is considered in Section 2 of this publication. Section 3 establishes requirements for the responsibilities associated with the predisposal management of radioactive waste. Requirements for the principal approaches to and the elements of the predisposal management of radioactive waste are established in Section 4. Section 5 establishes requirements for the safe development and operation of predisposal radioactive waste management facilities and safe conduct of activities. The Annex presents a discussion of the consistency of the safety requirements established in this publication with the fundamental safety principles

Safety performance indicators used by the Russian Safety Regulatory Authority in its practical activities on nuclear power plant safety regulation

International Nuclear Information System (INIS)

Khazanov, A.L.

2005-01-01

The Sixth Department of the Nuclear, Industrial and Environmental Regulatory Authority of Russia, Scientific and Engineering Centre for Nuclear and Radiation Safety process, analyse and use the information on nuclear power plants (NPPs) operational experience or NPPs safety improvement. Safety performance indicators (SPIs), derived from processing of information on operational violations and analysis of annual NPP Safety Reports, are used as tools to determination of trends towards changing of characteristics of operational safety, to assess the effectiveness of corrective measures, to monitor and evaluate the current operational safety level of NPPs, to regulate NPP safety. This report includes a list of the basic SPIs, those used by the Russian safety regulatory authority in regulatory activity. Some of them are absent in list of IAEA-TECDOC-1141 ('Operational safety performance indicators for nuclear power plants'). (author)

PSA in design of passive/active safety reactors

International Nuclear Information System (INIS)

Sato, T.; Tanabe, A.; Kondo, S.

1995-01-01

PSAs in the design of advanced reactors are applied mainly in level 1 PSA areas. However, even in level 1 PSA, there are certain areas where special care must be taken depending on plant design concepts. This paper identifies these areas both for passive and active safety reactor concepts. For example, 'long-term PSA' and shutdown PSA are very important for a passive safety reactor concept from the standpoint of effectiveness of a grace period and passive safety systems. External events are also important for an active safety reactor concept. These kinds of special PSAs are difficult to conduct precisely in a conceptual design stage. This paper shows methods of conducting these kinds of special PSAs simply and conveniently and the use of acquired insights for the design of advanced reactors. This paper also clarifies the meaning or definition of a grace period from the standpoint of PSA

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

International Nuclear Information System (INIS)

Rzentkowski, G.

2016-01-01

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

AREVA General Inspectorate Annual Report 2013 - Status of safety in nuclear facilities

International Nuclear Information System (INIS)

Oursel, Luc; Riou, Jean

2014-06-01

This annual report by AREVA's General Inspectorate deals with the status of nuclear safety and radiation protection in the group's facilities and operations over the course of 2013. Based on the findings made during implementation of the annual inspection program, this annual report also includes the results of the analysis of significant events and the observations and assessments of specialists in the Safety Health Security Sustainable Development Department (SHSSDD), supplemented by regular interaction with the safety regulators, different government agencies, stakeholders and other nuclear operators. Additionally, this report presents the action plans put into motion and the directions taken for continuous improvement in risk prevention for operations conducted in France and internationally. In 2013, the level of safety in the group's nuclear facilities and operations remained satisfactory, although improvements are necessary in some domains. This report is based on established indicators, analyses of reported events, responses to commitments made to the regulators, and the results of different improvement actions reported on in the inspected and supported entities. In 2013, no level 2 event on the International Nuclear and Radiological Event Scale (INES) was reported, the bottom-up reporting of weak signals was confirmed, dose levels were low and there were no radiological impacts on the environment. The General Inspectorate conducted 45 inspections in 30 of the group's entities in 2013. Of these, 10 concerned sites outside France and 7 were conducted following events or particular situations. These inspections gave rise to 176 recommendations, which the inspected entities have translated into action plans. Verification of these different action plans according to planned procedures and announced schedules gave rise to 16 follow-up inspections. The major lessons learned from these inspections relate to project management, facility compliance and operational

The Inspector General's report on Nuclear Safety and Radiation Protection 2016

International Nuclear Information System (INIS)

2017-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2016; 2 - Operational safety: encouraging results; 3 - High-profile focus on safety; 4 - Risk prevention: effort must be intensified; 5 - Team skills and commitment; 6 - Simplification; 7 - Maintenance quality; 8 - Nuclear fuel; 9 - New build; 10 - Protection against site security threats; 11 - Appendices

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (French Edition); Cadre gouvernemental, legislatif et reglementaire de la surete. Prescriptions generales de surete. Partie 1

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-11-15

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered.

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (Spanish Edition); Marco gubernamental, juridico y regulador para la seguridad. Requisitos de Seguridad Generales. Parte 1

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-11-15

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered.

International Atomic Energy Agency Activities on Education and Training in Radiation, Transport and Waste Safety: Strategic Approach for a Sustainable System

International Nuclear Information System (INIS)

Marbit, K.; Sadagopan, G.

2005-01-01

The statutory safety functions of the international Atomic Energy Agency (IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place enabling the government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. The IAEA education and training activities follows the the resolutions of its general conferences and reflects the latest IAEA standards and guidance. several general conference resolutions have emphasized the importance of education and training (e.g. GC (XXXV)/RES/552 in 1991,GC (XXXVI)/ RES/584 in 1992, GC (43)/RES/13 in 1999 and more recently GC (44)/RES/13 in 2000). In response to GC (44) /RES/13, the IAEA prepared a strategic approach to education and training in radiation and waste safety (strategy on education and training) aiming at establishing, by 2010 sustainable education and training programmes in member states. This strategy was endorsed by the general conference resolution GC(45)/RES/10C that, inter alia, urged the secretariat to implement the strategy on education and training, and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. The General Conference resolutions GC(46)RES/9C in 2002 and GC(47)RES/7 in 2003 urged the Agency to continue its efforts to implement the Strategy. The purpose of this paper is to present the newly established Strategic Approach to Education and Training in Radiation, Transport and Waste Safety and its implementation

International Atomic Energy Agency Activities on Education and Training in Radiation Transport and Waste Safety: Strategic Approach for a Sustainable System

International Nuclear Information System (INIS)

Mrabit, K.; Sadagopan, G.

2004-01-01

The statutory safety functions of the International Atomic Energy Agency (IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place enabling the Government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. The IAEA education and training activities follows the resolutions of its General Conferences and reflects the latest IAEA standards and guidance. Several General Conference resolutions have emphasized the importance of education and training [e.g. GC(XXXV)/RES/552 in 1991; GC(XXXVI)/RES/584 in 1992; GC(43)/RES/13 in 1999 and more recently GC(44)/RES/13 in 2000]. In response to GC(44)/RES/13, the IAEA prepared a S trategic Approach to Education and Training in Radiation and Waste Safety ( Strategy on Education and Training) aiming at establishing, by 2010, sustainable education and training programmes in Member States. This Strategy was endorsed by the General Conference resolution GC(45)/RES/10C that, inter alia, urged the Secretariat to implement the Strategy on Education and Training, and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member State' national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. The General Conference resolutions GC(46)RES/9C in 2002 and GC(47)RES/7 in 2003 urged the Agency to continue its efforts to implement the Strategy. The purpose of this paper is to present the newly established Strategic Approach to Education and Training in Radiation, Transport and Waste Safety and its implementation. (Author)

GENERAL CONSIDERATIONS ON REGULATIONS AND SAFETY REQUIREMENTS FOR QUADRICYCLES

Directory of Open Access Journals (Sweden)

Ana Pavlovic

2015-12-01

Full Text Available In recent years, a new class of compact vehicles has been emerging and wide-spreading all around Europe: the quadricycle. These four-wheeled motor vehicles, originally derived from motorcycles, are a small and fuel-efficient mean of transportation used in rural or urban areas as an alternative to motorbikes or city cars. In some countries, they are also endorsed by local authorities and institutions which support small and environmentally-friendly vehicles. In this paper, several general considerations on quadricycles will be provided including the vehicle classification, evolution of regulations (as homologation, driver licence, emissions, etc, technical characteristics, safety requirements, most relevant investigations, and other additional useful information (e.g. references, links. It represents an important and actual topic of investigation for designers and manufacturers considering that the new EU regulation on the approval and market surveillance of quadricycles will soon enter in force providing conclusive requirements for functional safety environmental protection of these promising vehicles.

Annual report on occupational safety 1985

International Nuclear Information System (INIS)

1986-09-01

This report presents information on occupational safety relating to the Company's employees for the year 1985, and compares data with figures for the previous year. The following headings are listed: principle activities of BNFL, general policy and organisation, radiological safety, including whole body, skin and extremity, and internal organ doses, non-radiological safety, incidents reportable to the health and safety executive. (U.K.)

Evaluation of features to support safety and quality in general practice clinical software

Science.gov (United States)

2011-01-01

Background Electronic prescribing is now the norm in many countries. We wished to find out if clinical software systems used by general practitioners in Australia include features (functional capabilities and other characteristics) that facilitate improved patient safety and care, with a focus on quality use of medicines. Methods Seven clinical software systems used in general practice were evaluated. Fifty software features that were previously rated as likely to have a high impact on safety and/or quality of care in general practice were tested and are reported here. Results The range of results for the implementation of 50 features across the 7 clinical software systems was as follows: 17-31 features (34-62%) were fully implemented, 9-13 (18-26%) partially implemented, and 9-20 (18-40%) not implemented. Key findings included: Access to evidence based drug and therapeutic information was limited. Decision support for prescribing was available but varied markedly between systems. During prescribing there was potential for medicine mis-selection in some systems, and linking a medicine with its indication was optional. The definition of 'current medicines' versus 'past medicines' was not always clear. There were limited resources for patients, and some medicines lists for patients were suboptimal. Results were provided to the software vendors, who were keen to improve their systems. Conclusions The clinical systems tested lack some of the features expected to support patient safety and quality of care. Standards and certification for clinical software would ensure that safety features are present and that there is a minimum level of clinical functionality that clinicians could expect to find in any system.

Communication and general concern criterion prior to activation of the rapid response team: a grounded theory.

Science.gov (United States)

Martland, Jarrad; Chamberlain, Diane; Hutton, Alison; Smigielski, Michael

2016-11-01

Objective Patients commonly show signs and symptoms of deterioration for hours or days before cardiorespiratory arrest. Rapid response teams (RRT) were created to improve recognition and response to patient deterioration in these situations. Activation criteria include vital signs or 'general concern' by a clinician or family member. The general concern criterion for RRT activation accounts for nearly one-third of all RRT activity, and although it is well established that communication deficits between staff can contribute to poorer outcomes for patients, there is little evidence pertaining to communication and its effects on the general concern RRT activation. Thus, the aim of the present study was to develop a substantive grounded theory related to the communication process between clinicians that preceded the activation of an RRT when general concern criterion was used. Methods Qualitative grounded theory involved collection of three types of data details namely personal notes from participants in focus groups with white board notes from discussions and audio recordings of the focus groups sessions. Focus groups were conducted with participants exploring issues associated with clinician communication and how it related to the activation of an RRT using the general concern criterion. Results The three main phases of coding (i.e. open, axial and selective coding) analysis identified 322 separate open codes. The strongest theme contributed to a theory of ineffective communication and decreased psychological safety, namely that 'In the absence of effective communication there is a subsequent increase in anxiety, fear or concern that can be directly attributed to the activation of an RRT using the 'general concern' criterion'. The RRT filled cultural and process deficiencies in the compliance with an escalation protocol. Issues such as 'not for resuscitation documentation' and 'inability to establish communication with and between medical or nursing personnel' rated

Fourteenth general report on the activities of the European Communities in 1980

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

The general economic situation, Community achievements at home, enlargement of the Community, and the correlations of the Community and world events in 1980 are described. Activities of institutions connected with the Communities and financing Community activities in 1980 are also described. Other topics covered concerning the Community are: economic and monetary policy and internal market and industrial affairs, customs union, competition, financial institutions and taxation, employment and social policy, regional policies, environmental affairs, agriculture, fisheries, transport policy, energy, safety, research, and information markets. Considerations with countries (Greece, Spain, Portugal) which have applied or are being accepted as members are reviewed. Developments in the Community law are discussed. A section, The Year in Brief, is included. (MCW)

Field studies of safety security rescue technologies through training and response activities

Science.gov (United States)

Murphy, Robin R.; Stover, Sam

2006-05-01

This paper describes the field-oriented philosophy of the Institute for Safety Security Rescue Technology (iSSRT) and summarizes the activities and lessons learned during calendar year 2005 of its two centers: the Center for Robot-Assisted Search and Rescue and the NSF Safety Security Rescue industry/university cooperative research center. In 2005, iSSRT participated in four responses (La Conchita, CA, Mudslides, Hurricane Dennis, Hurricane Katrina, Hurricane Wilma) and conducted three field experiments (NJTF-1, Camp Hurricane, Richmond, MO). The lessons learned covered mobility, operator control units, wireless communications, and general reliability. The work has collectively identified six emerging issues for future work. Based on these studies, a 10-hour, 1 continuing education unit credit course on rescue robotics has been created and is available. Rescue robots and sensors are available for loan upon request.

On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

International Nuclear Information System (INIS)

Svensson, Ola; Salo, Ilkka; Allwin, Pernilla

2004-11-01

A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

The Inspector General's report on Nuclear Safety and Radiation Protection 2017

International Nuclear Information System (INIS)

2018-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2017; 2 - Nuclear safety results; 3 - Nuclear safety priority affirmed; 4 - Risk prevention: important to remain vigilant; 5 - Adapting people skills; 6 - Operating experience: contrasting approaches; 7 - Operations fundamentals to be reaffirmed; 8 - Importance of working closely with contract partners; 9 - Engineering support for the French fleet and new-build projects; 10 - Spares: an area for greater engagement by owners on-site; 11 - Appendices

SOS-1 seminar about safety culture

International Nuclear Information System (INIS)

Wahlstroem, B.; Hammar, L.

2000-01-01

The aim of the seminar was to discuss safety culture in nuclear power utilities, and to exchange experiences about how the term safety culture is accepted by the personnel. The titles of the presentations are: 1) Organisational culture. General ideas as basis for organising; 2) Safety culture - ability and will; 3) View on safety culture at Swedish and Finnish nuclear power plants; 4) Safety culture at Barsebaeck Power Company; 5) Safety culture at Olkiluoto Nuclear Power Plant; 6) How do we improve the safety culture at OKG AB?; 7) Safety culture activities at Ringhals; 8) Aspects in relation to safety culture; 9) Development of regulatory activities/effectiveness of STUK - development as an aspect of culture; 10) Organisational culture research at STUK's Department of Nuclear Reactor Regulation; 11) The IAEA safety culture services; 12) Industrial safety - different perspectives and cultures. (EHS)

Safety research activities on radioactive waste management in JNES

International Nuclear Information System (INIS)

Otsuka, Ichiro; Aoki, Hiroomi; Suko, Takeshi; Onishi, Yuko; Masuda, Yusuke; Kato, Masami

2010-01-01

Research activities in safety regulation of radioactive waste management are presented. Major activities are as follows. As for the geological disposal, major research areas are, developing 'safety indicators' to judge the adequacy of site investigation results presented by an implementer (NUMO), compiling basic requirements of safety design and safety assessment needed to make a safety review of the license application and developing an independent safety assessment methodology. In proceeding research, JNES, Japan Atomic Energy Agency (JAEA) and the National Institute of Advanced Industrial Science and Technology (AIST) signed an agreement of cooperative study on geological disposal in 2007. One of the ongoing joint studies under this agreement has been aimed at investigating regional-scale hydrogeological modeling using JAEA's Horonobe Underground Research Center. In the intermediate depth disposal, JNES conducted example analysis of reference facility and submitted the result to Nuclear Safety Commission of Japan (NSC). JNES is also listing issues to be addressed in the safety review of the license application and tries to make criteria of the review. Furthermore, JNES is developing analysis tool to evaluate long term safety of the facility and conducting an experiment to investigate long term behavior of engineered barrier system. In the near surface disposal of waste package, it must be confirmed by a regulatory inspector whether each package meets safety requirements. JNES continuously updates the confirmation methodology depending on new processing technologies. The clearance system was established in 2005. Two stages of regulatory involvement were adapted, 1) approval for measurement and judgment methods developed by the nuclear operator and 2) confirmation of measurement and judgment results based on approved methods. JNES is developing verification methodology for each stage. As for decommissioning, based on the regulatory needs and a research program

Regulatory Activities on Civil Nuclear Safety Equipment in China

International Nuclear Information System (INIS)

Gaoshang, Lu; Choi, Kwang Sik

2011-01-01

It is stipulated in IAEA Fundamental Safety Principles (SF1) that the fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. The fundamental safety objective applies for all facilities and activities and for all stages over the lifetime of a facility or radiation source, including planning, sitting, design, manufacturing, construction, commissioning and operation, as well as decommissioning and closure. So, according to the requirement, the related activities such as design, manufacturing, installation and non-destructive test that conducted on civil nuclear equipment should be well controlled by the vendors, the owner of the nuclear power plants and the regulatory body. To insure the quality of those equipment, Chinese government had taken a series of measures to regulate the related activities on them

Application of the management system for facilities and activities. Safety guide

International Nuclear Information System (INIS)

2006-01-01

This Safety Guide supports the Safety Requirements publication on The Management System for Facilities and Activities. It provides generic guidance to aid in establishing, implementing, assessing and continually improving a management system that complies with the requirements established. In addition to this Safety Guide, there are a number of Safety Guides for specific technical areas. Together these provide all the guidance necessary for implementing these requirements. This publication supersedes Safety Series No. 50-SG-Q1-Q7 (1996). The guidance provided here may be used by organizations in the following ways: - To assist in the development of the management systems of organizations directly responsible for operating facilities and activities and providing services for: Nuclear facilities; Activities using sources of ionizing radiation; Radioactive waste management; The transport of radioactive material; Radiation protection activities; Any other practices or circumstances in which people may be exposed to radiation from naturally occurring or artificial sources; The regulation of such facilities and activities; - To assist in the development of the management systems of the relevant regulatory bodies; - By the operator, to specify to a supplier, via contractual documentation, any guidance of this Safety Guide that should be included in the supplier's management system for the supply and delivery of products

Study of industry safety management

International Nuclear Information System (INIS)

Park, Pil Su

1987-06-01

This book deals with general remarks, industrial accidents, statistics of industrial accidents, unsafe actions, making machinery and facilities safe, safe activities, having working environment safe, survey of industrial accidents and analysis of causes, system of safety management and operations, safety management planning, safety education, human engineering such as human-machines system, system safety, and costs of disaster losses. It lastly adds individual protective equipment and working clothes including protect equipment for eyes, face, hands, arms and feet.

International assistance to upgrade the safety of Soviet-designed nuclear power plants. Selected activities in Eastern and Central Europe and the countries of the former Soviet Union

International Nuclear Information System (INIS)

Gillen, V.

1993-12-01

The overview is merely a snapshot of nuclear safety activities to assist the countries of Eastern and Central Europe and the former Soviet Union. While many other activities are planned or ongoing, this publication is meant to provide a general overview of the world community's commitment to improving the safety of Soviet-designed nuclear reactors

Safety risk assessment for vertical concrete formwork activities in civil engineering construction.

Science.gov (United States)

López-Arquillos, Antonio; Rubio-Romero, Juan Carlos; Gibb, Alistair G F; Gambatese, John A

2014-01-01

The construction sector has one of the worst occupational health and safety records in Europe. Of all construction tasks, formwork activities are associated with a high frequency of accidents and injuries. This paper presents an investigation of the activities and related safety risks present in vertical formwork for in-situ concrete construction in the civil engineering sector. Using the methodology of staticized groups, twelve activities and ten safety risks were identified and validated by experts. Every safety risk identified in this manner was quantified for each activity using binary methodology according to the frequency and severity scales developed in prior research. A panel of experts was selected according to the relevant literature on staticized groups. The results obtained show that the activities with the highest risk in vertical formwork tasks are: Plumbing and leveling of forms, cutting of material, handling materials with cranes, and climbing or descending ladders. The most dangerous health and safety risks detected were falls from height, cutting and overexertion. The research findings provide construction practitioners with further evidence of the hazardous activities associated with concrete formwork construction and a starting point for targeting worker health and safety programmes.

On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Svensson, Ola; Salo, Ilkka; Allwin, Pernilla (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

2004-11-15

A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

Crime, perceived safety, and physical activity: A meta-analysis.

Science.gov (United States)

Rees-Punia, Erika; Hathaway, Elizabeth D; Gay, Jennifer L

2018-06-01

Perceived safety from crime and objectively-measured crime rates may be associated with physical inactivity. The purpose of this meta-analysis is to estimate the odds of accumulating high levels of physical activity (PA) when the perception of safety from crime is high and when objectively-measured crime is high. Peer-reviewed studies were identified through PubMed, Web of Science, ProQuest Criminal Justice, and ScienceDirect from earliest record through 2016. Included studies measured total PA, leisure-time PA, or walking in addition to perceived safety from crime or objective measures of crime. Mean odds ratios were aggregated with random effects models, and meta-regression was used to examine effects of potential moderators: country, age, and crime/PA measure. Sixteen cross-sectional studies yielded sixteen effects for perceived safety from crime and four effects for objective crime. Those reporting feeling safe from crime had a 27% greater odds of achieving higher levels of physical activity (OR=1.27 [1.08, 1.49]), and those living in areas with higher objectively-measured crime had a 28% reduced odds of achieving higher levels of physical activity (OR=0.72 [0.61, 0.83]). Effects of perceived safety were highly heterogeneous (I 2 =94.09%), but explored moderators were not statistically significant, likely because of the small sample size. Despite the limited number of effects suitable for aggregation, the mean association between perceived safety and PA was significant. As it seems likely that perceived lack of safety from crime constrains PA behaviors, future research exploring moderators of this association may help guide public health recommendations and interventions. Copyright © 2017 Elsevier Inc. All rights reserved.

Specialists' meeting on passive and active safety features of LMFRs

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-07-01

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

Specialists' meeting on passive and active safety features of LMFRs

International Nuclear Information System (INIS)

1991-01-01

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

Nuclear power reactor safety research activities in CIAE

International Nuclear Information System (INIS)

Pu Shendi; Huang Yucai; Xu Hanming; Zhang Zhongyue

1994-01-01

The power reactor safety research activities in CIAE are briefly reviewed. The research work performed in 1980's and 1990's is mainly emphasised, which is closely related to the design, construction and licensing review of Qinshan Nuclear Power Plant and the safety review of Guangdong Nuclear Power Station. Major achievements in the area of thermohydraulics, nuclear fuel, probabilistic safety assessment and severe accident researches are summarized. The foreseeable research plan for the near future, relating to the design and construction of 600 MWe PWR NPP at Qinshan Site (phase II development) is outlined

Activities of the PNC Nuclear Safety Working Group

International Nuclear Information System (INIS)

Kato, W.Y.

1991-01-01

The Nuclear Safety Working Group of the Pacific Nuclear Council promotes nuclear safety cooperation among its members. Status of safety research, emergency planning, development of lists of technical experts, severe accident prevention and mitigation have been the topics of discussion in the NSWG. This paper reviews and compares the severe accident prevention and mitigation program activities in some of the areas of the Pacific Basin region based on papers presented at a special session organized by the NSWG at an ANS Topical Meeting as well as papers from other sources

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.

The safety of high activity long life nuclear waste

International Nuclear Information System (INIS)

Devillers, Ch.

1998-01-01

The article concerns the deep geological storage for managing high activity long life nuclear waste. He puts forward a context giving a structure to the discussions of those involved concerning an assessment of the safety of a deep geological deposit project. Three main aspects are put forward. The risks for future generations and the time scales to be considered: briefly, the deposit needs to satisfy two functions for protecting man and the environment, namely firstly isolating high activity radionuclides from the biosphere during the time required for their radioactive decay (about ten thousands years), and secondly delay and dilute long life radionuclides without any a priori time limit so as to reduce their effects in the biosphere to extremely low levels. The risks are linked to possible failures of the containment barriers whose causes need to be analysed and be provided against by suitable provisions concerning their design. The definition of these design provisions requires an in depth examination of uncertain elements. The main causes of uncertainty are listed according to the scale of time in question, that is O-10,000 years, 10,000-100,000 years and beyond 100,000 years, stressing the importance of selecting a stable geological site and more generally a solid concept that is not very sensitive in uncertainties. Beyond 100,000 years the extent of uncertainties no longer makes it possible to make realistic predictions. It is thus necessary to consider the alternative scenarios concerning geological and climatic changes and the corresponding increasing risks of radionuclides. The risks in question may be relativized by realizing that on this time scale, the residual activities of soluble and insoluble alpha and beta emitters are comparable to those of a storage centre located on the surface at the end of the monitoring period. Finally, the article considers the approach put forward concerning the safety of a deep geological storage advocated by the French

Nuclear Safety Regulations

International Nuclear Information System (INIS)

Novosel, N.; Prah, M.

2008-01-01

performed. This Ordinance regulates nuclear safety and protection conditions for siting, design, construction, use and decommissioning of a facility in which a nuclear activity is performed. This Ordinance defines facilities in which a nuclear activity is performed. Beside general conditions for siting, design, construction, use and decommissioning of a facility in which a nuclear activity is performed, this Ordinance regulates specific conditions for siting, design, construction, use and decommissioning of nuclear power plants or facilities with nuclear reactors and for radioactive waste disposal facilities.(author)

Multimegawatt Space Reactor Safety

International Nuclear Information System (INIS)

Stanley, M.L.

1989-01-01

The Multimegawatt (MMW) Space Reactor Project supports the Strategic Defense Initiative Office requirement to provide reliable, safe, cost-effective, electrical power in the MMW range. Specifically, power may be used for neutral particle beams, free electron lasers, electromagnetic launchers, and orbital transfer vehicles. This power plant technology may also apply to the electrical power required for other uses such as deep-space probes and planetary exploration. The Multimegawatt Space Reactor Project, the Thermionic Fuel Element Verification Program, and Centaurus Program all support the Multimegawatt Space Nuclear Power Program and form an important part of the US Department of Energy's (DOE's) space and defense power systems activities. A major objective of the MMW project is the development of a reference flight system design that provides the desired levels of public safety, health protection, and special nuclear material (SNM) protection when used during its designated missions. The safety requirements for the MMW project are a hierarchy of requirements that consist of safety requirements/regulations, a safety policy, general safety criteria, safety technical specifications, safety design specifications, and the system design. This paper describes the strategy and philosophy behind the development of the safety requirements imposed upon the MMW concept developers. The safety organization, safety policy, generic safety issues, general safety criteria, and the safety technical specifications are discussed

Implementing and measuring safety goals and safety culture. 4. Utility's Activities for Better Safety Culture After the JCO Accident

International Nuclear Information System (INIS)

Omoto, Akira

2001-01-01

The criticality accident at the JCO plant prompted the Government to enact a law for nuclear emergency preparedness. The nuclear industry established NSnet to facilitate opportunities for peer review among its members. This paper describes the activities by NSnet and TEPCO's Kashiwazaki-Kariwa nuclear power station (NPS) for a better safety culture. Created as a voluntary organization by the nuclear industry in 1999, NSnet has 35 members and is assisted by CRIEPI and NUPEC for its activities relevant to human factors. Given the fact that nuclear facility operators not belonging to WANO had no institutional system available for exchange of experiences and good practices for better safety among themselves, NSnet's activities focus on peer review by member organizations and onsite seminars. Starting April 2000 with visits to three fuel fabricators, NSnet intends to have 23 peer-review visits in 2 yr (Ref. 1). The six-member review team stays on-site for 4 days, during which time they review-using guidelines available from WANO and IAEA-OSART-six areas: organization/management, emergency preparedness, education/training, operation/ maintenance, protection against occupational radiation exposure, and prevention of accidents. A series of on-site seminars is held at members' nuclear facilities, to which NSnet dispatches experts for lectures. NSnet plans to hold such seminars twice per month. Other activities include information-sharing through a newsletter, a Web site (www. nsnet.gr.jp), and others. Although considerable differences exist in the design and the practices in operation/maintenance between power reactors and JCO, utilities can extract lessons from the accident that will be worth consideration for their own facilities in the areas of safety culture, education and training, and interface between design and operation. This thinking prompted the Nuclear Safety Promotion Center at Kashiwazaki-Kariwa NPS, to which the author belonged at that time, to launch the

PA activity by using nuclear power plant safety demonstration and analysis

International Nuclear Information System (INIS)

Tsuchiya, Mitsuo; Kamimae, Rie

1999-01-01

INS/NUPEC presents one of Public acceptance (PA) methods for nuclear power in Japan, 'PA activity by using Nuclear Power Plant Safety Demonstration and Analysis', by using one of videos which is explained and analyzed accident events (Loss of Coolant Accident). Safety regulations of The National Government are strictly implemented in licensing at each of basic design and detailed design. To support safety regulation activities conducted by the National Government, INS/NLTPEC continuously implement Safety demonstration and analysis. With safety demonstration and analysis, made by assuming some abnormal conditions, what impacts could be produced by the assumed conditions are forecast based on specific design data on a given nuclear power plants. When analysis results compared with relevant decision criteria, the safety of nuclear power plants is confirmed. The decision criteria are designed to help judge if or not safety design of nuclear power plants is properly made. The decision criteria are set in the safety examination guidelines by taking sufficient safety allowance based on the latest technical knowledge obtained from a wide range of tests and safety studies. Safety demonstration and analysis is made by taking the procedure which are summarized in this presentation. In Japan, various PA (Public Acceptance) pamphlets and videos on nuclear energy have been published. But many of them focused on such topics as necessity or importance of nuclear energy, basic principles of nuclear power generation, etc., and a few described safety evaluation particularly of abnormal and accident events in accordance with the regulatory requirements. In this background, INS/NUPEC has been making efforts to prepare PA pamphlets and videos to explain the safety of nuclear power plants, to be simple and concrete enough, using various analytical computations for abnormal and accident events. In results, PA activity of INS/NUPEC is evaluated highly by the people

Communication and Consultation with Interested Parties by the Regulatory Body. General Safety Guide

International Nuclear Information System (INIS)

2017-01-01

This Safety Guide provides recommendations on meeting the safety requirements concerning communication and consultation with the public and other interested parties by the regulatory body about the possible radiation risks associated with facilities and activities, and about processes and decisions of the regulatory body. The Safety Guide can be used by authorized parties in circumstances where there are regulatory requirements placed on them for communication and consultation. It may also be used by other organizations or individuals considering their responsibilities for communication and consultation with interested parties.

General design safety principles for nuclear power plants

International Nuclear Information System (INIS)

1986-01-01

This Safety Guide provides the safety principles and the approach that have been used to implement the Code in the Safety Guides. These safety principles and the approach are tied closely to the safety analyses needed to assist the design process, and are used to verify the adequacy of nuclear power plant designs. This Guide also provides a framework for the use of other design Safety Guides. However, although it explains the principles on which the other Safety Guides are based, the requirements for specific applications of these principles are mostly found in the other Guides

The Inspector General's report on Nuclear Safety and Radiation Protection 2014

International Nuclear Information System (INIS)

2015-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2014; 2- Contrasting trends in nuclear safety in different sets of plants; 3 - Making safety culture central to management; 4 - Towards an integrated approach to risk management; 5 - Relying on professional unified operations; 6 - The quest for robust maintenance; 7 - Nuclear engineering: a major asset for the operator; 8 - Nuclear managers - confidence builders; 9 - on course for reactor operation beyond 40 years in France; 10 - Service life challenges in the UK; 11 - Preparing the future: from the EPR to other new models; 12 - Noteworthy operational events; 13- Appendices: Results for the nuclear fleets (EDF SA, EDF Energy; Maps of the nuclear power plants(EDF SA, EDF Energy); Key dates for the nuclear units (EDF SA, EDF Energy); Abbreviations

The Inspector General's report on Nuclear Safety and Radiation Protection 2015

International Nuclear Information System (INIS)

2016-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2015; 2 - Operational safety: mixed results; 3 - Nuclear safety clearly prioritised; 4 - Risk prevention: progress in France; 5 - Reinforced emergency preparedness post-Fukushima; 6 - Fire prevention: still a weak link; 7 - Continuous investment in training and careers; 8 - Using maintenance to leverage improved operational quality; 9 - Chemistry in France: a transition in need of strong support; 10 - Decommissioning projects are progressing; 11 - EPRs in China, France and the UK; 12 - Preparing for the future; 13 - A window on the world; 14 - Appendices: Results for the nuclear fleets (EDF SA, EDF Energy; Maps of the nuclear power plants(EDF SA, EDF Energy); Key dates for the nuclear units (EDF SA, EDF Energy); Abbreviations

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

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

Addressing the fundamental issues in reliability evaluation of passive safety of AP1000 for a comparison with active safety of PWR

International Nuclear Information System (INIS)

Hashim Muhammad; Yoshikawa, Hidekazu; Yang Ming

2013-01-01

Passive safety systems adopted in advanced Pressurized Water Reactor (PWR), such as AP1000 and EPR, should attain higher reliability than the existing active safety systems of the conventional PWR. The objective of this study is to discuss the fundamental issues relating to the reliability evaluation of AP1000 passive safety systems for a comparison with the active safety systems of conventional PWR, based on several aspects. First, comparisons between conventional PWR and AP1000 are made from the both aspects of safety design and cost reduction. The main differences between these PWR plants exist in the configurations of safety systems: AP1000 employs the passive safety system while reducing the number of active systems. Second, the safety of AP1000 is discussed from the aspect of severe accident prevention in the event of large break loss of coolant accidents (LOCA). Third, detailed fundamental issues on reliability evaluation of AP1000 passive safety systems are discussed qualitatively by using single loop models of safety systems of both PWRs plants. Lastly, methodology to conduct quantitative estimation of dynamic reliability for AP1000 passive safety systems in LOCA condition is discussed, in order to evaluate the reliability of AP1000 in future by a success-path-based reliability analysis method (i.e., GO-FLOW). (author)

A review of the nuclear safety activities in Italy

International Nuclear Information System (INIS)

Merelli, A.

1989-01-01

A review of research programs carried out in Italy in the field of nuclear reactor safety was done in 1986, in the frame of the activities of the Commission of the European Communities, the International Energy Agency and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. The report contains information on these programs, as well as information on the organization of safety research in Italy and the evolution of safety research programs

IAEA activity related to safety of nuclear desalination

International Nuclear Information System (INIS)

Gasparini, M.

2000-01-01

The nuclear plants for desalination to be built in the future will have to meet the standards of safety required for the best nuclear power plants currently in operation or being designed. The current safety approach, based on the achievement of the fundamental safety functions and defence in depth strategy, has been shown to be a sound foundation for the safety and protection of public health, and gives the plant the capability of dealing with a large variety of sequences, even beyond the design basis. The Department of Nuclear Safety of the IAEA is involved in many activities, the most important of which are to establish safety standards, and to provide various safety services and technical knowledge in many Technical Co-operation assistance projects. The department is also involved in other safety areas, notably in the field of future reactors. The IAEA is carrying out a project on the safety of new generation reactors, including those used for desalination, with the objective of fostering an exchange of information on safety approaches, promoting harmonization among Member States and contributing towards the development and revision of safety standards and guidelines for nuclear power plant design. The safety, regulatory and environmental concerns in nuclear powered desalination are those related directly to nuclear power plants, with due consideration given to the coupling process. The protection of product water against radioactive contamination must be ensured. An effective infrastructure, including appropriate training, a legal framework and regulatory regime, is a prerequisite to considering use of nuclear power for desalination plants, also in those countries with limited industrial infrastructures and little experience in nuclear technology or safety. (author)

Improvement of the safety level of installations with the generalization of procedures

International Nuclear Information System (INIS)

Cornille, Y.; Dupraz, B.; Schektman, N.

1986-06-01

The generalization of control procedures to the largest possible spectra of accidental situations which is being developed on pressurized water reactor units will allow to increase the safety level of these installations. This improvement has been quantified for some situations pointing out an appreciable mitigation of meltdown risk which could result. A new improvement is aimed with the definition and the utilization of new procedures ''by states'' which will allow an optimized treatment of situations resulting from multiple failures, now treated in the procedures SPI - SPU - U1. The needs related to these procedures and their development led to joint research and development programs between Electricite de France and the Institute of Protection and Nuclear Safety [fr

Manpower analysis in transportation safety. Final report

Energy Technology Data Exchange (ETDEWEB)

Bauer, C.S.; Bowden, H.M.; Colford, C.A.; DeFilipps, P.J.; Dennis, J.D.; Ehlert, A.K.; Popkin, H.A.; Schrader, G.F.; Smith, Q.N.

1977-05-01

The project described provides a manpower review of national, state and local needs for safety skills, and projects future manning levels for transportation safety personnel in both the public and private sectors. Survey information revealed that there are currently approximately 121,000 persons employed directly in transportation safety occupations within the air carrier, highway and traffic safety, motor carrier, pipeline, rail carrier, and marine carrier transportation industry groups. The projected need for 1980 is over 145,000 of which over 80 percent will be in highway safety. An analysis of transportation tasks is included, and shows ten general categories about which the majority of safety activities are focused. A skills analysis shows a generally high level of educational background and several years of experience are required for most transportation safety jobs. An overall review of safety programs in the transportation industry is included, together with chapters on the individual transportation modes.

Operational safety analysis status of Novi Han repository

International Nuclear Information System (INIS)

Boiadjiev, A.

2000-01-01

This article presents the status of the safety studies and activities related to Novi Han repository. The case of this facility is such that no clear boundary exists between post-closure safety assessment and operational safety assessment. The major findings of these activities are given. The Safety Analysis Report (SAR) for Novi Han repository is developed by Risk Engineering Ltd. under a contract with the Committee on the Use of Atomic Energy for Peaceful Purposes. The general structure and main conclusions and recommendations of the SAR are presented. (author)

Health and safety annual report 1987

International Nuclear Information System (INIS)

1988-01-01

The principal activities and organisation of BNFL are reviewed in relation to the impact these activities have on the workforce, members of the general public and the environment, together with services for occupational safety within the company. (author)

SACRD: a data base for fast reactor safety computer codes, general description

International Nuclear Information System (INIS)

Greene, N.M.; Forsberg, V.M.; Raiford, G.B.; Arwood, J.W.; Simpson, D.B.; Flanagan, G.F.

1979-01-01

SACRD is a data base of material properties and other handbook data needed in computer codes used for fast reactor safety studies. Data are available in the thermodynamics, heat transfer, fluid mechanics, structural mechanics, aerosol transport, meteorology, neutronics, and dosimetry areas. Tabular, graphical and parameterized data are provided in many cases. A general description of the SACRD system is presented in the report

29 CFR 780.205 - Nursery activities generally.

Science.gov (United States)

2010-07-01

... 29 Labor 3 2010-07-01 2010-07-01 false Nursery activities generally. 780.205 Section 780.205 Labor... as It Relates to Specific Situations Nursery and Landscaping Operations § 780.205 Nursery activities generally. The employees of a nursery who are engaged in the following activities are employed in...

System analysis of vehicle active safety problem

Science.gov (United States)

Buznikov, S. E.

2018-02-01

The problem of the road transport safety affects the vital interests of the most of the population and is characterized by a global level of significance. The system analysis of problem of creation of competitive active vehicle safety systems is presented as an interrelated complex of tasks of multi-criterion optimization and dynamic stabilization of the state variables of a controlled object. Solving them requires generation of all possible variants of technical solutions within the software and hardware domains and synthesis of the control, which is close to optimum. For implementing the task of the system analysis the Zwicky “morphological box” method is used. Creation of comprehensive active safety systems involves solution of the problem of preventing typical collisions. For solving it, a structured set of collisions is introduced with its elements being generated also using the Zwicky “morphological box” method. The obstacle speed, the longitudinal acceleration of the controlled object and the unpredictable changes in its movement direction due to certain faults, the road surface condition and the control errors are taken as structure variables that characterize the conditions of collisions. The conditions for preventing typical collisions are presented as inequalities for physical variables that define the state vector of the object and its dynamic limits.

Survey Result for the Safety Culture Attitude of HANARO in 2008

International Nuclear Information System (INIS)

Wu, Jong Sup; An, Seok Hwa

2009-01-01

One of the important aims of a nuclear management system is to foster a strong safety culture. The safety culture activities for HANARO have been implemented and the importance of safety management in nuclear activities has also been emphasized since its first operation. HANARO developed its own safety culture indicators by referring to the IAEA's documents for the purpose of the evaluation of the safety culture attitude. In June 2008 a survey on the safety culture was conducted based on the new safety culture indicators. The result of the survey shows that the safety culture activities contribute positively to its safe operation. But it is necessary to encourage some activities like training, resources and organizational culture. The survey was helpful to understand the general trends of the safety attitudes and to set the safety culture activities necessary for the improvement of its safe operation

Safety Culture Improvement Activities of YGN 3 and 4

International Nuclear Information System (INIS)

Cho, Il Hoon

2006-01-01

In nuclear power industry all over the world, we can never overemphasize the importance of nuclear safety. After the Chernobyl accident occurred in 1986, Korean nuclear energy industry had made every effort to enhance nuclear safety culture further. And, as a result of the efforts, Korean government declared the five principles for the nuclear energy safety regulation, which were included in the Nuclear Energy Safety Policy Statement published in 1994. In 2001, through the announcement of Nuclear Safety Charter for the peaceful use of nuclear energy, the Ministry of Science and Technology proclaimed at home and abroad that the protection of citizens and environment by securing nuclear safety should be the highest priority in nuclear energy industry. Occupying almost 40% share of domestic electricity generation, Korea Hydro and Nuclear Power Co. decided 'Safety Top Priority Management' as president's management policy, and clearly presented the safety goal to the personnel. By this, the management can effectively place stress on securing safety, which is our highest priority and the only way to win public confidence toward nuclear energy industry. This is prepared to shortly introduce the activities for improving safety culture in Yonggwang Nuclear Power unit 3 and 4 (YGN 3 and 4)

Study on application of safety checklist in preventive maintenance activities

International Nuclear Information System (INIS)

Shi Jin; Chen Song; Liu Jingquan

2013-01-01

The paper describes the principles and the characteristics of safety checklist as a risk evaluation method. Examples of application of safety checklists to preventive maintenance activities such as criteria comparison and checkup items in place in nuclear power plants are illustrated in details with issues appeared in the checklist establishment. Checklist has a good application in the RCM analysis or in the actual preventive maintenance program for Chashma Nuclear Power Plant indicated by concrete instances. In the light of safety checklist which is used to sustain preventive maintenance as a simple and applicable risk analysis approach, we can get deep knowledge of risks of nuclear power plant to perfect preventive maintenance activities. (authors)

Road identification for its-integrated systems of automotive active safety

Directory of Open Access Journals (Sweden)

V. Ivanov

2005-04-01

Full Text Available The paper discusses several aspects of active safety control for automotive application. Particular emphasis is placed on the fuzzy logic determination of friction properties of a tyre-road contact. An example of vehicle control systems equipped with off-board sensors of road roughness, temperature, moisture and rain intensity demonstrates the implementation of this approach. The paper proposes conceptual solutions for preventive active safety control applied to vehicles which are integrated in an intelligent transportation system.

Laboratory Safety Awareness Among General Physics Undergraduate Students

Directory of Open Access Journals (Sweden)

C. O. Ponferrada

2017-12-01

Full Text Available Safety awareness in the laboratory is essential to reduce occupational risks. This study was conducted to determine the students’ safety awareness in a Physics laboratory. This study determined the student perception towards safety awareness by factors of gender and college from which students are enrolled. A sum of 324 students enrolled in Physics10 (Mechanics and Heat and Physics11 (Electricity and Magnetism in the Mindanao University of Science and Technology (MUST were randomly selected as survey respondents. A modified survey questionnaire was used as research instrument. The results show that the students had positive level of safety awareness and perceived positively on the preventive measures to reduce laboratory risk. Further, regardless of gender students enrolled in Physics 10 were more positively aware towards safety awareness than students enrolled in Physics 11. Similarly, a variation among the students perception towards safety awareness from the College of Engineering and Architecture (CEA and College of Industrial and Information Technology (CIIT occurred. Overall, present findings indicate a need to introduce laboratory safety awareness in Physics classes.

Patient safety in primary care: a survey of general practitioners in the Netherlands

Directory of Open Access Journals (Sweden)

Wensing Michel

2010-01-01

Full Text Available Abstract Background Primary care encompasses many different clinical domains and patient groups, which means that patient safety in primary care may be equally broad. Previous research on safety in primary care has focused on medication safety and incident reporting. In this study, the views of general practitioners (GPs on patient safety were examined. Methods A web-based survey of a sample of GPs was undertaken. The items were derived from aspects of patient safety issues identified in a prior interview study. The questionnaire used 10 clinical cases and 15 potential risk factors to explore GPs' views on patient safety. Results A total of 68 GPs responded (51.5% response rate. None of the clinical cases was uniformly judged as particularly safe or unsafe by the GPs. Cases judged to be unsafe by a majority of the GPs concerned either the maintenance of medical records or prescription and monitoring of medication. Cases which only a few GPs judged as unsafe concerned hygiene, the diagnostic process, prevention and communication. The risk factors most frequently judged to constitute a threat to patient safety were a poor doctor-patient relationship, insufficient continuing education on the part of the GP and a patient age over 75 years. Language barriers and polypharmacy also scored high. Deviation from evidence-based guidelines and patient privacy in the reception/waiting room were not perceived as risk factors by most of the GPs. Conclusion The views of GPs on safety and risk in primary care did not completely match those presented in published papers and policy documents. The GPs in the present study judged a broader range of factors than in previously published research on patient safety in primary care, including a poor doctor-patient relationship, to pose a potential threat to patient safety. Other risk factors such as infection prevention, deviation from guidelines and incident reporting were judged to be less relevant than by policy

Patient safety in primary care: a survey of general practitioners in The Netherlands.

Science.gov (United States)

Gaal, Sander; Verstappen, Wim; Wensing, Michel

2010-01-21

Primary care encompasses many different clinical domains and patient groups, which means that patient safety in primary care may be equally broad. Previous research on safety in primary care has focused on medication safety and incident reporting. In this study, the views of general practitioners (GPs) on patient safety were examined. A web-based survey of a sample of GPs was undertaken. The items were derived from aspects of patient safety issues identified in a prior interview study. The questionnaire used 10 clinical cases and 15 potential risk factors to explore GPs' views on patient safety. A total of 68 GPs responded (51.5% response rate). None of the clinical cases was uniformly judged as particularly safe or unsafe by the GPs. Cases judged to be unsafe by a majority of the GPs concerned either the maintenance of medical records or prescription and monitoring of medication. Cases which only a few GPs judged as unsafe concerned hygiene, the diagnostic process, prevention and communication. The risk factors most frequently judged to constitute a threat to patient safety were a poor doctor-patient relationship, insufficient continuing education on the part of the GP and a patient age over 75 years. Language barriers and polypharmacy also scored high. Deviation from evidence-based guidelines and patient privacy in the reception/waiting room were not perceived as risk factors by most of the GPs. The views of GPs on safety and risk in primary care did not completely match those presented in published papers and policy documents. The GPs in the present study judged a broader range of factors than in previously published research on patient safety in primary care, including a poor doctor-patient relationship, to pose a potential threat to patient safety. Other risk factors such as infection prevention, deviation from guidelines and incident reporting were judged to be less relevant than by policy makers.

Revenue sources for financing transportation safety activities in Virginia : phase two, state sources.

Science.gov (United States)

1980-01-01

Senate Bill 85, an action of the 1978 General Assembly, amended the Code of Virginia to provide, in part, that the Division of Highway Safety be succeeded by the newly created Department of Transportation Safety effective July 1, 1978. In its Declara...

Safety related terms for advanced nuclear plants

International Nuclear Information System (INIS)

1995-12-01

The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

Safety related terms for advanced nuclear plants

International Nuclear Information System (INIS)

1991-09-01

The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

New Safety rules

CERN Multimedia

Safety Commission

2008-01-01

The revision of CERN Safety rules is in progress and the following new Safety rules have been issued on 15-04-2008: Safety Procedure SP-R1 Establishing, Updating and Publishing CERN Safety rules: http://cern.ch/safety-rules/SP-R1.htm; Safety Regulation SR-S Smoking at CERN: http://cern.ch/safety-rules/SR-S.htm; Safety Regulation SR-M Mechanical Equipment: http://cern.ch/safety-rules/SR-M.htm; General Safety Instruction GSI-M1 Standard Lifting Equipment: http://cern.ch/safety-rules/GSI-M1.htm; General Safety Instruction GSI-M2 Standard Pressure Equipment: http://cern.ch/safety-rules/GSI-M2.htm; General Safety Instruction GSI-M3 Special Mechanical Equipment: http://cern.ch/safety-rules/GSI-M3.htm. These documents apply to all persons under the Director General’s authority. All Safety rules are available at the web page: http://www.cern.ch/safety-rules The Safety Commission

Review of nuclear regulatory activities associated with safety culture and the management of safety in the United Kingdom

International Nuclear Information System (INIS)

Woodhouse, P.A.

1995-01-01

This paper describes some of the key regulatory activities which have taken place in the United Kingdom in recent years in the areas of safety culture and management of safety. It explains how the UK's nuclear licensing regime, regulated and enforced by the Nuclear Installations Inspectorate, (NII), provides the framework for a viable safety management system and identifies a management of safety model which a NII Task Force has developed. It finally identifies further work which is being undertaken by the NII. (author). 4 refs, 2 figs

Nuclear Safety Culture & Leadership in Slovenske Elektrarne

International Nuclear Information System (INIS)

Janko, P.

2016-01-01

This presentation shows practically how nuclear safety culture is maintained and assessed in Slovenske elektrarne, supported by human performance program and leadership model. Safety is the highest priority and it must be driven by the Leaders in the field. Human Performance is key to safety and therefore key to our success. Safety Policy of our operating organization—licence holder, is in line with international best practices and nuclear technology is recognised as special and unique. All nuclear facilities adopt a clear safety policy and are operated with overriding priority to nuclear safety, the protection of nuclear workers, the general public and the environment from risk of harm. The focus is on nuclear safety, although the same principles apply to radiological safety, industrial safety and environmental safety. Safety culture is assessed regularly based (every two years) on eight principles for strong safety culture in nuclear utilities. Encourage excellence in all plant activities and to go beyond compliance with applicable laws and regulations. Adopt management approaches embodying the principles of Continuous Improvement and risk Management is never ending activity for us. (author)

Analysis of Paks NPP Personnel Activity during Safety Related Event Sequences

International Nuclear Information System (INIS)

Bareith, A.; Hollo, Elod; Karsa, Z.; Nagy, S.

1998-01-01

Within the AGNES Project (Advanced Generic and New Evaluation of Safety) the Level-1 PSA model of the Paks NPP Unit 3 was developed in form of a detailed event tree/fault tree structure (53 initiating events, 580 event sequences, 6300 basic events are involved). This model gives a good basis for quantitative evaluation of potential consequences of actually occurred safety-related events, i.e. for precursor event studies. To make these studies possible and efficient, the current qualitative event analysis practice should be reviewed and a new additional quantitative analysis procedure and system should be developed and applied. The present paper gives an overview of the method outlined for both qualitative and quantitative analyses of the operator crew activity during off-normal situations. First, the operator performance experienced during past operational events is discussed. Sources of raw information, the qualitative evaluation process, the follow-up actions, as well as the documentation requirements are described. Second, the general concept of the proposed precursor event analysis is described. Types of modeled interactions and the considered performance influences are presented. The quantification of the potential consequences of the identified precursor events is based on the task-oriented, Level-1 PSA model of the plant unit. A precursor analysis system covering the evaluation of operator activities is now under development. Preliminary results gained during a case study evaluation of a past historical event are presented. (authors)

IAEA activities on safety aspects of NPP ageing

International Nuclear Information System (INIS)

Pachner, J.

1998-01-01

A review of IAEA activities concerned with safety aspects of nuclear power plants ageing is given for the period from 1995 to 1998 with the prospects till year 2000. Coordinated Research programs were conducted on Management Ageing of Concrete Containment Buildings; Management of Ageing of In-Containment I and C cables. TECDOCs were published on Assessment and Management of Ageing of Major NPP Components Important for Safety of CANDU, PWR and BWR NPPs. Technical Committee Meetings and Interregional training courses concerned with the same subjects were held

IAEA safety standards and approach to safety of advanced reactors

International Nuclear Information System (INIS)

Gasparini, M.

2004-01-01

The paper presents an overview of the IAEA safety standards including their overall structure and purpose. A detailed presentation is devoted to the general approach to safety that is embodied in the current safety requirements for the design of nuclear power plants. A safety approach is proposed for the future. This approach can be used as reference for a safe design, for safety assessment and for the preparation of the safety requirements. The method proposes an integration of deterministic and risk informed concepts in the general frame of a generalized concept of safety goals and defence in depth. This methodology may provide a useful tool for the preparation of safety requirements for the design and operation of any kind of reactor including small and medium sized reactors with innovative safety features.(author)

Perspective on Secure Development Activities and Features of Safety I and C Systems

International Nuclear Information System (INIS)

Kang, Youngdoo; Yu, Yeong Jin; Kim, Hyungtae; Kwon, Yong il; Park, Yeunsoo; Choo, Jaeyul; Son, Jun Young; Jeong, Choong Heui

2015-01-01

The Enforcement Decree of the Act on Physical Protection and Radiological Emergency (ED-APPRE) was revised December 2013 to include security requirements on computer systems at nuclear facilities to protect those systems against malicious cyber-attacks. It means Cyber-Security-related measures, controls and activities of safety I and C systems against cyber-attacks shall meet the requirements of ED-APPRE. Still regulation upon inadvertent access or non-malicious modifications to the safety I and C systems is covered under the Nuclear Safety Act. The objective of this paper is to propose KINS' regulatory perspective on secure development and features against non-malicious access or modification of safety I and C systems. Secure development activities and features aim to prevent inadvertent and non-malicious access, and to prevent unwanted action from personnel or connected systems for ensuring reliable operation of safety I and C systems. Secure development activities of safety I and C systems are life cycle activities to ensure unwanted, unneeded and undocumented code is not incorporated into the systems. Secure features shall be developed, verified and qualified throughout the development life cycle

Perspective on Secure Development Activities and Features of Safety I and C Systems

Energy Technology Data Exchange (ETDEWEB)

Kang, Youngdoo; Yu, Yeong Jin; Kim, Hyungtae; Kwon, Yong il; Park, Yeunsoo; Choo, Jaeyul; Son, Jun Young; Jeong, Choong Heui [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

The Enforcement Decree of the Act on Physical Protection and Radiological Emergency (ED-APPRE) was revised December 2013 to include security requirements on computer systems at nuclear facilities to protect those systems against malicious cyber-attacks. It means Cyber-Security-related measures, controls and activities of safety I and C systems against cyber-attacks shall meet the requirements of ED-APPRE. Still regulation upon inadvertent access or non-malicious modifications to the safety I and C systems is covered under the Nuclear Safety Act. The objective of this paper is to propose KINS' regulatory perspective on secure development and features against non-malicious access or modification of safety I and C systems. Secure development activities and features aim to prevent inadvertent and non-malicious access, and to prevent unwanted action from personnel or connected systems for ensuring reliable operation of safety I and C systems. Secure development activities of safety I and C systems are life cycle activities to ensure unwanted, unneeded and undocumented code is not incorporated into the systems. Secure features shall be developed, verified and qualified throughout the development life cycle.

Blanket safety by GEMSAFE methodology

International Nuclear Information System (INIS)

Sawada, Tetsuo; Saito, Masaki

2001-01-01

General Methodology of Safety Analysis and Evaluation for Fusion Energy Systems (GEMSAFE) has been applied to a number of fusion system designs, such as R-tokamak, Fusion Experimental Reactor (FER), and the International Thermonuclear Experimental Reactor (ITER) designs in the both stages of Conceptual Design Activities (CDA) and Engineering Design Activities (EDA). Though the major objective of GEMSAFE is to reasonably select design basis events (DBEs) it is also useful to elucidate related safety functions as well as requirements to ensure its safety. In this paper, we apply the methodology to fusion systems with future tritium breeding blankets and make clear which points of the system should be of concern from safety ensuring point of view. In this context, we have obtained five DBEs that are related to the blanket system. We have also clarified the safety functions required to prevent accident propagations initiated by those blanket-specific DBEs. The outline of the methodology is also reviewed. (author)

Nuclear installations safety in France. Compilation of regulatory guides

International Nuclear Information System (INIS)

1988-01-01

General plan: 1. General organization of public officials. Procedures 1.1. Texts defining the general organization and the procedures 1.2. Interventing organisms; 2. Texts presenting a technical aspect other than basic safety rules and associated organization texts; 2.1. Dispositions relating to safety of nuclear installations 2.2. Dispositions relating to pressure vessels 2.3. Dispositions relating to quality 2.4. Dispositions relating to radioactive wastes release 2.5. Dispositions relating to activities depending of classified installations; 3. Basic Safety Rules (BSR) 3.1. BSR relating to PWR 3.2. BSR relating to nuclear installations other than PWR 3.3. Other BSR [fr

The Evaluation of the Safety Benefits of Combined Passive and On-Board Active Safety Applications

Science.gov (United States)

Page, Yves; Cuny, Sophie; Zangmeister, Tobias; Kreiss, Jens-Peter; Hermitte, Thierry

2009-01-01

One of the objectives of the European TRACE project (TRaffic Accident Causation in Europe, 2006–2008) was to estimate the proportion of injury accidents that could be avoided and/or the proportion of injury accidents where the severity could be mitigated for on-the-market safety applications, if 100 % of the car fleet would be equipped with them. We have selected for evaluation the Electronic Stability Control (ESC) and the Emergency Brake Assist (EBA) applications. As for passive safety systems, recent cars are designed to offer overall safety protection. Car structure, load limiters, front airbags, side airbags, knee airbags, pretensioners, padding and non aggressive structures in the door panel, the dashboard, the windshield, the seats, and the head rest also contribute to applying more protection. The whole safety package is very difficult to evaluate separately, one element independently segmented from the others. We decided to consider evaluating the effectivenessof the whole passive safety package, This package,, for the sake of simplicity, was the number of stars awarded at the Euro NCAP testing. The challenges were to compare the effectiveness of some safety configuration SC I, with the effectiveness of a different safety configuration SC II. A safety configuration is understood as a package of safety functions. Ten comparisons have been carried out such as the evaluation of the safety benefit of a fifth star given that the car has four stars and an EBA. The main outcome of this analysis is that any addition of a passive or active safety function selected in this analysis is producing increased safety benefits. For example, if all cars were five stars fitted with EBA and ESC, instead of four stars without ESC and EBA, injury accidents would be reduced by 47.2% for severe injuries and 69.5% for fatal injuries. PMID:20184838

Workplace activities to promote small attempts for safety. Toward development of safety culture in a nuclear power plant

International Nuclear Information System (INIS)

Fukui, Hirokazu; Sugiman, Toshio

2007-01-01

Activities that could possibly grow into learning activities for developing safety culture were explored by intensive fieldwork in a nuclear power plant depending on Engestroem's activity theory. As a first step to achieve this goal, workers' small attempts that might contribute to nurturing a safety culture were investigated. Eight kinds of activity were observed and interpreted as having the possibility to facilitate small recognition and small practice, i.e., activities including (1) workgroup as community, (2) other workgroups and other departments as community, (3) meeting drawing remarks as mediating artifacts, (4) study session and Off-the-Job-Training as mediating artifact, (5) award as mediating artifact, (6) extended leave as mediating artifact, (7) check sheet as mediating artifact, and (8) skill-transfer system as mediating artifact. (author)

European standardization activities on safety of liquid helium cryostats

CERN Multimedia

CERN. Geneva

2016-01-01

This talk gives a general overview on the challenges of designing safety units for liquid helium cryostats with regard to existing industry standards. It reviews the work of a national working group that published the technical guideline DIN SPEC 4683 in April 2015, which is dedicated to the particular conditions in liquid helium cryostats. Based on both this guideline and equivalent documents from e.g. CEA, CERN, a working group is being formed at the European Committee for Standardization, associated to CEN/TC 268, which will work on a European standard on safety of liquid helium cryostats. The actual status and the schedule of this project are presented.

Usage, biological activity, and safety of selected botanical dietary supplements consumed in the United States

Directory of Open Access Journals (Sweden)

P. Annécie Benatrehina

2018-04-01

Full Text Available In view of the continuous growth of the botanical dietary supplement industry and the increased popularity of lesser known or exotic botanicals, recent findings are described on the phytochemical composition and biological activities of five selected fruits consumed in the United States, namely, açaí, noni, mangosteen, black chokeberry, and maqui berry. A review of the ethnomedicinal uses of these plants has revealed some similarities ranging from wound-healing to the treatment of fever and infectious diseases. Laboratory studies on açaí have shown both its antioxidant and anti-inflammatory activities in vitro, and more importantly, its neuroprotective properties in animals. Anthraquinones and iridoid glucosides isolated from noni fruit induce the phase II enzyme quinone reductase (QR, and noni fruit juice exhibited antitumor and antidiabetic activities in certain animal models. Antitumorigenic effects of mangosteen in animal xenograft models of human cancers have been attributed to its xanthone content, and pure α-mangostin was shown to display antineoplastic activity in mice despite a reported low oral bioavailability. Work on the less extensively investigated black chokeberry and maqui berry has focused on recent isolation studies and has resulted in the identification of bioactive secondary metabolites with QR-inducing and hydroxyl-radical scavenging properties. On the basis of the safety studies and toxicity case reports described herein, these fruits may be generally considered as safe. However, cases of adulteration found in a commercialized açaí product and some conflicting results from mangosteen safety studies warrant further investigation on the safety of these marketed botanical dietary supplements. Keywords: Açaí, Noni, Mangosteen, Black chokeberry, Maqui berry

Environmental assessment of general-purpose heat source safety verification testing

International Nuclear Information System (INIS)

1995-02-01

This Environmental Assessment (EA) was prepared to identify and evaluate potential environmental, safety, and health impacts associated with the Proposed Action to test General-Purpose Heat Source (GPHS) Radioisotope Thermoelectric Generator (RTG) assemblies at the Sandia National Laboratories (SNL) 10,000-Foot Sled Track Facility, Albuquerque, New Mexico. RTGs are used to provide a reliable source of electrical power on board some spacecraft when solar power is inadequate during long duration space missions. These units are designed to convert heat from the natural decay of radioisotope fuel into electrical power. Impact test data are required to support DOE's mission to provide radioisotope power systems to NASA and other user agencies. The proposed tests will expand the available safety database regarding RTG performance under postulated accident conditions. Direct observations and measurements of GPHS/RTG performance upon impact with hard, unyielding surfaces are required to verify model predictions and to ensure the continual evolution of the RTG designs that perform safely under varied accident environments. The Proposed Action is to conduct impact testing of RTG sections containing GPHS modules with simulated fuel. End-On and Side-On impact test series are planned

Intensive care unit nurses' perceptions of safety after a highly specific safety intervention.

Science.gov (United States)

Elder, N C; Brungs, S M; Nagy, M; Kudel, I; Render, M L

2008-02-01

It is unknown if successful changes in specific safety practices in the intensive care unit (ICU) generalize to broader concepts of patient safety by staff nurses. To explore perceptions of patient safety among nursing staff in ICUs following participation in a safety project that decreased hospital acquired infections. After implementation of practices that reduced catheter-related bloodstream infections in ICUs at four community hospitals, ICU nurses participated in focus groups to discuss patient safety. Audiotapes from the focus groups were transcribed, and two independent reviewers categorised the data which were triangulated with responses from selected questions of safety climate surveys and with the safety checklists used by management leadership on walk rounds. Thirty-three nurses attended eight focus groups; 92 nurses and managers completed safety climate surveys, and three separate leadership checklists were reviewed. In focus groups, nurses predominantly related patient safety to dangers in the physical environment (eg, bed rails, alarms, restraints, equipment, etc.) and to medication administration. These areas also represented 47% of checklist items from leadership walk rounds. Nurses most frequently mentioned self-initiated "double checking" as their main safety task. Focus-group participants and survey responses both noted inconsistency between management's verbal and written commitment compared with their day-to-day support of patient safety issues. ICU nurses who participated in a project to decrease hospital acquired infections did not generalize their experience to other aspects of patient safety or relate it to management's interest in patient safety. These findings are consistent with many adult learning theories, where self-initiated tasks, combined with immediate, but temporary problem-solving, are stronger learning forces than management-led activities with delayed feedback.

Managing for safety at nuclear installations

International Nuclear Information System (INIS)

1996-01-01

This publication, by the Health and Safety Executive's (HSE's) Nuclear Safety Division (NSD), provides a statement of the criteria the Nuclear Installations Inspectorate (NII) uses to judge the adequacy of any proposed or existing system for managing a nuclear installation in so far as it affects safety. These criteria have been developed from the basic HSE model, described in the publication Successful health and safety management that applies to industry generally, in order to meet the additional needs for managing nuclear safety. In addition, the publication identifies earlier studies upon which this work was based together with the key management activities and outputs. (Author)

Overview of Indian position: Passive and active safety features of LMFBRs

International Nuclear Information System (INIS)

Paranjpe, S.R.

1991-01-01

Since PWR and BWR type reactors are considered to have acceptable level of safety, there is a general statement that LMFBR type reactors should be designed to be 'at least as safe' as PWRs and BWRs. Nuclear safety issues considered include the following: flexibility of operation over the entire power range, effectiveness of steps ensuring the safety as well as plant availability under foreseeable incident conditions; guaranteed safe shut-down of the reactor; ability to remove safely and reliably the decay heat under shut-down conditions; containment capability including protection of the reactor from external events. It is concluded that liquid metal fast breeder reactors (LMFBRs) can be designed very easily to eliminate anxieties about their safety and no difficulties are expected in the licensing procedure of this type of reactors

Using Active Learning to Identify Health Information Technology Related Patient Safety Events.

Science.gov (United States)

Fong, Allan; Howe, Jessica L; Adams, Katharine T; Ratwani, Raj M

2017-01-18

The widespread adoption of health information technology (HIT) has led to new patient safety hazards that are often difficult to identify. Patient safety event reports, which are self-reported descriptions of safety hazards, provide one view of potential HIT-related safety events. However, identifying HIT-related reports can be challenging as they are often categorized under other more predominate clinical categories. This challenge of identifying HIT-related reports is exacerbated by the increasing number and complexity of reports which pose challenges to human annotators that must manually review reports. In this paper, we apply active learning techniques to support classification of patient safety event reports as HIT-related. We evaluated different strategies and demonstrated a 30% increase in average precision of a confirmatory sampling strategy over a baseline no active learning approach after 10 learning iterations.

CERN's new safety policy

CERN Multimedia

2014-01-01

The documents below, published on 29 September 2014 on the HSE website, together replace the document SAPOCO 42 as well as Safety Codes A1, A5, A9, A10, which are no longer in force. As from the publication date of these documents any reference made to the document SAPOCO 42 or to Safety Codes A1, A5, A9 and A10 in contractual documents or CERN rules and regulations shall be deemed to constitute a reference to the corresponding provisions of the documents listed below.   "The CERN Safety Policy" "Safety Regulation SR-SO - Responsibilities and organisational structure in matters of Safety at CERN" "General Safety Instruction GSI-SO-1 - Departmental Safety Officer (DSO)" "General Safety Instruction GSI-SO-2 - Territorial Safety Officer (TSO)" "General Safety Instruction GSI-SO-3 - Safety Linkperson (SLP)" "General Safety Instruction GSI-SO-4 - Large Experiment Group Leader In Matters of Safety (LEXGLI...

The Inspector General's report on Nuclear Safety and Radiation Protection 2008

International Nuclear Information System (INIS)

2009-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's analysis and conclusions at the end of 2008; 2 - Nuclear safety management; 3 - Radiation protection; 4 - A changing relationship with the nuclear safety authority; 5 - Support for the nuclear plants in service; 6 - Succeeding with the EPR; 7 - Operating the installations for longer; 8 - Further opening up to the outside world; 9 - Renewal of skills; 10 - Labour relations; 11 - The driving forces of cultural change; 12 - Promote change and regulate its pace; 13 - The contribution of the medical staff; 14 - Relations with contractors; 15 - The fire hazard; 16 - Nuclear fuel; 17 - Decommissioning; 18 - Emergency response management; 19 - Events at EDF; 19.1 - The Tricastin nuclear power plant fuel assemblies; 19.2 - Steam generator behaviour; 19.3 - Reactor building evacuation; 20 - Visits

PATIENT SAFETY IN SURGERY: THE QUALITY OF IMPLEMENTATION OF PATIENT SAFETY CHECKLISTS IN A REGIONAL HOSPITAL

Directory of Open Access Journals (Sweden)

V. Karyadinata

2012-09-01

Full Text Available Introduction. Patient safety and the avoidance of inhospital adverse events is a key focus of clinical practice and medical audit. A large of proportion of medical errors affect surgical patients in the peri-operative setting. Safety checklists have been adopted by the medical profession from the aviation industry as a cheap and reliable method of avoiding errors which arise from complex or stressful situations. Current evidence suggests that the use of periooperative checklists has led to a decrease in surgical morbidity and hospital costs. Aim. To assess the quality of implementation of a modified patient safety checklist in a UK district general hospital. Methods. An observational tool was designed to assess in real time the peri-operative performance of the surgical safety checklist in patients undergoing general surgical, urological or orthopaedic procedures. Initiation of the checklist, duration of performance and staff participation were audited in real time. Results. 338 cases were monitored. Nurses were most active in initiating the safety checklist. The checklist was performed successfully in less than a minute in most cases. 11-24% of staff (according to professional group present in the operating room did not participate in the checklist. Critical safety checks (patient identity and procedure name were performed in all cases across all specialties. Variations were noted in checking other categories, such as deep vein thrombosis (DVT prophylaxis or patient warming. Conclusions. There is still a potential for improving the practice and culture of surgical patient safety activities. Staff training and designation of patient safety leadership roles is needed in increasing compliance and implementation of patient safety mechanism, such as peri-operative checklists. There is significant data to advocate the need to implement patient safety surgical checklists internationally

Quality Control Activities Related to Mechanical Maintenance of Safety Related Components at Krsko NPP

International Nuclear Information System (INIS)

Djakovic, D.

2016-01-01

For successful, safe and reliable operation of nuclear power plant, maintenance processes have to be systematically controlled and procedures for quality control of maintenance activities shall be established. This is requested by the quality assurance program, which shall provide control over activities affecting the quality of structures, systems, and components, considering their importance to safety. As a part of Quality and Nuclear Oversight Division (QNOD; SKV), the Quality Control Department (QC) provides quality control activities, which are deeply involved in maintenance processes at Krsko NPP, both on safety related and non-safety related (non-nuclear safety) components. QC activities on safety related components have to fulfil all requirements, which will enable the components to perform their intended safety functions. This paper describes quality control activities related to mechanical maintenance of safety related components at Krsko NPP and significant role of the Krsko plant QC Department in three particular maintenance cases connected with safety related components. In these three specific cases, the QC has confirmed its importance in compliance with quality assurance program and presented its significant added value in providing safe and reliable operation of the plant. The first maintenance activity was installation of nozzle check valves in the scope of a modification for improving regulation of spent fuel pit pumps. The QC Department performed receipt inspection of the valves. Using non-destructive examination methods and X-ray spectrometry, it was found out that the valve diffuser was made of improper material, which could cause progressive corrosion of the valve diffuser in borated water and consequently a loss of safety function of the valves followed by long-term consequences. The second one was the receipt inspection of containment ventilation fan coolers. The coolers were claimed and sent back to the supplier because the QC Department

Regulatory regime and its influence in the nuclear safety

International Nuclear Information System (INIS)

Laaksonen, J.

1999-01-01

Main elements of nuclear regulatory regime in general is presented. These elements are: national rules and safety regulations, system of nuclear facility licensing, activities of regulatory body. Regulatory body is needed to specify the national safety regulations, review and assess the safety documentation presented to support license application, make inspections to verify fulfilment of safety regulations and license conditions, monitor the quality of work processes of user organization, and to assess whether these processes provide a high safety level, promote high safety culture, promote maintenance and development of national infrastructure relevant to nuclear safety, etc

Further activities of safety culture toward nuclear transportation industry

International Nuclear Information System (INIS)

Machida, Y.; Shimakura, D.

2004-01-01

On September 30, 1999, a criticality accident occurred at the uranium processing facility of the JCO Co. Ltd. (hereinafter referred to as ''JCO'') Tokai plant, located in Tokaimura, Ibaraki Prefecture. This was an unprecedented accident in Japan's history of peaceful use of nuclear power, resulting in three workers exposed to severe radiation, two of whom died, and the evacuation and enforced indoor confinement of local residents. Nuclear power suppliers must take personal responsibility for ensuring safety. In this connection, the electric power industry, heavy electric machinery manufacturers, fuel fabricators, and nuclear power research organizations gathered together to establish the Nuclear Safety Network (NSnet) in December 1999, based on the resolve to share and improve the level of the safety culture across the entire nuclear power industry and to assure that such an accident never occurs again. NSnet serves as a link between nuclear power enterprises, research organizations, and other bodies, based on the principles of equality and reciprocity. A variety of activities are pursued, such as diffusing a safety culture, implementing mutual evaluation among members, and exchanging safety-related information. Aiming to share and improve the safety culture throughout the entire nuclear power industry, NSnet thoroughly implements the principle of safety first, while at the same time making efforts to restore trust in nuclear power

General Approaches and Requirements on Safety and Security of Radioactive Materials Transport in Russian Federation

International Nuclear Information System (INIS)

Ershov, V.N.; Buchel'nikov, A.E.; Komarov, S.V.

2016-01-01

Development and implementation of safety and security requirements for transport of radioactive materials in the Russian Federation are addressed. At the outset it is worth noting that the transport safety requirements implemented are in full accordance with the IAEA's ''Regulations for the Safe Transport of Radioactive Material (2009 Edition)''. However, with respect to security requirements for radioactive material transport in some cases the Russian Federation requirements for nuclear material are more stringent compared to IAEA recommendations. The fundamental principles of safety and security of RM managements, recommended by IAEA documents (publications No. SF-1 and GOV/41/2001) are compared. Its correlation and differences concerning transport matters, the current level and the possibility of harmonization are analysed. In addition a reflection of the general approaches and concrete transport requirements is being evaluated. Problems of compliance assessment, including administrative and state control problems for safety and security provided at internal and international shipments are considered and compared. (author)

Status and trends in IAEA safety standards

International Nuclear Information System (INIS)

Lipar, M.

2004-01-01

While safety is a national responsibility, international standards and approaches to safety promote consistency and facilitate international technical co-operation and trade, and help to provide assurance that nuclear and radiation related technologies are used safely. The standards also provide support for States in meeting their international obligations. One general international obligation is that a State must not pursue activities that cause damage in another State. More specific obligations on Contracting States are set out in international safety related conventions. The internationally agreed IAEA safety standards provide the basis for States to demonstrate that they are meeting these obligations. These standards are founded in the IAEA's Statute, which authorizes the Agency to establish standards of safety for nuclear and radiation related facilities and activities and to provide for their application. The safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment. (orig.) [de

Exposure to ionizing radiations having a medical origin. Propositions for the implementation and the development of epidemiology surveillance activities in general population; Exposition aux rayonnements ionisants d'origine medicale. Propositions pour la mise en place et le developpement d'activites de surveillance epidemiologique en population generale

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-09-01

This report gives propositions relative to the implementation and the development of epidemiology surveillance activities in general population in relation with medical exposure to ionizing radiations. It is intended for the General Direction of Health and General Direction of Nuclear Safety and Radiation Protection. These propositions have been elaborated by a work group coordinated and run by InVS and gathering the following organisms: French Agency of sanitary safety of health products (A.F.S.S.A.P.S.), Center of Quality Assurance of technological applications in the area of health (C.A.A.T.S.), Direction of Hospitals and Care organization (D.H.O.S.), General Direction of Health (D.G.S.), General Direction of Nuclear Safety and Radiation Protection (D.G.S.N.R.), National Federation of radiologists physicists (F.N.M.R.), institute of Radiation Protection and Nuclear Safety (I.R.S.N.), INSERM 'epidemiology of cancers', French Society of Biology and Nuclear Medicine (S.F.B.M.N.), French Society of Medical Physics (S.F.P.M.), French Society of Radiology (S.F.R.). (N.C.)

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

International Nuclear Information System (INIS)

Song, Tae Young

2007-01-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

Energy Technology Data Exchange (ETDEWEB)

Song, Tae Young [Nuclear Engineering and Technology Institute, Daejeon (Korea, Republic of)

2007-07-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas.

Active SMS-based influenza vaccine safety surveillance in Australian children.

Science.gov (United States)

Pillsbury, Alexis; Quinn, Helen; Cashman, Patrick; Leeb, Alan; Macartney, Kristine

2017-12-18

Australia's novel, active surveillance system, AusVaxSafety, monitors the post-market safety of vaccines in near real time. We analysed cumulative surveillance data for children aged 6 months to 4 years who received seasonal influenza vaccine in 2015 and/or 2016 to determine: adverse event following immunisation (AEFI) rates by vaccine brand, age and concomitant vaccine administration. Parent/carer reports of AEFI occurring within 3 days of their child receiving an influenza vaccine in sentinel immunisation clinics were solicited by Short Message Service (SMS) and/or email-based survey. Retrospective data from 2 years were combined to examine specific AEFI rates, particularly fever and medical attendance as a proxy for serious adverse events (SAE), with and without concomitant vaccine administration. As trivalent influenza vaccines (TIV) were funded in Australia's National Immunisation Program (NIP) in 2015 and quadrivalent (QIV) in 2016, respectively, we compared their safety profiles. 7402 children were included. Data were reported weekly through each vaccination season; no safety signals or excess of adverse events were detected. More children who received a concomitant vaccine had fever (7.5% versus 2.8%; p vaccine was associated with the highest increase in AEFI rates among children receiving a specified concomitant vaccine: 30.3% reported an AEFI compared with 7.3% who received an influenza vaccine alone (p safety profiles included low and expected AEFI rates (fever: 4.3% for TIV compared with 3.2% for QIV (p = .015); injection site reaction: 1.9% for TIV compared with 3.0% for QIV (p safety profile between brands. Active participant-reported data provided timely vaccine brand-specific safety information. Our surveillance system has particular utility in monitoring the safety of influenza vaccines, given that they may vary in composition annually. Copyright © 2017 Elsevier Ltd. All rights reserved.

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)

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)

Draft IAEA Action Plan on Nuclear Safety. Report by the Director General

International Nuclear Information System (INIS)

Amano, Y.

2011-01-01

In accordance with paragraphs 23 and 24 of the Declaration adopted by the Ministerial Conference on Nuclear Safety held on 20-24 June 2011, the Director General was requested to prepare and present to the Board of Governors and the General Conference at their September 2011 meetings a report on the Ministerial Conference and a draft Action Plan, building on the Ministerial Declaration, the conclusions and recommendations of the working sessions of the Ministerial Conference and the expertise and knowledge available therein, and to facilitate consultations among Member States on the draft Action Plan. This draft Action Plan is the result of an extensive process of consultations with Member States and responds to the request contained in the Ministerial Declaration.

Summary of the Safety Culture Activities in HANARO of KAERI

International Nuclear Information System (INIS)

Lim, In-Cheol; Wu, Jong-Sup; Lee, Kye-Hong

2006-01-01

The definition of safety culture in HANARO takes the IAEA's definition and it is the assembly of characteristics of attitudes in the HANARO center and individuals which establishes that, as an overriding priority, the HANARO safety issues receive the attention warranted by their significance. Since the power operation of HANARO started in 1996, HANARO has been operated for about 11 years and its degree of utilization and the number of experimental facilities have increased. This achievement is partly due to the spread of safety culture to the operators and the reactor users. In this paper, the safety culture activities done by the HANARO center of KAERI are described, and its efforts necessary for an improvement of it are presented

Safety goals and safety culture opening plenary. 2. Safety Regulation Implemented by Gosatomnadzor of Russia

International Nuclear Information System (INIS)

Gutsalov, A.T.; Bukrinsky, A.M.

2001-01-01

This paper describes principles and approaches used by Gosatomnadzor of Russia in establishing safety goals. The link between safety goals and safety culture is demonstrated. The paper also contains information on nuclear regulatory activities in Russia. Regulatory documents of Gosatomnadzor of Russia do not provide precise definitions of safety goals as IAEA documents INSAG-3 or INSAG-12 do. However, overall activities of Gosatomnadzor of Russia are directed to the achievement of these safety goals, as Gosatomnadzor of Russia is a federal executive authority responsible for the regulation of nuclear and radiation safety in accordance with the Russian Federal Law 'On the Use of Nuclear Energy'. Thus, in the Statement of the Policy of the Russian Regulatory Authority, enacted in 1992, it was established that the overall activities of Gosatomnadzor of Russia are directed to the achievement of the main goal. This goal is to establish conditions that ensure that personnel, the public, and the environment are protected from unacceptable radiation and nonproliferation of nuclear materials. The practical application of such a method as given by the publication of Statements of Policy of Gosatomnadzor of Russia may be considered as a safety culture element. 'General Provisions of NPP Safety Ensuring' (OPB-88/ 97) is a regulatory document of the highest level in the hierarchy of regulatory documents of Gosatomnadzor of Russia. It establishes quantitative values of safety goals as do the foregoing IAEA documents. Thus, this regulatory document sets up the following: 1. The estimated total probability of severe accidents should not exceed 10 5 /reactor.yr. 2. The estimated probability of the worst possible radioactive release to the environment specified in the standards should not exceed 10 -7 /reactor.yr in the case of severe beyond-design-basis accidents. 3. The probability of a reactor vessel failure should not exceed 10 -7 /reactor.yr. The foregoing values are somehow

Handling and safety enhancement of race cars using active aerodynamic systems

Science.gov (United States)

Diba, Fereydoon; Barari, Ahmad; Esmailzadeh, Ebrahim

2014-09-01

A methodology is presented in this work that employs the active inverted wings to enhance the road holding by increasing the downward force on the tyres. In the proposed active system, the angles of attack of the vehicle's wings are adjusted by using a real-time controller to increase the road holding and hence improve the vehicle handling. The handling of the race car and safety of the driver are two important concerns in the design of race cars. The handling of a vehicle depends on the dynamic capabilities of the vehicle and also the pneumatic tyres' limitations. The vehicle side-slip angle, as a measure of the vehicle dynamic safety, should be narrowed into an acceptable range. This paper demonstrates that active inverted wings can provide noteworthy dynamic capabilities and enhance the safety features of race cars. Detailed analytical study and formulations of the race car nonlinear model with the airfoils are presented. Computer simulations are carried out to evaluate the performance of the proposed active aerodynamic system.

A strategic approach to quality improvement and patient safety education and resident integration in a general surgery residency.

Science.gov (United States)

O'Heron, Colette T; Jarman, Benjamin T

2014-01-01

To outline a structured approach for general surgery resident integration into institutional quality improvement and patient safety education and development. A strategic plan to address Accreditation Council for Graduate Medical Education (ACGME) Clinical Learning Environment Review assessments for resident integration into Quality Improvement and Patient Safety initiatives is described. Gundersen Lutheran Medical Foundation is an independent academic medical center graduating three categorical residents per year within an integrated multi-specialty health system serving 19 counties over 3 states. The quality improvement and patient safety education program includes a formal lecture series, online didactic sessions, mandatory quality improvement or patient safety projects, institutional committee membership, an opportunity to serve as a designated American College of Surgeons National Surgical Quality Improvement Project and Quality in Training representative, mandatory morbidity and mortality conference attendance and clinical electives in rural surgery and international settings. Structured education regarding and participation in quality improvement and patient safety programs are able to be accomplished during general surgery residency. The long-term outcomes and benefits of these strategies are unknown at this time and will be difficult to measure with objective data. © 2013 Published by Association of Program Directors in Surgery on behalf of Association of Program Directors in Surgery.

General principles of the nuclear criticality safety for handling, processing and transportation fissile materials in the USSR

International Nuclear Information System (INIS)

Vnukov, V.S.; Rjazanov, B.G.; Sviridov, V.I.; Frolov, V.V.; Zubkov, Y.N.

1991-01-01

The paper describes the general principles of nuclear criticality safety for handling, processing, transportation and fissile materials storing. Measures to limit the consequences of critical accidents are discussed for the fuel processing plants and fissile materials storage. The system of scientific and technical measures on nuclear criticality safety as well as the system of control and state supervision based on the rules, limits and requirements are described. The criticality safety aspects for various stages of handling nuclear materials are considered. The paper gives descriptions of the methods and approaches for critical risk assessments for the processing facilities, plants and storages. (Author)

Quarterly report on the activities in Safety Administration Division. The fourth quarter of 2002

International Nuclear Information System (INIS)

Yamamoto, Junta

2003-11-01

The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a safety and health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in January to March in 2003. (author)

Quarterly report on the activities in Safety Administration Division. The second quarter of 2003

International Nuclear Information System (INIS)

Yamamoto, Junta

2004-08-01

The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a safety and health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in July to September in 2003. (author)

Quarterly report on the activities in safety Administration Division. The forth quarter of 2003

International Nuclear Information System (INIS)

Yamamoto, Junta

2005-01-01

The activities of Safety Administration Division covers many fields in Tokai-works such as the management of a safety and health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in January to March in 2004. (author)

Quarterly report on the activities in Safety Administration Division. The first quarter of 2003

International Nuclear Information System (INIS)

Yamamoto, Junta

2004-02-01

The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a safety and health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in April to June in 2003. (author)

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

International Nuclear Information System (INIS)

Crocker, J.G.; Cohen, S.

1982-07-01

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

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

International Nuclear Information System (INIS)

Katona, T.

1995-01-01

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

Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy

International Nuclear Information System (INIS)

TRAWINSKI, B.J.

2000-01-01

The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system

Further activities of safety culture toward nuclear transportation industry

Energy Technology Data Exchange (ETDEWEB)

Machida, Y.; Shimakura, D. [NSnet, Tokyo (Japan)

2004-07-01

On September 30, 1999, a criticality accident occurred at the uranium processing facility of the JCO Co. Ltd. (hereinafter referred to as ''JCO'') Tokai plant, located in Tokaimura, Ibaraki Prefecture. This was an unprecedented accident in Japan's history of peaceful use of nuclear power, resulting in three workers exposed to severe radiation, two of whom died, and the evacuation and enforced indoor confinement of local residents. Nuclear power suppliers must take personal responsibility for ensuring safety. In this connection, the electric power industry, heavy electric machinery manufacturers, fuel fabricators, and nuclear power research organizations gathered together to establish the Nuclear Safety Network (NSnet) in December 1999, based on the resolve to share and improve the level of the safety culture across the entire nuclear power industry and to assure that such an accident never occurs again. NSnet serves as a link between nuclear power enterprises, research organizations, and other bodies, based on the principles of equality and reciprocity. A variety of activities are pursued, such as diffusing a safety culture, implementing mutual evaluation among members, and exchanging safety-related information. Aiming to share and improve the safety culture throughout the entire nuclear power industry, NSnet thoroughly implements the principle of safety first, while at the same time making efforts to restore trust in nuclear power.

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

Safety margin evaluation concepts for plant Up rates and life extension. Results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP)

International Nuclear Information System (INIS)

Belac, J

2006-01-01

This presentation summarizes results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP) aimed to develop generalized safety margin concept and means of its quantification for the process of evaluating plant safety in the frame of plant life extension and power up rating activities to be used by OECD member countries. (author)

Developing safety culture in nuclear activities. Practical suggestions to assist progress

International Nuclear Information System (INIS)

2000-01-01

The term 'safety culture' was introduced by the International Nuclear Safety Advisory Group (INSAG) in Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident published by the IAEA as Safety Series No. 75-INSAG-1 in 1986, and expanded in Basic Safety Principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3 in 1988. This publication supplements INSAG-4 published in 1991 which includes the definition and concept of safety culture describing practices valuable in establishing and maintaining a sound safety culture in a number of countries. It is intended for those who design, construct, manufacture, operate, maintain or decommission nuclear facilities. It should be practically useful for all those involved in operating nuclear facilities. It will also provide a reference for groups such as regulators who have an interest in developing, improving and evaluating safety culture training and individuals engaged in nuclear activities, and for bodies such as ethics review committees who should take into account safety culture issues for certifying professional excellence in the medical field

Developing safety culture in nuclear activities. Practical suggestions to assist progress

International Nuclear Information System (INIS)

1998-01-01

The term 'safety culture' was introduced by the International Nuclear Safety Advisory Group (INSAG) in Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident published by IAEA as safety Series No. 75-INSAG-1 in 1986, and expanded in Basic Safety principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3 in 1988. This publication supplements INSAG-4 published in 1991 which includes the definition and concept of safety culture describing practices valuable in establishing and maintaining a sound safety culture in a number of countries. It is intended for those who design, construct, manufacture, operate, maintain or decommission nuclear facilities. It should be practically useful for all those involved in operating nuclear facilities. It will also provide a reference for groups such as regulators who have an interest in developing, improving and evaluating safety culture training and individuals engaged in nuclear activities, and for bodies such as ethics review committees who should take into account safety culture issues for certifying professional excellence in the medical field

Does perceived neighborhood walkability and safety mediate the association between education and meeting physical activity guidelines?

Science.gov (United States)

Pratt, Michael; Yin, Shaoman; Soler, Robin; Njai, Rashid; Siegel, Paul Z; Liao, Youlian

2015-04-09

The role of neighborhood walkability and safety in mediating the association between education and physical activity has not been quantified. We used data from the 2010 and 2012 Communities Putting Prevention to Work Behavioral Risk Factor Surveillance System and structural equation modeling to estimate how much of the effect of education level on physical activity was mediated by perceived neighborhood walkability and safety. Neighborhood walkability accounts for 11.3% and neighborhood safety accounts for 6.8% of the effect. A modest proportion of the important association between education and physical activity is mediated by perceived neighborhood walkability and safety, suggesting that interventions focused on enhancing walkability and safety could reduce the disparity in physical activity associated with education level.

Safety and Health Perceptions in Work-related Transport Activities in Ghanaian Industries

Directory of Open Access Journals (Sweden)

Charles Atombo

2017-06-01

Conclusion: OSH culture is not fully complied in industries transport activities. This study, therefore, supports the use of safety seminars and training sessions for industry workers responsible for transport operations for better integration of safety standards.

Status of Safety and Environmental Activities for Inertial Fusion Energy

International Nuclear Information System (INIS)

Latkowski, J.F.; Reyes, S.; Cadwallader, L.C.; Sharpe, J.P.; Marshall, T.D.; Merrill, B.J.; Moore, R.L.; Petti, D.A.; Falquina, R.; Rodriguez, A.; Sanz, J.; Cabellos, O.

2003-01-01

Over the past several years, significant progress has been made in the analysis of safety and environmental (S and E) issues for inertial fusion energy (IFE). Detailed safety assessments have been performed for the baseline power plant concepts, as well as for a conceptual target fabrication facility. Safety analysis results are helping to drive the agenda for experiments. A survey of the S and E characteristics - both radiological and chemical - of candidate target materials has been completed. Accident initiating events have been identified and incorporated into master logic diagrams, which will be essential to the detailed safety analyses that will be needed in the future. Studies of aerosol generation and transport will have important safety implications. A Monte Carlo-based uncertainty analysis procedure has been developed for use in neutron activation calculations. Finally, waste management issues are receiving increased attention and are deserving of further discussion

The safety activities of the ICAO and the IAEA

International Nuclear Information System (INIS)

Franzen, L.F.; Iansiti, E.

1983-01-01

The article presents a comparative analysis of the safety activities of the IAEA and the International Civil Aviation Organization (ICAO), from which possible solutions for the problems faced by the nuclear community are suggested

Analysis of general aviation single-pilot IFR incident data obtained from the NASA Aviation Safety Reporting System

Science.gov (United States)

Bergeron, H. P.

1983-01-01

An analysis of incident data obtained from the NASA Aviation Safety Reporting System (ASRS) has been made to determine the problem areas in general aviation single-pilot IFR (SPIFR) operations. The Aviation Safety Reporting System data base is a compilation of voluntary reports of incidents from any person who has observed or been involved in an occurrence which was believed to have posed a threat to flight safety. This paper examines only those reported incidents specifically related to general aviation single-pilot IFR operations. The frequency of occurrence of factors related to the incidents was the criterion used to define significant problem areas and, hence, to suggest where research is needed. The data was cataloged into one of five major problem areas: (1) controller judgment and response problems, (2) pilot judgment and response problems, (3) air traffic control (ATC) intrafacility and interfacility conflicts, (4) ATC and pilot communication problems, and (5) IFR-VFR conflicts. In addition, several points common to all or most of the problems were observed and reported. These included human error, communications, procedures and rules, and work load.

Safety surveillance of activities on nuclear pressure components in China

International Nuclear Information System (INIS)

Li Ganjie; Li Tianshu; Yan Tianwen

2005-01-01

The nuclear pressure components, which perform the nuclear safety functions, are one of the key physical barriers for nuclear safety. For the national strategy on further development of nuclear power and localization of nuclear pressure components, there still exist some problems in preparedness on the localization. As for the technical basis, what can not be overlooked is the management. Aiming at the current problems, National Nuclear Safety Administration (NNSA) has taken measures to strengthen the propagation and popularization of nuclear safety culture, adjust the review and approval policies for nuclear pressure components qualification license, establish more stringent management requirements, and enhance the surveillance of activities on nuclear pressure equipment. Meanwhile, NNSA has improved the internal management and the regulation efficiency on nuclear pressure components. At the same time, with the development and implementation of 'Rules on the Safety Regulation for Nuclear Safety Important Components' to be promulgated by the State Council of China, NNSA will complete and improve the regulation on nuclear pressure components and other nuclear equipment. (authors)

General philosophy of safety standards

International Nuclear Information System (INIS)

Dunster, H.J.

1987-01-01

Safety standards should be related to the form and magnitude of the risk they aim to limit. Because of the lack of direct information at the exposure levels experienced, radiation protection standards have to be based on risk assumptions that, while plausible, are not proven. The pressure for standards has come as much from public perceptions and fears as from the reality of the risk. (author)

Highway Safety Program Manual: Volume 3: Motorcycle Safety.

Science.gov (United States)

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

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

Annual report on the activities in Safety Administration Department. Report of the fiscal year 2010

Energy Technology Data Exchange (ETDEWEB)

Aoki, Yoshikazu [Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, Tokai, Ibaraki (Japan)

2014-01-15

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of the occupational safety and health, the crisis management, the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2010 until March, 2011. (author)

Receptionist input to quality and safety in repeat prescribing in UK general practice: ethnographic case study.

Science.gov (United States)

Swinglehurst, Deborah; Greenhalgh, Trisha; Russell, Jill; Myall, Michelle

2011-11-03

To describe, explore, and compare organisational routines for repeat prescribing in general practice to identify contributors and barriers to safety and quality. Ethnographic case study. Four urban UK general practices with diverse organisational characteristics using electronic patient records that supported semi-automation of repeat prescribing. 395 hours of ethnographic observation of staff (25 doctors, 16 nurses, 4 healthcare assistants, 6 managers, and 56 reception or administrative staff), and 28 documents and other artefacts relating to repeat prescribing locally and nationally. Potential threats to patient safety and characteristics of good practice. Observation of how doctors, receptionists, and other administrative staff contributed to, and collaborated on, the repeat prescribing routine. Analysis included mapping prescribing routines, building a rich description of organisational practices, and drawing these together through narrative synthesis. This was informed by a sociological model of how organisational routines shape and are shaped by information and communications technologies. Results Repeat prescribing was a complex, technology-supported social practice requiring collaboration between clinical and administrative staff, with important implications for patient safety. More than half of requests for repeat prescriptions were classed as "exceptions" by receptionists (most commonly because the drug, dose, or timing differed from what was on the electronic repeat list). They managed these exceptions by making situated judgments that enabled them (sometimes but not always) to bridge the gap between the idealised assumptions about tasks, roles, and interactions that were built into the electronic patient record and formal protocols, and the actual repeat prescribing routine as it played out in practice. This work was creative and demanded both explicit and tacit knowledge. Clinicians were often unaware of this input and it did not feature in policy

A generalized framework for assessment of safety margins in nuclear power plants

International Nuclear Information System (INIS)

Gavrilas, M.; Youngblood, B.; Prelewicz, D.; Meyer, Jim

2004-01-01

analyses, e.g., OK or core damage (CD) as descriptors of fuel barrier damage state. Ideally, the plant safety metric would quantify the probability of exceeding the safety limits for each defense-in-depth barrier. Because obtaining such probabilities is beyond the state-of-the art, safety indices are conceptualized to be proxies for the probability of exceeding the safety limit for design basis accidents (DBA). A second group of safety indices is associated with beyond-DBA events, and are conceptualized to be proxies for the extent of barrier damage. As will be shown elsewhere, individual safety indices can explicitly account for code uncertainty in deterministic barrier state descriptions. The complete set of safety indices is assembled into a plant safety metric. In the assembly process, the probability of occurrence of all relevant threat events is used to weigh the safety indices and extract additional plant safety figures of merit. Thus, the proposed conceptual framework is consistent with the objectives set forth in the letter on the subject from the Advisory Committee on Reactor Safety (ACRS). The proposed method is comprehensive and spans the space from licensing to severe accidents. It relies on traditional safety concepts that are at the core of current regulatory activities. Conceptually, individual indices as well as the overall plant safety metrics are understandable to stake holders and usable by decision makers. The definition of a barrier state lends itself to applying the proposed approach to trajectories for which the independent variable is not time. For example, the approach can be applied to compare deterministic analyses for different nodalization schemes. The proposed framework is applicable to comparing plant safety states before and after a wide range of design/operating modifications. The framework is sufficiently comprehensive to be sensitive to a broad range of design modifications, changes in operating conditions and regulatory requirements

Regulatory activities in the area of fuel safety and performance

International Nuclear Information System (INIS)

Viktorov, A.; Couture, M.

2005-01-01

Generic Action Item 94G02 'Impact of Fuel Bundle Condition on Reactor Safety' in many ways determined the present priorities in regulatory activities related to fuel performance. As one of the closure criteria it required that all licensees establish 'an effective formal and systematic process for integrating fuel design, fuel and channel inspection, laboratory examination, research, operating limits and safety analysis'. To date, such a process has been, to a large extent, put in place by all licensees. To assure that such processes remain operational and effective after the GAI closure, CNSC required, through S-99, to report annually on fuel performance and major activities in the fuel safety area. The scope of reported information has been defined to allow CNSC staff evaluation of key events and trends in fuel performance. To compliment reporting by the industry, CNSC staff has conducted targeted inspections of fuel compliance programs at all sites. Combined together, these activities provide the regulator with the confidence that CANDU fuel is robust and operates with safety margins. The scrutiny, to which fuel performance has been subjected lately, has allowed identification of certain programmatic weaknesses and gaps in the knowledge concerning the fuel behaviour under various conditions. It has become apparent that top-level strategies for assessment of fuel performance may have been inadequate and far from systematic; fuel inspection practices and capabilities have varied significantly from site to site; certain issues were identified but remained unaddressed for significant time; priorities in experimental or design support activities were not assigned consistently. The presentation gives examples of areas where, in the opinion of the CNSC staff, further work is required to support fuel design and safety envelopes. The implementation of new CANFLEX fuel designs is currently being considered by the industry and CNSC staff has been engaged in the review

Intergovernmental Organisation Activities

International Nuclear Information System (INIS)

2014-01-01

This section treats of the following activities, sorted by Organisation: 1 - European Atomic Energy Community: Proposed binding instruments, Adopted legally binding instruments, Non-legally binding instruments; 2 - International Atomic Energy Agency: Convention on Nuclear Safety, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, International Expert Group on Nuclear Liability, Legislative assistance activities; 3 - OECD Nuclear Energy Agency: Appointment of new Director-General, International experts in Japan to review safety after Fukushima Daiichi, China Atomic Energy Authority co-operation workshop

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

Science.gov (United States)

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

2015-01-01

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

78 FR 34703 - Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report

Science.gov (United States)

2013-06-10

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0004] Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report AGENCY: Pipeline and Hazardous Materials Safety Administration, DOT. ACTION: Notice and request...

Safety culture aspects of managing for safety. Experience of a large nuclear reprocessing site

International Nuclear Information System (INIS)

Rycraft, H.S.

1996-01-01

The Nuclear Industry is going through turbulent times both in terms of public acceptance and business issues. Safety is one area which impacts on whether the business is allowed to continue, and how an organisation organizes itself. The need to cut costs to make nuclear power a viable energy resource, has forced the nuclear utilities to review manning policies, and management style, and in particular how to maintain safety standards during a period of change, and ultimately support continuing improvement of standards. The shrinking workforce requires a new style of management, one that depends more on the people of the organisation taking responsibility for safety at all levels of the organisation. Not only personal safety but the safety of their colleagues, general public and the environment. The safety culture of an organisation is indivisible from the company culture, each aspect of a culture influences the whole and so the balance between business, safety and quality, has to be managed. BNFL provides a full fuel cycle service to nuclear power plants, and associated services to many national and international organisations. The following notes are taken from the work carried out in the company, and mostly at the Nuclear Reprocessing and Waste storage Site at Sellafield, based in the North West of England. Following the recent re-organisation, the site now employs 6200 people and has a further 1500 contractors working on construction activities on the site. Activities on the site range from remote handling to hands on tasks, involving highly active materials to low level waste. (author)

Potential safety features and safety analysis aspects for high performance light water reactor (HPLWR)

International Nuclear Information System (INIS)

Aksan, N.; Schulenberg, T.; Squarer, D.

2003-01-01

Research Activities are ongoing worldwide to develop advanced nuclear power plants with high thermal efficiency for the purpose to improve their economical competitiveness. Within the 5th Framework Programme of the European Commission, a project has been launched with the main objective to assess the technical and economical feasibility of a high efficiency LWR operating at super critical pressure conditions. Several European research institutions, industrial partners and the University of Tokyo participated and worked in this common research project. Within the aims of the development of the HPLWR is to use both passive and active safety systems for performing safety related functions in the event of transients or accidents. Consequently substantial effort has been invested in order to define the safety features of the plant in a European environment, as well as to incorporate passive safety features into the design. Throughout this process, the European Utility Requirements (EUR) and requirements known from Generation IV initiative were considered as a guideline in general terms in order to include further advanced ideas. The HPLWR general features were compared to both requirements, indicating a potential to meet these. Since, the supercritical HPLWR represents a challenge for best-estimate safety codes like RELAP5, CATHARE and TRAB due to the fact that these codes were developed for two-phase or single-phase coolant at pressures far below critical point, work on the preliminary assessment of the appropriateness of these codes have been performed for selected relevant phenomena, and application of the codes to the selected transients on the basis of defined 'reference design'. An overview on their successful upgrade to supercritical pressures and application to some plant safety analysis are provided in the paper. Further elaborations in relation to future needs are also discussed. (author)

Annual activity report of Ignalina NPP Safety Analysis Group for 1996 year

International Nuclear Information System (INIS)

Ushpuras, E.; Augutis, J.; Bubelis, E.

1997-03-01

The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1996 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system. Ignalina Safety Analysis Report was prepared on the basis of these results. 37 refs., 9 tabs., 96 figs

Discussion on safety culture general contract model of consultation enterprises

International Nuclear Information System (INIS)

Dong Huimin; Zhang Hao

2012-01-01

With a high safety requirement, long construction period, a large amount of investment and many influencing factors of the preparation and implementation of project schedule, local nuclear power always is built through EPC. Safety level depends on EPC. Some measures should be taken for local consultation enterprises to improve situation of safety. Some suggestion as follows: safety culture should be received enough attention; management system should be established in according with requirement of safety culture; try to encourage employee involvement; to assess it in time; safety system should be entirely compatible with enterprises system. (authors)

Safety update on the use of recombinant activated factor VII in approved indications.

Science.gov (United States)

Neufeld, Ellis J; Négrier, Claude; Arkhammar, Per; Benchikh el Fegoun, Soraya; Simonsen, Mette Duelund; Rosholm, Anders; Seremetis, Stephanie

2015-06-01

This updated safety review summarises the large body of safety data available on the use of recombinant activated factor VII (rFVIIa) in approved indications: haemophilia with inhibitors, congenital factor VII (FVII) deficiency, acquired haemophilia and Glanzmann's thrombasthenia. Accumulated data up to 31 December 2013 from clinical trials as well as post-marketing data (registries, literature reports and spontaneous reports) were included. Overall, rFVIIa has shown a consistently favourable safety profile, with no unexpected safety concerns, in all approved indications. No confirmed cases of neutralising antibodies against rFVIIa have been reported in patients with congenital haemophilia, acquired haemophilia or Glanzmann's thrombasthenia. The favourable safety profile of rFVIIa can be attributed to the recombinant nature of rFVIIa and its localised mechanism of action at the site of vascular injury. Recombinant FVIIa activates factor X directly on the surface of activated platelets, which are present only at the site of injury, meaning that systemic activation of coagulation is avoided and the risk of thrombotic events (TEs) thus reduced. Nonetheless, close monitoring for signs and symptoms of TE is warranted in all patients treated with any pro-haemostatic agent, including rFVIIa, especially the elderly and any other patients with concomitant conditions and/or predisposing risk factors to thrombosis. Copyright © 2015 Elsevier Ltd. All rights reserved.

White paper on nuclear safety in 2004

International Nuclear Information System (INIS)

2005-05-01

The white paper consists of four parts. The first part described the regulation of nuclear facility decommissioning and the clearance level at which the decommissioned waste materials are not necessarily treated as radioactive materials. The second part explained the main operations of the nuclear safety regulation of the Nuclear Safety Commission and the regulatory bodies in 2004 and Mihama unit 3 accident. The third part introduced various activities for the general preservation of nuclear safety in Japan, such as safety regulation systems for nuclear facilities, disaster preparedness of nuclear facilities, progress in nuclear research, environmental radiation surveys and international cooperation on nuclear safety. The forth part contained various materials and data related to the Nuclear Safety Commission. (J.P.N.)

Present state of 'Mutsu', the general inspection of safety and the repair of shielding

International Nuclear Information System (INIS)

1980-01-01

The Agency has carried out the works based on the plan for the repair of shielding and the general inspection of safety in the nuclear ship ''Mutsu'' also in 1979. As for the repair of shielding, the permission by the prime minister to alter the nuclear reactor installation was obtained. The contents of the alteration are the repair of primary and secondary shieldings and the additional construction of a tank for storing liquid waste. As for the general inspection of safety, the tests for confirming the functions of main machinery and equipments have been carried out since January, 1979. A set of testing apparatuses was made as the preparation for the flaw detection test of steam generator tubes. As for the general inspection of softwares, the re-evaluation of the design of nuclear reactor plant and the analysis of the accidents in nuclear reactor plant were almost completed. Considering the accident of TMI No. 2 reactor, the inspection of softwares is in progress. The contract for these repair and inspection is not yet made, and the negotiations are under way. The nuclear ship ''Mutsu'' was brought to Sasebo Port in October, 1978, and dry-docked in July, 1979. As the result of inspection, any rust and wear were not found on the bottom plates, rudder and propeller. The survey of environmental radioactivity in Sasebo and Ominato, the budget for the repair and inspection, and the movement of the government are also reported. (Kako, I.)

Construction safety in DOE. Part 1, Students guide

Energy Technology Data Exchange (ETDEWEB)

Handwerk, E C

1993-08-01

This report is the first part of a compilation of safety standards for construction activities on DOE facilities. This report covers the following areas: general safety and health provisions; occupational health and environmental control/haz mat; personal protective equipment; fire protection and prevention; signs, signals, and barricades; materials handling, storage, use, and disposal; hand and power tools; welding and cutting; electrical; and scaffolding.

Safety assessment of discharge chute isolation barrier preparation and installation activities. Revision 3

International Nuclear Information System (INIS)

Meichle, R.H.

1994-01-01

This revision adds a section addressing impacts of dropping surfacing tool and rack cutter on the basin floor, and corrects typographical errors. The safety assessment is made for the activities for the preparation and installation of the discharge chute isolation barriers. The safety assessment includes a hazard assessment and comparisons of potential accidents/events to those addressed by the current safety basis documentation. No significant hazards were identified. An evaluation against the USQ evaluation questions was made and the determination made that the activities do not represent a USQ. Hazard categorization techniques were used to provide a basis for readiness review classifications

A Study of Cyber Security Activities for Development of Safety-related Controller

Energy Technology Data Exchange (ETDEWEB)

Lee, Myeongkyun; Song, Seunghwan; Yoo, Kwanwoo; Yun, Donghwa [Korea Univ., Seoul (Korea, Republic of)

2014-05-15

Nuclear Power Plant Regulatory guide describes the regulatory requirements to implement cyber security activities to ensure that design and operate to respond to cyber threats that exploited to vulnerability of digital-based technologies associated with safety-related digital instrumentation and control systems at nuclear power plants. Cyber security activities coverage is instrumentation and control systems to perform safety functions and digital-based equipment to use development, test, analysis and asset for instrumentation and control systems. Regulatory guidance is required to the cyber security activities that should be performed in each development phase of safety-related controller. Development organization should establish and implement to cyber security plans for responding to cyber threats throughout each lifecycle phase and the result of the cyber security activities should be generated to the documents. In addition, the independent verification and validation organization should perform simulated penetration test for enhancing response capabilities to cyber security threats and development organization should establish and implement response hardening solutions for the cyber security vulnerabilities identified in the simulated penetration test.

A Study of Cyber Security Activities for Development of Safety-related Controller

International Nuclear Information System (INIS)

Lee, Myeongkyun; Song, Seunghwan; Yoo, Kwanwoo; Yun, Donghwa

2014-01-01

Nuclear Power Plant Regulatory guide describes the regulatory requirements to implement cyber security activities to ensure that design and operate to respond to cyber threats that exploited to vulnerability of digital-based technologies associated with safety-related digital instrumentation and control systems at nuclear power plants. Cyber security activities coverage is instrumentation and control systems to perform safety functions and digital-based equipment to use development, test, analysis and asset for instrumentation and control systems. Regulatory guidance is required to the cyber security activities that should be performed in each development phase of safety-related controller. Development organization should establish and implement to cyber security plans for responding to cyber threats throughout each lifecycle phase and the result of the cyber security activities should be generated to the documents. In addition, the independent verification and validation organization should perform simulated penetration test for enhancing response capabilities to cyber security threats and development organization should establish and implement response hardening solutions for the cyber security vulnerabilities identified in the simulated penetration test

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.)

National report of the Slovak Republic compiled according to the terms of the convention on nuclear safety

International Nuclear Information System (INIS)

Adamovsky, V.; Betak, A.; Balaj, J.; Bystricka, S.; Grebeciova, J.; Husarcek, J.; Metke, E.; Pospisil, M.; Smrtnik, I.; Turner, M.; Uhrik, P.; Zemanova, D.; Bulla, R.; Filip, A.; Jurina, V.; Sedlak, M.; Tomek, J.; Zimermann, M.

2013-06-01

A brief safety report of the Slovak Republic in 2013 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovak Republic in terms of the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in the Slovak Republic; ((6) Annexes; (6.1) List of nuclear installations and technical and economic indicators; (6.2) Selected generally binding legal regulations and safety guidelines in relation to nuclear and radiation safety; (6.3) List of selected national and international documents applicable to safety of nuclear installations; (6.4) Limits for radioactive discharges; (6.5) IAEA Action Plan on Nuclear Safety; (6.6) Team of authors.

Personnel Risks in Ensuring Safety of Medical Activity

Directory of Open Access Journals (Sweden)

O. L. Zadvornaya

2017-01-01

Full Text Available Purpose: modern strategies of management of the organization require the formation of special management approaches based on the analysis of the mechanisms and processes of the organization of medical activities related to possible risks in activity of medical personnel. Based on international experience and own research the authors have identified features of a system of management of personnel risk in medical activities, examined approaches showing the sequence and contents of the main practical activities of the formation, maintenance and development of the system of management of personnel risks. Emphasized is the need for further research and implementation of the system of management of personnel risk in health care organizations. Study and assessment of personnel risks affecting the security of medical activities aimed at the development of the system of personnel risk management, development of a system of identification and monitoring of HR risk indicators with a purpose to improve institutional management and increase efficiency of activity of medical organizations. Methods: in the present study, the following methods were used: systemic approach, content analysis, methods of social diagnosis (questionnaires, interviews, comparative analysis, method of expert evaluations, method of statistical processing of information. Results: approaches to predict the occurrence and development of personnel risks have been reviewed and proposed. Conclusions and Relevance: patient safety is a global issue affecting countries at all levels of development. Each year, the WHO identifies a number of systemic and technical aspects and trends in the field of patient safety related to actions of medical workers. Existing imbalances in the staffing of the health system of the Russian Federation increase the probability of potential risks in medical practice. The personnel policy of healthcare of the Russian Federation requires further improvement and

Safety

International Nuclear Information System (INIS)

1998-01-01

A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Nuclear safety; (2) Industrial and health safety; (3) Radiation safety; and Fire protection

Health and safety annual report 1989

International Nuclear Information System (INIS)

1989-01-01

This 1989 annual report on Health and Safety in BNFL is intended to give the public a general review of the impact of the Company's activities on its workforce, the public and the environment. The activities at Sellafield, Springfields, Chapelcross, Drigg and Capenhurst are outlined, together with sections on medical services and transport, and radiation monitoring of workforce and the environment. (author)

Working group 5: Safety

International Nuclear Information System (INIS)

Vinck, W.

1976-01-01

The technical aspects of safety for the LWR nuclear power plants, and a reprocessing plant are considered. The origin, the type and the extent of the risks for the civil populations are presented for normal working as well as accidental conditions. A general estimate of comparative risks is given for the nuclear industry with respect to other activities. The legal Belgian aspects and their applications, the kind and the quality of the technical testings, the back-fitting of plants are analysed. Considerations are given on the probabilistic analysis, the safety, and the off-shore power plants. (A.F.)

Meeting the global demand of sports safety: the intersection of science and policy in sports safety.

Science.gov (United States)

Timpka, Toomas; Finch, Caroline F; Goulet, Claude; Noakes, Tim; Yammine, Kaissar

2008-01-01

Sports and physical activity are transforming, and being transformed by, the societies in which they are practised. From the perspectives of both competitive and non-competitive sports, the complexity of their integration into today's society has led to neither sports federations nor governments being able to manage the safety problem alone. In other words, these agencies, whilst promoting sport and physical activity, deliver policy and practices in an uncoordinated way that largely ignores the need for a concurrent overall policy for sports safety. This article reviews and analyses the possibility of developing an overall sports safety policy from a global viewpoint. Firstly, we describe the role of sports in today's societies and the context within which much sport is delivered. We then discuss global issues related to injury prevention and safety in sports, with practical relevance to this important sector, including an analysis of critical policy issues necessary for the future development of the area and significant safety gains for all. We argue that there is a need to establish the sports injury problem as a critical component of general global health policy agendas, and to introduce sports safety as a mandatory component of all sustainable sports organizations. We conclude that the establishment of an explicit intersection between science and policy making is necessary for the future development of sports and the necessary safety gains required for all participants around the world. The Safe Sports International safety promotion programme is outlined as an example of an international organization active within this arena.

IAEA Director General reviews state of the world's nuclear security, safety and technology at annual IAEA General Conference

International Nuclear Information System (INIS)

2002-01-01

The IAEA has been unable to draw any conclusion or provide any assurance regarding Iraq's compliance with its obligations under the Security Council resolutions, it will therefore be important for the Agency to resolve, upon re-commencement of inspections, the key issue of whether the situation regarding Iraq's nuclear activities and capabilities has changed in any material way since December 1998. Regarding the status of IAEA's Safeguards Agreement with the Democratic People's Republic of Korea (DPRK) the Agency continues to be unable to verify that the DPRK has declared all the nuclear material that is subject to Agency safeguards measures under its NPT safeguards agreement. The work required to verify the correctness and completeness of the DPRK's initial declaration could take three or four years. On the issue of nuclear non-proliferation, the universalization, consolidation and strengthening of the non-proliferation regime, including concrete steps to reduce the number of and dependence on nuclear weapons, are more important than ever for the continuing sustainability and credibility of the regime. Only 27 countries had brought into force Additional Protocols agreements with the Agency, which gives the Agency increased authority to provide assurances that countries were using their nuclear actives for peaceful civilian purposes only. All countries are urged to do so. An expanded effort was needed including threat assessments to protect nuclear facilities against attack, sabotage or theft. The focus of these efforts must be expanded to cover other nuclear facilities, including research installations that also have nuclear and other radioactive material. A significant short-term priority is to bring radioactive sources under appropriate control, whether in use, storage, orphaned or in transport. Concerning global nuclear safety, it is satisfying to note that nuclear safety continues to improve at power plants worldwide. The future of nuclear power, depends on

Safety Review Services, Site Review Services and IRRS

International Nuclear Information System (INIS)

Yllera, Javier

2010-01-01

The selection and the evaluation of the site for a nuclear power plant are crucial parts of establishing a nuclear power programme and can be significantly affected by costs, public acceptance and safety considerations. Siting is the process of selecting a suitable site for a facility. This is area containing the plant, defined by a boundary and under effective control of the Plant Management. For safety related issues comparison within topics is generally quite straightforward. For example, sites with relatively higher seismic hazard would be penalized in comparison with those in more stable areas. The site for the NPP is generally chosen at a relatively ‘aseismic’ part of the country. This generally means that well known seismogenic sources are more than at least 50 kms from the site. The proposed sites for nuclear installations shall be examined with respect to the frequency and the severity of natural and human induced events and phenomena that could affect the safety of the installation. The Events unconnected with the operation of a facility or activity which could have an effect on the safety of the facility or activity. The relationship between the site and the design for the nuclear installation shall be examined to ensure that the radiological risk to the public and the environment arising from releases defined by the source terms is acceptably low. The Nuclear Regulatory Authority should issue a document that sets out the technical safety and security criteria against which the Site Permit Application for a new NPP will be reviewed. The objective of the Site Safety Review Services (SSRS) is provided upon request from a Member State. An independent review and assessment of the site and nuclear installation safety in relation to external natural and man induced hazards. This is to make recommendations on additional analysis or plant modifications to be carried out in order to comply with the IAEA Safety Standards and to enhance safety

National report of Brazil. Nuclear Safety Convention

International Nuclear Information System (INIS)

1998-09-01

This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

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.

Visit safety

CERN Document Server

2012-01-01

Experiment areas, offices, workshops: it is possible to have co-workers or friends visit these places.     You already know about the official visits service, the VIP office, and professional visits. But do you know about the safety instruction GSI-OHS1, “Visits on the CERN site”? This is a mandatory General Safety Instruction that was created to assist you in ensuring safety for all your visits, whatever their nature—especially those that are non-official. Questions? The HSE Unit will be happy to answer them. Write to safety-general@cern.ch.   The HSE Unit

On-going and some future safety related activities of the OECD/NEA

International Nuclear Information System (INIS)

Frescura, G.

2001-01-01

The CSNI and CNRA structures and current activities of direct relevance to WWERs are presented. The nuclear regulatory challenges arising from economic deregulation like: direct safety challenges, infrastructure issues, increased pressure on regulatory bodies etc. are given. The OECD/NEA initiatives on assuring nuclear safety competence are mentioned

Regulatory support activities of JNES by thermal-hydraulic and safety analyses

International Nuclear Information System (INIS)

Kasahara, Fumio

2008-01-01

Current status and some related topics on regulatory support activities of Japan Nuclear Energy Safety Organization (JNES) by thermal-hydraulic and safety analyses are reported. The safety of nuclear facilities is secured primarily by plant owners and operators. However, the regulatory body NISA (Nuclear and Industrial Safety Agency) has conducted a strict regulation to confirm the adequacy of the site condition as well as the basic and detailed design. The JNES has been conducting independent analyses from applicants (audit analyses, etc.) by direction of NISA and supporting its review. In addition to the audit analysis, thermal-hydraulic and safety analyses are used in such areas as analytical evaluation for investigation of causes of accidents and troubles, level 2 PSA for risk informed regulation, etc. Recent activities of audit analyses are for the application of Tsuruga 3 and 4 (APWR), the spent fuel storage facility for the establishment, and the LMFBR Monju for the core change. For the trouble event evaluation, the criticality accident analysis of Sika1 was carried out and the evaluation of effectiveness of accident management (AM) measure for Tomari 3 (PWR) and Monju was performed. The analytical codes for these evaluations are continuously revised by reflecting the state-of-art technical information and validated using the information provided by the data from JAEA, OECD project, etc. (author)

National legislative and regulatory activities

International Nuclear Information System (INIS)

2014-01-01

This section of the Bulletin presents a summary of the recent national legislative and regulatory activities sorted by country and topic: - Algeria: Nuclear security. - France: Radioactive waste management; Nuclear safety and radiological protection; General legislation; International co-operation. - Germany: International trade. - Indonesia: Nuclear security, General legislation. - Ireland: Nuclear safety and radiological protection; General legislation. - Lithuania: Nuclear security; Nuclear safety and radiological protection. - Slovak Republic: International co-operation; Liability and compensation; Environmental protection. - Switzerland: Radioactive waste management. - United Arab Emirates: Liability and compensation. - United States: Radioactive waste management; Licensing and regulatory infrastructure

Medication safety activities of hospital pharmacists in Ghana; challenges and perceived impact on patient care.

Science.gov (United States)

Acheampong, Franklin; Bruce, Elizabeth; Anto, Berko Panyin

2015-01-01

Pharmacists by their training have the competences and skills to promote safe use of medicines which is an essential component of patient safety. This study explored the perceptions of hospital pharmacists' role in medication safety in Ghana, identified their attendant challenges and ways of enhancing such roles in the future. A self-administered questionnaire was delivered to 200 pharmacists selected conveniently from the 10 regions of Ghana. Questions in the questionnaire were based on a systematic literature review that had catalogued and summarised all the activities of hospital pharmacists related to medication safety. A total of 176 (88% response rate) questionnaires were completed and returned. Almost all pharmacists (97.7%) believed that they were involved in medication safety activities in their daily routine. The frequently performed activities were counselling of out-patient (91.8%), training pharmacy and other clinical students (72.2%), reporting on medication errors (70%), and reconciling medications (69.2%). The mean weekly time spent on the activities ranged from 6.5 to 19.8 hours. Participants who had clinical pharmacy related additional qualifications (χ2 = 37.749; p = 0.049) and worked in tertiary care hospitals (χ2 = 26.6; p = 0.377) undertook more medication safety activities than those without. The cited challenges faced by participants included inadequate time available (62.7%), spending most time in managerial activities (47.3%), lack of formal structures of engagement (43.8%), lack of motivation by superiors (34.9%), and no formal schedule by supervisor (32%). Only 7.7% stated they lack interest in performing those activities. Pharmacists undertake many medication safety activities routinely that they perceive to have impact on patient care outcomes. Restructuring of their managerial roles will contribute to freeing time for pharmacists to engage more in those activities.

Safety activities and human resource development at NCA

International Nuclear Information System (INIS)

Kumanomido, Hironori; Sakurada, Koichi; Yanagisawa, Shigeru; Masuyama, Tadaharu

2015-01-01

Toshiba Nuclear Critical Assembly (NCA) has been safely operated since the first criticality in December 1963. The topics covered in this Yayoi Meeting Report are: (1) the outline of NCA, (2) the safety control situation mainly after the Great East Japan Earthquake in 2011, (3) educational training incorporates the lessons learned in this earthquake, and (4) human resource development during 2008-2015. Regarding safety control, facility maintenance has been conducted systematically according to the maintenance plan from the viewpoint of preventive maintenance. Regarding educational training, two disaster handling training based on the safety regulation and one nuclear emergency drill based on the emergency drill plan for licensee of nuclear energy activity based on the Act of Special Measures Concerning Nuclear Emergency Preparedness every year. Regarding human resource development, development training was given to 358 people including students. This year, training that does not require NCA operation was conducted including gamma-ray spectrum measurement of NCA fuel rod and neutron deceleration property measurement using 252 Cf neutron source. (S.K.)

A generic standard for assessing and managing activities with significant risk to health and safety

International Nuclear Information System (INIS)

Wilde, T.S.; Sandquist, G.M.

2005-01-01

Some operations and activities in industry, business, and government can present an unacceptable risk to health and safety if not performed according to established safety practices and documented procedures. The nuclear industry has extensive experience and commitment to assessing and controlling such risks. This paper provides a generic standard based upon DOE Standard DOE-STD-3007- 93, Nov 1993, Change Notice No. 1, Sep 1998. This generic standard can be used to assess practices and procedures employed by any industrial and government entity to ensure that an acceptable level of safety and control prevail for such operations. When any activity and operation is determined to involve significant risk to health and safety to workers or the public, the organization should adopt and establish an appropriate standard and methodology to ensure that adequate health and safety prevail. This paper uses DOE experience and standards to address activities with recognized potential for impact upon health and safety. Existing and future assessments of health and safety issues can be compared and evaluated against this generic standard for insuring that proper planning, analysis, review, and approval have been made. (authors)

Quality and safety in radiotherapy

CERN Document Server

Pawlicki, Todd

2010-01-01

The first text to focus solely on quality and safety in radiotherapy, this work encompasses not only traditional, more technically oriented, quality assurance activities, but also general approaches of quality and safety. It includes contributions from experts both inside and outside the field to present a global view. The task of assuring quality is no longer viewed solely as a technical, equipment-dependent endeavor. Instead, it is now recognized as depending on both the processes and the people delivering the service. Divided into seven broad categories, the text covers: Quality Management

Innovation and Safety. A prestudy

International Nuclear Information System (INIS)

Rollenhagen, Carl; Hansson, Sven Ove; Hortberg, Johan; Jakobsson, Fredrik; Zhau, Victoria Jing; Mojeri, Sara

2010-04-01

The project summarized in this report was initiated to explore relations between innovation and safety. The first two sections of the report discuss some previously conducted research and give a general background to the subject. It is concluded that safety research and innovation research, by and large, has developed as separate academic disciplines. The concepts of 'innovative safety culture' and 'safe innovation cultures' are suggested as two concepts that can be used to integrate research: innovative safety cultures depart from safety culture research but attempts to introduce an innovative dimension with the aim to create adaptive and innovative safety cultures that efficiently can handle risks arising from existing innovations. Safe innovation cultures have focus on innovation itself, but with the ambition to introduce concepts and methods from safety research in the innovative processes. Three subprojects conducted in the context of the present research are summarized. The first project examines how an existing organization (e.g. SKB - Swedish Nuclear Fuel and Waste Management) attempts to integrate both innovative activities and operative activities in the same organisation. Interviews with key personnel explored different views about how innovative and safety work coexists in the organisation. The second project focuses on how major retrofit projects of a nuclear power plant is managed in parallel to operative activities (e.g. operating the plant on an everyday basis). By means of an innovative technique (e.g. system groups) seminars were held to suggest improvements in the technical change process. The third project conducted a risk analysis of a major organisational change (e.g. control centres for energy distribution). Experiences from the three projects are finally discussed in terms of similarities and differences associated with the cultures for innovation and safety. Suggestions for further research are made

Defining safety culture and the nexus between safety goals and safety culture. 4. Enhancing Safety Culture Through the Establishment of Safety Goals

International Nuclear Information System (INIS)

Tateiwa, Kenji; Miyata, Koichi; Yahagi, Kimitoshi

2001-01-01

Safety culture is the perception of each individual and organization of a nuclear power plant that safety is the first priority, and at Tokyo Electric Power Company (TEPCO), we have been practicing it in everyday activities. On the other hand, with the demand for competitiveness of nuclear power becoming even more intense these days, we need to pursue efficient management while maintaining the safety level at the same time. Below, we discuss how to achieve compatibility between safety culture and efficient management as well as enhance safety culture. Discussion at Tepco: safety culture-nurturing activities such as the following are being implemented: 1. informing the employees of the 'Declaration of Safety Promotion' by handing out brochures and posting it on the intranet home page; 2. publishing safety culture reports covering stories on safety culture of other industry sectors, recent movements on safety culture, etc.; 3. conducting periodic questionnaires to employees to grasp how deeply safety culture is being established; 4. carrying out educational programs to learn from past cases inside and outside the nuclear industry; 5. committing to common ownership of information with the public. The current status of safety culture in Japan sometimes seems to be biased to the quest of ultimate safety; rephrasing it, there have been few discussions regarding the sufficiency of the quantitative safety level in conjunction with the safety culture. Safety culture is one of the most crucial foundations guaranteeing the plant's safety, and for example, the plant safety level evaluated by probabilistic safety assessment (PSA) could be said to be valid only on the ground that a sound and sufficient safety culture exists. Although there is no doubt that the safety culture is a fundamental and important attitude of an individual and organization that keeps safety the first priority, the safety culture in itself should not be considered an obstruction to efforts to implement

Mathematical modelling of active safety system functions as tools for development of driverless vehicles

Science.gov (United States)

Ryazantsev, V.; Mezentsev, N.; Zakharov, A.

2018-02-01

This paper is dedicated to a solution of the issue of synthesis of the vehicle longitudinal dynamics control functions (acceleration and deceleration control) based on the element base of the vehicle active safety system (ESP) - driverless vehicle development tool. This strategy helps to reduce time and complexity of integration of autonomous motion control systems (AMCS) into the vehicle architecture and allows direct control of actuators ensuring the longitudinal dynamics control, as well as reduction of time for calibration works. The “vehicle+wheel+road” longitudinal dynamics control is complicated due to the absence of the required prior information about the control object. Therefore, the control loop becomes an adaptive system, i.e. a self-adjusting monitoring system. Another difficulty is the driver’s perception of the longitudinal dynamics control process in terms of comfort. Traditionally, one doesn’t pay a lot of attention to this issue within active safety systems, and retention of vehicle steerability, controllability and stability in emergency situations are considered to be the quality criteria. This is mainly connected to its operational limits, since it is activated only in critical situations. However, implementation of the longitudinal dynamics control in the AMCS poses another challenge for the developers - providing the driver with comfortable vehicle movement during acceleration and deceleration - while the possible highest safety level in terms of the road grip is provided by the active safety system (ESP). The results of this research are: universal active safety system - AMCS interaction interface; block diagram for the vehicle longitudinal acceleration and deceleration control as one of the active safety system’s integrated functions; ideology of adaptive longitudinal dynamics control, which enables to realize the deceleration and acceleration requested by the AMCS; algorithms synthesised; analytical experiments proving the

Strategy for public understanding and participation in nuclear safety regulation

Energy Technology Data Exchange (ETDEWEB)

Kim, H. J.; Chung, Yun Hyung

2004-02-15

The objective of this study is to help the general public and local residents to better understand and trust nuclear safety regulation. In order to obtain public confidence in nuclear safety regulation, the emotion and demand of public should be first understood and the change in an attitude to meet the present circumstances actively is requisite. Hence it is intended that a genuine communication shall be newly arranged and accomplished on the basis of mutual understanding. To achieve this, a series of public opinion poll have performed periodically and symposium for the public acceptance is held in order to frame a policy based on the understanding of nuclear safety and regulation of the general public and local residents. Besides nuclear safety indicators including safety sentiment indicators are being developed as a means to understand the safety of operating nuclear power plants from the viewpoint of the general public, a plan for the harmonious communication of nuclear safety information is established, and handbooks of nuclear terminologies and report-writing are under development in part. Finally plans for convergence of the public opinions and a wide public involvement in nuclear safety regulation are formulated and their applicability as organization and administration program is now under consideration.

Statement to the forty-fourth regular session of the IAEA General Conference 2000. IAEA General Conference. Vienna, 18 September 2000

International Nuclear Information System (INIS)

ElBaradei, M.

2000-01-01

In his Statement on the forty-fourth regular session of the General Conference of the IAEA, the Director General of the Agency highlighted IAEA's achievements in connection with its major functions: as catalyst for the development and transfer of nuclear technology (nuclear power, nuclear fuel cycle and waste management, preservation of nuclear expertise, nuclear science and applications, laboratory and research activities, future challenges in nuclear technology), as a recognized authority on nuclear safety (international conventions, establishment of international standards, safety services, early shutdown of nuclear power plants, decommissioning issues, Kursk submarine accident, future challenges in nuclear safety), and as an instrument for the verification of nuclear non-proliferation (safeguards agreements and additional protocols, implementation of United Nations Security Council Resolutions relating to Iraq, safeguards agreement with the Democratic People's Republic of Korea, application of IAEA Safeguards in the Middle East, other verification activities, security of material, future challenges in verification. He also discussed the Agency's technical co-operation programme and the Agency management for maximum efficiency and effectiveness, and the new outreach policy

Proceedings of fuel safety research specialists' meeting

International Nuclear Information System (INIS)

Suzuki, Motoe

2002-08-01

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

National report of the Slovak Republic. Compiled in terms of the convention on nuclear safety. September 2004

International Nuclear Information System (INIS)

Balaj, J.; Jurina, V.; Kasana, A.

2004-09-01

A brief national safety report of the Slovak Republic in 2004 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovakia according to the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; (6) Annexes: 6.1 List of nuclear installations and technical and economic parameters; 6.2 Some generally binding legal documents concerning nuclear and radiation safety; 6.3 Limits of radioactive discharges; 6.4 Author team. Contents, list of abbreviations used as well as reference index are included

Report on nuclear safety on the operation of nuclear facilities in 1989

International Nuclear Information System (INIS)

Gregoric, M.; Levstek, M. F.; Horvat, D.; Kocuvan, M.; Cresnar, N.

1990-01-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1989.

Report on nuclear safety on the operation of nuclear facilities in 1990

International Nuclear Information System (INIS)

Gregoric, M.; Grlicarev, I.; Horvat, D.; Levstek, M.F.; Lukacs, E.; Kocuvan, M.; Skraban, A.

1991-06-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1990.

Neighbourhood social trust and youth perceptions of safety during daily activities.

Science.gov (United States)

Flynn, Kalen; Richmond, Therese S; Branas, Charles C; Wiebe, Douglas J

2017-10-07

Exposure to adverse neighbourhood conditions can negatively impact adolescent well-being and perceived safety. However, the impact of neighbourhood social trust on perceived safety is largely unknown. We studied 139 adolescent men to investigate how their perceptions of safety varied as a function of social trust levels in the neighbourhoods they traversed; neighbourhoods that were not necessarily their own. Adolescents mapped their minute-by-minute activities over a recent day and rated their perceived safety on a 10-point scale during in-person interviews. Neighbourhood social trust was measured via a citywide random sample survey. Mixed effects regression showed that, compared with their safety perceptions when in areas of low social trust, older adolescents were 73% more likely to feel unsafe when in areas of medium social trust, and 89% more likely to feel unsafe when in areas of high social trust. Inverse relationships between neighbourhood social trust and adolescents' perceived safety highlight the complex interplay between youth, environmental contexts and safety. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

Sandia Laboratories environment and safety programs

International Nuclear Information System (INIS)

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

1975-01-01

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

Criticality safety basics, a study guide

Energy Technology Data Exchange (ETDEWEB)

V. L. Putman

1999-09-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates.

Criticality safety basics, a study guide

International Nuclear Information System (INIS)

Putman, V.L.

1999-01-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates

Overview of the activities of the OECD/NEA/NSC working party on nuclear criticality safety

International Nuclear Information System (INIS)

Nouri, A.; Blomquist, R.; Bradyraap, M.; Briggs, B.; Cousinou, P.; Nomura, Y.; Weber, W.

2003-01-01

The OECD Nuclear Energy Agency (NEA) started dealing with criticality-safety related subjects back in the seventies. In the mid-nineties, several activities related to criticality-safety were grouped together into the Working Party on Nuclear Criticality Safety. This working party has since been operating and reporting to the Nuclear Science Committee. Six expert groups co-ordinate various activities ranging from experimental evaluations to code and data inter-comparisons for the study of static and transient criticality behaviours. The paper describes current activities performed in this framework and the achievements of the various expert groups. (author)

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)

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

International Nuclear Information System (INIS)

Maraman, W.J.

1979-12-01

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

Reactor safety

International Nuclear Information System (INIS)

Butz, H.P.; Heuser, F.W.; May, H.

1985-01-01

The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

How trust in institutions and organizations builds general consumer confidence in the safety of food: a decomposition of effects.

Science.gov (United States)

de Jonge, J; van Trijp, J C M; van der Lans, I A; Renes, R J; Frewer, L J

2008-09-01

This paper investigates the relationship between general consumer confidence in the safety of food and consumer trust in institutions and organizations. More specifically, using a decompositional regression analysis approach, the extent to which the strength of the relationship between trust and general confidence is dependent upon a particular food chain actor (for example, food manufacturers) is assessed. In addition, the impact of specific subdimensions of trust, such as openness, on consumer confidence are analyzed, as well as interaction effects of actors and subdimensions of trust. The results confirm previous findings, which indicate that a higher level of trust is associated with a higher level of confidence. However, the results from the current study extend on previous findings by disentangling the effects that determine the strength of this relationship into specific components associated with the different actors, the different trust dimensions, and specific combinations of actors and trust dimensions. The results show that trust in food manufacturers influences general confidence more than trust in other food chain actors, and that care is the most important trust dimension. However, the contribution of a particular trust dimension in enhancing general confidence is actor-specific, suggesting that different actors should focus on different trust dimensions when the purpose is to enhance consumer confidence in food safety. Implications for the development of communication strategies that are designed to regain or maintain consumer confidence in the safety of food are discussed.

Criticality Safety Problems Related to Storage of Highly Active Liquid Waste

International Nuclear Information System (INIS)

Amin, E.

1999-01-01

The geometries of liquid waste storage tanks are not generally safe against criticality. Normally, this does not cause problems as fissile materials exist in nitric acid solution only as depleted uranium or in insignificant concentration of the originally reprocessed inventory of plutonium. However, if sedimentation of solid particles would occur, the deposited material would cause criticality safety problems. Particularly, non-horizontal installation of the storage tanks would increase the Eigen value. The effect of the storage tank inclination and the presence of transplutonium elements on the criticality safety are investigated using the NCNSRC code packages. The results are compared well with a similar German published results

IAEA Sets Up Team to Drive Nuclear Safety Action Plan

International Nuclear Information System (INIS)

2011-01-01

Full text: The International Atomic Energy Agency is setting up a Nuclear Safety Action Team to oversee prompt implementation of the IAEA Action Plan on Nuclear Safety and ensure proper coordination among all stakeholders. The 12-point Action Plan, drawn up in the wake of the Fukushima Daiichi accident, was approved by the Agency's Board of Governors on 13 September and endorsed by all 151 Member States at its General Conference last week. The team will work within the Agency's Department of Nuclear Safety and Security, headed by Deputy Director General Denis Flory, and will coordinate closely with the Director General's Office for Policy. ''The Action Plan requires immediate follow-up,'' Director General Yukiya Amano said. ''This compact, dedicated team will assist Deputy Director General Flory in implementing the measures agreed in the Action Plan.'' Gustavo Caruso, Head of the Regulatory Activities Section in the IAEA's Division of Installation Safety, has been designated as the team's Special Coordinator for the implementation of the Action Plan. The IAEA has already started implementing its responsibilities under the Action Plan, including development of an IAEA methodology for stress tests for nuclear power plants. The methodology will be ready in October. (IAEA)

The Management System for Facilities and Activities. Safety Requirements

International Nuclear Information System (INIS)

2011-01-01

This publication establishes requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States in establishing and implementing effective management systems that integrate all aspects of managing nuclear facilities and activities in a coherent manner. It details the planned and systematic actions necessary to provide adequate confidence that all these requirements are satisfied. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement.

Statement of the Director General to the forty-third regular session of the General Conference of the International Atomic Energy Agency

International Nuclear Information System (INIS)

ElBaradei, M.

1999-01-01

In his Statement on the forty-third regular session of the General Conference of the IAEA, the Director General of the Agency presented the past, present and future programme of the Agency in terms of the three 'pillars' that constitute its mandate: Nuclear technology (with emphasis on nuclear power and nuclear applications); Nuclear, radiation and waste safety (with emphasis on international conventions prescribing the basic legal norms for the safe use of nuclear energy, internationally accepted safety standards, and measures to assist Member States in the implementation of these conventions and standards, including technological solutions for improving safety); Nuclear verification and the security of material (with emphasis on IAEA safeguards, and physical protection of nuclear material), including possible new verification activities and specific verification issues (Iraq, DPRK, Middle East region). The Director General also touched in his Statement on two supporting elements that undergird these 'pillars': effective interaction with partners and the public, and achieving excellence in management

Two types of a passive safety containment for a near future BWR with active and passive safety systems

International Nuclear Information System (INIS)

Sato, Takashi; Akinaga, Makoto; Kojima, Yoshihiro

2009-01-01

The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.

Two types of a passive safety containment for a near future BWR with active and passive safety systems

Energy Technology Data Exchange (ETDEWEB)

Sato, Takashi [Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama (Japan)], E-mail: takashi44.sato@glb.toshiba.co.jp; Akinaga, Makoto; Kojima, Yoshihiro [Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama (Japan)

2009-09-15

The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.

Application of the Management System for Facilities and Activities. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This publication provides guidance for following the requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that coherently integrate all aspects of managing nuclear facilities and activities. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement; Appendix I: Transition to an integrated management system; Appendix II: Activities in the document control process; Appendix III: Activities in the procurement process; Appendix IV: Performance of independent assessments; Annex I: Electronic document management system; Annex II: Media for record storage; Annex III: Record retention and storage; Glossary.

Using the electronic health record to build a culture of practice safety: evaluating the implementation of trigger tools in one general practice.

Science.gov (United States)

Margham, Tom; Symes, Natalie; Hull, Sally A

2018-04-01

Identifying patients at risk of harm in general practice is challenging for busy clinicians. In UK primary care, trigger tools and case note reviews are mainly used to identify rates of harm in sample populations. This study explores how adaptions to existing trigger tool methodology can identify patient safety events and engage clinicians in ongoing reflective work around safety. Mixed-method quantitative and narrative evaluation using thematic analysis in a single East London training practice. The project team developed and tested five trigger searches, supported by Excel worksheets to guide the case review process. Project evaluation included summary statistics of completed worksheets and a qualitative review focused on ease of use, barriers to implementation, and perception of value to clinicians. Trigger searches identified 204 patients for GP review. Overall, 117 (57%) of cases were reviewed and 62 (53%) of these cases had patient safety events identified. These were usually incidents of omission, including failure to monitor or review. Key themes from interviews with practice members included the fact that GPs' work is generally reactive and GPs welcomed an approach that identified patients who were 'under the radar' of safety. All GPs expressed concern that the tool might identify too many patients at risk of harm, placing further demands on their time. Electronic trigger tools can identify patients for review in domains of clinical risk for primary care. The high yield of safety events engaged clinicians and provided validation of the need for routine safety checks. © British Journal of General Practice 2018.

Annual activity report of Ignalina NPP Safety Analysis Group for 1995 year

International Nuclear Information System (INIS)

Ushpuras, E.; Augutis, J.; Bubelis, E.

1995-01-01

The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1995 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system. 18 refs., 9 tabs., 110 figs

National report of the Slovak Republic. Compiled according to the terms of the convention on nuclear safety, June 2010

International Nuclear Information System (INIS)

Balaj, J.; Homola, J.; Rovny, J.; Metke, E.; Zemanova, D.; Grebeciova, J.; Turner, M.; Pospisil, M.; Bystricka, S.; Jurina, V.; Rovny, I.; Soltes, L.; Husarova, M.; Petrovic, J.; Fazekasova, H.; Zizkova, D.; Vagac, M.; Maudry, J.; Hacaj, A.; Betak, A.; Barbaric, M.

2010-06-01

A brief safety report of the Slovak Republic in 2010 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented.These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovak Republic in terms of the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; ((6) Annexes; (6.1) List of nuclear installations and technical and economic indicators; (6.2) Selected generally binding legal regulations and safety guidelines in relation to nuclear and radiation safety; (6.3) List of selected national and international documents applicable to safety of nuclear installations; (6.4) Limits for radioactive discharges; (6.5) Team of authors.

Food Safety Program in Asian Countries.

Science.gov (United States)

Yamaguchi, Ryuji; Hwang, Lucy Sun

2015-01-01

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

The social context moderates the relationships between neighborhood safety and adolescents’ physical activities

Science.gov (United States)

Background. Previous studies of neighborhood safety and physical (in)activity have typically neglected to consider the youth’s peer context as a modifier of these relationships. Objective. Test the independent and interactive effects of perceived neighborhood safety and time spent with friends and p...

Change in neighborhood traffic safety: does it matter in terms of physical activity?

NARCIS (Netherlands)

Jongeneel-Grimen, Birthe; Busschers, Wim; Droomers, Mariël; van Oers, Hans A. M.; Stronks, Karien; Kunst, Anton E.

2013-01-01

There is limited evidence on the causality of previously observed associations between neighborhood traffic safety and physical activity (PA). This study aims to contribute to this evidence by assessing the extent to which changes over time in neighborhood traffic safety were associated with PA.

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

International Nuclear Information System (INIS)

Baltes, B.

1994-01-01

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

Evaluating the effectiveness of active vehicle safety systems.

Science.gov (United States)

Jeong, Eunbi; Oh, Cheol

2017-03-01

Advanced vehicle safety systems have been widely introduced in transportation systems and are expected to enhance traffic safety. However, these technologies mainly focus on assisting individual vehicles that are equipped with them, and less effort has been made to identify the effect of vehicular technologies on the traffic stream. This study proposed a methodology to assess the effectiveness of active vehicle safety systems (AVSSs), which represent a promising technology to prevent traffic crashes and mitigate injury severity. The proposed AVSS consists of longitudinal and lateral vehicle control systems, which corresponds to the Level 2 vehicle automation presented by the National Highway Safety Administration (NHTSA). The effectiveness evaluation for the proposed technology was conducted in terms of crash potential reduction and congestion mitigation. A microscopic traffic simulator, VISSIM, was used to simulate freeway traffic stream and collect vehicle-maneuvering data. In addition, an external application program interface, VISSIM's COM-interface, was used to implement the AVSS. A surrogate safety assessment model (SSAM) was used to derive indirect safety measures to evaluate the effectiveness of the AVSS. A 16.7-km freeway stretch between the Nakdong and Seonsan interchanges on Korean freeway 45 was selected for the simulation experiments to evaluate the effectiveness of AVSS. A total of five simulation runs for each evaluation scenario were conducted. For the non-incident conditions, the rear-end and lane-change conflicts were reduced by 78.8% and 17.3%, respectively, under the level of service (LOS) D traffic conditions. In addition, the average delay was reduced by 55.5%. However, the system's effectiveness was weakened in the LOS A-C categories. Under incident traffic conditions, the number of rear-end conflicts was reduced by approximately 9.7%. Vehicle delays were reduced by approximately 43.9% with 100% of market penetration rate (MPR). These results

Recent and current activities of the OECD/NEA Working Group on Fuel Safety (NEA/CSNI). Recent and Current Activities of the Working Group on Fuel Safety (NEA/CSNI)

International Nuclear Information System (INIS)

Petit, Marc

2013-01-01

The Working Group on Fuel Safety (WGFS) is part of the Committee on the Safety of Nuclear Installations (CSNI) of the Nuclear Energy Agency and has the main mission of advancing the current understanding and addressing fuel safety issues. Recent and current activities of the working group have addressed mainly the loss of coolant accident (LOCA), the reactivity initiated accident (RIA), the fuel safety criteria and leaking fuel issues, as well as Fukushima-related fuel topics. In the area of LOCA, the group issued different documents, the most notable being a very comprehensive state of the art report [NEA/CSNI/R (2009)15]. Regarding RIA, some documents were finalised and issued in the recent years, as well as a state of the art report [NEA/CSNI/R (2010)1]. The question of leaking fuel and how it is handled in the reactors is an activity that is just starting. Of particular interest to people developing new fuel concepts is the Nuclear Fuel Safety Criteria Technical Review - Second Edition [NEA/CSNI/R (2012)3]. This document provides a broad overview of the numerous criteria used in the NEA member countries to demonstrate to safe use of fuel in light water reactors. The WGFS has started discussions about fuel related issues raised by the Fukushima accident, in particular, hydrogen production. New concepts have been proposed to solve these issues but it appears that these concepts will need to go through a long qualification process to assess their adequacy for the different situations considered in the evaluation of fuel safety, from normal operation to accident conditions

Safety class methodology

International Nuclear Information System (INIS)

Donner, E.B.; Low, J.M.; Lux, C.R.

1992-01-01

DOE Order 6430.1A, General Design Criteria (GDC), requires that DOE facilities be evaluated with respect to ''safety class items.'' Although the GDC defines safety class items, it does not provide a methodology for selecting safety class items. The methodology described in this paper was developed to assure that Safety Class Items at the Savannah River Site (SRS) are selected in a consistent and technically defensible manner. Safety class items are those in the highest of four categories determined to be of special importance to nuclear safety and, merit appropriately higher-quality design, fabrication, and industrial test standards and codes. The identification of safety class items is approached using a cascading strategy that begins at the 'safety function' level (i.e., a cooling function, ventilation function, etc.) and proceeds down to the system, component, or structure level. Thus, the items that are required to support a safety function are SCls. The basic steps in this procedure apply to the determination of SCls for both new project activities, and for operating facilities. The GDC lists six characteristics of SCls to be considered as a starting point for safety item classification. They are as follows: 1. Those items whose failure would produce exposure consequences that would exceed the guidelines in Section 1300-1.4, ''Guidance on Limiting Exposure of the Public,'' at the site boundary or nearest point of public access 2. Those items required to maintain operating parameters within the safety limits specified in the Operational Safety Requirements during normal operations and anticipated operational occurrences. 3. Those items required for nuclear criticality safety. 4. Those items required to monitor the release of radioactive material to the environment during and after a Design Basis Accident. Those items required to achieve, and maintain the facility in a safe shutdown condition 6. Those items that control Safety Class Item listed above

Classification of Radioactive Waste. General Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste.

Classification of Radioactive Waste. General Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste

Generalized periodic EEG activity in two cases of neurosyphilis

Directory of Open Access Journals (Sweden)

Anghinah Renato

2006-01-01

Full Text Available Neurosyphilis is a recognized cause of epileptic seizures and cognitive impairment, but is not usually associated with the finding of generalized periodic activity in the EEG. We report two similar cases characterized by progressive cognitive impairment followed by partial complex seizures, in whom the EEG showed generalized periodic activity. Both cerebrospinal fluid and the response to penicillin therapy confirmed the diagnoses of neurosyphilis in the two cases. The finding of EEG generalized periodic activity in patients with cognitive or behavioral disorders is usually associated with Creutzfeldt-Jakob disease, although there are other conditions, some of them potentially reversible, which may also present this EEG abnormality. Neurosyphilis has tended not to be included among them, and our present findings support the importance of first ruling out neurosyphilis in those patients with cognitive or behavioral disorders associated with generalized periodic epileptiform discharges.

78 FR 50079 - Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed...

Science.gov (United States)

2013-08-16

... DEPARTMENT OF THE INTERIOR Bureau of Safety and Environmental Enforcement [Docket ID BSEE-2013-0005; OMB Control Number 1014-0017: 134E1700D2 EEEE500000 ET1SF0000.DAQ000] Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed Collection; Comment Request...

Safety of Cargo Aircraft Handling Procedure

Directory of Open Access Journals (Sweden)

Daniel Hlavatý

2017-07-01

Full Text Available The aim of this paper is to get acquainted with the ways how to improve the safety management system during cargo aircraft handling. The first chapter is dedicated to general information about air cargo transportation. This includes the history or types of cargo aircraft handling, but also the means of handling. The second part is focused on detailed description of cargo aircraft handling, including a description of activities that are performed before and after handling. The following part of this paper covers a theoretical interpretation of safety, safety indicators and legislative provisions related to the safety of cargo aircraft handling. The fourth part of this paper analyzes the fault trees of events which might occur during handling. The factors found by this analysis are compared with safety reports of FedEx. Based on the comparison, there is a proposal on how to improve the safety management in this transportation company.

Linking Safety Analysis to Safety Requirements

DEFF Research Database (Denmark)

Hansen, Kirsten Mark

Software for safety critical systems must deal with the hazards identified by safety analysistechniques: Fault trees, event trees,and cause consequence diagrams can be interpreted as safety requirements and used in the design activity. We propose that the safety analysis and the system design use...

The promotion of work safety. A continuous task for the Swiss gas industry

International Nuclear Information System (INIS)

Luescher, H.J.

1993-01-01

The modern Western European population values the work safety very highly because of ethical and economical reasons. In Switzerland too, safety at work is actively promoted. Based on national legislation and on the SGWA-Association Statutes, the Swiss Gas Industry, with great engagement, promotes the measures for accident prevention. Following a general introduction into the legislative basis, possible ways and means for the promotion of safety at work are described. Subsequently, the concrete activities of the Gas Supply Authorities and the SGWA are pointed out, followed by a description of the future work-safety programmes of the Swiss Gas Industry. (orig.) [de

Health and safety annual report 1988

International Nuclear Information System (INIS)

1989-01-01

This report on health and safety provides a review of the impact of the Comapny's activities on its workforce, the public and the environment. New sections include safety auditing, emergency planning and health and safety research. BNFL operates five sites in north west England and southern Scotland. The head office and Engineering Design Centre is at Risley, near Warrington. Fuel is manufactured at Springfields near Preston, uranium is enriched for modern nuclear power stations at Capenhurst near Chester and spent fuel is reprocessed at Sellafield. BNFL also operate Calder Hall (Sellafield) and Chapelcross (Scotland) power stations and a disposal site for low-level radioactive wastes at Drigg near Sellafield. Radiation sources and BNFL's radioactive discharge are first explained generally and then specifically for each BNFL site. Industrial and radiological safety within BNFL are described. (UK)

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

International Nuclear Information System (INIS)

2017-01-01

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

Tank farm health and safety plan. Revision 2

International Nuclear Information System (INIS)

Mickle, G.D.

1995-01-01

This Tank Farm Health and Safety Plan (HASP) for the conduct of all operations and work activities at the Hanford Site 200 Area Tank Farms is provided in order to minimize health and safety risks to workers and other onsite personnel. The HASP accomplishes this objective by establishing requirements, providing general guidelines, and conveying farm and facility-specific hazard communication information. The HASP, in conjunction with the job-specific information required by the HASP, is provided also as a reference for use during the planning of work activities at the tank farms. This HASP applies to Westinghouse Hanford Company (WHC), other prime contractors to the U.S. Department of Energy (DOE), and subcontractors to WHC who may be involved in tank farm work activities. This plan is intended to be both a requirements document and a useful reference to aid tank farm workers in understanding the safety and health issues that are encountered in routine and nonroutine work activities. The HASP defines the health and safety responsibilities of personnel working at the tank farms. It has been prepared in recognition of and is consistent with National Institute of Safety and Health (NIOSH), and Occupational Safety and Health Administration (OSHA)/Unlimited State Coast Guard (USCG)/U.S. Environmental Protection Agency (EPA), Occupational Safety and Health Guidance Manual for Hazardous Waste Site Activities (NIOSH 1985); WHC-CM-4-3, Industrial Safety Manual, Volume 4, open-quotes Health and Safety Programs for Hazardous Waste Operations;close quotes 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response; WHC-CM-1-1, Management Policies; and WHC-CM-1-3, Management Requirements and Procedures. When differences in governing regulations or policies exist, the more stringent requirements shall apply until the discrepancy can be resolved

Tank farm health and safety plan. Revision 2

Energy Technology Data Exchange (ETDEWEB)

Mickle, G.D.

1995-03-29

This Tank Farm Health and Safety Plan (HASP) for the conduct of all operations and work activities at the Hanford Site 200 Area Tank Farms is provided in order to minimize health and safety risks to workers and other onsite personnel. The HASP accomplishes this objective by establishing requirements, providing general guidelines, and conveying farm and facility-specific hazard communication information. The HASP, in conjunction with the job-specific information required by the HASP, is provided also as a reference for use during the planning of work activities at the tank farms. This HASP applies to Westinghouse Hanford Company (WHC), other prime contractors to the U.S. Department of Energy (DOE), and subcontractors to WHC who may be involved in tank farm work activities. This plan is intended to be both a requirements document and a useful reference to aid tank farm workers in understanding the safety and health issues that are encountered in routine and nonroutine work activities. The HASP defines the health and safety responsibilities of personnel working at the tank farms. It has been prepared in recognition of and is consistent with National Institute of Safety and Health (NIOSH), and Occupational Safety and Health Administration (OSHA)/Unlimited State Coast Guard (USCG)/U.S. Environmental Protection Agency (EPA), Occupational Safety and Health Guidance Manual for Hazardous Waste Site Activities (NIOSH 1985); WHC-CM-4-3, Industrial Safety Manual, Volume 4, {open_quotes}Health and Safety Programs for Hazardous Waste Operations;{close_quotes} 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response; WHC-CM-1-1, Management Policies; and WHC-CM-1-3, Management Requirements and Procedures. When differences in governing regulations or policies exist, the more stringent requirements shall apply until the discrepancy can be resolved.

National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. 2005

International Nuclear Information System (INIS)

Hekel, P.; Ivan, J.; Lukacovic, K.; Parimucha, F.; Suss, J; Tomek, J.; Jurina, V.; Kobzova, D.; Konecny, L.; Homola, J.; Zavazanova, A.; Metke, E.; Turner, M.; Vaclav, J.; Ziakova, M.; Pospisil, M.; Petrik, T.

2005-09-01

The National Report (Compiled in terms of the Joint Convention - September 2005) contains information how each of the obligations of the Joint Convention have been implemented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) and other Slovak organisations are presented. These activities are reported under the headings: (A) Introduction; (B) Spent fuel and radioactive waste management; C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of RAW management; (I) Transboundary movement of SF and RAW; (J) Disused sealed sources; (K) planned activiries to improve safety; (L) Annexes

Fundamental safety principles. Safety fundamentals

International Nuclear Information System (INIS)

2007-01-01

This publication states the fundamental safety objective and ten associated safety principles, and briefly describes their intent and purpose. The fundamental safety objective - to protect people and the environment from harmful effects of ionizing radiation - applies to all circumstances that give rise to radiation risks. The safety principles are applicable, as relevant, throughout the entire lifetime of all facilities and activities - existing and new - utilized for peaceful purposes, and to protective actions to reduce existing radiation risks. They provide the basis for requirements and measures for the protection of people and the environment against radiation risks and for the safety of facilities and activities that give rise to radiation risks, including, in particular, nuclear installations and uses of radiation and radioactive sources, the transport of radioactive material and the management of radioactive waste

Fundamental safety principles. Safety fundamentals

International Nuclear Information System (INIS)

2006-01-01

This publication states the fundamental safety objective and ten associated safety principles, and briefly describes their intent and purpose. The fundamental safety objective - to protect people and the environment from harmful effects of ionizing radiation - applies to all circumstances that give rise to radiation risks. The safety principles are applicable, as relevant, throughout the entire lifetime of all facilities and activities - existing and new - utilized for peaceful purposes, and to protective actions to reduce existing radiation risks. They provide the basis for requirements and measures for the protection of people and the environment against radiation risks and for the safety of facilities and activities that give rise to radiation risks, including, in particular, nuclear installations and uses of radiation and radioactive sources, the transport of radioactive material and the management of radioactive waste

Introduction to safety theory

International Nuclear Information System (INIS)

Meyna, A.

1982-01-01

After a general introduction to safety theory, safety characteristics are defined and quantified. This is followed by a calculation of the safety characteristics of simple, safety-relevant systems in general and in consideration of common-mode errors. The qualitative and quantitative role of human errors is discussed for various models, and a simple man-machine model is developed for investigation of common-mode errors and human error. The main part of the paper deals with safety analysis in complex systems. After a general review, the common inductive and deductive methods of analysis are presented and commented on and their fields of application discussed. Analytical and simulation codes are presented as methods of evaluation for big, complex event trees - i.e. ''hazard trees in the sense of safety engineering (as a subset of safety relevance). After a basic classification and mathematical formulation of Markovian processes, the author shows that these may be used successfully for calculation of safety characteristics if transition rates are constant and if the number of system states is limited. (orig./RW) [de

77 FR 22387 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

Science.gov (United States)

2012-04-13

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

77 FR 58616 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

Science.gov (United States)

2012-09-21

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

25 Years of Community Activities towards Harmonization of Nuclear Safety Criteria and Requirements - Achievements and Prospects

International Nuclear Information System (INIS)

Lillington, J.N.; Turland, B.D.; Haste, T.J.; Seiler, J.M.; Carretero, A.; Perez, T.; Geutges, A.; Van Hienen, J.F.A.; Jehee, J.N.T.; Sehgal, B.R.; Mattila, L.; Holmstrom, H.; Karwat, H.; Maroti, L.; Toth, I.; Husarcek, J.

2001-10-01

The main objective was to advise the EC on future challenges and opportunities in terms of enhanced co-operation in the area of nuclear safety and harmonization of safety requirements and practices in an enlarged European Union. The activities were divided into 3 sub-tasks as follows: part A, to prepare an analysis, synthesis and assessment of the main achievements from Community activities related to the Resolutions on the technological problems of nuclear safety of 1975 and 1992, with due consideration for related research activities; part B, to prepare an overview of safety philosophies and practices in EU Member States, taking account of their specific national practices in terms of legal framework, type and age of operating nuclear reactors; part C, to provide elements of a strategy for future activities in the frame of the Council Resolutions, with particular attention to the context of enlargement of the EU. (author)

ASN report on nuclear safety and radioprotection status in France in 2010

International Nuclear Information System (INIS)

2011-01-01

After a general overview of the activity of the ASN (the French nuclear safety authority), of its missions and organisation, this activity report indicates the main events of 2010 concerning the actions performed by the ASN and the activities controlled by the ASN. These both aspects are then detailed. The actions performed by the ASN are dealing with nuclear activities (ionizing radiations and risks for health and for the environment), principles and actors of nuclear safety control, radioprotection and environment protection, regulation, control of nuclear activities and exposures to ionizing radiations, emergency situations, public information, international relationship, regional overview of nuclear safety and radioprotection. The activities controlled by the ASN are the medical uses of ionizing radiations, their non medical uses, the transport of radioactive materials, electronuclear plants, installations related to nuclear fuel cycle, nuclear research installations and other nuclear installations, the safety of nuclear installation dismantling, radioactive wastes and polluted sites

National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2003

International Nuclear Information System (INIS)

Burclova, J.; Ivan, J.; Jurina, V.

2003-04-01

A brief national safety report of the Slovak Republic in 2003 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (A) Introduction; (B) Policies and practices; (C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement; (J) Disused sealed sources; (K) Planned activities to improve safety; (L) Annexes: (I and II) List of SF and RAW management nuclear facilities; (III) List of nuclear facilities subject to decommissioning; (IV) Inventory of stored SF (t HM); (V) Inventory of disposed of and stored RAW; (VI) List of selected national laws, regulations and guidelines; (VII) List of international expert reports and safety analysis reports; (VIII) List of authors

National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2003

Energy Technology Data Exchange (ETDEWEB)

Burclova, J [Nuclear Regulatory Authority of the Slovak Republic, Bratislava (Slovakia); Ivan, J [Slovenske elektrarne, a.s., Bratislava (Slovakia); Jurina, V [Health Ministry of the Slovak Republic, Bratislava (Slovakia); and others

2003-04-01

A brief national safety report of the Slovak Republic in 2003 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (A) Introduction; (B) Policies and practices; (C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement; (J) Disused sealed sources; (K) Planned activities to improve safety; (L) Annexes: (I and II) List of SF and RAW management nuclear facilities; (III) List of nuclear facilities subject to decommissioning; (IV) Inventory of stored SF (t HM); (V) Inventory of disposed of and stored RAW; (VI) List of selected national laws, regulations and guidelines; (VII) List of international expert reports and safety analysis reports; (VIII) List of authors.

Regulatory activities in reactor safety

International Nuclear Information System (INIS)

Salvatore, J.E.L.

1987-01-01

The safety phylosophy in designs and operation of nuclear power plants and, the steps for evaluating the safety and quality assurance, in the licensing procedure are described. The CNEN organization structure and the licensing procedure for nuclear power plants in Brazil are presented. (M.C.K.) [pt

Healh and Safety at Work etc. Act 1974

International Nuclear Information System (INIS)

1974-01-01

The main purpose of this Act is to provide a single comprehensive and integrated system of law dealing with the health, safety and welfare of workpeople, and the health and safety of the public as affected by work activities. The Act establishes a Health and Safety Commission and a Health and Safety Executive to be generally responsible for administering health and safety legislation, including those provisions of the Nuclear Installations Act 1965 governing the licensing of nuclear installations, a function which was exercised by the Secretary of State for Energy and the Secretary of State for Scotland. The provisions of the Nuclear Installations Act 1965 and 1969 which give effect to the Paris Convention and the Brussels Supplementary Convention are not affected by the Act. (NEA) [fr

Instructional games and activities for criticality safety training

International Nuclear Information System (INIS)

Bullard, B.; McBride, J.

1993-01-01

During the past several years, the Training and Management Systems Division (TMSD) staff of Oak Ridge Institute for Science and Education (ORISE) has designed and developed nuclear criticality safety (NCS) training programs that focus on high trainee involvement through the use of instructional games and activities. This paper discusses the instructional game, initial considerations for developing games, advantages and limitations of games, and how games may be used in developing and implementing NCS training. It also provides examples of the various instructional games and activities used in separate courses designed for Martin Marietta Energy Systems (MMES's) supervisors and U.S. Nuclear Regulatory Commission (NRC) fuel facility inspectors

The role of informal dimensions of safety in high-volume organisational routines: an ethnographic study of test results handling in UK general practice.

Science.gov (United States)

Grant, Suzanne; Checkland, Katherine; Bowie, Paul; Guthrie, Bruce

2017-04-27

The handling of laboratory, imaging and other test results in UK general practice is a high-volume organisational routine that is both complex and high risk. Previous research in this area has focused on errors and harm, but a complementary approach is to better understand how safety is achieved in everyday practice. This paper ethnographically examines the role of informal dimensions of test results handling routines in the achievement of safety in UK general practice and how these findings can best be developed for wider application by policymakers and practitioners. Non-participant observation was conducted of high-volume organisational routines across eight UK general practices with diverse organisational characteristics. Sixty-two semi-structured interviews were also conducted with the key practice staff alongside the analysis of relevant documents. While formal results handling routines were described similarly across the eight study practices, the everyday structure of how the routine should be enacted in practice was informally understood. Results handling safety took a range of local forms depending on how different aspects of safety were prioritised, with practices varying in terms of how they balanced thoroughness (i.e. ensuring the high-quality management of results by the most appropriate clinician) and efficiency (i.e. timely management of results) depending on a range of factors (e.g. practice history, team composition). Each approach adopted created its own potential risks, with demands for thoroughness reducing productivity and demands for efficiency reducing handling quality. Irrespective of the practice-level approach adopted, staff also regularly varied what they did for individual patients depending on the specific context (e.g. type of result, patient circumstances). General practices variably prioritised a legitimate range of results handling safety processes and outcomes, each with differing strengths and trade-offs. Future safety

Defining safety culture and the nexus between safety goals and safety culture. 3. A Methodology for Identifying Deficiencies in Safety Culture

International Nuclear Information System (INIS)

Apostolakis, George; Weil, Rick

2001-01-01

At present, the drivers of performance problems at nuclear power plants (NPPs) are organizational in nature. Organizational deficiencies and other 'latent' conditions cause human errors, resulting in incidents that impact the performance of NPPs. Therefore, the human reliability community, regulators, and others concerned with NPP safety express the view that safety culture and organizational factors play an important role in plant safety. However, we have yet to identify one complete set of organizational factors, establish links between deficient safety culture and performance, or develop adequate tools to measure safety culture. This paper will contribute to the resolution of these issues. Safety culture is not a single factor but rather is a collection of several distinct factors. This paper asserts that in order to pro-actively manage safety culture at NPPs, leading indicators and appropriate measurements must be identified and developed. Central to this effort are the identification of the distinct factors comprising safety culture and the relationships between those factors and performance. We have identified several factors important to safety culture. We have developed a methodology that is a combination of traditional root-cause analysis and theories of human error, most notably Reason's theory of accident causation. In addition to this methodology's usefulness in identifying deficiencies in safety culture, it could also be used as a starting point to identify leading indicators of deteriorating safety performance. We have identified six organizational factors as being important: communication, formalization, goal prioritization, problem identification, roles and responsibilities, and technical knowledge. In addition, we have found that certain organizational factors, although pervasive throughout the organization, have a much greater influence on the successful outcome of particular tasks of work processes, rather than being equally important to all

Perceived neighborhood safety related to physical activity but not recreational screen-based sedentary behavior in adolescents.

Science.gov (United States)

Lenhart, Clare M; Wiemken, Andrew; Hanlon, Alexandra; Perkett, Mackenzie; Patterson, Freda

2017-09-18

A growing proportion of adolescents have poor cardiovascular health behaviors, including low levels of physical activity and high levels of sedentary behavior, thus increasing the likelihood of poor heart health in later years. This study tested the hypothesis that low perceived neighborhood safety would be associated with low levels of physical activity and high levels of recreational sedentary behavior in high-school students. Using cross-sectional, weighted data from the 2015 Pennsylvania (USA) State and Philadelphia city Youth Risk Behavior Survey, multivariable logistic regression modeling was used to examine the association between perceived neighborhood safety, and physical activity levels and recreational screen-based sedentary behavior time respectively, while controlling for potential confounders. After adjustment for other significant correlates of physical activity, students with low perceived neighborhood safety had a 21% reduced odds of being physically active on 5 or more days of the last week as compared to those who felt safe (p = 0.044). Perceived safety was not related to sedentary behavior; but sports team participation emerged as a strong correlate of low screen-based sedentary behavior (OR = 0.73, p = .002). These data add to a growing body of work demonstrating the importance of perceived safety with physical activity levels in youth. Sports team participation may be a viable target to reduce screen-based sedentary time.

Perceived neighborhood safety related to physical activity but not recreational screen-based sedentary behavior in adolescents

Directory of Open Access Journals (Sweden)

Clare M. Lenhart

2017-09-01

Full Text Available Abstract Background A growing proportion of adolescents have poor cardiovascular health behaviors, including low levels of physical activity and high levels of sedentary behavior, thus increasing the likelihood of poor heart health in later years. This study tested the hypothesis that low perceived neighborhood safety would be associated with low levels of physical activity and high levels of recreational sedentary behavior in high-school students. Methods Using cross-sectional, weighted data from the 2015 Pennsylvania (USA State and Philadelphia city Youth Risk Behavior Survey, multivariable logistic regression modeling was used to examine the association between perceived neighborhood safety, and physical activity levels and recreational screen-based sedentary behavior time respectively, while controlling for potential confounders. Results After adjustment for other significant correlates of physical activity, students with low perceived neighborhood safety had a 21% reduced odds of being physically active on 5 or more days of the last week as compared to those who felt safe (p = 0.044. Perceived safety was not related to sedentary behavior; but sports team participation emerged as a strong correlate of low screen-based sedentary behavior (OR = 0.73, p = .002. Conclusion These data add to a growing body of work demonstrating the importance of perceived safety with physical activity levels in youth. Sports team participation may be a viable target to reduce screen-based sedentary time.

75 FR 4904 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

Science.gov (United States)

2010-01-29

... amend regulations protecting persons who work on, under, or between rolling equipment; and persons...-7257] Railroad Safety Advisory Committee (RSAC); Working Group Activity Update AGENCY: Federal Railroad... Committee (RSAC) Working Group Activities. SUMMARY: The FRA is updating its announcement of RSAC's Working...

Active and intelligent packaging: The indication of quality and safety.

Science.gov (United States)

Janjarasskul, Theeranun; Suppakul, Panuwat

2018-03-24

The food industry has been under growing pressure to feed an exponentially increasing world population and challenged to meet rigorous food safety law and regulation. The plethora of media consumption has provoked consumer demand for safe, sustainable, organic, and wholesome products with "clean" labels. The application of active and intelligent packaging has been commercially adopted by food and pharmaceutical industries as a solution for the future for extending shelf life and simplifying production processes; facilitating complex distribution logistics; reducing, if not eliminating the need for preservatives in food formulations; enabling restricted food packaging applications; providing convenience, improving quality, variety and marketing features; as well as providing essential information to ensure consumer safety. This chapter reviews innovations of active and intelligent packaging which advance packaging technology through both scavenging and releasing systems for shelf life extension, and through diagnostic and identification systems for communicating quality, tracking and brand protection.

Environmental, Health and Safety Assessment: ATS 7H Program (Phase 3R) Test Activities at the GE Power Systems Gas Turbine Manufacturing Facility, Greenville, SC

Energy Technology Data Exchange (ETDEWEB)

None

1998-11-17

International Technology Corporation (IT) was contracted by General Electric Company (GE) to assist in the preparation of an Environmental, Health and Safety (HI&3) assessment of the implementation of Phase 3R of the Advanced Turbine System (ATS) 7H program at the GE Gas Turbines facility located in Greenville, South Carolina. The assessment was prepared in accordance with GE's contractual agreement with the U.S. Department of Energy (GE/DOE Cooperative Agreement DE-FC21-95MC3 1176) and supports compliance with the requirements of the National Environmental Policy Act of 1970. This report provides a summary of the EH&S review and includes the following: General description of current site operations and EH&S status, Description of proposed ATS 7H-related activities and discussion of the resulting environmental, health, safety and other impacts to the site and surrounding area. Listing of permits and/or licenses required to comply with federal, state and local regulations for proposed 7H-related activities. Assessment of adequacy of current and required permits, licenses, programs and/or plans.

Considering lessons learned about safety culture and their reflection to activity. After Fukushima Daiichi Nuclear Power Plant accident experience

International Nuclear Information System (INIS)

Obu, Etsuji; Hamada, Jun; Fukano, Takuya

2011-01-01

Fukushima Daiichi Nuclear Power Plant accident forced neighboring residents to evacuate for a long time and gave Public anxieties greatly and significant effects to social activities in Japan. Public trust of nuclear power was lost by not preventing the accident and future of nuclear power became reconsidered, which nuclear industry people regretted deeply. Japan Nuclear Technology Institute (JANTI) had conducted activities enhancing safety culture in nuclear industry. It would be necessary to consider improvements of accident prevention and mitigation measures after evaluating the accident in a viewpoint of 'safety culture'. Based on published information and knowledge accumulated by activities of JANTI, the accident was examined taking account of greatness of nuclear accident and its effects from the side of safety culture. Lessons learned about safety culture were pointed out as; (1) reconfirmation of specialty of nuclear technology. (2) reinforcement of questioning and learning attitudes and (3) improvement of evaluation capability of nuclear safety and safety assurance against external event. These were reflected in activities such as; (1) reconsideration of safety culture assessment, (2) strengthening further support to improve safety culture consciousness and (3) improvement of peer review activity. (T. Tanaka)

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

Integrated Safety in ''SARAF'

International Nuclear Information System (INIS)

Dickstein, P.; Grof, Y.; Machlev, M.; Pernick, A.

2004-01-01

As of the very early stages of the accelerator project at the Soreq Nuclear Research Center ''SARAF'' a safety group was established which has been an inseparable participant in the planning and design of the new facility. The safety group comprises of teams responsible for the shielding, radiation protection and general industrial safety aspects of ''SARAF''. The safety group prepared and documented the safety envelope for the accelerator, dealing with the safety requirements and guidelines for the first, pre-operational, stages of the project. The safety envelope, though based upon generic principles, took into account the accelerator features and the expected modes of operation. The safety envelope was prepared in a hierarchical structure, containing Basic Principles, Basic Guidelines, General Principles for Safety Implementation, Safety Requirements and Safety Underlining Issues. The above safety envelope applies to the entire facility, which entails the accelerator itself and the experimental areas and associated plant and equipment utilizing and supporting the production of the accelerated particle beams

PSI annual report 1995. General volume

Energy Technology Data Exchange (ETDEWEB)

Salzmann, M [ed.

1996-04-01

The report gives an overview of the PSI`s activities in 1995 in the fields of research: nuclear and particle physics, life sciences, solid state research at large facilities, applied solid state physics, nuclear energy, safety, and general energy research. The theme 1995 of the report deals with the proton therapy at PSI. figs., tabs.

PSI annual report 1995. General volume

International Nuclear Information System (INIS)

Salzmann, M.

1996-04-01

The report gives an overview of the PSI's activities in 1995 in the fields of research: nuclear and particle physics, life sciences, solid state research at large facilities, applied solid state physics, nuclear energy, safety, and general energy research. The theme 1995 of the report deals with the proton therapy at PSI. figs., tabs

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

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

International Nuclear Information System (INIS)

2014-01-01

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

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

International Nuclear Information System (INIS)

2016-01-01

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

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

International Nuclear Information System (INIS)

2015-01-01

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

The Health and Safety Executive's regulatory framework for control of nuclear criticality safety

International Nuclear Information System (INIS)

Smith, K.; Simister, D.N.

1991-01-01

In the United Kingdom the Health and Safety at Work Act, 1974 is the main legal instrument under which risks to people from work activities are controlled. Certain sections of the Nuclear Installations Act, 1965 which deal with the licensing of nuclear sites and the regulatory control of risks arising from them, including the risk from accidental criticality, are relevant statutory provisions of the Health and Safety at Work Act. The responsibility for safety rests with the operator who has to make and implement arrangements to prevent accidental criticality. The adequacy of these arrangements must be demonstrated in a safety case to the regulatory authorities. Operators are encouraged to treat each plant on its own merits and develop the safety case accordingly. The Nuclear Installations Inspectorate (NII), for its part, assesses the adequacy of the operator's safety case against the industry's own standards and criteria, but more particularly against the NII's safety assessment principles and guides, and international standards. Risks should be made as low as reasonably practicable. Generally, the NII seeks improvements in safety using an enforcement policy which operates at a number of levels, ranging from persuasion through discussion to the ultimate deterrent of withdrawal of a site licence. This paper describes the role of the NII, which includes a specialist criticality expertise, within the Health and Safety Executive, in regulating the nuclear sites from the criticality safety viewpoint. (Author)

Annual activity report of Ignalina NPP Safety Analysis Group for the year 1997

International Nuclear Information System (INIS)

Ushpuras, E.; Augutis, J.; Bubelis, E.; Kaliatka, A

1998-01-01

The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for the year 1997 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system

Kozloduy nuclear power plant. Units 1-4. Status of safety assessment activities. Rev. 2

International Nuclear Information System (INIS)

1999-01-01

This paper presents the results of the status of safety assessment activities carried out by the Kozloduy Nuclear Power Plant (KNPP) in order to evaluate the current status of the safety of its reactor units 1-4. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of Russian design developed according to the safety standards in force in USSR in late 60-s. Now a days 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short Tenn Program was implemented between the years 1991 and 1997 thanks of the strong safety commitment of NEK and KNPP staff and the broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. The plant current safety level analysis has been performed using IAEA analytical methodology according to 50-SG-O12 standard 'Periodic safety review of operational nuclear power plants'. The approach and criteria for acceptable safety level

IAEA activities in preparation of reglamentary documents on nuclear power plant safety

International Nuclear Information System (INIS)

Konstantinov, L.V.

1976-01-01

The activities of the IAEA in the field of working out practical rules and recommendations ensuring the nuclear power plant safety are discussed. The practical rules will establish the aims and the minimum of requirements, that must be carried out to ensure the necessary safety of systems, components and equipment of the nuclear power plant throughout the whole period of its exploitation. Described is the procedure of the document preparation, consisting of the collection of documents, edited in different countries, the integration of documents by the IAEA Secretariat, the consideratiom of documents by the Group of senior advisers, the preparation of the draft document, the additional wort at the document in accordaqce with the remarks of the IAEA member-countries, the edition and dissemination of documents. The necessity for the active participation of the CMEA member-countries in the development and discussion of documents concerning the nuclear power plant safety is stated [ru

Inherent safety characteristics of innovative reactors

International Nuclear Information System (INIS)

Heil, J.A.

1995-11-01

The added safety value of innovative or third generation reactor designs has been evaluated in order to determine the most suitable candidate for Dutch government funded research and development support. To this end, four innovative reactor concepts, viz. PIUS (Process Inherent Ultimate Safety), PRISM (Power Reactor Innovative Small), HTR-M (High Temperature Reactor Module) and MHTGR (Modular High Temperature Gas-cooled Reactor), have been studied and their passive and inherent safety characteristics have been outlined. Also the outlook for further technological and industrial development has been considered. The results of the study confirm the perspective of the innovative reactors for reduced dependence on active safety provisions and for a further reduced vulnerability to technical failures and human errors. The accident responses to generic accident initiators, viz. reactivity and cooling accidents, and also to reactor specific accidents show that neither active safety systems nor short term operator actions are required for maintaining the reactor core in a controlled and coolable condition. Whether this gives rise to a higher total safety of the innovative reactor designs, compared to evolutionary or advanced reactors, cannot be concluded. Supplementary experimental and analytical analyses of reactor specific accidents are required to be able to assess the safety of these innovative designs in a more quantitative manner. It is believed that the safety case of innovative reactors, which are less dependent on active safety systems, can be communicated with the general public in a more transparent way. Considering the perspective for further technological and industrial development it is not expected that any of the considered innovative reactor concepts will become commercially available within the next one to two decades. However, they could be made available earlier if they would receive sufficient financial backing. Considering the added safety perspectives

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-01-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the ''front end'' and ''back end'' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of the Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-10-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the 'front end' and 'back end' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of The Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

Nuclear safety. Volume 36, Number 2, July--December 1995

Energy Technology Data Exchange (ETDEWEB)

None

1995-12-01

The primary scope of the journal is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. The following subjects are covered here: (1) the Chernobyl accident; (2) general safety considerations; (3) accident analysis; (4) design features; (5) environmental effects; (6) operating experiences; (7) US NRC information and analyses; and (8) recent developments. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Safety Evakuation Of Triga-2000 Reactor Operation Viewed From Safety Culture

International Nuclear Information System (INIS)

Karliana, Itjeu

2001-01-01

The safety evaluation activities of TRIGA-2000 operation viewed from safety culture performed by questioners data collected from the operators and supervisor site of TRIGA-2000 P3TN, Bandung. There are 9 activity aspects surveyed, for instant to avail the policy of safety from their chairman, safety management, education and training, emergency aids planning, safety consultancy, accident information, safety analysis, safety devices, safety and occupational health. The surveying undertaken by filling the questioner that containing of 9 activity aspects and 20 samples of employees. The safety evaluation results' of the operation personnel in TRIGA-2000 P3TN are good implemented by both the operators and supervisors should be improve and attention need to provide the equipment's. The education and training especially for safety refreshment must be performing

A semi annual report on the activities in safety administration division. Report of the second half of 2004

International Nuclear Information System (INIS)

Yamamoto, Junta

2005-07-01

The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in October, 2004 to March, 2005. (author)

In vitro Activity and Safety Assessment of New Synthesized Thiazolo ...

African Journals Online (AJOL)

Purpose: To synthesis a series of novel thiazolo pyrimidine derivatives and evaluate them in vitro for their safety and anthelmintic activity against E. multilocularis metacestodes using BALB/c mice. Methods: A new series of substituted amino thiazole, hydrazinothiazole and thiazolo pyrimidine derivatives (2-6) were ...