Safety inspections to TRIGA reactors

International Nuclear Information System (INIS)

Byszewski, W.

1988-01-01

The operational safety advisory programme was created to provide useful assistance and advice from an international perspective to research reactor operators and regulators on how to enhance operational safety and radiation protection on their reactors. Safety missions cover not only the operational safety of reactors themselves, but also the safety of associated experimental loops, isotope laboratories and other experimental facilities. Safety missions are also performed on request in other Member States which are interested in receiving impartial advice and assistance in order to enhance the safety of research reactors. The results of the inspections have shown that in some countries there are problems with radiation protection practices and nuclear safety. Very often the Safety Analysis Report is not updated, regulatory supervision needs clarification and improvement, maintenance procedures should be more formalised and records and reports are not maintained properly. In many cases population density around the facility has increased affecting the validity of the original safety analysis

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

International Nuclear Information System (INIS)

Van Binnebeek, J.J.; Aubrey, Richard; Grandame, Melvyn; Aro, Ilari; Balloffet, Yves; Klonk, Hartmut; Manzella, Pietro; Koizumi, Hiroyoshi; Bouvrie, E.C. des; Forsberg, Staffan; Lang, Hans-Guenter; Mehew, Robert; Warren, Thomas; Woodhouse, Paul; Gallo, Robert M.; Campbell, Rob; )

1997-01-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

Energy Technology Data Exchange (ETDEWEB)

Van Binnebeek, J. J. [AIB-Vincotte Nuclear - AVN, Avenue du Roi, 157, B-1060 Brussels (Belgium); Aubrey, Richard; Grandame, Melvyn [Atomic Energy Control Board - AECB, P.O. Box 1046, Station B, 280 Slater Street, Ottawa, Ontario K1P 5S9 (Canada); Aro, Ilari [Finnish Centre for Radiation and Nuclear Safety - STUK, P.O. Box 14, FIN-00881 Helsinki (Finland); Balloffet, Yves [DRIRE Rhone Alpes, 146, rue Pierre Corneille, 69426 Lyon CEDEX 03 (France); Klonk, Hartmut [Bundesamt fuer Strahlenschutz - BfS, Federal Office for Radiation Protection, Postbox 10 01 49, 38201 Salzgitter 1 (Germany); Manzella, Pietro [A.N.P.A., Via V. Brancati, 48, 1-00144 Roma EUR (Italy); Koizumi, Hiroyoshi [Tech. Stan. Dept. - JAPEIC, Shin-Toranomon Bldg., 1-5-11, Akasaka, Minato-ku, Tokyo 107 (Japan); Bouvrie, E.C. des [Ministry of Social Affairs and Employment, Nuclear Safety Dept. KFD, P.O. Box 90804, 2509 LV The Hague (Netherlands); Forsberg, Staffan [Swedish Nuclear Power Inspectorate - SKI, Klarabergsviadukten 90, S-10658 Stockholm (Sweden); Lang, Hans-Guenter [Section Plant Coordination and Inspection, Swiss Federal Nuclear Safety Inspectorate - HSK, CH-5232 Villigen-HSK (Switzerland); Mehew, Robert; Warren, Thomas; Woodhouse, Paul [Health and Safety Executive - NII, St. Peter' s House, Balliol Road, Bootle, Merseyside L20 3LZ (United Kingdom); Gallo, Robert M. [Special Inspection Branch, US Nuclear Regulatory Commission - US NRC, Mail Stop 0-9A1, Washington, DC 20555 (United States); Campbell, Rob [International Atomic Energy Agency - IAEA, P.O. Box 100, A-1400 Vienna (International Atomic Energy Agency (IAEA))

1997-07-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities.

Development of small reactor safety criteria in Canada

International Nuclear Information System (INIS)

Ernst, P.C.; French, P.M.; Axford, D.J.; Snell, V.G.

1990-01-01

A number of new small reactor designs have been proposed in Canada over the last several years and some have reached the stage where licensing discussions have been initiated with the Atomic Energy Control Board (AECB). An inter-organizational Small Reactor Criteria (SRC) working group was formed in 1988 to propose safety and licensing criteria for these small reactors. Two levels of criteria are proposed. The first level forms a safety philosophy and the second is a set of criteria for specific reactor applications. The safety philosophy consists of three basic safety objectives together with evaluation criteria, and fourteen fundamental principles measured by specific criteria, which must be implemented to meet the safety objectives. Two of the fourteen principles are prime: defence in depth, and safety culture; the other twelve principles can be seen as deriving from them. A benefit of this approach is that the concepts of defence in depth and safety culture become well-defined. The objectives and principles are presented in the paper and their criteria are summarized. The second level of criteria, under development, will form a safety application set and will provide small reactor criteria in a number of general areas, such as regulatory process and safety assessment, as well as for specific reactor life-cycle activities, from siting through to decommissioning. The criteria are largely deterministic. However, the frequencies and consequences of postulated accidents are assessed against numerical criteria to assist in judging the acceptability of plant design, operation, and proposed siting. All criteria proposed are designed to be testable in some evidentiary fashion, readily enabling an assessment of compliance for a given proposal

Safety inspections in construction sites: A systems thinking perspective.

Science.gov (United States)

Saurin, Tarcisio Abreu

2016-08-01

Although safety inspections carried out by government officers are important for the prevention of accidents, there is little in-depth knowledge on their outcomes and processes leading to these. This research deals with this gap by using systems thinking (ST) as a lens for obtaining insights into safety inspections in construction sites. Thirteen case studies of sites with prohibited works were carried out, discussing how four attributes of ST were used in the inspections. The studies were undertaken over 6 years, and sources of evidence involved participant observation, direct observations, analysis of documents and interviews. Two complementary ways for obtaining insights into inspections, based on ST, were identified: (i) the design of the study itself needs to be in line with ST; and (ii) data collection and analysis should focus on the agents involved in the inspections, the interactions between agents, the constraints and opportunities faced by agents, the outcomes of interactions, and the recommendations for influencing interactions. Copyright © 2015 Elsevier Ltd. All rights reserved.

Ferrocyanide Safety Program: Safety criteria for ferrocyanide watch list tanks

International Nuclear Information System (INIS)

Postma, A.K.; Meacham, J.E.; Barney, G.S.

1994-01-01

This report provides a technical basis for closing the ferrocyanide Unreviewed Safety Question (USQ) at the Hanford Site. Three work efforts were performed in developing this technical basis. The efforts described herein are: 1. The formulation of criteria for ranking the relative safety of waste in each ferrocyanide tank. 2. The current classification of tanks into safety categories by comparing available information on tank contents with the safety criteria; 3. The identification of additional information required to resolve the ferrocyanide safety issue

NSSS supplier's response to differing safety criteria

Energy Technology Data Exchange (ETDEWEB)

Cremades, J; Filkin, R; Franke, T [Westinghouse Electric Nuclear Energy Systems Europe (WENESE), Brussels (Belgium)

1980-11-01

The limited progress achieved to date in harmonizing national criteria has led to the development of designs which include the most common national requirements. Progress towards harmonization of safety criteria can be accelerated by expanding the IAEA leadership and co-ordination activities, and implementing an integrated approach to criteria development. National and International safety criteria are examined.

Department of Agriculture, Food Safety and Inspection Service

Science.gov (United States)

... Standard Forms FSIS United States Department of Agriculture Food Safety and Inspection Service About FSIS District Offices Careers Contact Us Ask ... Reports Fact Sheets Food Defense and Emergency Response Food Safety Education FSIS ... Assistance Contact Centers Cooperative Agreements Email Subscription ...

Post-earthquake building safety inspection: Lessons from the Canterbury, New Zealand, earthquakes

Science.gov (United States)

Marshall, J.; Jaiswal, Kishor; Gould, N.; Turner, F.; Lizundia, B.; Barnes, J.

2013-01-01

The authors discuss some of the unique aspects and lessons of the New Zealand post-earthquake building safety inspection program that was implemented following the Canterbury earthquake sequence of 2010–2011. The post-event safety assessment program was one of the largest and longest programs undertaken in recent times anywhere in the world. The effort engaged hundreds of engineering professionals throughout the country, and also sought expertise from outside, to perform post-earthquake structural safety inspections of more than 100,000 buildings in the city of Christchurch and the surrounding suburbs. While the building safety inspection procedure implemented was analogous to the ATC 20 program in the United States, many modifications were proposed and implemented in order to assess the large number of buildings that were subjected to strong and variable shaking during a period of two years. This note discusses some of the key aspects of the post-earthquake building safety inspection program and summarizes important lessons that can improve future earthquake response.

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

2002-05-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

1999-09-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

5 CFR 8301.104 - Additional rules for employees of the Food Safety and Inspection Service.

Science.gov (United States)

2010-01-01

... Food Safety and Inspection Service. 8301.104 Section 8301.104 Administrative Personnel DEPARTMENT OF....104 Additional rules for employees of the Food Safety and Inspection Service. Any employee of the Food Safety and Inspection Service not otherwise required to obtain approval for outside employment under...

Regulatory inspection of nuclear facilities and enforcement by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on the inspection of nuclear facilities, regulatory enforcement and related matters. The objective is to provide the regulatory body with a high level of confidence that operators have the processes in place to ensure compliance and that they do comply with legal requirements, including meeting the safety objectives and requirements of the regulatory body. However, in the event of non-compliance, the regulatory body should take appropriate enforcement action. This Safety Guide covers regulatory inspection and enforcement in relation to nuclear facilities such as: enrichment and fuel manufacturing plants; nuclear power plants; other reactors such as research reactors and critical assemblies; spent fuel reprocessing plants; and facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Section 2 sets out the objectives of regulatory inspection and enforcement. Section 3 covers the management of regulatory inspections. Section 4 covers the performance of regulatory inspections, including internal guidance, planning and preparation, methods of inspection and reports of inspections. Section 5 deals with regulatory enforcement actions. Section 6 covers the assessment of regulatory inspections and enforcement activities. The Appendix provides further details on inspection areas for nuclear facilities

Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team

International Nuclear Information System (INIS)

2015-01-01

The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

A NSSS supplier's response to differing safety criteria

International Nuclear Information System (INIS)

Cremades, J.; Filkin, R.; Franke, Th.

1980-01-01

The limited progress achieved to date in harmonizing national criteria has led to the development of designs which include the most common national requirements. Progress towards harmonization of safety criteria can be accelerated by expanding the IAEA leadership and co-ordination activities, and implementing an integrated approach to criteria development. National and International safety criteria are examined. (author)

Generic safety insights for inspection of boiling water reactors

International Nuclear Information System (INIS)

Higgins, J.C.; Taylor, J.H.; Fresco, A.N.; Hillman, B.M.

1987-01-01

As the number of operating nuclear power plants (NPP) increases, safety inspection has increased in importance. However, precisely what is important, and what is not important? What should one focus inspection efforts on. Over the last two years Probabilistic Risk Assessment (PR) techniques have been developed to aid in the inspection process. Broad interest in generic PRA-based methods has arisen in the past year, since only about 25% of the US nuclear power plants have completed PRAs, and also, inspectors want PRA-based tools for these plants. This paper describes the BNL program to develop generic BWR PRA-based inspection insights or inspection guidance designed to be applied to plants without PRAs

[Recommendations for inspections of the French nuclear safety authority].

Science.gov (United States)

Rousse, C; Chauvet, B

2015-10-01

The French nuclear safety authority is responsible for the control of radiation protection in radiotherapy since 2002. Controls are based on the public health and the labour codes and on the procedures defined by the controlled health care facility for its quality and safety management system according to ASN decision No. 2008-DC-0103. Inspectors verify the adequacy of the quality and safety management procedures and their implementation, and select process steps on the basis of feedback from events notified to ASN. Topics of the inspection are communicated to the facility at the launch of a campaign, which enables them to anticipate the inspectors' expectations. In cases where they are not physicians, inspectors are not allowed to access information covered by medical confidentiality. The consulted documents must therefore be expunged of any patient-identifying information. Exchanges before the inspection are intended to facilitate the provision of documents that may be consulted. Finally, exchange slots between inspectors and the local professionals must be organized. Based on improvements achieved by the health care centres and on recommendations from a joint working group of radiotherapy professionals and the nuclear safety authority, changes will be made in the control procedure that will be implemented when developing the inspection program for 2016-2019. Copyright © 2015. Published by Elsevier SAS.

Squale: evaluation criteria of functioning safety

International Nuclear Information System (INIS)

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

1998-05-01

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

MDEP Common Position CP-VICWG-01. Common Position: Establishment of Common QA/QM Criteria for the Multinational Vendor Inspection CP-VICWG-01

International Nuclear Information System (INIS)

2015-01-01

This document provides a set of common positions for harmonizing inspection criteria called 'Common QA/QM Criteria' which will be used in Multinational Vendor Inspections. This document was prepared by the Vendor Inspection Co-operation Working Group (VICWG) of the Multinational Design Evaluation Program (MDEP). The 'Common QA/QM Criteria' provides the basic areas for consideration when performing Vendor Inspections. The criteria have been developed in conformity with International Codes and Standards such as IAEA, ISO, etc. that MDEP member countries have adopted

Criteria for safety-related operator actions

International Nuclear Information System (INIS)

Gray, L.H.; Haas, P.M.

1983-01-01

The Safety-Related Operator Actions (SROA) Program was designed to provide information and data for use by NRC in assessing the performance of nuclear power plant (NPP) control room operators in responding to abnormal/emergency events. The primary effort involved collection and assessment of data from simulator training exercises and from historical records of abnormal/emergency events that have occurred in operating plants (field data). These data can be used to develop criteria for acceptability of the use of manual operator action for safety-related functions. Development of criteria for safety-related operator actions are considered

Safety and reliability criteria

International Nuclear Information System (INIS)

O'Neil, R.

1978-01-01

Nuclear power plants and, in particular, reactor pressure boundary components have unique reliability requirements, in that usually no significant redundancy is possible, and a single failure can give rise to possible widespread core damage and fission product release. Reliability may be required for availability or safety reasons, but in the case of the pressure boundary and certain other systems safety may dominate. Possible Safety and Reliability (S and R) criteria are proposed which would produce acceptable reactor design. Without some S and R requirement the designer has no way of knowing how far he must go in analysing his system or component, or whether his proposed solution is likely to gain acceptance. The paper shows how reliability targets for given components and systems can be individually considered against the derived S and R criteria at the design and construction stage. Since in the case of nuclear pressure boundary components there is often very little direct experience on which to base reliability studies, relevant non-nuclear experience is examined. (author)

TAPS safety evaluation criteria for reload fueling

International Nuclear Information System (INIS)

Mahendra Nath; Veeraraghavan, N.

1976-01-01

To improve operating performance of Tarapur reactors, several proposals are under consideration such as core expansion, change-over to an improved fuel design with lower heat rating, extension of fuel cycle lengths etc., which have a bearing on overall plant operating characteristics and reactor safety. For evaluating safety implications of the various proposals, it is necessary to formulate safety evaluation criteria for reload fuelling. Salient features of these criteria are discussed. (author)

Increase plant safety and reduce cost by implementing risk-informed in-service inspection programs

International Nuclear Information System (INIS)

Billington, A.; Monette, P.

2001-01-01

The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less that 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used to improve the effectiveness of inspecting safety-significant piping components, to reduce inspection requirements on other piping components, to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure, and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits from past projects is presented, since the methodology is applicable for WWER plant design. (author)

Increase plant safety and reduce cost by implementing risk-informed In-Service Inspection programs

International Nuclear Information System (INIS)

Billington, A.; Monette, P.; Doumont, C.

2000-01-01

The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less than 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used: to improve the effectiveness of inspecting safety-significant piping components; to reduce inspection requirements on other piping components; to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure; and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits of past projects is presented, since the methodology is applicable for VVER plant design. (author)

Occupational health and safety inspection of the Ranger Uranium Mine

International Nuclear Information System (INIS)

Rosen, R.

1987-04-01

The principal purpose of the inspection was to assess all aspects of occupational health and safety at the Ranger Uranium Mine. A major objective was to identify actual and potential hazards under normal and abnormal conditions, particularly in relation to those topics about which the unions had expressed some concern. An assessment was made of current safety policies, procedures and practices at the site; and, as far as practicable, those tasks which involved risks to workers were identified. The results and recommendations of the inspection are contained in this report

A risk-informed approach to optimising in-service inspection of piping

International Nuclear Information System (INIS)

Billington, A.; Monette, P.

1999-01-01

Traditional criteria for the selection of in-service inspection locations in piping, have come to be regarded as being out-of-touch with current knowledge of piping failures and with current measures of safety importance. An alternative , risk-informed, method has been developed and successfully licensed, that systematically establishes an inspection plan addressing all safety-related piping systems, in a way that is optimized with respect to the safety gain achieved through in-service inspection. The principles of the method are discussed and the results of several applications are summarized, all of which demonstrate that the risk-informed program would lead to significant improvements in the overall level of plant safety, while at the same time re-distributing the inspections in such a way that reduces both plant costs and radiation exposure to personnel.(author)

The 900 MWe water pressurized reactor safety re-examination at the occasion of their third decennial inspection

International Nuclear Information System (INIS)

2009-01-01

This document reports the safety re-examination actions performed on the French 900 MWe water pressurized reactors. This process includes three stages. The first one is an inventory of safety, design and operation requirements which are defined or specified in different texts: regulations, rules, criteria and specifications. This leads to compliance studies with respect to these documents and by in situ inspections, and then to corrective recommendations. After presenting this process, the report deals with specific safety studies which are related to external or internal aggressions (fire, explosions, flooding, climate, seism), to accidental situations (primary circuit cold overpressure, severe accidents, containment, level 1 and 2 safety probabilistic studies, passive failure of safeguard circuits, vapour generator tube failure, and so on), to design and sizing of civil engineering works and systems (radioactivity measurement system, safety injection system, recirculation function liability, liability of the irradiated fuel deactivation pool cooling system)

Nuclear Fuel Safety Criteria Technical Review - Second edition

International Nuclear Information System (INIS)

Beck, Winfried; Blanpain, Patrick; Fuketa, Toyoshi; Gorzel, Andreas; Hozer, Zoltan; Kamimura, Katsuichiro; Koo, Yang-Hyun; Maertens, Dietmar; Nechaeva, Olga; Petit, Marc; Rehacek, Radomir; Rey-Gayo, Jose Maria; Sairanen, Risto; Sonnenburg, Heinz-Guenther; Valach, Mojmir; Waeckel, Nicolas; Yueh, Ken; Zhang, Jinzhao; Voglewede, John

2012-01-01

Most of the current nuclear fuel safety criteria were established during the 1960's and early 1970's. Although these criteria were validated against experiments with fuel designs available at that time, a number of tests were based on unirradiated fuels. Additional verification was performed as these designs evolved, but mostly with the aim of showing that the new designs adequately complied with existing criteria, and not to establish new limits. In 1996, the OECD Nuclear Energy Agency (NEA) reviewed existing fuel safety criteria, focusing on new fuel and core designs, new cladding materials and industry manufacturing processes. The results were published in the Nuclear Fuel Safety Criteria Technical Review of 2001. The NEA has since re-examined the criteria. A brief description of each criterion and its rationale are presented in this second edition, which will be of interest to both regulators and industry (fuel vendors, utilities)

[Legislation and inspection for the health and safety of workers. Efficacy and limits].

Science.gov (United States)

Tozzi, G A

2009-01-01

To provide information regarding Occupational Health and Safety (OHS) Inspections in Europe. The dynamics that are transforming regulatory subsystems and complementary inspection services are described. Simplification initiatives, the limits and difficulties of applying the different models of Health and Safety Management Systems are discussed. Examples are given on how to evaluate legislation and technical standards during planning and enforcement. Different approaches for studying characteristics, methodologies and efficacy in practice of OHS Inspection are provided. Targeted inspections need to respond to the needs of enterprises and workers. Impartiality must be guaranteed and workers' participation should be facilitated.

Spectroscopic imaging technologies for online food safety and sanitation inspection

Science.gov (United States)

The Environmental Microbial and Food Safety Laboratory, ARS, USDA is one of the leading groups for the development of optoelectronic sensing technologies and methodologies for food quality, safety, and sanitation inspection. High throughput hyperspectral and multispectral imaging techniques use Ram...

The French nuclear safety authority's experience with radioactive transport inspection

International Nuclear Information System (INIS)

Jacob, E.; Aguilar, J.

2004-01-01

About 300,000 radioactive material packages are transported annually in France. Most consist of radioisotopes for medical, pharmaceutical or industrial use. On the other hand, the nuclear industry deals with the transport of fuel cycle materials (uranium, fuel assemblies, etc.) and waste from power plants, reprocessing plants and research centers. France is also a transit country for shipments such as spent fuel packages from Switzerland or Germany, which are bound for Sellafield in Great Britain. The French nuclear safety authority (DGSNR: Directorate General for Nuclear Safety and Radioprotection) has been responsible since 1997 for the safety of radioactive material transport. This paper presents DGNSR's experience with transport inspection: a feedback of key points based on 300 inspections achieved during the past five years is given

Inspection of licensee activities in emergency planning

International Nuclear Information System (INIS)

Van Binnebeek, J.J.; Gutierrez Ruiz, Luis Miguel; Bouvrie, E. des; Aro, Ilari; Gil, J.; Balloffet, Yves; Forsberg, Staffan; Klonk, H.; Lang, Hans-Guenter; Fichtinger, G.; Warren, T.; Manzella, P.; Gallo, R.; Koizumi, Hiroyoshi; Johnson, M.; Pittermann, P.

1998-01-01

The CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries Following discussions at several meetings on the topic of what is expected by the regulatory body regarding inspection criteria, WGIP proposed putting together a compilation of Member countries practices on regulatory inspection practices with respect to licensee emergency planning. CNRA approved this task and this report. Information was collected from a questionnaire which was issued in 1996. The report presents information on regulatory inspection activities with respect to emergency planning in NEA Member countries. The focus of the report is on the third section. It reviews the similarities and differences in inspection practices to evaluate compliance with the requirements over which the regulatory body (RB) has jurisdiction

Regulatory inspection practices for industrial safety (electrical, mechanical, material handling and conventional aspects)

International Nuclear Information System (INIS)

Agarwal, K.

2017-01-01

Regulatory Inspection (RI) of BARC facilities and projects are carried out under the guidance of BARC Safety Council (BSC) Secretariat. Basically facilities and projects have been divided into two board categories viz. radiological facilities and non-radiological facilities. The Rls of radiological facilities should be carried out under OPSRC and of non-radiological facilities under CFSRC. Periodicity of inspection shall be at least once in a year. The RI of projects is carried out under concerned DSRC. RI practices with industrial safety which includes electrical, mechanical, material handling and conventional aspect for these facilities starts with check lists. The inspection areas are prepared in the form of checklists which includes availability of approved documents, compliance status of previous RIT and various safety committee's recommendations, radiological status of facilities, prompt reporting of safety related unusual occurrences, major incident, site visit for verification of actual status of system/plant. The practices for inspection in the area of electrical safety shall include checking of maintenance procedure for all critical class IV system equipment's such as HT panel, LT panel, transformer and motors. Load testing of Class III system such as D.G. set etc. shall be carried out as technical specification surveillance schedule. Status of aviation lights, number of qualified staff, availability of qualified staff etc. shall be form of inspection

Ship inspection strategies: effects on maritime safety and environmental protection

NARCIS (Netherlands)

Heij, C.; Bijwaard, G.E.; Knapp, S.

2011-01-01

Global trade largely depends on maritime transport, and appropriate ships are needed to protect cargo but to minimize environmental damage and to this end, flag and port state authorities expend considerable effort in ship safety inspections. This paper investigates the safety gains of current

Assisting New York Dairy Farms with Preparing for OSHA Safety Inspections.

Science.gov (United States)

Tinc, Pamela J; Carrabba, Jim; Meyerhoff, Anna; Horsman, Melissa

2018-01-01

In 2013, the Occupational Safety and Health Administration announced a Local Emphasis Program targeted at New York farmers. This program involved random inspections of dairy farms across the state. This article provides an overview of the efforts made in New York to prepare farmers for these inspections. As a result of this program launch, several safety services offered by the New York Center for Agricultural Medicine and Health were significantly impacted, and required expansion and modification in order to meet the needs of New York farmers.

Natural Gas Vehicle Cylinder Safety, Training and Inspection Project

Energy Technology Data Exchange (ETDEWEB)

Hank Seiff

2008-12-31

Under the auspices of the National Energy Technology Laboratory and the US Department of Energy, the Clean Vehicle Education Foundation conducted a three-year program to increase the understanding of the safe and proper use and maintenance of vehicular compressed natural gas (CNG) fuel systems. High-pressure fuel systems require periodic inspection and maintenance to insure safe and proper operation. The project addressed the needs of CNG fuel containers (cylinders) and associated high-pressure fuel system components related to existing law, codes and standards (C&S), available training and inspection programs, and assured coordination among vehicle users, public safety officials, fueling station operators and training providers. The program included a public and industry awareness campaign, establishment and administration of a cylinder inspector certification training scholarship program, evaluation of current safety training and testing practices, monitoring and investigation of CNG vehicle incidents, evaluation of a cylinder recertification program and the migration of CNG vehicle safety knowledge to the nascent hydrogen vehicle community.

Review of fuel safety criteria in France

Energy Technology Data Exchange (ETDEWEB)

Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier [Institut de Radioprotection et du Surete Nucleaire, Fontenay-aux-Roses (France)

2018-01-15

Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

Review of fuel safety criteria in France

International Nuclear Information System (INIS)

Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier

2018-01-01

Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

Ensuring the nuclear safety of VVER-440 reactor pressure vessels in Skoda, Concern Enterprise, Plzen

International Nuclear Information System (INIS)

Hrbek, Z.

1985-01-01

Various types of routine inspections are described of reactor pressure vessels with the aim of identifying residual lifetime and overall safety. The inspection programme includes: choice of systems and instruments, type of tests, test frequency, safety criteria, measures to be taken in case of unsatisfactory results, documentation. The criteria are given for periodical inspections and requirements listed for instruments and equipment. The main three groups of tests are: visual inspection and dimension tests, surface inspection and volumetric inspection. Briefly described is some of the equipment used. (M.D.)

Ship Inspection Strategies: Effects on Maritime Safety and Environmental Protection

NARCIS (Netherlands)

C. Heij (Christiaan); G.E. Bijwaard (Govert); S. Knapp (Sabine)

2010-01-01

textabstractGlobal trade depends for a large part on maritime transport, and safe ships are needed not only to protect precious cargo but also to prevent environmental damage. Flag state and port state authorities spend much effort in ship safety inspections to ensure a minimum safety level and to

Promoting radiation protection and safety for X-ray inspection systems

International Nuclear Information System (INIS)

Maharaj, Harri P.

2008-01-01

This paper aims to present a regulatory perspective on radiation protection and safety relevant to facilities utilizing baggage X-ray inspection systems. Over the past several years there has been rapid growth in the acquisition and utilization of X-ray tube based inspection systems for security screening purposes worldwide. In addition to ensuring compliance with prescribed standards applicable to such X-ray systems, facilities subject to federal jurisdiction in Canada are required to comply with established codes of practice, which, not only are in accordance with occupational health and safety legislation but also are consistent with international guidance. Overall, these measures are aimed at reducing radiation risks and adverse health effects. Data, acquired in the past several years in a number of facilities through various instruments, namely, monitoring and surveillance, radiation safety audits, onsite evaluations, device registration processes and information developed, were considered in conjunction with detrimental traits. Changes are necessary to reduce radiation and safety risks from both an ALARA point of view and an accountability perspective. Establishing, developing, implementing and following a radiation protection program is warranted and advocated. Minimally, such a program shall be managed by a radiation safety officer. It shall promote and sustain a radiation safety culture in the workplace; shall ensure properly qualified individuals operate and service the X-ray systems in accordance with established and authorized procedures; and shall incorporate data recording and life cycle management principles. Such a program should be the norm for a facility that utilizes baggage X-ray inspection systems for security purposes, and it shall be subject to continuous regulatory oversight. (author)

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1991-04-01

The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

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

Science.gov (United States)

Sparer, Emily; Dennerlein, Jack

2013-01-01

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

Safety Design Criteria of Indian Sodium Cooled Fast Reactors

International Nuclear Information System (INIS)

Pillai, P.; Chellapandi, P.; Chetal, S.C.; Vasudeva Rao, P.R.

2013-01-01

• Important feedback has been gained through the design and safety review of PFBR. • The safety criteria document prepared by AERB and IGCAR would provide important input to prepare the dedicated document for the Sodium cooled Fast Reactors at the national and international level. • A common approach with regard to safety, among countries pursuing fast reactor program, is desirable. • Sharing knowledge and experimental facilities on collaborative basis. • Evolution of strong safety criteria – fundamental to assure safety

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1993-11-01

This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards

Radiation protection and safety guide no. GRPB-G-4: inspection

International Nuclear Information System (INIS)

Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

1995-01-01

The use of ionizing radiation and radiation sources in Ghana is on the increase due to national developmental efforts in Health Care, Food and Agriculture, Industry, Science and Technology. This regulatory Guide has been developed to assist both the Regulatory Body (Radiation Protection Board) and operating organizations to perform systematic inspections commensurate with the level of hazard associated with the application of radiation sources and radioactive materials. The present Guide applies to the Radiation Protection and Safety inspection and/or audit conducted by the Radiation Protection Board or Radiation Safety Officer. The present Guide is applicable in Ghana and to foreign suppliers of radiation sources. The present Guide applies to notifying person, licensee, or registrant and unauthorized practice

The study on safety facility criteria for radioactive waste repository

International Nuclear Information System (INIS)

Lee, S. H.; Choi, M. H.; Han, S. H. and others

1992-12-01

The radioactive waste repository are necessary to install the engineered safety systems to secure the safety for operation of the repository in the event of fire and earthquake. Since the development of safety facility criteria requires a thorough understanding about the characteristics of the engineered safety systems, we should investigate by means of literature survey and visit SKB. In particular, definition, composition of the systems, functional requirement of the systems, engineered safety systems of foreign countries, system design, operation and maintenance requirement should be investigated : fire protection system, ventilation system, drainage system, I and C system, electric system, radiation monitoring system. This proposed criteria consist of purpose, scope of application, ventilation system, fire protection system, drainage system, electric system and this proposed criteria can be applied as a basic reference for the final criteria

Fuel safety criteria and review by OECD / CSNI task force

International Nuclear Information System (INIS)

Van Doesburg, W.

1999-01-01

Full text of publication follows: with the advent of advanced fuel and core designs, and the implementation of more accurate (best estimate or statistical) design and analysis methods, there is a general feeling that safety margins have been or are being reduced. Historically, fuel safety margins were defined by adding conservatism to the safety limits, which in turn were also fixed in a conservative manner, here, the expression 'conservatism' expresses the fact that bounding or limiting numbers were chosen for model parameters, plant and fuel design data, and fuel operating history values. Unfortunately, as these conservatisms were not quantified (or quantifiable), the amount of safety available or the reduction thereof is difficult to substantiate. For the regulator, it is important to know the margin available with the utilities' request for approval of new fuel or methods; likewise, for the utility and vendor it is important to know what margins exist and what they are based on, to identify in which direction they can make further progress and optimize fuel and fuel cycle cost. Naturally, each party involved will have to decide on how much margin should be in place, to establish operational criteria and ensure that these can actually be met during operation. To assess the margins issue, safety criteria themselves need to be reviewed first. Most - if not all - of the currently existing safety criteria were established during the 60's and early 70's, and verified against experiments with fuel available at that time - mostly at zero exposure. Of course, verification was performed as designs progressed in later years, primarily with the aim to be able to prove that safety criteria were adequate as long as the said conservatisms would be retained, and not with the aim to reestablish limits. The mandate to the OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria (TFFSC) is to assess the adequacy of existing fuel safety criteria, in view of the 'new design' elements (new

Tank waste remediation system nuclear criticality safety inspection and assessment plan

International Nuclear Information System (INIS)

VAIL, T.S.

1999-01-01

This plan provides a management approved procedure for inspections and assessments of sufficient depth to validate that the Tank Waste Remediation System (TWRS) facility complies with the requirements of the Project Hanford criticality safety program, NHF-PRO-334, ''Criticality Safety General, Requirements''

77 FR 38857 - Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal...

Science.gov (United States)

2012-06-29

... Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water- Cooled Nuclear Power... Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled... draft regulatory guide (DG), DG-1280, ``Design, Inspection, and Testing Criteria for Air Filtration and...

Adequacy Criteria of Models of the Cargo Inspection System with Material Discrimination Option

International Nuclear Information System (INIS)

Osipov, S; Chakhlov, S; Osipov, O; Shtein, A; Van, J

2016-01-01

Generalized adequacy criteria for mathematical models in order to discriminate materials in X-ray inspection systems by the dual-energy method were developed. Two main approaches of the examination systems to produce the adequacy criteria by the final and the intermediate parameters of the dual-energy method were analyzed. The criteria were specified in respect to the discrimination by the effective atomic number and by the method of level functions. Experimental and theoretical estimates of the discrimination parameters of the test object constituents scanned by fan beams of X-ray radiation with the maximal energies of 4.5 and 9 MeV are given. (paper)

Development of the Risk-Based Inspection Techniques and Pilot Plant Activities

International Nuclear Information System (INIS)

Phillips, J.H.

1997-01-01

Risk-based techniques have been developed for commercial nuclear power plants. System boundaries and success criteria is defined using the probabilistic risk analysis or probabilistic safety analysis developed to meet the individual plant evaluation. Final ranking of components is by a plant expert panel similar to the one developed for maintenance rule. Components are identified as being high risk-significant or low-risk significant. Maintenance and resources are focused on those components that have the highest risk-significance. The techniques have been developed and applied at a number of pilot plants. Results from the first risk-based inspection pilot plant indicates that safety due to pipe failure can be doubled while the inspection reduced to about 80% when compared with current inspection programs. The reduction in inspection reduces the person-rem exposure resulting in further increases in safety. These techniques have been documented in publication by the ASME CRTD

Maintenance, surveillance and in-service inspection in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Effective maintenance, surveillance and in-service inspection (MS and I) are essential for the safe operation of a nuclear power plant. The objective of this Safety Guide is to provide recommendations and guidance for MS and I activities to ensure that SSCs important to safety are available to perform their functions in accordance with the assumptions and intent of the design. This Safety Guide covers the organizational and procedural aspects of MS and I. However, it does not give detailed technical advice in relation to particular items of plant equipment, nor does it cover inspections made for and/or by the regulatory body. This Safety Guide provides recommendations and guidance for preventive and remedial measures, including testing, surveillance and in-service inspection, that are necessary to ensure that all plant structures, systems and components (SSCs) important to safety are capable of performing as intended. This Safety Guide covers measures for fulfilling the organizational and administrative requirements for: establishing and implementing schedules for preventive and predictive maintenance, repairing defective plant items, selecting and training personnel, providing related facilities and equipment, procuring stores and spare parts, and generating, collecting and retaining maintenance records for establishing and implementing an adequate feedback system for information on maintenance. MS and I should be subject to quality assurance in relation to all aspects important to safety. Quality assurance has been dealt with in detail in other IAEA safety standards and is covered here only in specific instances, for emphasis. In Section 2, a concept of MS and I is presented and the interrelationship between maintenance, surveillance and inspection is discussed. Section 3 concerns the functions and responsibilities of different organizations involved in MS and I activities. Section 4 provides recommendations and guidance on such organizational aspects as

Maintenance, surveillance and in-service inspection in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Effective maintenance, surveillance and in-service inspection (MS and I) are essential for the safe operation of a nuclear power plant. The objective of this Safety Guide is to provide recommendations and guidance for MS and I activities to ensure that SSCs important to safety are available to perform their functions in accordance with the assumptions and intent of the design. This Safety Guide covers the organizational and procedural aspects of MS and I. However, it does not give detailed technical advice in relation to particular items of plant equipment, nor does it cover inspections made for and/or by the regulatory body. This Safety Guide provides recommendations and guidance for preventive and remedial measures, including testing, surveillance and in-service inspection, that are necessary to ensure that all plant structures, systems and components (SSCs) important to safety are capable of performing as intended. This Safety Guide covers measures for fulfilling the organizational and administrative requirements for: establishing and implementing schedules for preventive and predictive maintenance, repairing defective plant items, selecting and training personnel, providing related facilities and equipment, procuring stores and spare parts, and generating, collecting and retaining maintenance records for establishing and implementing an adequate feedback system for information on maintenance. MS and I should be subject to quality assurance in relation to all aspects important to safety. Quality assurance has been dealt with in detail in other IAEA safety standards and is covered here only in specific instances, for emphasis. In Section 2, a concept of MS and I is presented and the interrelationship between maintenance, surveillance and inspection is discussed. Section 3 concerns the functions and responsibilities of different organizations involved in MS and I activities. Section 4 provides recommendations and guidance on such organizational aspects as

A strategy for the risk-based inspection of pressure safety valves

International Nuclear Information System (INIS)

Chien, C.-H.; Chen, C.-H.; Chao, Y.J.

2009-01-01

The purpose of a pressure safety valve (PSV) is to protect the life and safety of pressure vessels in a pressurized system. If a weakened PSV fails to function properly, a catastrophic event might occur if no other protective means are provided. By utilizing the as-received test data and statistical analysis of the aging conditions of PSVs in lubricant process units, a risk-based inspection (RBI) system was developed in this study. First of all, the characteristics of PSV were discussed from the practical viewpoint of engineering inspection and maintenance. The as-received test data, which shows obvious PSV damage, will be separated from the data used in the following statistical analysis. Then, the relationship between the aging conditions and the corresponding PSV parameters was analyzed by using the statistical technique-analysis of variance (ANOVA). Finally, a strategy for semi-quantitative RBI is proposed. Also, a definitive estimated inspection interval for every PSV is suggested. The outcome indicated most of the risks result from a few PSVs, for which the corresponding inspection intervals will be shorter than the 2 years in accordance with relative standards and local government regulations

Safety Criteria and Standards for Bearing Capacity of Foundation

Directory of Open Access Journals (Sweden)

Yanlong Li

2017-01-01

Full Text Available This paper focuses on the evaluation standards of factor of safety for foundation stability analysis. The problem of foundation stability is analyzed via the methods of risk analysis of engineering structures and reliability-based design, and the factor of safety for foundation stability is determined by using bearing capacity safety-factor method (BSFM and strength safety-factor method (SSFM. Based on a typical example, the admissible factors of safety were calibrated with a target reliability index specified in relevant standards. Two safety criteria and their standards of bearing capacity of foundation for these two methods (BSFM and SSFM were established. The universality of the safety criteria and their standards for foundation reliability was verified based on the concept of the ratio of safety margin (RSM.

Development of inspection safety evaluation technology

Energy Technology Data Exchange (ETDEWEB)

Yoon, Seok Chul; Yoon, Yeo Chang; Kim, Jong Soo; Lee, Tae Young; Kim, Chang Ryol; Lee, Hyung Sub; Kim, Jong Soo

1995-12-01

The purpose of this project is to protection nation inspector`s over exposure from radiation that can be occurred by inspection activity at nuclear facilities and its environment, and to ensure the safety of inspection activity at the nuclear facilities. To effectively carry out the domestic inspection task to be enforced from 1996, the evaluation for special radiation exposure rate of nuclear facilities, air and surface contamination level, and measurement and monitoring of water contamination level were made to determine whether these measured values exceeded permissible limitations, and to protect the inspector`s over exposure from radiation at domestic nuclear facilities. Management of inspector`s exposure was carried out under assistance of the Department of Health Physics. Performance tests of two gamma detectors, one neutron detector, alpha and beta detector, and gamma spectroscopy analyzer were carried out to control dose on extremity, the characteristic test for extremity dosimeter was carried out and the theoretical calculation of gamma dose conversion factors based on ANSI N13.32 standard was performed. Under the 93+2 program, IAEA began to recognize the necessity of environmental observation technology development of air-borne particulates travelled from long distance location. Associated with the necessity of this technology development, a proposal of international joint research for development of the special radiation measurement and analysis has been prepared. (author). 21 tabs., 24 figs., 20 refs.

Documentation for first annual testing and inspections of Benificial Uses Shipping System (BUSS) Cask

International Nuclear Information System (INIS)

Lundeen, J.E.

1994-01-01

The purpose of this report is to compile date generated during the first annual tests and inspections of the Benificiai Uses Shipping System (BUSS) Cask. In addition, this report will verify that the testing criteria identified in chapter 8 of the BUSS Cask Safety Analysis Report for Packaging (SARP) was met. Section 8.2 ''Maintenance and Periodic Inspection Program'' of the BUSS Cask SARP requires that the following tests and inspections be performed on an annual basis: Hydrostatic pressure test; helium leak test; dye penetrant test on the trunnions and lifting lugs; and torque test on all bolts; impact limiter inspection and weight test. The first annual inspections and testing of the BUSS Cask were completed on May 5, 1994, and met the SARP criteria

Effect of a Publicly Accessible Disclosure System on Food Safety Inspection Scores in Retail and Food Service Establishments.

Science.gov (United States)

Choi, Jihee; Scharff, Robert L

2017-07-01

The increased frequency with which people are dining out coupled with an increase in the publicity of foodborne disease outbreaks has led the public to an increased awareness of food safety issues associated with food service establishments. To accommodate consumer needs, local health departments have increasingly publicized food establishments' health inspection scores. The objective of this study was to estimate the effect of the color-coded inspection score disclosure system in place since 2006 in Columbus, OH, by controlling for several confounding factors. This study incorporated cross-sectional time series data from food safety inspections performed from the Columbus Public Health Department. An ordinary least squares regression was used to assess the effect of the new inspection regime. The introduction of the new color-coded food safety inspection disclosure system increased inspection scores for all types of establishments and for most types of inspections, although significant differences were found in the degree of improvement. Overall, scores increased significantly by 1.14 points (of 100 possible). An exception to the positive results was found for inspections in response to foodborne disease complaints. Scores for these inspections declined significantly by 10.2 points. These results should be useful for both food safety researchers and public health decision makers.

Periodic inspection for safety of CANDU heat transport piping systems

International Nuclear Information System (INIS)

Ellyin, F.

1979-10-01

Periodic inspection of heat transport and emergency core cooling piping systems is intended to maintain an adequate level of safety throughout the life of the plant, and to protect plant personnel and the public from the consequences of a failure and release of fission products. This report outlines a rational approach to the periodic inspection based on a fully probabilistic model. It demonstrates the methodology based on theoretical treatment and experimental data whereby the strength of a pressurized pipe or vessel containing a defect could be evaluated. It also shows how the extension of the defect at various lifetimes could be predicted. These relationships are prerequisite for the probabilistic formulation and analysis for the periodic inspection of piping systems

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

Cooperative Behaviours with Swarm Intelligence in Multirobot Systems for Safety Inspections in Underground Terrains

Directory of Open Access Journals (Sweden)

Chika Yinka-Banjo

2014-01-01

Full Text Available Underground mining operations are carried out in hazardous environments. To prevent disasters from occurring, as often as they do in underground mines, and to prevent safety routine checkers from disasters during safety inspection checks, multirobots are suggested to do the job of safety inspection rather than human beings and single robots. Multirobots are preferred because the inspection task will be done in the minimum amount of time. This paper proposes a cooperative behaviour for a multirobot system (MRS to achieve a preentry safety inspection in underground terrains. A hybrid QLACS swarm intelligent model based on Q-Learning (QL and the Ant Colony System (ACS was proposed to achieve this cooperative behaviour in MRS. The intelligent model was developed by harnessing the strengths of both QL and ACS algorithms. The ACS optimizes the routes used for each robot while the QL algorithm enhances the cooperation between the autonomous robots. A description of a communicating variation within the QLACS model for cooperative behavioural purposes is presented. The performance of the algorithms in terms of without communication, with communication, computation time, path costs, and the number of robots used was evaluated by using a simulation approach. Simulation results show achieved cooperative behaviour between robots.

Radioactive waste storage facilities, involvement of AVN in inspection and safety assessment

International Nuclear Information System (INIS)

Simenon, R.; Smidts, O.

2006-01-01

The legislative and regulatory framework in Belgium for the licensing and the operation of radioactive waste storage buildings are defined by the Royal Decree of 20 July 2001 (hereby providing the general regulations regarding to the protection of the population, the workers and the environment against the dangers of ionising radiation). This RD introduces in the Belgian law the radiological protection and ALARA-policy concepts. The licence of each nuclear facility takes the form of a Royal Decree of Authorization. It stipulates that the plant has to be in conformity with its Safety Analysis Report. This report is however not a public document but is legally binding. Up to now, the safety assessment for radioactive waste storage facilities, which is implemented in this Safety Analysis Report, has been judged on a case-by-case basis. AVN is an authorized inspection organisation to carry out the surveillance of the Belgian nuclear installations and performs hereby nuclear safety assessments. AVN has a role in the nuclear safety and radiation protection during all the phases of a nuclear facility: issuance of licenses, during design and construction phase, operation (including reviewing and formal approval of modifications) and finally the decommissioning. Permanent inspections are performed on a regular basis by AVN, this by a dedicated site inspector, who is responsible for a site of an operator with nuclear facilities. Besides the day-to-day inspections during operation there are also the periodic safety reviews. AVN assesses the methodological approaches for the analyses, reviews and approves the final studies and results. The conditioned waste in Belgium is stored on the Belgoprocess' sites (region Mol-Dessel) for an intermediate period (about 80 years). In the meantime, a well-defined inspection programme is being implemented to ensure that the conditioned waste continues to be stored safely during this temporary storage period. This programme was draw up by

FAA National Aviation Safety Inspection Program. Annual Report FY90

Science.gov (United States)

1991-06-01

This report was undertaken to document, analyze, and place : into national perspective the findings from the 1990 National : Aviation Safety Inspection Program (NASIP). This report is the : fifth in a series of annual reports covering the results of ...

Safety principles and design criteria for nuclear power stations

International Nuclear Information System (INIS)

Gazit, M.

1982-01-01

The criteria and safety principles for the design of nuclear power stations are presented from the viewpoint of a nuclear engineer. The design, construction and operation of nuclear power stations should be carried out according to these criteria and safety principles to ensure, to a reasonable degree, that the likelihood of release of radioactivity as a result of component failure or human error should be minimized. (author)

Safety criteria of uranium enrichment plants

International Nuclear Information System (INIS)

Nardocci, A.C.; Oliveira Neto, J.M. de

1994-01-01

The applicability of nuclear reactor safety criteria applied to uranium enrichment plants is discussed, and a new criterion based on the soluble uranium compounds and hexafluoride chemical toxicities is presented. (L.C.J.A.). 21 refs, 4 tabs

Inspection and enforcement by the regulatory body for nuclear power plants. A safety guide. A publication within the NUSS programme

International Nuclear Information System (INIS)

1996-01-01

The purpose of this Safety Guide is to provide guidance on fulfilling the requirements for inspection and enforcement by the regulatory body, as set out in the Code on the Safety of Nuclear Power Plants; Governmental Organization. This Safety Guide deals with the responsibilities of the regulatory body, the organization of inspection programmes, the inspection resources of the regulatory body, methods of inspection, requirements on the applicant/licensee in regard to regulatory inspection, inspection reports, and regulatory action and enforcement. It is recognized that many of the provisions of this Safety Guide may be applicable to the regulations of other nuclear facilities and related activities including research reactors, fuel processing and manufacturing plants, irradiated fuel processing plants and radioactive waste management facilities. This Safety Guide does not deal specifically with the functions of a regulatory body responsible for such matters; however, the guidance presented here may be applied as appropriate to these activities. 11 refs, 1 fig

Safety criteria for the acquisition of meat in Brazilian University restaurants

Directory of Open Access Journals (Sweden)

Marizete Oliveira de Mesquita

2014-03-01

Full Text Available The present study's objective was to analyze the procedures aimed at guaranteeing sanitary conditions when acquiring meat. The study was conducted with university restaurants of the Federal Institutions of Higher Education (IFES located in the five regions of Brazil. Data were collected using a questionnaire and an evaluation list, which was available online to restaurant professionals. The results showed that restaurants chose one or two types of meat, the most frequent of which were beef and chicken. In restaurants managed by the IFES, the acquisition of raw material occurred by bidding. For vendor selection, the restaurants required product registration with the Inspection Service and requested regulation of the supplier by the Health Surveillance. Monitoring was carried out through a technical visit to the supplier and a review of the past records of the supplier. A higher percentage of restaurants in the Southeast region met appropriate sanitary and hygienic criteria for the receipt of meat, followed by the South, Midwest, Northeast and North. We conclude that restaurants meet most of the safety criteria set in the legislation. However, some weaknesses are evident in the physical and functional structure, the system of transportation of raw material and the records of control measures at the place of reception.

Guidance for the definition and application of probabilistic safety criteria

International Nuclear Information System (INIS)

Holmberg, J.-E.; Knochenhauer, M.

2011-05-01

The project 'The Validity of Safety Goals' has been financed jointly by NKS (Nordic Nuclear Safety Research), SSM (Swedish Radiation Safety Authority) and the Swedish and Finnish nuclear utilities. The national financing went through NPSAG, the Nordic PSA Group (Swedish contributions) and SAFIR2010, the Finnish research programme on NPP safety (Finnish contributions). The project has been performed in four phases during 2006-2010. This guidance document aims at describing, on the basis of the work performed throughout the project, issues to consider when defining, applying and interpreting probabilistic safety criteria. Thus, the basic aim of the document is to serve as a checklist and toolbox for the definition and application of probabilistic safety criteria. The document describes the terminology and concepts involved, the levels of criteria and relations between these, how to define a probabilistic safety criterion, how to apply a probabilistic safety criterion, on what to apply the probabilistic safety criterion, and how to interpret the result of the application. The document specifically deals with what makes up a probabilistic safety criterion, i.e., the risk metric, the frequency criterion, the PSA used for assessing compliance and the application procedure for the criterion. It also discusses the concept of subsidiary criteria, i.e., different levels of safety goals. The results from the project can be used as a platform for discussions at the utilities on how to define and use quantitative safety goals. The results can also be used by safety authorities as a reference for risk-informed regulation. The outcome can have an impact on the requirements on PSA, e.g., regarding quality, scope, level of detail, and documentation. Finally, the results can be expected to support on-going activities concerning risk-informed applications. (Author)

Guidance for the definition and application of probabilistic safety criteria

Energy Technology Data Exchange (ETDEWEB)

Holmberg, J.-E. (VTT Technical Research Centre of Finland (Finland)); Knochenhauer, M. (Scandpower AB (Sweden))

2011-05-15

The project 'The Validity of Safety Goals' has been financed jointly by NKS (Nordic Nuclear Safety Research), SSM (Swedish Radiation Safety Authority) and the Swedish and Finnish nuclear utilities. The national financing went through NPSAG, the Nordic PSA Group (Swedish contributions) and SAFIR2010, the Finnish research programme on NPP safety (Finnish contributions). The project has been performed in four phases during 2006-2010. This guidance document aims at describing, on the basis of the work performed throughout the project, issues to consider when defining, applying and interpreting probabilistic safety criteria. Thus, the basic aim of the document is to serve as a checklist and toolbox for the definition and application of probabilistic safety criteria. The document describes the terminology and concepts involved, the levels of criteria and relations between these, how to define a probabilistic safety criterion, how to apply a probabilistic safety criterion, on what to apply the probabilistic safety criterion, and how to interpret the result of the application. The document specifically deals with what makes up a probabilistic safety criterion, i.e., the risk metric, the frequency criterion, the PSA used for assessing compliance and the application procedure for the criterion. It also discusses the concept of subsidiary criteria, i.e., different levels of safety goals. The results from the project can be used as a platform for discussions at the utilities on how to define and use quantitative safety goals. The results can also be used by safety authorities as a reference for risk-informed regulation. The outcome can have an impact on the requirements on PSA, e.g., regarding quality, scope, level of detail, and documentation. Finally, the results can be expected to support on-going activities concerning risk-informed applications. (Author)

Car seat inspection among children older than 3 years: Using data to drive practice in child passenger safety.

Science.gov (United States)

Kroeker, Amber M; Teddy, Amy J; Macy, Michelle L

2015-09-01

Motor vehicle crashes are the leading cause of unintentional death and disability among children 4 years to 12 years of age in the United States. Despite the high risk of injury from motor vehicle crashes in this age group, parental awareness and child passenger safety programs in particular may lack focus on this age group. This is a retrospective cross-sectional analysis of child passenger safety seat checklist forms from two Safe Kids coalitions in Michigan (2013) to identify restraint type upon arrival to car seat inspections. Other variables were included if the coalition provided a new child safety seat and if the child had a sibling who underwent a car seat inspection. χ statistics were used to compare change in restraint use on arrival and at departure, the proportion of children attending a car seat inspection event by age, the age category of children by site, the proportion of children with siblings also undergoing a car seat inspection by age, and the distribution of a new child safety seat by age. Data were available from 1,316 Safe Kids Huron Valley and 3,215 Safe Kids Greater Grand Rapids car seat inspections. Just 10.8% of the total seats inspected were booster seats. Child safety seats for infant and young children were more commonly inspected (rear-facing carrier [40.3%], rear-facing convertible [10.2%], and forward-facing [19.3%] car seats). Few children at inspections used a seat belt only (5.4%) or had no restraint (13.8%). Children 4 years and older were found to be in a suboptimal restraint at least 30% of the time. Low proportions of parents use car seat inspections for children in the booster seat age group. The proportion of children departing the inspection in a more protective restraint increased with increasing age. This highlights an area of weakness in child passenger safety programs and signals an opportunity to strengthen efforts on The Booster Age Child. Epidemiologic/prognostic study, level III.

Improving safety margin of LWRs by rethinking the emergency core cooling system criteria and safety system capacity

Energy Technology Data Exchange (ETDEWEB)

Lee, Youho, E-mail: euo@kaist.ac.kr; Kim, Bokyung, E-mail: bkkim2@kaist.ac.kr; NO, Hee Cheon, E-mail: hcno@kaist.ac.kr

2016-10-15

Highlights: • Zircaloy embrittlement criteria can increase to 1370 °C for CP-ECR lower than 13%. • The draft ECCS criteria of U.S. NRC allow less than 5% in power margin. • The Japanese fracture-based criteria allow around 5% in power margin. • Increasing SIT inventory is effective in assuring safety margin for power uprates. - Abstract: This study investigates the engineering compatibility between emergency core cooling system criteria and safety water injection systems, in the pursuit of safety margin increase of light water reactors. This study proposes an acceptable temperature increase to 1370 °C as long as equivalent cladding reacted calculated by the Cathcart–Pawel equation is below 13%, after an extensive literature review. The influence of different ECCS criteria on the safety margin during large break loss of coolant accident is investigated for OPR-1000 by the system code MARS-KS, implemented with the KINS-REM method. The fracture-based emergency core cooling system (ECCS) criteria proposed in this study are shown to enable power margins up to 10%. In the meantime, the draft U.S. NRC’s embrittlement criteria (burnup-sensitive) and Japanese fracture-based criteria are shown to allow less than 5%, and around 5% of power margins, respectively. Increasing safety injection tank (SIT) water inventory is the key, yet convenient, way of assuring safety margin for power increase. More than 20% increase in the SIT water inventory is required to allow 15% power margins, for the U.S. NRC’s burnup-dependent embrittlement criteria. Controlling SIT water inventory would be a useful option that could allow the industrial desire to pursue power margins even under the recent atmosphere of imposing stricter ECCS criteria for the considerable burnup effects.

Panel 1: Safety design criteria

International Nuclear Information System (INIS)

Yllera, Javier

2013-01-01

There is general consensus in the nuclear community, and more after the Fukushima accident, that the deployment of nuclear energy has to be done at the highest levels of nuclear safety and that safety cannot be compromised by other factors. It is well understood that reactors that are being licensed and the new generations of reactors that will be constructed in the future will need to reach higher safety levels than the existing ones. Several countries and international organizations or international groups are launching initiatives to harmonise safety goals, safety requirements, safety objectives, regulations, criteria or safety reference levels. There are differences in the meanings of these terms and the working approaches, but the overall purpose is the same: to specify how new plants can be safer. In this context, the IAEA has an statutory function for developing international nuclear safety standards. The IAEA safety standards are per se not mandatory for IAEA Member States. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA’s standards for use in their national regulations in different ways. The IAEA Safety Standards represent international consensus on what must constitute a high level of safety for nuclear installations. In the area of NPP design, IAEA safety standards that are published are intended to apply primarily to new plants. It might not be practicable to apply all the requirements to plants that are already in operation. In addition, the focus is primarily on plants with water cooled reactors

Simplified probabilistic approach to determine safety factors in deterministic flaw acceptance criteria

International Nuclear Information System (INIS)

Barthelet, B.; Ardillon, E.

1997-01-01

The flaw acceptance rules in nuclear components rely on deterministic criteria supposed to ensure the safe operating of plants. The interest of having a reliable method of evaluating the safety margins and the integrity of components led Electricite de France to launch a study to link safety factors with requested reliability. A simplified analytical probabilistic approach is developed to analyse the failure risk in Fracture Mechanics. Assuming lognormal distributions of the main random variables, it is possible considering a simple Linear Elastic Fracture Mechanics model, to determine the failure probability as a function of mean values and logarithmic standard deviations. The 'design' failure point can be analytically calculated. Partial safety factors on the main variables (stress, crack size, material toughness) are obtained in relation with reliability target values. The approach is generalized to elastic plastic Fracture Mechanics (piping) by fitting J as a power law function of stress, crack size and yield strength. The simplified approach is validated by detailed probabilistic computations with PROBAN computer program. Assuming reasonable coefficients of variations (logarithmic standard deviations), the method helps to calibrate safety factors for different components taking into account reliability target values in normal, emergency and faulted conditions. Statistical data for the mechanical properties of the main basic materials complement the study. The work involves laboratory results and manufacture data. The results of this study are discussed within a working group of the French in service inspection code RSE-M. (authors)

Licensing procedures and safety criteria for research reactors in France

International Nuclear Information System (INIS)

Berry, J.L.; Lerouge, B.

1980-11-01

This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. Some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors. At the end, a few considerations are given to the consequences of the Osiris core conversion

Health department inspection criteria more likely to be associated with outbreak restaurants in Minnesota.

Science.gov (United States)

Petran, Ruth L; White, Bruce W; Hedberg, Craig W

2012-11-01

Millions of routine restaurant inspections are performed each year in the United States, and the Centers for Disease Control and Prevention has reported that a majority of foodborne illness outbreaks occur in restaurant settings. In an attempt to relate the data collected during inspections in Minnesota to illness likelihood, data from routine inspections conducted at outbreak restaurants were compared with data from routine inspections conducted at nonoutbreak restaurants. The goal was to identify differences in recorded violations. Significantly more violations were recorded at restaurants that had outbreaks. The majority of these violations were related to contamination in the facility and environment and to food handling procedures. Relative risks also were calculated for violations significantly more likely to occur at locations that had outbreaks of norovirus infection, Clostridium perfringens infection or toxin-type illness, and Salmonella infection. These three pathogens are estimated to cause the majority of foodborne illnesses in the United States. Meta-analysis of composited data for the three pathogens revealed 11 violations significantly more likely (α restaurants than during inspections at nonoutbreak restaurants. Application of this information permits assessment of health department inspection data in a consistent fashion. This approach can help identify criteria more likely to be associated with outbreak locations and allow operators to focus on interventions that will have the most significant impact in higher risk establishments.

Compilation of nuclear safety criteria potential application to DOE nonreactor facilities

International Nuclear Information System (INIS)

1992-03-01

This bibliographic document compiles nuclear safety criteria applied to the various areas of nuclear safety addressed in a Safety Analysis Report for a nonreactor nuclear facility (NNF). The criteria listed are derived from federal regulations, Nuclear Regulatory Commission (NRC) guides and publications, DOE and DOE contractor publications, and industry codes and standards. The titles of the chapters and sections of Regulatory Guide 3.26, ''Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants'' were used to format the chapters and sections of this compilation. In each section the criteria are compiled in four groups, namely: (1) Code of Federal Regulations, (2) USNRC Regulatory Guides, (3) Codes and Standards, and (4) Supplementary Information

Synthesis of the IRSN report on the second safety re-inspection of the Orphee research reactor

International Nuclear Information System (INIS)

2010-01-01

The second safety inspection of the Orphee base nuclear installation notably relies on international and French return on experience. This inspection addressed the robustness of the installation against extreme aggressions, organisational processes, radiation protection, waste and effluent management, the security of the reactor operation, handling operation security, nuclear waste warehousing safety, internal aggressions, the third confinement barrier, and the radiological consequences of incidental and accidental situations

A plan for safety and integrity of research reactor components

International Nuclear Information System (INIS)

Moatty, Mona S. Abdel; Khattab, M.S.

2013-01-01

Highlights: ► A plan for in-service inspection of research reactor components is put. ► Section XI of the ASME Code requirements is applied. ► Components subjected to inspection and their classes are defined. ► Flaw evaluation and its acceptance–rejection criteria are reviewed. ► A plan of repair or replacement is prepared. -- Abstract: Safety and integrity of a research reactor that has been operated over 40 years requires frequent and thorough inspection of all the safety-related components of the facility. The need of increasing the safety is the need of improving the reliability of its systems. Diligent and extensive planning of in-service inspection (ISI) of all reactor components has been imposed for satisfying the most stringent safety requirements. The Safeguards Officer's responsibilities of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code ASME Code have been applied. These represent the most extensive and time-consuming part of ISI program, and identify the components subjected to inspection and testing, methods of component classification, inspection and testing techniques, acceptance/rejection criteria, and the responsibilities. The paper focuses on ISI planning requirements for welded systems such as vessels, piping, valve bodies, pump casings, and control rod-housing parts. The weld in integral attachments for piping, pumps, and valves are considered too. These are taken in consideration of safety class (1, 2, 3, etc.), reactor age, and weld type. The parts involve in the frequency of inspection, the examination requirements for each inspection, the examination method are included. Moreover the flaw evaluation, the plan of repair or replacement, and the qualification of nondestructive examination personnel are considered

Inspection planning

International Nuclear Information System (INIS)

Korosec, D.; Levstek, M.F.

2001-01-01

Slovenian Nuclear Safety Administration (SNSA) division of nuclear and radiological safety inspection has developed systematic approach to their inspections. To be efficient in their efforts regarding regular and other types of inspections, in past years, the inspection plan has been developed. It is yearly based and organized on a such systematic way, that all areas of nuclear safety important activities of the licensee are covered. The inspection plan assures appropriate preparation for conducting the inspections, allows the overview of the progress regarding the areas to be covered during the year. Depending on the licensee activities and nature of facility (nuclear power plant, research reactor, radioactive waste storage, others), the plan has different levels of intensity of inspections and also their frequency. One of the basic approaches of the plan is to cover all nuclear and radiological important activities on such way, that all regulatory requests are fulfilled. In addition, the inspection plan is a good tool to improve inspection effectiveness based on previous experience and allows to have the oversight of the current status of fulfillment of planned inspections. Future improvement of the plan is necessary in the light of newest achievements on this field in the nuclear world, that means, new types of inspections are planned and will be incorporated into plan in next year.(author)

Safety criteria for nuclear chemical plants

International Nuclear Information System (INIS)

Ball, P.W.; Curtis, L.M.

1983-01-01

Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

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.)

Risk informed In-service Inspection

International Nuclear Information System (INIS)

Corak, Z.

2003-01-01

insights. It is expected that licensees will ask for modifications of plant's design, operation, and other activities that require NRC approval to incorporate risk insights into their ISI programs. In-service inspection program in which is incorporated risk insights is known as risk-informed in-service inspection programs, RI-ISI. Until the RI-ISI is approved for generic use, the staff expects that licensees will ask for modifications of ISI programs by requesting NRC to approve alternative inspection programs. Alternative inspection programs must meet 10 CFR 50.55a (a)(3)(i) which says that 'the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety'. As always, licensees should identify how the chosen approach, methods, data, and criteria are appropriate for the decisions that have to be made. RI-ISI can provide reduction of scope and frequency of inspections that may lead to higher risk. The higher risk means that a probability of failure or consequences are higher and shutdown of nuclear power plants is more likely to occur. RI-ISI can also provide extensive scope of inspection or increased frequency of inspection. (author)

OSE inspection of computer security: Review

International Nuclear Information System (INIS)

Jaehne, E.M.

1987-01-01

The inspection process within the Department of Energy (DOE) serves the function of analyzing and reporting on the performance of security measures and controls in specific areas at sites throughout DOE. Three aspects of this process are discussed based on experience in computer security: Policy basis of performance inspections; Role and form of standards and criteria in inspections; and Conducting an inspection using the standards and criteria. Inspections are based on DOE and other applicable policy in each area. These policy statements have a compliance orientation in which the paper trail is often more clearly discernible than the security intention. The relationship of policy to performance inspections is discussed. To facilitate bridging the gap between the paper trail and the security intention defined by policy, standards and criteria were developed in each area. The consensus process and structure of the resulting product for computer security are discussed. Standards and criteria are inspection tools that support the site in preparing for an inspection and the inspector in conducting one. They form a systematic approach that facilitates consistency in the analysis and reporting of inspection results. Experience using the computer security standards and criteria is discussed

Fuel safety criteria in NEA member countries - Compilation of responses received from member countries

International Nuclear Information System (INIS)

2003-03-01

In 2001 the Committee on the Safety of Nuclear Installations (CSNI) issued a report on Fuel Safety Criteria Technical Review. The objective was to review the present fuel safety criteria and judge to which extent they are affected by the 'new' design elements, such as different cladding materials, higher burnup, the use of MOX fuels, etc. The report stated that the current framework of fuel safety criteria remains generally applicable, being largely unaffected by the 'new' or modern design elements. The levels (numbers) in the individual safety criteria may, however, change in accordance with the particular fuel and core design features. Some of these levels have already been - or are continuously being - adjusted. The level adjustments of several other criteria (RIA, LOCA) also appears to be needed, on the basis of experimental data and the analysis thereof. As a follow-up, among its first tasks, the CSNI Special Expert Group on Fuel Safety Margins (SEG FSM) initiated the collection of information on the present fuel safety criteria used in NEA member states with the objective to solicit national practices in the use of fuel safety criteria, in particular to get information on their specific national levels/values, including their recent adjustments, and to identify the differences and commonalties between the different countries. Two sources of information were used to produce this report: a compilation of responses to a questionnaire prepared for the June 2000 CNRA meeting, and individual responses from the SEGFSM members to the new revised questionnaire issued by the task Force preparing this report. In accordance with the latter, the fuel safety criteria discussed in this report were divided into three categories: (A) safety criteria - criteria imposed by the regulator; (B) operational criteria - specific to the fuel design and provided by the fuel vendor as part of the licensing basis; (C) design criteria - limits employed by vendors and/or utilities for fuel

Inspection Frequency, Sociodemographic Factors, and Food Safety Violations in Chain and Nonchain Restaurants, Philadelphia, Pennsylvania, 2013-2014.

Science.gov (United States)

Leinwand, Sarah E; Glanz, Karen; Keenan, Brendan T; Branas, Charles C

We explored how restaurant inspection frequency and restaurant neighborhood sociodemographic characteristics are related to food safety inspection outcomes in chain and nonchain restaurants to better understand external factors that may influence inspection outcomes. We categorized the results of restaurant inspections in Philadelphia, Pennsylvania, in 2013 and 2014 by restaurant type (chain or nonchain), inspection frequency (1, 2, or ≥3 per 2-year study period), and violation type (total number of violations, foodborne-illness risk factor violation, or good retail practice violation). We collected 2013 US Census block group sociodemographic data for each restaurant neighborhood. We used nested mixed-effects regression analyses to determine the association between restaurant inspection frequency and inspection violations, as well as between inspection violations and restaurant neighborhood sociodemographic variables, stratified by restaurant type. Compared with nonchain restaurants, chain restaurants had significantly fewer total violations per inspection (mean [SD]: 6.5 [4.6] vs 9.6 [6.8] violations, P chain restaurants. For nonchain restaurants, a higher proportion of black residents in a restaurant neighborhood was associated with 0.6 ( P food safety inspection frequency, based on whether or not restaurants are part of chains, could reduce the frequency of violations, particularly in restaurants with the most violations.

Advanced Inspection and Repair Welding Techniques for SCC Countermeasures

International Nuclear Information System (INIS)

Takagi, T.; Nishimoto, K.; Uchimoto, T.

2012-01-01

Feasibility studies of advanced inspection and repair welding techniques were conducted in the framework of the Nuclear and Industry Safety Agency of Japan (NISA) project on the enhancement of ageing management and maintenance of NPPs. In this paper, features of NDE methods investigated in the projects, main results of research activities and prospect of nickel based alloy weld inspection are discussed. We also make a review for the integrity and reliability evaluation techniques for repair welding of ageing plants which were intensively investigated in view of regulatory criteria, in NISA project. (author)

Nuclear safety inspection in treatment process for SG heat exchange tubes deficiency of unit 1, TNPS

International Nuclear Information System (INIS)

Zhang Chunming; Song Chenxiu; Zhao Pengyu; Hou Wei

2006-01-01

This paper describes treatment process for SG heat exchange tubes deficiency of Unit 1, TNPS, nuclear safety inspection of Northern Regional Office during treatment process for deficiency and further inspection after deficiency had been treated. (authors)

Analisis Kepatuhan Supervisor Terhadap Implementasi Program Occupational Health & Safety (Ohs) Planned Inspection Di PT. Ccai

OpenAIRE

Sarah, Dewi; Ekawati, Ekawati; Widjasena, Baju

2015-01-01

The Government has issued Regulation Legislation No. 50 Year 2012 on Health and Safety Management System (SMK3). CCAI is a company that has implemented SMK3. The application of the CCAI SMK3 supported by K3 program one of them is OHS Planned Inspection. This study aimed to analyze the implementation of Occupational Health & Safety (OHS) program Planned Inspection in CCAI. The subjects of this study amounted to five people as the main informants and 2 as an informant triangulation. The res...

Super Phenix 1: in Service inspection of main and safety tanks weldments

International Nuclear Information System (INIS)

Asty, Michel; Vertut, Jean; Argous, J.P.

1980-05-01

In service inspection of the main tank of the Super Phenix 1 reactor is a new demand as compared to Phenix: the authorities have asked that surface and internal defects could be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks

Super Phenix 1: In-service inspection of main and safety tanks weldments

Energy Technology Data Exchange (ETDEWEB)

Asty, M [DTech/STA, Centre d' Etudes Nucleaires de Saclay (France); Vertut, J [DPR/STEP, Centre d' Etudes Nucleaires de Saclay (France); Argous, J P [DRNR/STRS, Centre d' Etudes Nucleaires de Cadarache (France)

1980-11-01

In Service Inspection of the main tank of the Super Phenix 1 reactor is a new demand compared to Phenix: the authorities have asked that surface and internal defects be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks. (author)

Super Phenix 1: In-service inspection of main and safety tanks weldments

International Nuclear Information System (INIS)

Asty, M.; Vertut, J.; Argous, J.P.

1980-01-01

In Service Inspection of the main tank of the Super Phenix 1 reactor is a new demand compared to Phenix: the authorities have asked that surface and internal defects be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks. (author)

APPLICATION OF LEAN CONCEPT TO SHIP SAFETY INSPECTION: A CASE STUDY AT PORT OF SURABAYA

Directory of Open Access Journals (Sweden)

F. Cahyadi

2012-06-01

Full Text Available The Lean Concept is a mindset widely used in various industries seeking for efficiency and effectiveness through improvement of process flow and elimination of waste. This research applies lean thinking to ship safety inspection at Port of Surabaya to investigate the existing procedure and to identify the wastes and non-value-add (NVA activity. It used a combination of literature review, examination on the data of 520 inspections that have been carried out to 201 ships in the last two years (2009 - 2011, investigation on related regulations and guidelines, observation on the actual conduct of inspection, and interview with 59 marine inspectors and ship officers. Analysis is conducted using Value Stream Mapping (VSM. It is found that the existing procedure lacks significant impact in terms of imposing a reduction in the total number of detected deficiency between the earlier and subsequent inspections. Only 37% of the ships experience a reduction, indicating that the performance of inspection is currently at the level of 37 on a 100-point scale. It was mainly due to severe violation of the regulations, which is demonstrated by the issuance of ship certificate regardless of corrective action undertaken relating to the detected deficiency. Keywords: Lean concept, ship safety inspection, value stream mapping.

Inspection of radiation sources and regulatory enforcement (supplement to IAEA Safety Standards Series No. GS-G-1.5)

International Nuclear Information System (INIS)

2010-08-01

The achievement and maintenance of a high level of safety in the use of radiation sources depends on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for carrying out regulatory inspections, and taking necessary enforcement actions. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the processes for carrying out regulatory inspections and taking enforcement actions. It includes information on the development and use of procedures and standard review plans (i.e. checklists) for inspection. Specific procedures for inspection of radiation practices and sources are provided in the Appendices

Inspection of radiation sources and regulatory enforcement (supplement to IAEA Safety Standards Series No. GS-G-1.5)

International Nuclear Information System (INIS)

2007-04-01

The achievement and maintenance of a high level of safety in the use of radiation sources depends on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for carrying out regulatory inspections, and taking necessary enforcement actions. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the processes for carrying out regulatory inspections and taking enforcement actions. It includes information on the development and use of procedures and standard review plans (i.e. checklists) for inspection. Specific procedures for inspection of radiation practices and sources are provided in the Appendices

Discussions about safety criteria and guidelines for radioactive waste management.

Science.gov (United States)

Yamamoto, Masafumi

2011-07-01

In Japan, the clearance levels for uranium-bearing waste have been established by the Nuclear Safety Commission (NSC). The criteria for uranium-bearing waste disposal are also necessary; however, the NSC has not concluded the discussion on this subject. Meanwhile, the General Administrative Group of the Radiation Council has concluded the revision of its former recommendation 'Regulatory exemption dose for radioactive solid waste disposal', the dose criteria after the institutional control period for a repository. The Standardization Committee on Radiation Protection in the Japan Health Physics Society (The Committee) also has developed the relevant safety criteria and guidelines for existing exposure situations, which are potentially applicable to uranium-bearing waste disposal. A new working group established by The Committee was initially aimed at developing criteria and guidelines specifically for uranium-bearing waste disposal; however, the aim has been shifted to broader criteria applicable to any radioactive wastes.

How Agencies Inspect. A Comparative Study of Inspection Policies in Eight Swedish Government Agencies

International Nuclear Information System (INIS)

Lindblom, Lars; Clausen, Jonas; Edvardsson, Karin; Hayenhielm, Madeleine; Hermansson, Helene; Nihlen, Jessica; Palm, Elin; Ruden, Christina; Wikman, Per; Hansson, Sven Ove

2003-04-01

Eight Swedish authorities with inspection tasks in the areas of health, safety, and environmental protection have been compared, namely the authorities responsible for nuclear safety, radiation protection, railway, marine and aviation safety, environmental protection, chemicals control, and health and safety on workplaces. Significant differences in inspection policies and practices between the authorities were found, such as: diverging definitions of supervision and inspection that complicate comparisons, different priority-setting principles for inspections, variations in inspection frequencies (between 13 and 0.03 inspections per company and year), different practices with respect to notifying companies before inspection visits, and in particular, large differences in the extent to which non-compliance with regulations is reported to legal authorities. It was concluded that these agencies have much to gain from increasing their cooperation in methods development, evaluation studies, and education of inspectors

Safety-related operator actions: methodology for developing criteria

International Nuclear Information System (INIS)

Kozinsky, E.J.; Gray, L.H.; Beare, A.N.; Barks, D.B.; Gomer, F.E.

1984-03-01

This report presents a methodology for developing criteria for design evaluation of safety-related actions by nuclear power plant reactor operators, and identifies a supporting data base. It is the eleventh and final NUREG/CR Report on the Safety-Related Operator Actions Program, conducted by Oak Ridge National Laboratory for the US Nuclear Regulatory Commission. The operator performance data were developed from training simulator experiments involving operator responses to simulated scenarios of plant disturbances; from field data on events with similar scenarios; and from task analytic data. A conceptual model to integrate the data was developed and a computer simulation of the model was run, using the SAINT modeling language. Proposed is a quantitative predictive model of operator performance, the Operator Personnel Performance Simulation (OPPS) Model, driven by task requirements, information presentation, and system dynamics. The model output, a probability distribution of predicted time to correctly complete safety-related operator actions, provides data for objective evaluation of quantitative design criteria

Evaluation and improvement in nondestructive examination (NDE) reliability for inservice inspection of light water reactors

International Nuclear Information System (INIS)

Doctor, S.R.; Andersen, E.S.; Bowey, R.E.; Diaz, A.A.; Good, M.S.; Heasler, P.G.; Hockey, R.L.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V.

1991-01-01

This program is intended to establish the effectiveness, reliability and adequacy of inservice inspection of reactor pressure vessels and primary piping systems and the impact of ISI reliability on system integrity. The objectives of the program include: (a) determine the effectiveness and reliability of ultrasonic inservice inspection (ISI) performed on commercial, light water reactor pressure vessels and piping; (b) recommend Code changes to the inspection procedures to improve the reliability of ISI; (c) using fracture mechanics analysis, determine the impact of NDE unreliability on system safety and determine the level of inspection reliability required to assure a suitably low failure probability; (d) evaluate the degree of reliability improvement which could be achieved using improved NDE techniques; and (e) based on importance of component to safety, material properties, service conditions, and NDE uncertainties, formulate improved inservice inspection criteria (including sampling plan, frequency, and reliability of inspection) for revisions to ASME Section XI and regulatory requirements needed to assure suitably low failure probabilities

The role of probabilistic safety assessment and probabilistic safety criteria in nuclear power plant safety

International Nuclear Information System (INIS)

1992-01-01

The purpose of this Safety Report is to provide guidelines on the role of probabilistic safety assessment (PSA) and a range of associated reference points, collectively referred to as probabilistic safety criteria (PSC), in nuclear safety. The application of this Safety Report and the supporting Safety Practice publication should help to ensure that PSA methodology is used appropriately to assess and enhance the safety of nuclear power plants. The guidelines are intended for use by nuclear power plant designers, operators and regulators. While these guidelines have been prepared with nuclear power plants in mind, the principles involved have wide application to other nuclear and non-nuclear facilities. In Section 2 of this Safety Report guidelines are established on the role PSA can play as part of an overall safety assurance programme. Section 3 summarizes guidelines for the conduct of PSAs, and in Section 4 a PSC framework is recommended and guidance is provided for the establishment of PSC values

Criteria Document for B-plant's Surveillance and Maintenance Phase Safety Basis Document

International Nuclear Information System (INIS)

SCHWEHR, B.A.

1999-01-01

This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S and M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S and M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S and M Phase safety basis document

Human factors engineering design review acceptance criteria for the safety parameter display

International Nuclear Information System (INIS)

McGevna, V.; Peterson, L.R.

1981-01-01

This report contains human factors engineering design review acceptance criteria developed by the Human Factors Engineering Branch (HFEB) of the Nuclear Regulatory Commission (NRC) to use in evaluating designs of the Safety Parameter Display System (SPDS). These criteria were developed in response to the functional design criteria for the SPDS defined in NUREG-0696, Functional Criteria for Emergency Response Facilities. The purpose of this report is to identify design review acceptance criteria for the SPDS installed in the control room of a nuclear power plant. Use of computer driven cathode ray tube (CRT) displays is anticipated. General acceptance criteria for displays of plant safety status information by the SPDS are developed. In addition, specific SPDS review criteria corresponding to the SPDS functional criteria specified in NUREG-0696 are established

Safety Design Criteria (SDC) for Gen-IV Sodium-cooled Fast Reactor

International Nuclear Information System (INIS)

Nakai, Ryodai

2013-01-01

SDC Development Background & Objectives: • Safety Design Criteria (SDC) Development for Gen-IV SFR: – Proposed at the GIF Policy Group (PG) meeting in October 2010 –SDC “harmonization” is increasingly important for: • Realization of enhanced safety designs meeting to Gen-IV safety goals and safety approach common to SFR systems; • Preparation for the forthcoming licensing in the near future; • Because Gen-IV SFR are progressing into conceptual design stage. • The SDC is the Reference criteria: – Of the designs of safety-related Structures, Systems & Components that are specific to the SFR system; – For clarifying the requisites systematically & comprehensively; – When the technology developers apply the basic safety approach and use the codes & standards for conceptual design of the Gen-IV SFR system

Radiological Protection Criteria for the Safety of LILW Repository in Croatia

International Nuclear Information System (INIS)

Levanat, I.; Lokner, V.; Subasic, D.

2000-01-01

Preparations for a LILW repository development in Croatia, conducted by APO Hazardous Waste Management Agency, have reached a point where the first safety assessment of the prospective facility is being attempted. For evaluation of the calculated radiological impact in the assessed option of repository development, a set of radiological protection criteria should be included in the definition of the assessment context. The Croatian regulations do not explicitly require that the repository development be supported by such safety assessment process, and do not provide a specific set of radiological criteria intended for the repository assessment which would be suitable for the constrained optimization of protection. For the initial safety assessment iterations of the prospective repository, which will address long term performance of the facility for various design and other safety options, we propose to use relatively simple radiological protection criteria, consisting only of individual dose and risk constraints for the general population. The numerical values for these constraints are established in accordance with the recognized international recommendations and in compliance with all possibly relevant Croatian safety requirements. (author)

Working Towards Unified Safety Design Criteria for Modular High Temperature Gas-cooled Reactor Designs

International Nuclear Information System (INIS)

Reitsma, Frederik; Silady, Fred; Kunitomi, Kazuhiko

2014-01-01

The Nuclear Power Development Section of the IAEA recently received approval for a Coordinated Research Project (CRP) to investigate and make proposals on modular High Temperature Gas-cooled Reactor (HTGR) Safety design criteria. It is expected that these criteria would consider past experience and existing safety standards in the light of modular HTGR material and design characteristics to propose safety design criteria. It will consider the deterministic and risk-informed safety design standards that apply to the wide spectrum of Off- normal events under development worldwide for existing and planned HTGRs. The CRP would also take into account lessons from the Fukushima Daiichi accident, clarifying the safety approach and safety evaluation criteria for design and beyond design basis events, including those events that can affect multiple reactor modules and/or are dependent on the application proximate to the plant site. (e. g., industrial process steam/heat). The logical flow of criteria is from the fundamental inherent safety characteristics of modular HTGRs and associated expected performance characteristics, to the safety functions required to ensure those characteristics during the wide spectrum of Off-normal events, and finally to specific criteria related to those functions. This is detailed in the paper with specific examples included of how it may be applied. The results of the CRP will be made available to the member states and HTGR community. (author)

Safety approach to the selection of design criteria for the CRBRP reactor refueling system

International Nuclear Information System (INIS)

Meisl, C.J.; Berg, G.E.; Sharkey, N.F.

1979-01-01

The selection of safety design criteria for Liquid Metal Fast Breeder Reactor (LMFBR) refueling systems required the extrapolation of regulations and guidelines intended for Light Water Reactor refueling systems and was encumbered by the lack of benefit from a commercially licensed predecessor other than Fermi. The overall approach and underlying logic are described for developing safety design criteria for the reactor refueling system (RRS) of the Clinch River Breeder Reactor Plant (CRBRP). The complete selection process used to establish the criteria is presented, from the definition of safety functions to the finalization of safety design criteria in the appropriate documents. The process steps are illustrated by examples

Inspection surveys of x-ray inspection systems: results of five years and implications on future management of radiation risks

International Nuclear Information System (INIS)

Maharaj, H.P.

1999-01-01

Until the mid-1980s, federal inspectors performed radiation surveys annually on individual x-ray inspection systems which were operated for security screening purposes in federal facilities nationwide, and problems identified were corrected. The surveys were undertaken because of perceived high radiation risks and a need to ensure worker and public external exposures were minimized. The x-ray inspection systems are federally regulated under the Radiation Emitting Devices (RED) Act and, initially they were assessed by model type against the design, construction and performance criteria specified in the applicable RED regulations (Schedule II, Part IV) and were found compliant. A subsequent study not only demonstrated a much lower radiation risk attributed to a combination of technological advances in x-ray system design with narrow primary beams, high efficiency detectors and image processing capability, but also stressed the need for proper equipment maintenance and continued education of operators and maintenance personnel. Survey frequency was thus reduced to once every 2-3 years in accordance with a 1993 federal operational standard (Safety Code 29). The radiation protection principles in Safety Code 29 are similar to those of the 1996 International Atomic Energy Agency (IAEA) Basic Safety Standards for the protection against ionizing radiation and the safety of radiation sources. The purpose of this study was to assess inspection-survey data from 1993 through 1997 to elicit guidance toward the future management of radiation risks associated with the operation of such x-ray systems. (author)

Probabilistic safety analysis and risk-based inspection of nuclear research reactors: state-of-the-art and implementation proposal

Energy Technology Data Exchange (ETDEWEB)

Marques, Raíssa O.; Vasceoncelos, Vanderley de; Soares, Wellington A.; Silva Júnior, Silvério F.; Raso, Amanda L.; Mesquita, Amir Z., E-mail: raissaomarques@gmail.com, E-mail: vasconv@cdtn.br, E-mail: soaresw@cdtn.br, E-mail: silvasf@cdtn.br, E-mail: amandaraso@hotmail.com, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

Industrial facilities systems deteriorate over time during operation, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) classifies such systems by their risk information with the purpose of prioritizing inspection efforts. RBI can reduce inspection activities, resulting in lower risk levels, and maintaining reliability and safety in acceptable levels. Risk-Informed In-Service Inspection (RI-ISI) is a RBI approach used in nuclear industry. RI-ISI uses outcomes from Probabilistic Safety Analysis (PSA) of Nuclear Power Plants (NPP) to plan In-Service Inspections (ISI). Despite nuclear research reactors are simpler and have lower risks than power reactors, the application of PSA to them may be useful for safety improvements once they are more flexible, provide easier access to its core, and allow changes in fuel configurations in case of experimental tests. Ageing management of structures, systems and components important to safety of a nuclear research reactor throughout its lifetime is also required to assure continued adequacy of safety levels, reliable operation, and compliance with operational limits and conditions. This includes periodic review of ISI programs in which monitoring of material deterioration and aging effects are considered, and that can be supported by the RBI approach. A review of state-of-the-art of PSA and RBI applications to nuclear reactors is presented in this work. Advantages to apply these methodologies are also analyzed. PSA and RBI implementation proposal applied to nuclear research reactors is also presented, as well as its application to a TRIGA research nuclear reactor using computer codes developed by ReliaSoft® Corporation. (author)

Probabilistic safety analysis and risk-based inspection of nuclear research reactors: state-of-the-art and implementation proposal

International Nuclear Information System (INIS)

Marques, Raíssa O.; Vasceoncelos, Vanderley de; Soares, Wellington A.; Silva Júnior, Silvério F.; Raso, Amanda L.; Mesquita, Amir Z.

2017-01-01

Industrial facilities systems deteriorate over time during operation, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) classifies such systems by their risk information with the purpose of prioritizing inspection efforts. RBI can reduce inspection activities, resulting in lower risk levels, and maintaining reliability and safety in acceptable levels. Risk-Informed In-Service Inspection (RI-ISI) is a RBI approach used in nuclear industry. RI-ISI uses outcomes from Probabilistic Safety Analysis (PSA) of Nuclear Power Plants (NPP) to plan In-Service Inspections (ISI). Despite nuclear research reactors are simpler and have lower risks than power reactors, the application of PSA to them may be useful for safety improvements once they are more flexible, provide easier access to its core, and allow changes in fuel configurations in case of experimental tests. Ageing management of structures, systems and components important to safety of a nuclear research reactor throughout its lifetime is also required to assure continued adequacy of safety levels, reliable operation, and compliance with operational limits and conditions. This includes periodic review of ISI programs in which monitoring of material deterioration and aging effects are considered, and that can be supported by the RBI approach. A review of state-of-the-art of PSA and RBI applications to nuclear reactors is presented in this work. Advantages to apply these methodologies are also analyzed. PSA and RBI implementation proposal applied to nuclear research reactors is also presented, as well as its application to a TRIGA research nuclear reactor using computer codes developed by ReliaSoft® Corporation. (author)

Probabilistic safety criteria at the safety function/system level

International Nuclear Information System (INIS)

1989-09-01

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

Periodic safety analyses; Les essais periodiques

Energy Technology Data Exchange (ETDEWEB)

Gouffon, A; Zermizoglou, R

1990-12-01

The IAEA Safety Guide 50-SG-S8 devoted to 'Safety Aspects of Foundations of Nuclear Power Plants' indicates that operator of a NPP should establish a program for inspection of safe operation during construction, start-up and service life of the plant for obtaining data needed for estimating the life time of structures and components. At the same time the program should ensure that the safety margins are appropriate. Periodic safety analysis are an important part of the safety inspection program. Periodic safety reports is a method for testing the whole system or a part of the safety system following the precise criteria. Periodic safety analyses are not meant for qualification of the plant components. Separate analyses are devoted to: start-up, qualification of components and materials, and aging. All these analyses are described in this presentation. The last chapter describes the experience obtained for PWR-900 and PWR-1300 units from 1986-1989.

29 CFR 1960.25 - Qualifications of safety and health inspectors and agency inspections.

Science.gov (United States)

2010-07-01

... conditions affecting employee safety and health, coordination of inspection functions is encouraged. ... HEALTH ADMINISTRATION, DEPARTMENT OF LABOR (CONTINUED) BASIC PROGRAM ELEMENTS FOR FEDERAL EMPLOYEE... shall be conducted by inspectors qualified to recognize and evaluate hazards of the working environment...

Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team; Strategische Umweltpruefung zum Nationalen Entsorgungsprogramm. Beschreibung des Untersuchungsumfangs. Unterlage fuer den Scoping-Termin

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-01-06

The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

Standard Practice for Visual Inspections of Photovoltaic Modules

CERN Document Server

American Society for Testing and Materials. Philadelphia

2008-01-01

1.1 This practice covers procedures and criteria for visual inspections of photovoltaic modules. 1.2 Visual inspections of photovoltaic modules are normally performed before and after modules have been subjected to environmental, electrical, or mechanical stress testing, such as thermal cycling, humidity-freeze cycling, damp heat exposure, ultraviolet exposure, mechanical loading, hail impact testing, outdoor exposure, or other stress testing that may be part of photovoltaic module testing sequence. 1.3 This practice does not establish pass or fail levels. The determination of acceptable or unacceptable results is beyond the scope of this practice. 1.4 There is no similar or equivalent ISO standard. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Evaluation of proposed German safety criteria for high-temperature gas-cooled reactors

International Nuclear Information System (INIS)

Barsell, A.W.

1980-05-01

This work reviews proposed safety criteria prepared by the German Bundesministerium des Innern (BMI) for future licensing of gas-cooled high-temperature reactor (HTR) concepts in the Federal Republic of Germany. Comparison is made with US General Design Criteria (GDCs) in 10CFR50 Appendix A and with German light water reactor (LWR) criteria. Implications for the HTR design relative to the US design and safety approach are indicated. Both inherent characteristics and design features of the steam cycle, gas turbine, and process heat concepts are taken into account as well as generic design options such as a pebble bed or prismatic core

Influence of visual clutter on the effect of navigated safety inspection: a case study on elevator installation.

Science.gov (United States)

Liao, Pin-Chao; Sun, Xinlu; Liu, Mei; Shih, Yu-Nien

2018-01-11

Navigated safety inspection based on task-specific checklists can increase the hazard detection rate, theoretically with interference from scene complexity. Visual clutter, a proxy of scene complexity, can theoretically impair visual search performance, but its impact on the effect of safety inspection performance remains to be explored for the optimization of navigated inspection. This research aims to explore whether the relationship between working memory and hazard detection rate is moderated by visual clutter. Based on a perceptive model of hazard detection, we: (a) developed a mathematical influence model for construction hazard detection; (b) designed an experiment to observe the performance of hazard detection rate with adjusted working memory under different levels of visual clutter, while using an eye-tracking device to observe participants' visual search processes; (c) utilized logistic regression to analyze the developed model under various visual clutter. The effect of a strengthened working memory on the detection rate through increased search efficiency is more apparent in high visual clutter. This study confirms the role of visual clutter in construction-navigated inspections, thus serving as a foundation for the optimization of inspection planning.

Control system of the inspection robots group applying auctions and multi-criteria analysis for task allocation

Science.gov (United States)

Panfil, Wawrzyniec; Moczulski, Wojciech

2017-10-01

In the paper presented is a control system of a mobile robots group intended for carrying out inspection missions. The main research problem was to define such a control system in order to facilitate a cooperation of the robots resulting in realization of the committed inspection tasks. Many of the well-known control systems use auctions for tasks allocation, where a subject of an auction is a task to be allocated. It seems that in the case of missions characterized by much larger number of tasks than number of robots it will be better if robots (instead of tasks) are subjects of auctions. The second identified problem concerns the one-sided robot-to-task fitness evaluation. Simultaneous assessment of the robot-to-task fitness and task attractiveness for robot should affect positively for the overall effectiveness of the multi-robot system performance. The elaborated system allows to assign tasks to robots using various methods for evaluation of fitness between robots and tasks, and using some tasks allocation methods. There is proposed the method for multi-criteria analysis, which is composed of two assessments, i.e. robot's concurrency position for task among other robots and task's attractiveness for robot among other tasks. Furthermore, there are proposed methods for tasks allocation applying the mentioned multi-criteria analysis method. The verification of both the elaborated system and the proposed tasks' allocation methods was carried out with the help of simulated experiments. The object under test was a group of inspection mobile robots being a virtual counterpart of the real mobile-robot group.

Homogenization of independent inspection criteria of Quality Assurance in the maintenance activities

International Nuclear Information System (INIS)

Gomez Cardinanos, R.

2012-01-01

Among the official documents governing the operation of Spanish nuclear power plants is the Quality Manual and Quality Assurance. This manual gives a formal answer to the requirements of the regulations and the Nuclear Safety Council. To monitor the compliance of its requirements, the plants are controlled by independent organizations. Since 2007, in nuclear Sta. Maria de Garona is developed a project to improve the performance of the QA inspectors during maintenance activities. Results of the project have been edited data sheets on specific activities of maintenance. The project aims to incorporate sheets that help QA inspectors in their daily inspection.

Aspects of the Optimization on the In-Service Inspection

International Nuclear Information System (INIS)

Korosec, D.; Vojvodic Tuma, J.

2002-01-01

In the present paper, the aspects of optimizing In-Service Inspection (ISI) is discussed. Slovenian Nuclear Safety Administration (SNSA) and its authorized organization for the ISI activities, Institute of Metals and Technologies, are actually permanently involved in the ISI processes of the nuclear power plant (NPP) Krsko. Based on the previous experience on the ISI activities, evaluation of the results and review of the new ISI program, the decision was made to improve recent regulatory and professional practice. That means, the conclusion was made to optimize the evaluation process of the ISI as a process. Traditional criteria, standards and practice gives good fundament for the improvements implementation. Improvements can be done on the way that the more broad knowledge about safety important components of the systems shall bee added to the basic practice. It is necessary to identify conditions of the safety important components, such as realistic stress and fatigue conditions, material properties changes due aging processes, the temperature cycling effects, existing flaws characterization in the light of the previous detection and equipment technique used, assessment of the measurement accuracy on the results etc. In addition to the above mentioned, risk assessment and evaluation of the whole ISI shall be done. To do this it is necessary to made risk evaluation, based on previous structural element probability assessment. Probabilistic risk assessment is important and one of the most powerful tools in the ISI optimization. Some basic work on the filed of the risk informed methods related to the nuclear safety components has been already done. Based on reference documentation, the most important steps in risk informed ISI are discussed: scope definition, consequence evaluation, failure probability estimation, risk evaluation, non-destructive examination method selection and possibilities of implementation, monitoring and feedback. Recent experience on the ISI

Criteria for guidance in the safety assessment of nuclear installations in the United Kingdom

International Nuclear Information System (INIS)

Gausden, R.; Fryer, D.R.H.

1977-01-01

There is an increasing appreciation of the need for a consistent approach to nuclear safety between various groups having an interest in safety and between various types of installation. Licensing for construction and ultimate approval to operate any nuclear installation depend in the United Kingdom upon a searching assessment of the design, construction and operation of the proposed plant. Criteria of the kind discussed in this paper have been used by the Nuclear Installations Inspectorate in this assessment process. From time to time they are subject to comments from other bodies in the U.K. One aim of the criteria is to set out the broad objectives that should be met regarding the magnitude of radiological consequences of accidents or normal operation. In addition, the criteria give guidance on the design philosophy for nuclear safety and the principles of fault evaluation. Criteria must be conceived so that while maintaining safety standards their application does not frustrate design and development. It is also important that undue formalism is not induced in the assessment process at the expense of inhibiting the judgement of safety assessors. A balance must, therefore, be struck between detailed and generalised guidance. It is also accepted that experience in the use and interpretation of criteria will indicate a need for improvement and additions: the criteria are, therefore, regarded as living rather than fixed statements which are expected to develop in response to any need for change in a safe direction that may arise. In developing them, the Inspectorate has drawn heavily upon the experience accumulated during its 16 years of operation and has also referred to criteria published by other organisations. The paper deals specifically with certain of the most important sections of the criteria and indicates the total range of subjects which need to be included in such criteria

Argentine criteria on nuclear safety and emergencies: their impact on the Argos PHWR 380 design

International Nuclear Information System (INIS)

Gonzalez, A. J.

1988-01-01

This paper describes first the safety criteria of the Argentine regulatory authority with emphasis on the probabilistic safety criteria based on a limitation of individual risks. Then, it is presented a discussion on emergency criteria in relation to evacuation and relocation measures. Finally, the paper briefly describes the design of an Argentine offer for a safer heavy water reactor where these criteria are applied. 9 figs., 1 tab., 46 refs. (author)

Competition and safety in the law on technical inspection and control - is it a contradiction?

International Nuclear Information System (INIS)

Roth, H.A.

1987-01-01

For some time now, objections have been raised against the argument that technical inspection and control should indeed remain a task exlusively for the Technical Control Boards and their offices, organisations and employed inspectors, because competition in this very safety-related sector would not be a positive factor of selection but rather a mechanism reducing the inspection quality, resulting in a hazardous lowering of the safety level. The objections are primarily raised by the free-lance technical experts and their organisations who would like to enlarge their field of activity in this direction. The book at hand discusses the question how much free manoeuvering space there is for the legislative body to deal with such demands and reconcile the interests of safety and competition. The problem is discussed with a view to the Basic Law, which is said to create no legal basis for the demand for more competition in this field. The Basic Law leaves this decision to the discretion of the legislature. (orig./HP) [de

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

Inspection program for U.S. research reactors

International Nuclear Information System (INIS)

Isaac, Patrick J.

2010-01-01

This paper presents an established program for inspection of nuclear research reactors to ensure that systems and techniques are in accordance with regulatory requirements and to provide protection for the health and safety of the public. The inspection program, implemented from the time a facility gets licensed, remains in effect through operations, shutdown, decommissioning, and until the license is terminated. The program establishes inspection methodology for operating, safeguards, and decommissioning activities. Using a performance- based approach, inspectors focus their attention on activities important to safety. Inspection procedures allow the inspectors to assess facility safety and compliance to applicable requirements. A well designed inspection program is an integral part of the mechanism to ensure that the level of performance in the strategic areas of reactor safety, radiation safety, and safeguards is acceptable and provides adequate protection of public health and safety. (author)

Technical objectives of inspection

International Nuclear Information System (INIS)

Sorenson, R.J.; Stewart, K.B.; Schneider, R.A.

1976-01-01

The various technical objectives of inspection are discussed in a very general manner. The discussion includes how the inspection function is related to the assumed threat, the various degrees of assurance and reliance on criteria, and the hierarchy of assurance which is obtained from the various types or levels of inspection

Licensing procedures and safety criteria for research reactors in France

International Nuclear Information System (INIS)

Berry, J.L.; Lerouge, B.

1983-01-01

From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon

Licensing procedures and safety criteria for research reactors in France

Energy Technology Data Exchange (ETDEWEB)

Berry, J L; Lerouge, B [Centre d' Etudes Nucleaires de Saclay (France)

1983-08-01

From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon.

LMFBR safety criteria and guidelines for consideration in the design of future plants

International Nuclear Information System (INIS)

1990-01-01

For many years the Commission of the European Communities has been conducting activities aimed at the progressive harmonization of safety requirements and criteria applied to nuclear installations in the Community. These activities cover thermal and fast reactors. This publication represents a major achievement in reaching this goal. The document, which has been prepared in the framework of activities of the CEC fast-reactor safety working group (SWG), consists of safety criteria and guidelines for fast reactors. It represents the common view of all EC Member States which have a fast-reactor programme or are interested in fast-reactor development. The criteria and guidelines are structured according to different types of possible faults, such as core reactivity faults, general cooling faults, subassembly faults, faults outside the core and causes external to the station. Only those events are considered which are in the design basis of current fast-reactor projects. Proposed measures or guidelines to satisfy the criteria are based on the present knowledge and proven technology

Optimal allocation of international atomic energy agency inspection resources

International Nuclear Information System (INIS)

Markin, J.T.

1987-01-01

Each year the Department of Safeguards of the International Atomic Energy Agency (IAEA) conducts inspections to confirm that nuclear materials and facilities are employed for peaceful purposes. Because of limited inspection resources, however, the IAEA cannot fully attain its safeguards goals either quantitatively as measured by the inspection effort negotiated in the facility attachments or qualitatively as measured by the IAEA criteria for evaluating attainment of safeguards goals. Under current IAEA procedures the allocation of inspection resources assigns essentially equal inspection effort to facilities of the same type. An alternative approach would incorporate consideration of all material categories and facilities to be assigned inspection resources when allocating effort to a particular facility. One such method for allocating inspection resources is based on the IAEA criteria. The criteria provide a framework for allocating inspection effort that includes a ranking of material types according to their safeguards importance, an implicit definition of inspection activities for each material and facility type, and criteria for judging the attainment of safeguards goals in terms of the quality and frequency of these inspection activities. This framework is applicable to resource allocation for an arbitrary group of facilities such as a state's fuel cycle, the facilities inspected by an operations division, or all of the facilities inspected by the IAEA

Evaluation of structural welds with respect to reliability and inservice inspection

International Nuclear Information System (INIS)

Marci, G.

1980-01-01

The ongoing developments with respect to large forgings for nuclear pressure vessels and the present philosophy of inservice inspection in the Federal Republic of Germany (FRG) (inspection of weld regions only) seem to be oriented towards a monolithic pressure vessel requiring no inservice inspection. This raises questions as to the task of inservice inspection in the framework of the total reliability of a nuclear pressure vessel. The inherent 'weak spots' associated with welds of ferritic low alloyed steels are the microstructural features of stress relief cracks and regions of coarse grains. An analysis as to the effects of stress relief cracks and regions of coarse grains in the heat affected zones of welds on subcritical crack growth is performed. It is shown that these 'weak spots' cannot be considered a particular safety hazard to vessel integrity. Therefore welds per se should not constitute the criteria for the performance of inservice inspection. Rather, the inservice inspection programme should check the regions where manufacturing history, loading conditions, and materials degradation are expected to enhance subcritical crack growth. (author)

APPLICATION OF LEAN CONCEPT TO SHIP SAFETY INSPECTION: A CASE STUDY AT PORT OF SURABAYA

OpenAIRE

Cahyadi, F.

2012-01-01

The Lean Concept is a mindset widely used in various industries seeking for efficiency and effectiveness through improvement of process flow and elimination of waste. This research applies lean thinking to ship safety inspection at Port of Surabaya to investigate the existing procedure and to identify the wastes and non-value-add (NVA) activity. It used a combination of literature review, examination on the data of 520 inspections that have been carried out to 201 ships in the last two years ...

Technological progress, safety, and the guardian role of inspection (with Appendix: Antecedants of the Nuclear Installation Inspectorate)

International Nuclear Information System (INIS)

Critchley, O.H.

1981-01-01

Technological progress inevitably brings hazards which must be inspected to reduce the occurence of any attendant risks to a minimum. Although the responsibility for regulatory safety inspection in Britain is spread amongst a number of specialist inspectorates, it is arguably the most fully developed, efficient and satisfactorily operating regime of its kind, this being especially true for commercial nuclear installations. The latter aspect is a complex mix of engineering, legal and managerial practices which has been modelled on the developments in safety technology in atomic energy in the Manhattan Project and in the UKAEA, among others, and on to the present Nuclear Installations Inspectorate. (U.K.)

Risk based maintenance to increase safety and decrease costs

International Nuclear Information System (INIS)

Phillips, J.H.

2000-01-01

Risk-Based techniques have been developed for commercial nuclear power plants for the last eight years by a team working through the ASME Center for Research and Technology Development (CRTD). System boundaries and success criteria is defined using the Probabilistic Risk Analysis or Probabilistic Safety Analysis developed to meet the Individual Plant Evaluation. Final ranking of components is by a plant expert panel similar to the one developed for the Maintenance Rule. Components are identified as being high risk-significant or low risk-significant. Maintenance and resources are focused on those components that have the highest risk-significance. The techniques have been developed and applied at a number of plants. Results from the first risk-based inspection pilot plant indicates safety due to pipe failure can be doubled while the inspection reduced to about 80% when compared with current inspection programs. Pilot studies on risk-based testing indicate that about 60% of pumps and 25 to 30% of valves in plants are high safety-significant The reduction in inspection and testing reduces the person-rem exposure and resulting in further increases in safety. These techniques have been documented in publications by the ASME CRTD which are referenced. (author)

Optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 with an optimized cost perspective

International Nuclear Information System (INIS)

Jinil Mok; Poong Hyun Seong

1996-01-01

In this work, a model for determining the optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 is developed, which is to minimize economic loss caused by inadvertent trip and the system failure. This model uses cost benefit analysis method and the part for optimal inspection period considers the human error. The model is based on three factors as follows: (i) The cumulative failure distribution function of the safety system, (ii) The probability that the safety system does not operate due to failure of the system or human error when the safety system is needed at an emergency condition and (iii) The average probability that the reactor is tripped due to the failure of system components or human error. The model then is applied to evaluate the safety system in Wolsung Nuclear Power Plant Unit 1. The optimal replacement periods which are calculated with proposed model differ from those used in Wolsung NPP Unit 1 by about a few days or months, whereas the optimal inspection periods are in about the same range. (author)

Plant specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events

International Nuclear Information System (INIS)

2011-01-01

The German Parliament requested (17 March 2011) a comprehensive inspection of German nuclear power plants. For this purpose independent expert commissions should perform a new risk analysis of all German NPPS and nuclear installations with respect to the lessons learned from the Fukushima (Japan) events and other extraordinary damage scenarios. The Reactor safety commission (RSK) was assigned by the German Bundesamt fuer Strahlenschutz to develop a catalogue of requirements for this safety inspection. The contribution summarizes the required inspection volume (status 30.03.2011) including the following events: natural events like earth quakes, floods, weather-based consequences and possible superposition. Additionally the following assumptions have to be considered: event independent postulated common failures or systematic faults, station blackout larger than 2 hours, long-term failure of the auxiliary cooling water supply; aggravating boundary conditions for the performance of emergency measures (non-availability of power supply), hydrogen generation and detonation hazard, restricted personnel availability, non-accessibility due to high radiation levels, impeded technical support from outside. (orig.)

33 CFR 165.169 - Safety and Security Zones: New York Marine Inspection Zone and Captain of the Port Zone.

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones: New... Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PORTS AND WATERWAYS SAFETY... Areas First Coast Guard District § 165.169 Safety and Security Zones: New York Marine Inspection Zone...

JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors. (3) Progress of component design

International Nuclear Information System (INIS)

Enuma, Yasuhiro; Kawasaki, Nobuchika; Orita, Junichi; Eto, Masao; Miyagawa, Takayuki

2015-01-01

In the frame work of generation IV international forum (GIF), safety design criteria (SDC) and safety design guideline (SDG) for the generation IV sodium-cooled fast reactors have been developing in the circumstance of worldwide deployment of SFRs. JAEA, JAPC, MFBR have been investigating design study for JSFR to satisfy SDC in the feasibility study of SDG for Sodium-cooled Fast Reactor (SFR). In addition to the safety measures, maintainability, reparability and manufacturability are taken into account in the JSFR design study. This paper describes the design of main components. Enlargement of the access route for the inspection devices and addition of the access routes were carried out for the reactor structure. The pump-integrated IHX (pump/IHX) was modified for the primary heat exchanger (PHX), which was installed for the decay heat removal in the IHX at the upper plenum, to be removable for improved repair and maintenance. For the steam generator (SG), protective wall tube type design is under investigation as an option with less R and D risks. (author)

Task of radiation hygiene inspection at NPPs

International Nuclear Information System (INIS)

Shevts, J.; Kunz, Eh.

1983-01-01

The task and functions of the radiation-hygiene inspection in Czechoslovakia are presented. The radiation safety related information amounts that are to be presented to the hygiene inspection institutions are determined. The hygiene inspection content and forms at the stages of NPP designing, construction and operation are discussed. The hygiene inspection place is determined within the general radiation safety system [ru

Radiation safety for baggage x-ray inspection systems

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-05-01

This book is an outgrowth of a course on radiation safety aimed at technicians responsible for conducting maintenance on baggage x-ray inspection systems used in federally operated facilities. The need for a single reference book became apparent to the instructor in 1984. In an effort to provide a cohesive development of the subject, a set of lecture notes was prepared and revised annually since 1984, from which this book has evolved. This book is intended to present concepts necessary for an elementary but comprehensive knowledge of radiation safety. While some material coverage may appear somewhat detailed, it is a deliberate attempt to strengthen areas of demonstrated weaknesses observed in course attenders and to provide guidance on the numerous questions about man-made radiation asked by course attenders over the years. Numerical examples are included in most chapters for clarity and ease of understanding. The problems given at the end of most chapters provide the reader with the opportunity of applying the material presented in the chapters to situations of practical interest. It is important that these problems be considered an integral part of the course and students attempt to solve them. 36 refs., 9 tabs., 17 figs.

Radiation safety for baggage x-ray inspection systems

International Nuclear Information System (INIS)

1994-05-01

This book is an outgrowth of a course on radiation safety aimed at technicians responsible for conducting maintenance on baggage x-ray inspection systems used in federally operated facilities. The need for a single reference book became apparent to the instructor in 1984. In an effort to provide a cohesive development of the subject, a set of lecture notes was prepared and revised annually since 1984, from which this book has evolved. This book is intended to present concepts necessary for an elementary but comprehensive knowledge of radiation safety. While some material coverage may appear somewhat detailed, it is a deliberate attempt to strengthen areas of demonstrated weaknesses observed in course attenders and to provide guidance on the numerous questions about man-made radiation asked by course attenders over the years. Numerical examples are included in most chapters for clarity and ease of understanding. The problems given at the end of most chapters provide the reader with the opportunity of applying the material presented in the chapters to situations of practical interest. It is important that these problems be considered an integral part of the course and students attempt to solve them. 36 refs., 9 tabs., 17 figs

Joint road safety operations in tunnels and open roads

Science.gov (United States)

Adesiyun, Adewole; Avenoso, Antonio; Dionelis, Kallistratos; Cela, Liljana; Nicodème, Christophe; Goger, Thierry; Polidori, Carlo

2017-09-01

The objective of the ECOROADS project is to overcome the barrier established by the formal interpretation of the two Directives 2008/96/EC and 2004/54/EC, which in practice do not allow the same Road Safety Audits/Inspections to be performed inside tunnels. The projects aims at the establishment of a common enhanced approach to road infrastructure and tunnel safety management by using the concepts and criteria of the Directive 2008/96/CE on road infrastructure safety management and the results of related European Commission (EC) funded projects. ECOROADS has already implemented an analysis of national practices regarding Road Safety Inspections (RSI), two Workshops with the stakeholders, and an exchange of best practices between European tunnel experts and road safety professionals, which led to the definition of common agreed safety procedures. In the second phase of the project, different groups of experts and observers applied the above common procedures by inspecting five European road sections featuring both open roads and tunnels in Belgium, Albania, Germany, Serbia and Former Yugoslav Republic of Macedonia. This paper shows the feedback of the 5 joint safety operations and how they are being used for a set of - recommendations and guidelines for the application of the RSA and RSI concepts within the tunnel safety operations.

In-service inspection techniques

International Nuclear Information System (INIS)

Backfisch, W.; Zipser, R.R.

1980-01-01

The owner of a nuclear power plant (NPP) is obligated and interested to maintain - by regular maintenance and in-service inspections - the operational safety and availability of the plant for the subsequent operating period in a condition, as is specified as the basis of the erection and the last operational permits. In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. Below, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor or on a boiling-water reactor) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

Restaurant inspection frequency: The RestoFreq Study.

Science.gov (United States)

Medu, Olanrewaju; Turner, Hollie; Cushon, Jennifer A; Melis, Deborah; Rea, Leslie; Abdellatif, Treena; Neudorf, Cory O; Schwandt, Michael

2017-03-01

Foodborne illness is an important contributor to morbidity and health system costs in Canada. Using number of critical hazards as a proxy for food safety, we sought to better understand how to improve food safety in restaurants. We compared the current standard of annual inspections to twice-yearly inspections among restaurants "at risk" for food safety infractions. These were restaurants that had three or more elevated-risk inspection ratings in the preceding 36 months. We conducted a two-arm randomized controlled trial between November 2012 and October 2014. The intervention was twice-yearly routine restaurant inspection compared to standard once-yearly routine inspection. Included were all restaurants within Saskatoon Health Region that were assessed as "at risk", with 73 restaurants in the intervention arm and 78 in the control arm. Independent sample t-tests were conducted between groups to compare: i) average number of critical hazards per inspection; and ii) proportion of inspections resulting in a rating indicating an elevated hazard. Over time we noted statistically significant improvements across both study arms, in number of both critical food safety hazards (decreased by 61%) and elevated-risk inspection ratings (decreased by 45%) (p < 0.0001). We observed no significant differences between the two groups pre- or post-intervention. Results suggest increasing the number of annual routine inspections in high-risk restaurants was not associated with a significant difference in measures of compliance with food safety regulations. Findings of this study do not provide evidence supporting increased frequency of restaurant inspection from annually to twice annually.

The role of the United States Food Safety and Inspection Service after the Chernobyl accident

Energy Technology Data Exchange (ETDEWEB)

Engel, Ronald E; Randecker, Victor; Johnson, Wesley [Food Safety and Inspection Service, United States Department of Agriculture (United States)

1989-09-01

The Food Safety and Inspection Service (FSIS) of the United States Department of Agriculture (USDA) inspects domestic and imported meat and poultry food products to assure the public that they are safe, wholesome, not economically adulterated and properly labeled. The Service also monitors the activities of meat and poultry plants and related activities in allied industries, and establishes standards and approves labels for meat and poultry products. As part of its responsibility, shortly after the Chernobyl accident occurred, FSIS developed a plan to assess this accident's impact on domestically produced and imported meat and poultry.

The role of the United States Food Safety and Inspection Service after the Chernobyl accident

International Nuclear Information System (INIS)

Engel, Ronald E.; Randecker, Victor; Johnson, Wesley

1989-01-01

The Food Safety and Inspection Service (FSIS) of the United States Department of Agriculture (USDA) inspects domestic and imported meat and poultry food products to assure the public that they are safe, wholesome, not economically adulterated and properly labeled. The Service also monitors the activities of meat and poultry plants and related activities in allied industries, and establishes standards and approves labels for meat and poultry products. As part of its responsibility, shortly after the Chernobyl accident occurred, FSIS developed a plan to assess this accident's impact on domestically produced and imported meat and poultry

A critical overview of safety-related and technological criteria for nuclear fuel

International Nuclear Information System (INIS)

Lahodova, M.; Valach, M.

2000-10-01

A detailed overview of the safety criteria, methods of analysis and computer codes used in OECD countries is presented. A critical analysis of the validity of criteria in the high burnup domain was performed, and recommendations for testing their validity based on available experimental data are put forth. (author)

Commercial Vehicle Safety Alliance (CVSA)/Department of Energy (DOE) cooperative agreement final report

International Nuclear Information System (INIS)

Slavich, Antoinette; Daust, James E.

1999-01-01

This S and T product is a culmination of the activities, including research of the Commercial Vehicle Safety Alliance (CVSA) in developing and implementing inspection procedures and the out-of-service criteria for states and tribes to use when inspecting HRCQ and Transuranic shipments of radioactive materials. The report also contains the results of a pilot study to test the procedures

Chapter 4. Assessment and inspection of nuclear installations

International Nuclear Information System (INIS)

2001-01-01

Supervisory activity of Nuclear Regulatory Authority of the Slovak Republic (UJD) upon the safety of nuclear installations in compliance with the 'Atomic Act' and other legal regulations includes also inspection and assessment activities of UJD. Assessment activity of UJD in relation to nuclear installations lies in assessment of safety documentation for constructions realised as nuclear installations, or constructions through which changes are realised on nuclear installations. The scope of safety documentation required for the assessment is stipulated in the Atomic Act. In 2000 the assessment activity focused first of all on Unit 1 of NPP Bohunice after completing its Gradual Reconstruction Programme, on National Repository of Radioactive waste in Mochovce and on radioactive waste conditioning and treatment technology in Jaslovske Bohunice. Activities of UJD in assessment focused mainly on control of compliance with requirements for nuclear safety, assessment of commissioning programmes, operating procedures, limits and conditions, etc. The assessment of changes, which influence nuclear safety of nuclear installations in operation, realisation of which is conditioned by the approval from UJD, is a significant part of the assessment activity of UJD. Mainly it is the assessment of design changes, changes in limits and conditions, operating procedures, changes in programmes of periodical testing of equipment important in terms of nuclear safety, changes in physical protection of nuclear equipment, etc. The assessment of nuclear installations operational safety, based on assessment of operational events, on maintaining limits and conditions of safe operation, on operational safety performance indicators and on inspection results is a separate category in the assessment activity of UJD. Inspection activity specified in the 'Atomic Act' is governed by an internal guideline, an important part of which is an annual inspection plan that considers the following types of

Reliability-based service life assessment of concrete structures in nuclear power plants: optimum inspection and repair

International Nuclear Information System (INIS)

Ellingwood, B.R.; Mori, Y.

1995-01-01

Research is being conducted to address aging management of safety-related reinforced concrete structures in nuclear power plants (NPPs). Documentation is being prepared to identify potential structural safety issues and to recommend criteria for use in evaluating reinforced concrete structures for continued service. Time-dependent reliability analysis provides the framework and quantitative tools for the condition assessment. The role of in-service inspection and repair in ensuring continued reliability in-service is examined. (author). 19 refs., 4 figs

Safeguarding the nuclear safety of WWER-440 reactor pressure vessels at SKODA Plzen

International Nuclear Information System (INIS)

Hrbek, Z.

1986-01-01

The approach is described of the SKODA enterprise to safety assurance and to providing the reliability of WWER-440 reactor pressure vessels. The philosophy is analyzed of in-service inspection and determination of the residual service life of pressure vessels. This follows up on the so-called conception of basic safety whose main aim is to preclude failures at production stage by the selection of suitable material, namely by optimizing the choice of raw materials, of metallurgical procedures such as will lead to high purity of the pressure vessel material, by introducing multiple inspection in production, reducing the sensitivity of materials to technological operations, and by high-quality welds. The quality of in-service inspections is given by the use of technical diagnostic instruments of peak quality and of modern methods of nondestructive materials testing. The instruments and methods used are described. It is stated that the experience gained with in-service inspection will make it possible to draw up operating regulations and safety criteria for nuclear installations and own inspection regulations, this with regard to technical and economic factors. (Z.M.)

Safety of WWER type nuclear power plants - viewing from Hungary

International Nuclear Information System (INIS)

Voeroess, L.

1991-01-01

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

Multispectral fluorescence imaging techniques for nondestructive food safety inspection

Science.gov (United States)

Kim, Moon S.; Lefcourt, Alan M.; Chen, Yud-Ren

2004-03-01

The use of spectral sensing has gained acceptance as a rapid means for nondestructive inspection of postharvest food produce. Current technologies generally use color or a single wavelength camera technology. The applicability and sensitivity of these techniques can be expanded through the use of multiple wavelengths. Reflectance in the Vis/NIR is the prevalent spectral technique. Fluorescence, compared to reflectance, is regarded as a more sensitive technique due to its dynamic responses to subtle changes in biological entities. Our laboratory has been exploring fluorescence as a potential means for detection of quality and wholesomeness of food products. Applications of fluorescence sensing require an understanding of the spectral characteristics emanating from constituents and potential contaminants. A number of factors affecting fluorescence emission characteristics are discussed. Because of relatively low fluorescence quantum yield from biological samples, a system with a powerful pulse light source such as a laser coupled with a gated detection device is used to harvest fluorescence, in the presence of ambient light. Several fluorescence sensor platforms developed in our laboratory, including hyperspectral imaging, and laser-induced fluorescence (LIF) and steady-state fluorescence imaging systems with multispectral capabilities are presented. We demonstrate the potential uses of recently developed fluorescence imaging platforms in food safety inspection of apples contaminated with animal feces.

Study on the Safety Classification Criteria of Mechanical Systems and Components for Open Pool-Type Research Reactors

International Nuclear Information System (INIS)

Belal, Al Momani; Jo, Jong Chull

2013-01-01

This paper describes a new compromised safety classification approach based on the comparative study of the different practices in safety classification of mechanical systems and components of open pool-type RRs, which have been adopted by several developed countries in the nuclear power area. It is hoped that the proposed safety classification criteria will be used to develop a harmonized consensus international standard. Different safety classification criteria for systems, structures, and components (SSCs) of nuclear reactors are used among the countries that export or import nuclear reactor technology, which may make the nuclear technology trade and exchange difficult. Thus, such various different approaches of safety classification need to be compromised to establish a global standard. This article proposes practicable optimized criteria for safety classification of SSCs for open pool-type research reactors (RRs)

Study on the Safety Classification Criteria of Mechanical Systems and Components for Open Pool-Type Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Belal, Al Momani [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Jo, Jong Chull [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-10-15

This paper describes a new compromised safety classification approach based on the comparative study of the different practices in safety classification of mechanical systems and components of open pool-type RRs, which have been adopted by several developed countries in the nuclear power area. It is hoped that the proposed safety classification criteria will be used to develop a harmonized consensus international standard. Different safety classification criteria for systems, structures, and components (SSCs) of nuclear reactors are used among the countries that export or import nuclear reactor technology, which may make the nuclear technology trade and exchange difficult. Thus, such various different approaches of safety classification need to be compromised to establish a global standard. This article proposes practicable optimized criteria for safety classification of SSCs for open pool-type research reactors (RRs)

Risk informed approach to the in-service inspection activities

International Nuclear Information System (INIS)

Korosec, D.; Vojvodic Tuma, J.

2004-01-01

In the present paper, the aspects of Risk Informed In-Service Inspection (RI-ISI) are discussed. Slovenian Nuclear Safety Administration (SNSA) and its authorized organization for the ISI activities, Institute of Metals and Technologies (IMT), are actually permanently involved in the ISI processes of the nuclear power plant (NPP) Krsko. Based on the previous experience on the ISI activities, evaluation of the results and review of the existing practice in nuclear world, the activities are started to asses the piping of systems in the light of probability of failure. This is so called Risk Informed approach. By the design established criteria, standards and practice gives good fundaments for the improvements implementation. Improvements can be done on the way that the more broad knowledge about safety important components of the systems shall bee added to the basic practice. It is necessary to identify conditions of the safety important components, such as realistic stress and fatigue conditions, material properties changes due aging processes, the temperature cycling effects, existing flaws characterization in the light of the previous detection and equipment technique used, assessment of the measurement accuracy on the results etc. In addition to this deterministic approach, the principles of risk evaluation methods should be used. NPP Krsko has, as practically majority of NPP's, probabilistic risk assessment (PRA) studies for all safety important systems and components. The methods and results from these studies can be efficiently used to upgrade classical deterministic results, based on which the in-service program as a whole is usually done. In addition to the above mentioned, risk assessment and evaluation of the piping shall be done, which is not covered by the existing PRA analysis. To do this it is necessary to made risk evaluation of the piping segments, based on previous structural element probability assessment. Probabilistic risk assessment is important

Analysis of differences in fuel safety criteria for WWER and western PWR nuclear power plants

International Nuclear Information System (INIS)

2003-11-01

In 2001 the OECD issued a report of the NEA/CSNI (Committee on the Safety of Nuclear Installations) Task Force on the existing safety criteria for reactor fuel for western LWR nuclear power plants (both for PWRs and BWRs) under new design elements. Likewise in 2001, the IAEA released a report by a Working Group on the existing safety criteria for reactor fuel for WWER nuclear power plants under new design requirements. However, it was found that it was not possible to compare the two sets of criteria on the basis upon which they had been established. Therefore, the IAEA initiated an assessment of the common features and differences in fuel safety criteria between plants of eastern and western design, focusing on western PWRs and eastern WWER reactors. Between October 2000 and November 2001, the IAEA organized several workshops with representatives from eastern and western European countries in which the current fuel safety related criteria for PWR and WWER reactors were reviewed and compared. The workshops brought together expert representatives from the Russian Federation, from the Ukraine and from western countries that operate PWRs. The first workshop focused on a general overview of the fuel safety criteria in order for all representatives to appreciate the various criteria and their respective bases. The second workshop (which involved one western and one eastern expert) concentrated on addressing and explaining the differences observed, and documenting all these results in preparation for a panel discussion. This panel discussion took place during the third workshop, where the previously obtained results were reviewed in detail and final recommendations were made. This report documents the findings of the workshops. It highlights the common features and differences between PWR and WWER fuel, and may serve as a general basis for the safety evaluation of these fuels. Therefore, it will be very beneficial for licensing activities for PWR and WWER plants, as it

The Determinants of Federal and State Enforcement of Workplace Safety Regulations: OSHA Inspections 1990-2010*

Science.gov (United States)

Jung, Juergen

2013-01-01

We explore the determinants of inspection outcomes across 1.6 million Occupational Safety and Health Agency (OSHA) audits from 1990 through 2010. We find that discretion in enforcement differs in state and federally conducted inspections. State agencies are more sensitive to local economic conditions, finding fewer standard violations and fewer serious violations as unemployment increases. Larger companies receive greater lenience in multiple dimensions. Inspector issued fines and final fines, after negotiated reductions, are both smaller during Republican presidencies. Quantile regression analysis reveals that Presidential and Congressional party affiliations have their greatest impact on the largest negotiated reductions in fines. PMID:24659856

Development approach on usage of radiation and inspection of QA according to the change of approval procedure of safety regulatory guides

International Nuclear Information System (INIS)

Oh, B. J.; Ahn, H. Z.; Kim, S. W.; Yoo, S. O.; Kang, S. C.; Yang, S. H.; Han, S. J.; Kim, H. S.; Kim, H. J.

2002-01-01

In accordance with 2001 amendment of the Atomic Energy Act(AEA), KINS also amended its internal 'Regulation on Implementation of Entrusted AEA-related Work'. Up to now the nuclear safety-specialized institute has used its internally developed guidelines in the safety regulation. From now on, however, the institute will enhance the objectivity and transparency by having the instruments approved by the Ministry of Science ad Technology. In this paper, we introduced the major points and directions to be considered to the development of the safety regulatory guides on Inspection for the quality assurance of the nuclear reactor facilities and the use of radioisotopes, and review and inspection for dosimeter reading

Reliability Assessment and Reliability-Based Inspection and Maintenance of Offshore Wind Turbines

DEFF Research Database (Denmark)

Ramirez, José Rangel

actions are the most relevant and effective means of control of deterioration. The risk-based inspection planning methodology, based on Bayesian decision theory, represents an important tool to identify the suitable strategy to inspect and control the deterioration in structures such as offshore wind...... performance during the life cycle. The deterioration processes, such as fatigue and corrosion, are typically affecting offshore structural systems. This damage decreases the system performance and increases the risk of failure, thus not fulfilling the established safety criteria. Inspection and maintenance...... to their offshore location, no pollution risks and low human risks since they are unmanned. This allows the allocation of lower reliability level compared to e.g. oil & gas installations. With the incursion to water depths between 20 and 50 meters, the use of jacket and tripod structures represents a feasible...

Safety procedures in operation of inspection and maintenance of pressure reduction and metering stations

International Nuclear Information System (INIS)

Villas Boas, Ademar Jose; Biesemeyer, Marco Aurelio R.

2000-01-01

Each local Natural Gas Distribution Company in Brazil has its own working procedures for operations of inspection and maintenance on equipment and accessories connected to the gas network. Some of these Companies developed a better elaborated and documented way of working routines, while others only work based on their operators experience. The objective of this work is to create a standard procedure for operations of inspection and maintenance of Pressure Reducing Stations and Metering Stations, mainly the ones concerned to safety aspects. This work has no intention of exhausting all aspects related to this subject but to become the first step to standardize these types of operations among Natural Gas Distribution Companies. (author)

Inspection of Emergency Arrangements

International Nuclear Information System (INIS)

2013-01-01

NPPs. - Where RBs have an influence over land use around NPPs, they use the knowledge of their local or resident inspectors to inform decisions. - Inspectors check that appropriate action levels or criteria to identify an actual or radiological emergency are clearly defined and readily available to decision makers. - When observing emergency exercises inspectors check that: an appropriate and timely declaration is made, plant operators respond in accordance with the emergency plan and emergency instructions, and an appropriate level of response is initiated on and off-site. - RBs conduct follow-up inspections after real events, to ensure that the correct emergency response has been followed. - Inspectors verify that reliable data will be used to support the evaluation of environmental impact from a nuclear or radiological emergency, to the extent that this is within the jurisdiction of the RB. - Routine inspections and emergency exercise observations include a check that lines of communication are sufficiently resilient. - When observing emergency exercises inspectors, where practicable, check that timely, accurate and consistent information is provided to the public, in accordance with the off-site emergency plan. - RBs inspect the ability of the operator to give accurate medical and radiological information about casualties, to enable the correct treatment to be given. - Additional emergency equipment that is held in reserve off-site, provided to enhance resilience (post Fukushima), is included in the RB planned inspection and/or emergency exercise programme. - Inspectors check that licensee staff are adequately trained to connect and use additional equipment provided to enhance resilience. - Inspectors utilise the NPP operator's approved on-site emergency plan when inspecting on-site emergency arrangements. - RBs include human factors staff in emergency exercise evaluation teams to consider safety culture and human performance. - RBs consider the need for exercise

Designs for remote inspection of the ALMR Reactor Vessel Auxiliary Cooling System (RVACS)

International Nuclear Information System (INIS)

Sweeney, F.J.; Carroll, D.G.; Chen, C.; Crane, C.; Dalton, R.; Taylor, J.R.; Tosunoglu, S.; Weymouth, T.

1993-01-01

One of the most important safety systems in General Electric's (GI) Advanced Liquid Metal Reactor (ALMR) is the Reactor Vessel Auxiliary Cooling System (RVACS). Because of high temperature, radiation, and restricted space conditions, GI desired methods to remotely inspect the RVACS, emissive coatings, and reactor vessel welds during normal refueling operations. The DOE/NE Robotics for Advanced Reactors program formed a team to evaluate the ALMR design for remote inspection of the RVACS. Conceptual designs for robots to perform the required inspection tasks were developed by the team. Design criteria for these remote systems included robot deployment, power supply, navigation, environmental hardening of components, tether management, communication with an operator, sensing, and failure recovery. The operation of the remote inspection concepts were tested using 3-D simulation models of the ALMR. In addition, the team performed an extensive technology review of robot components that could survive the environmental conditions in the RVACS

A Criteria Standard for Conflict Resolution: A Vision for Guaranteeing the Safety of Self-Separation in NextGen

Science.gov (United States)

Munoz, Cesar; Butler, Ricky; Narkawicz, Anthony; Maddalon, Jeffrey; Hagen, George

2010-01-01

Distributed approaches for conflict resolution rely on analyzing the behavior of each aircraft to ensure that system-wide safety properties are maintained. This paper presents the criteria method, which increases the quality and efficiency of a safety assurance analysis for distributed air traffic concepts. The criteria standard is shown to provide two key safety properties: safe separation when only one aircraft maneuvers and safe separation when both aircraft maneuver at the same time. This approach is complemented with strong guarantees of correct operation through formal verification. To show that an algorithm is correct, i.e., that it always meets its specified safety property, one must only show that the algorithm satisfies the criteria. Once this is done, then the algorithm inherits the safety properties of the criteria. An important consequence of this approach is that there is no requirement that both aircraft execute the same conflict resolution algorithm. Therefore, the criteria approach allows different avionics manufacturers or even different airlines to use different algorithms, each optimized according to their own proprietary concerns.

49 CFR 193.2623 - Inspecting LNG storage tanks.

Science.gov (United States)

2010-10-01

... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Maintenance § 193.2623 Inspecting LNG storage tanks. Each LNG... 49 Transportation 3 2010-10-01 2010-10-01 false Inspecting LNG storage tanks. 193.2623 Section 193...

Squale: evaluation criteria of functioning safety; Squale: criteres d`evaluation de la surete de fonctionnement

Energy Technology Data Exchange (ETDEWEB)

Deswarte, Y; Kaaniche, M [Centre National de la Recherche Scientifique (CNRS), 31 - Toulouse (France). Laboratoire d` Analyse et d` Architecture des Systemes; Corneillie, P [CE2A-DI, 92 - Courbevoie (France); Benoit, P [Matra Transport International, 92 - Montrouge (France)

1998-05-01

The SQUALE (security, safety and quality evaluation for dependable systems) project is part of the ACTS (advanced communications, technologies and services) European program. Its aim is to develop confidence evaluation criteria to test the functioning safety of systems. All industrial sectors that use critical applications (nuclear, railway, aerospace..) are concerned. SQUALE evaluation criteria differ from the classical evaluation methods: they are independent of the application domains and industrial sectors, they take into account the overall functioning safety attributes, and they can progressively change according to the level of severity required. In order to validate the approach and to refine the criteria, a first experiment is in progress with the METEOR automatic underground railway and another will be carried out on a telecommunication system developed by Bouygues company. (J.S.) 15 refs.

Safety analysis, risk assessment, and risk acceptance criteria

International Nuclear Information System (INIS)

Jamali, K.

1997-01-01

This paper discusses a number of topics that relate safety analysis as documented in the Department of Energy (DOE) safety analysis reports (SARs), probabilistic risk assessments (PRA) as characterized primarily in the context of the techniques that have assumed some level of formality in commercial nuclear power plant applications, and risk acceptance criteria as an outgrowth of PRA applications. DOE SARs of interest are those that are prepared for DOE facilities under DOE Order 5480.23 and the implementing guidance in DOE STD-3009-94. It must be noted that the primary area of application for DOE STD-3009 is existing DOE facilities and that certain modifications of the STD-3009 approach are necessary in SARs for new facilities. Moreover, it is the hazard analysis (HA) and accident analysis (AA) portions of these SARs that are relevant to the present discussions. Although PRAs can be qualitative in nature, PRA as used in this paper refers more generally to all quantitative risk assessments and their underlying methods. HA as used in this paper refers more generally to all qualitative risk assessments and their underlying methods that have been in use in hazardous facilities other than nuclear power plants. This discussion includes both quantitative and qualitative risk assessment methods. PRA has been used, improved, developed, and refined since the Reactor Safety Study (WASH-1400) was published in 1975 by the Nuclear Regulatory Commission (NRC). Much debate has ensued since WASH-1400 on exactly what the role of PRA should be in plant design, reactor licensing, 'ensuring' plant and process safety, and a large number of other decisions that must be made for potentially hazardous activities. Of particular interest in this area is whether the risks quantified using PRA should be compared with numerical risk acceptance criteria (RACs) to determine whether a facility is 'safe.' Use of RACs requires quantitative estimates of consequence frequency and magnitude

MDEP Technical Report TR-VICWG-04. Technical Report: Assessment of Multinational Vendor Inspection of Valinox Nuclear

International Nuclear Information System (INIS)

2015-01-01

From July 7-11, 2014, the NRC led a team of inspectors representing regulators from France, the United Kingdom, and the United States in performing the first Multinational Design Evaluation Program (MDEP) multinational inspection at Valinox Nuclear in Montbard, France. Valinox Nuclear's primary product line is steam generator tubes for the nuclear industry. The purpose of the inspection was to assess Valinox's compliance with the quality assurance/quality control (QA/QM) criteria described in the Multinational Design Evaluation Program (MDEP) Vendor Inspection Cooperation Working Group (VICWG) Technical Report, TR-VICWG-03, 'Common QA/QM Criteria for Multinational Vendor Inspection', Revision 1, dated January 20, 2014, and MDEP Protocol, VICWG-01, 'Witnessed, Joint, and Multinational Vendor Inspection Protocol', Revision 2, dated March 20, 2014, respectively. The inspection also offered the inspectors an opportunity to pilot the VICWG draft common position document to gain valuable insights into the effectiveness of application of the common QA/QM criteria to vendor inspections performed by a multinational inspection team. During this inspection, the inspection team evaluated implementation of Valinox's quality assurance (QA) program with respect to 15 specific criteria: 1. Quality management system; 2. Grading; 3. Documentation of the quality management system; 4. Control of documents and records; 5. Responsibility and Leadership; 6. Human resources; 7. Process Implementation; 8. Control of planning and implementation changes; 9. Purchasing (including aspects of CSFI); 10. Control of implementation including Control of special processes; 11. Monitoring and measurement of product and service; 12. Assessment; 13. Non-conformances; 14. Corrective and preventive actions; and 15. Safety culture. By letter dated 26 August 2014, the NRC issued a vendor inspection report to Valinox Nuclear, which documented four findings (Non

Safety criteria related to microheterogeneities in LWR mixed oxide fuels

International Nuclear Information System (INIS)

Renard, A.; Mostin, N.

1978-01-01

The main safety aspets of PuO 2 microheterogeneities in the pellets of LWR mixed oxide fuels are reviewed. Points of interest are studied, especially the transient behaviour in accidental conditions and criteria are deduced for use in the specification and quality control of the fabricated product. (author)

Inspection of licensee - Maintenance programme and activities

International Nuclear Information System (INIS)

2013-01-01

An effective maintenance programme is critical to sustained safe and reliable operation of nuclear power plants. The Working Group on Inspection Practices (WGIP) concluded that when a licensee has an effective maintenance programme, the overall operating safety of the plant is improved and the protection of public health and safety enhanced. All Regulatory Bodies (RB) consider maintenance to be an important area for oversight. Although a variety of inspection practices are being used; RB are actively monitoring licensee performance. Specifically the following conclusions were reached and commendable practices identified: - Maintenance oversight by regulators appears to be in a stable continuous improvement state. Most regulators are executing inspection oversight based on an existing regulatory framework. - The performance of a licensee's maintenance programme is recognized as important part of maintaining nuclear safety. The result of the maintenance program assessment is included in the overall performance assessment of a license. - Maintenance inspection activities are recognized as an important part of the regulatory oversight process. Inspection activities are based on the safety significance and nature of work being performed by the licensee. - The effectiveness of the maintenance inspection activities is recognized to rely on properly qualified inspectors; who are adequately supported by specialists. Training and qualification of inspectors should be based on how the RB reviews and inspects licensee maintenance programmes. - Reporting requirements are identified to provide information on the licensees maintenance programme, and to help guide inspection activities. - Performance Indicators are recognized as a useful tool for helping focus regulatory activities. Basic PI are identified and tracked by the RB, and use of PI by the licensee is monitored. - Inspections are designed to confirm that the licensee is planning and scheduling maintenance with due

Analysis of existing work-zone devices with MASH safety performance criteria.

Science.gov (United States)

2009-02-01

Crashworthy, work-zone, portable sign support systems accepted under NCHRP Report No. 350 were analyzed to : predict their safety peformance according to the TL-3 MASH evaluation criteria. An analysis was conducted to determine : which hardware param...

What do implementers need in terms of regulatory safety criteria for the post-closure phase?

International Nuclear Information System (INIS)

Cahen, B.

2010-01-01

Bruno Cahen, Director Safety Division (ANDRA) presented the point of view of the NEA Integration Group for the Safety Case (IGSC) on 'What do implementers need in terms of regulatory safety criteria for the post-closure phase?' B. Cahen acknowledged that the national experience in siting and developing conceptual designs of geological disposal is growing rapidly. It implies increasing opportunities for interactions between implementers and regulators. There has been large development of international guidance in the recent years. Many regulators have already developed a regulatory framework. The implementers need practical, transparent and deliverable regulations. These regulations should draw on experiences gained from development of geological disposal projects. The IGSC has identified five key questions that the RF may focus on: 1. Over what time frame are the waste deemed to present a hazard? 2. Over what time frames are regulatory criteria applied and do they change over time? 3. Over what time frame(s) are safety assessments required to be conducted? 4. How do implementers have to address uncertainties in the long time frames? 5. What happens after cut-offs: are additional analyses needed? What types of arguments are to be used? Stable, understandable and practical criteria mean, namely, that they need to be developed on a strong scientific and societal basis, that there is consistency of safety options and requirements for different types of waste, that, in the longer time frames, the emphasis is given to robust systems, passive safety and multiple safety functions and that the criteria should fit the various phases of the project (siting, designing, operating, closure and post-closure). Experience feedback from safety cases shows that safety priorities depend very much on time frames. The derived safety criteria for the individual components should lead to measurable, verifiable specifications. The assessment of geological repository post-closure safety

Attitude of the Korean dentists towards radiation safety and selection criteria

International Nuclear Information System (INIS)

Lee, Byung Do; Ludlow, John B.

2013-01-01

X-ray exposure should be clinically justified and each exposure should be expected to give patients benefits. Since dental radiographic examination is one of the most frequent radiological procedures, radiation hazard becomes an important public health concern. The purpose of this study was to investigate the attitude of Korean dentists about radiation safety and use of criteria for selecting the frequency and type of radiographic examinations. The study included 267 Korean dentists. Five questions related to radiation safety were asked of each of them. These questions were about factors associated with radiation protection of patients and operators including the use of radiographic selection criteria for intraoral radiographic procedures. The frequency of prescription of routine radiographic examination (an example is a panoramic radiograph for screening process for occult disease) was 34.1%, while that of selective radiography was 64.0%. Dentists' discussion of radiation risk and benefit with patients was infrequent. More than half of the operators held the image receptor by themselves during intraoral radiographic examinations. Lead apron/thyroid collars for patient protection were used by fewer than 22% of dental offices. Rectangular collimation was utilized by fewer than 15% of dental offices. The majority of Korean dentists in the study did not practice radiation protection procedures which would be required to minimize exposure to unnecessary radiation for patients and dental professionals. Mandatory continuing professional education in radiation safety and development of Korean radiographic selection criteria is recommended.

Attitude of the Korean dentists towards radiation safety and selection criteria

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Do [Dept. of Oral and Maxillofacial Radiology and Wonkwang Dental Research Institute, College of Dentistry, Wonkwang University, Iksan (Korea, Republic of); Ludlow, John B. [Graduate Program in Oral and Maxillofacial Radiology, School of Dentistry, University of North Carolina, Chapel Hill (United States)

2013-09-15

X-ray exposure should be clinically justified and each exposure should be expected to give patients benefits. Since dental radiographic examination is one of the most frequent radiological procedures, radiation hazard becomes an important public health concern. The purpose of this study was to investigate the attitude of Korean dentists about radiation safety and use of criteria for selecting the frequency and type of radiographic examinations. The study included 267 Korean dentists. Five questions related to radiation safety were asked of each of them. These questions were about factors associated with radiation protection of patients and operators including the use of radiographic selection criteria for intraoral radiographic procedures. The frequency of prescription of routine radiographic examination (an example is a panoramic radiograph for screening process for occult disease) was 34.1%, while that of selective radiography was 64.0%. Dentists' discussion of radiation risk and benefit with patients was infrequent. More than half of the operators held the image receptor by themselves during intraoral radiographic examinations. Lead apron/thyroid collars for patient protection were used by fewer than 22% of dental offices. Rectangular collimation was utilized by fewer than 15% of dental offices. The majority of Korean dentists in the study did not practice radiation protection procedures which would be required to minimize exposure to unnecessary radiation for patients and dental professionals. Mandatory continuing professional education in radiation safety and development of Korean radiographic selection criteria is recommended.

Wireless Roadside Inspection Proof of Concept Test Final Report

Energy Technology Data Exchange (ETDEWEB)

Capps, Gary J [ORNL; Franzese, Oscar [ORNL; Knee, Helmut E [ORNL; Plate, Randall S [ORNL; Lascurain, Mary Beth [ORNL

2009-03-01

The U.S. Department of Transportation (DOT) FMCSA commissioned the Wireless Roadside Inspection (WRI) Program to validate technologies and methodologies that can improve safety through inspections using wireless technologies that convey real-time identification of commercial vehicles, drivers, and carriers, as well as information about the condition of the vehicles and their drivers. It is hypothesized that these inspections will: -- Increase safety -- Decrease the number of unsafe commercial vehicles on the road; -- Increase efficiency -- Speed up the inspection process, enabling more inspections to occur, at least on par with the number of weight inspections; -- Improve effectiveness -- Reduce the probability of drivers bypassing CMV inspection stations and increase the likelihood that fleets will attempt to meet the safety regulations; and -- Benefit industry -- Reduce fleet costs, provide good return-on-investment, minimize wait times, and level the playing field. The WRI Program is defined in three phases which are: Phase 1: Proof of Concept Test (POC) Testing of commercially available off-the-shelf (COTS) or near-COTS technology to validate the wireless inspection concept. Phase 2: Pilot Test Safety technology maturation and back office system integration Phase 3: Field Operational Test Multi-vehicle testing over a multi-state instrumented corridor This report focuses on Phase 1 efforts that were initiated in March, 2006. Technical efforts dealt with the ability of a Universal Wireless Inspection System (UWIS) to collect driver, vehicle, and carrier information; format a Safety Data Message Set from this information; and wirelessly transmit a Safety Data Message Set to a roadside receiver unit or mobile enforcement vehicle.

Review of activities relevant to in-service inspection

International Nuclear Information System (INIS)

Imanaka, N.

1980-01-01

Nuclear power plants are requested to provide continuing safety that cannot compare with other industries, as plant safety is a matter of much concern. To provide continuous assurance for plant safety there is increasing tendency to demand much of inspection of components during the lifetime. This inservice inspection of LMFBRs should be investigated from a view point of different systems and characteristics from LWRs. In this paper a review for inservice inspection of LMFBRs is described. To provide a continuous assurance of safety to the LMFBR, it is essential to develop how to construct the components to maintain the integrity throughout the service lifetime. Especially how to design is urged for this object. In-service inspection should be located only to compensate some uncertainty remained at the design stage, as it is too much complex in practice. As for inspection techniques, leak monitoring is assumed to be a best way to assure the plant safety continuously with the minimum plant outage time and minimum radioactive hazard to the inspectors

Safety and Inspection Planning of Older Installations

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard; Ersdal, G.

2007-01-01

A basic assumption often made in risk/reliability based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and a no-...

Safety and Inspection Planning of Older Installations

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard; Ersdal, G.

2008-01-01

A basic assumption often made in risk- and reliability-based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and ...

Evaluation of radiological safety in industrial gammagraphy services during the construction of Bolivia-Brazil gas transmission lines (GASBOL), by regulatory inspections from brazilian CNEN

International Nuclear Information System (INIS)

Aquino, Josilto O. de; Silva, Francisco Cesar A. da; Leocadio, Joao Carlos; Pinho, Adaugoberto S. de; Souza, Luiz Antonio C. de; Lourenco, Manoel J.; Nicola, Marcello S.; Melo, Ivan F.

2001-01-01

This paper presents a brief description of the Brazilian Regulatory Authority's (National Commission of Nuclear Energy - CNEN) action about safety control on industrial radioactive installations. It shows some specific radiation safety inspections that were done during the construction of the Bolivia-Brazil Gas Transmission Line (GASBOL). In this GASBOL work, it was used industrial radiography sources for weld quality control. During two years were done thirty regulatory safety inspections in these movable installations that use gamma radiography devices. As final result, it was noticed that the national system of inspection to control the safe use of radioactive sources in industrial activities is really efficient because none overexposure was detect and every CNEN's recommendations were applied by the operators. Some result about the gamma devices and violations are also showed. (author)

9 CFR 381.309 - Finished product inspection.

Science.gov (United States)

2010-01-01

... Section 381.309 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Canning and Canned Products § 381.309...

Developing inspection strategies to support local activities

DEFF Research Database (Denmark)

Jensen, Per Langå

2003-01-01

An analysis of the Danish development in regulatory praxsis within occupational health and safety with a detailed description of Adapted Inspection.......An analysis of the Danish development in regulatory praxsis within occupational health and safety with a detailed description of Adapted Inspection....

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

Recurrent safety inspection of German nuclear power plant - performance, schedule and goals. As of 11 August 1995; Periodische Sicherheitsueberpruefung (PSUe) fuer deutsche Kernkraftwerke - Durchfuehrung der PSUe. Vom 11. August 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-23

The recurrent safety inspection is intended as an inspection supplementing the continuous operation monitoring activities within the framework given by the supervisory activities of the supervisory authority. The first recurrent safety inspection is scheduled to be performed about ten years after start-up of the plant, with subsequent inspection intervals to cover ten-year periods, and recorded operating and monitoring results to be taken into account at each recurrent inspection. The purpose of the recurrent safety inspections is to ascertain that post-inspection operation of the plant meets the then required safety standards. Significant testing results of the latest inspection are to be analysed and compared with regard to the current state of the art and operating results accumulated since the previous inspection, for subsequent definition of enhancements if required. (orig./HP) [Deutsch] Die PSUesoll eine Ergaenzung der staendigen Ueberpruefung im Rahmen der atomrechtlichen Aufsicht ueber den Betrieb sein. Eine erstmalige PSUesoll etwa zehn Jahre nach Inbetriebnahme erfolgen. Die weiteren Ueberpruefungen sollen danach jeweils im Abstand von etwa zehn Jahren stattfinden. Die zwischenzeitlichen Erfahrungen aus Betrieb und Aufsicht sind einzubeziehen. Ziel der PSUemuss sein, festzustellen, ob die Anlage auch im Hinblick auf den kuenftigen Betrieb ein ausreichendes Sicherheitsniveau besitzt. Zu diesem Zweck muessen repraesentative Ereignisse dann detailliert untersucht werden, wenn neue Erkenntnisse aus Forschung und Entwicklung sowie aus der Betriebserfahrung seit der letzten Periodischen Sicherheitsueberpruefung dies erfordern. (orig./HP)

9 CFR 318.309 - Finished product inspection.

Science.gov (United States)

2010-01-01

... Section 318.309 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION AND VOLUNTARY... Canning and Canned Products § 318.309 Finished product inspection. (a) Finished product inspections must...

Review of design criteria and safety analysis of safety class electric building for fuel test loop

Energy Technology Data Exchange (ETDEWEB)

Kim, J. Y.

1998-02-01

Steady state fuel test loop will be equipped in HANARO to obtain the development and betterment of advanced fuel and materials through the irradiation tests. HANARO fuel test loop was designed for CANDU and PWR fuel testing. Safety related system of Fuel Test Loop such as emergency cooling water system, component cooling water system, safety ventilation system, high energy line break mitigation system and remote control room was required 1E class electric supply to meet the safety operation in accordance with related code. Therefore, FTL electric building was designed to construction and install the related equipment based on seismic category I. The objective of this study is to review the design criteria and analysis the safety function of safety class electric building for fuel test loop, and this results will become guidance for the irradiation testing in future. (author). 10 refs., 6 tabs., 30 figs.

High-pressure safety at the Lawrence Livermore Laboratory, an energy research facility

International Nuclear Information System (INIS)

Burton, W.A.

1976-01-01

The high-pressure safety program at Lawrence Livermore Laboratory, Livermore, California, has been successful in preventing lost-time high-pressure accidents over the past 12 years. Program organization, personnel training and qualification, pressure vessel design criteria and documentation, and pressure testing and inspection are discussed

Documentation for fiscal year 1995 annual BUSS cask SARP testing and inspections

International Nuclear Information System (INIS)

Saueressig, P.T.

1994-01-01

The purpose of this report is to compile the data generated during the Fiscal Year (FY) 1995 annual tests and inspections performed on the Beneficial Uses Shipping System (BUSS) cask. The BUSS Cask Model R-1 is a type B shipping container used for shipment of radioactive cesium-137 and strontium-90 capsules to Waste Encapsulation and Storage Facility (WESF). The primary purpose of the BUSS Cask is to provide shielding and confinement as well as impact, puncture, and thermal protection for the capsules under both normal and accident conditions. Section 8.2 ''Maintenance and Periodic Inspection Program'' of the BUSS Cask SARP requires that the following tests and inspections be performed on an annual basis: hydrostatic pressure test; helium leak test; dye penetrant test on the trunnions and life lugs; torque test on all permanent bolts; and impact limiter inspection and weight test. In addition to compiling the generated data, this report will verify that the testing criteria identified in section 8.2 of the BUSS Cask Safety Analysis Report for Packaging (SARP) was met

Documentation for fiscal year 1995 annual BUSS cask SARP testing and inspections

Energy Technology Data Exchange (ETDEWEB)

Saueressig, P.T.

1994-11-08

The purpose of this report is to compile the data generated during the Fiscal Year (FY) 1995 annual tests and inspections performed on the Beneficial Uses Shipping System (BUSS) cask. The BUSS Cask Model R-1 is a type B shipping container used for shipment of radioactive cesium-137 and strontium-90 capsules to Waste Encapsulation and Storage Facility (WESF). The primary purpose of the BUSS Cask is to provide shielding and confinement as well as impact, puncture, and thermal protection for the capsules under both normal and accident conditions. Section 8.2 ``Maintenance and Periodic Inspection Program`` of the BUSS Cask SARP requires that the following tests and inspections be performed on an annual basis: hydrostatic pressure test; helium leak test; dye penetrant test on the trunnions and life lugs; torque test on all permanent bolts; and impact limiter inspection and weight test. In addition to compiling the generated data, this report will verify that the testing criteria identified in section 8.2 of the BUSS Cask Safety Analysis Report for Packaging (SARP) was met.

9 CFR 355.7 - Inauguration of inspection.

Science.gov (United States)

2010-01-01

... INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA; INSPECTION... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Inauguration of inspection. 355.7 Section 355.7 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE...

Limitations of the inspection and testing concepts for pressurised components from the viewpoint of operating experience

International Nuclear Information System (INIS)

Schulz, H.

2001-01-01

The role of in-service inspection and testing is to contribute to a safe and reliable operation of systems, structures and components. It is therefore the objective of inspections and tests to identify malfunctions and degradations at a stage early enough to avoid detrimental impacts on safety as well as on the reliability of the plant. Taking mostly the pressure boundary of German light-water reactors as an example, it is the intention of this paper to analyse how successful present inspection and testing requirements are and to discuss limitations. Based on a review of the world-wide operating experience the following questions of a more generic nature are addressed: - Are the relevant damage mechanisms being addressed in our codes and standards? - What are the criteria to develop a representative scope of inspection? - How to maintain a sufficient level of information for a decreasing number of nuclear power plants in operation? It can be concluded that the revision of codes and standards according to lessons learned from operating experience remains as an ongoing process. Furthermore, the criteria applied to derive a representative scope of inspection need to be addressed in more detail, specifically with respect to corrosion. The continuous evaluation of operating experience of a large number of plants is the most valuable source to identify beginning degradations. (author)

Overview criteria for the environmental, safety and health evaluation of remedial action project planning

International Nuclear Information System (INIS)

Stenner, R.D.; Denham, D.H.

1984-10-01

Overview criteria (i.e., subject areas requiring review) for evaluating remedial action project plans with respect to environmental, safety and health issues were developed as part of a Department of Energy, Office of Operational Safety, technical support project. Nineteen elements were identified as criteria that should be addressed during the planning process of a remedial action (decontamination and decommissioning) project. The scope was interpreted broadly enough to include such environmental, safety and health issues as public image, legal obligation and quality assurance, as well as more obvious concerns such as those involving the direct protection of public and worker health. The nineteen elements are discussed along with suggested ways to use a data management software system to organize and report results

49 CFR 396.13 - Driver inspection.

Science.gov (United States)

2010-10-01

... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL MOTOR CARRIER SAFETY REGULATIONS INSPECTION, REPAIR, AND MAINTENANCE § 396.13 Driver inspection. Before driving a motor vehicle, the driver shall: (a) Be satisfied that the motor vehicle is in safe operating condition; (b) Review the last driver vehicle inspection...

OSE inspection of protection program operations field perspective of inspections

International Nuclear Information System (INIS)

Brown, R.W.; Martin, H.R.

1987-01-01

Protection Program Operations includes three functional areas: Physical Protection Systems, Protective Forces, and System Performance Testing. The Office of Security Evaluations (OSE) inspects field offices in these areas by evaluating programs relative to Standards and Criteria and by performing a variety of exercises and other types of tests to assure protective systems are effective and maintained at a proper level to meet the defined threat. Their perception of the OSE inspections has been positive. The approach taken by ID, with key areas/activities emphasized, during each phase of the field inspection process is described in this report. The most important areas for field offices to concentrate are: inspection preparations through self-evaluation, improving communications, assigning knowledgeable trusted agents, increasing awareness of facility procedures and operations, and assuring daily validations of inspected areas. Emphasis is placed on striving for a balance in reporting both positive and negative findings, and for consistency between ratings and the importance of report findings. OSE efforts to develop improved rating methodologies are encouraged

Food safety assurance systems: Microbiological testing, sampling plans, and microbiological criteria

NARCIS (Netherlands)

Zwietering, M.H.; Ross, T.; Gorris, L.G.M.

2014-01-01

Microbiological criteria give information about the quality or safety of foods. A key component of a microbiological criterion is the sampling plan. Considering: (1) the generally low level of pathogens that are deemed tolerable in foods, (2) large batch sizes, and (3) potentially substantial

Modeling of a remote inspection system for NSSS components

International Nuclear Information System (INIS)

Choi, Yoo Rark; Kim, Jae Hee; Lee, Jae Cheol

2003-03-01

Safety inspection for safety-critical unit of nuclear power plant has been processed using off-line technology. Thus we can not access safety inspection system and inspection data via network such as internet. We are making an on-line control and data access system based on WWW and JAVA technologies which can be used during plant operation to overcome these problems. Users can access inspection systems and inspection data only using web-browser. This report discusses about analysis of the existing remote system and essential techniques such as Web, JAVA, client/server model, and multi-tier model. This report also discusses about a system modeling that we have been developed using these techniques and provides solutions for developing an on-line control and data access system

Working group 8: inspection tools

Energy Technology Data Exchange (ETDEWEB)

Billey, Deb; Kania, Richard; Nickle, Randy; Wang, Rick; Westwood, Stephen

2011-07-01

This eighth working group of the Banff 2011 conference discussed the inspection tools and techniques used by the upstream and downstream pipeline industry to evaluate pipeline integrity. Special attention was given to the challenges and successes related to in-line inspection (ILI) technology. The background of current dent assessment criteria in B31.8 was presented, including dent definition for ILI vendors and pipeline operators as well as codes (CSA Z662 and B31.8). The workshop described examples of dents and assessments showing inconsistency with current criteria as set out by TCPL and Marathon. This workshop produced a single, industry-wide definition of the dent. It was found that the strain based criteria were more practical because depth based is conservative and may miss shallow occurrences. The creation of joint industry group was proposed to develop strain based criteria for incorporation into CSAZ662 and B31.8.

Safety detaching hook specification.

CSIR Research Space (South Africa)

Roux, JD

1999-05-01

Full Text Available hydraulic tensioning system The impactor must subject the safety detaching hook to an impact energy of 150 kJ minimum. A high speed digital imaging system, capable of recording at least 2000 full frames per second, shall be used to record video images... document compiled by the Contractor, detailing all major events in the production phase, including but not necessarily limited to inspection requirements, test procedures and acceptance/rejection criteria, sampling plans and equipment to be employed...

Safety-related subject fields, institutions, associations, inspection boards and authorities

International Nuclear Information System (INIS)

Cebulla, E.

1986-01-01

The chapter outlines the various branches of industry where safety plays an important role, adapting the scheme applied by the Federal German Labour Office. The various sections of this chapter deal with legal provisions and relevant institutions, with natural and man-made hazards, with industrial systems requiring inspection and surveillance, with agriculture and forestry including animal husbandry, with manufacturing branches, the building industry, traffic and transport, with the services sector, househoulds, leisure and sports, and with establishments and activities where the handling of radioactive substances is a major source of hazards (e.g. in the medical field, for which a particularly extensive literature index is given). Aspects of power supply industries and water pollution prevention are discussed where appropriate. (DG) [de

Advanced Approach of Reactor Pressure Vessel In-service Inspection

International Nuclear Information System (INIS)

Matokovic, A.; Picek, E.; Pajnic, M.

2006-01-01

The most important task of every utility operating a nuclear power plant is the continuously keeping of the desired safety and reliability level. This is achieved by the performance of numerous inspections of the components, equipment and system of the nuclear power plant in operation and in particular during the scheduled maintenance periods at re-fueling time. Periodic non-destructive in-service inspections provide most relevant criteria of the integrity of primary circuit pressure components. The task is to reliably detect defects and realistically size and characterize them. One of most important and the most extensive examination is a reactor pressure vessel in-service inspection. That inspection demand high standards of technology and quality and continual innovation in the field of non-destructive testing (NDT) advanced technology as well as regarding reactor pressure vessel tool and control systems. A remote underwater contact ultrasonic technique is employed for the examination of the defined sections (reactor welds), whence eddy current method is applied for clad surface examinations. Visual inspection is used for examination of the vessel inner surface. The movement of probes and data positioning are assured by using new reactor pressure vessel tool concept that is fully integrated with NDT systems. The successful performance is attributed thorough pre-outage planning, training and successful performance demonstration qualification of chosen NDT techniques on the specimens with artificial and/or real defects. Furthermore, use of advanced approach of inspection through implementation the state of the art examination equipment significantly reduced the inspection time, radiation exposure to examination personnel, shortening nuclear power plant outage and cutting the total inspection costs. The advanced approach as presented in this paper offer more flexibility of application (non-destructive tests, local grinding action as well as taking of boat samples

Findings of the inspection grading system on industrial radiography

International Nuclear Information System (INIS)

Gloria Doloressa

2011-01-01

The use of industrial radiography techniques evolve rapidly and widely. Various jobs in industry require the examination of welding techniques / connecting pipes and metal construction. The use of industrial radiography is one type of utilization of nuclear energy must get control so that its use does not cause harmful impacts to worker safety, community, and environment. Regulations is done through inspections, in order to supervise the observance of the terms in the licensing and legislation in the field of nuclear safety. The main purpose of inspection is to ensure the utilization of radiation sources of radiation have been used with. Findings of the inspection is a decline in the performance of licensees in meeting safety requirements. The Grading System to the findings of the inspection needs to be done to improve the effectiveness and efficiency of inspection, and it is expected that the company can improve the management of radiation safety. (author)

Opinions of the well-informed persons about the nuclear reactor facility periodical inspection

International Nuclear Information System (INIS)

Aeba, Yoichi; Ishikawa, Michio; Enomoto, Toshiaki; Oomori, Katsuyoshi

2005-01-01

Falsifications of self-inspection records in the shrouds and of leakage rates for containment vessels at TEPCO nuclear power plants destroyed public trust in nuclear safety. The Nuclear Reactor Regulation Law and Electric Utility Law were amended to enhance the nuclear safety regulation system. The major improvements are that operators are legally required to conduct inspection (periodical operator inspection) and recording and keeping inspection results. The operator performs 'periodical operator inspection' regularly, and Nuclear and Industrial Safety Agency (NISA) performs periodical inspection' about particularly important facilities/function in safety. Sixteen opinions of well-informed persons about the nuclear reactor facility periodical inspection were presented in this special number. Interval of periodical inspection less than thirteen months was disputed. Maintenance activities should be more rationalized based on risk information. (T. Tanaka)

29 CFR 1960.31 - Inspections by OSHA.

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false Inspections by OSHA. 1960.31 Section 1960.31 Labor... MATTERS Inspection and Abatement § 1960.31 Inspections by OSHA. (a) The Secretary or the Secretary's... scheduled inspections as an integral part of OSHA's evaluation of an agency's safety and health program in...

Verification of implementation of the radiological safety standards through the regulatory inspections

International Nuclear Information System (INIS)

Perez Gonzalez, Francisco; Fornet Rodriguez, Ofelia M.

2008-01-01

Full text: As an element of the updating process of the legal framework on radiological safety in Cuba, a new rule was put into force; the Radiological Basic Safety Standards (RBSS) in January 2002. Five years after the application of these new safety requirements, it was considered appropriate to assess the effectiveness of its implementation. Therefore, in this work the authors analysed the outcomes of the regulatory inspections conducted in this period upon medical and industrial practices in a sample of facilities representative of those with the highest radiological risks in the territory under supervision of a Territorial Delegation of the Nuclear Regulatory Authority. For better understanding of this presentation, a summary explanation of the structure of the rule is given in its introduction. The work was to identify for each deficiency, or finding, or counter-measure; out of the relevant inspections; the corresponding requirement/Article of the RBSS that shows difficulties in implementation. For each installation an analysis is made with regard to the relevant articles difficult to implement. Finally, the appraisal is shown separately for the medical practice, and for the industrial practice, and also in general for the whole sample of installations under review. The study showed that the implementation of the Standards has been satisfactory and uniform in the practices under review. So far it seems that there have not been major difficulties with the implementation of the Titles; III On Intervention, IV Dose Limits, as well as with the Especial, Final, and Transitory Dispositions. On the other hand, it is shown there is a need for continued work only with regard to the implementation of the requirements in Section IV Verification of Safety and in Section V On the responsibilities with regard to occupational exposure in Chapter III Title I, and correspondingly in Chapter II Occupational Exposure in Title II. It is recommended to conduct this kind of

Automated ultrasonic inspection of nuclear plant components

International Nuclear Information System (INIS)

Baron, J.A.; Dolbey, M.P.

1982-01-01

For reasons of safety and efficiency, automated systems are used in performing ultrasonic inspection of nuclear components. An automated system designed specifically for the inspection of headers in a nuclear plant is described. In-service inspection results obtained with this system are shown to correlate with pre-service inspection results obtained by manual methods

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...

Selection of tolerable risk criteria for dam safety decision making

International Nuclear Information System (INIS)

Nielsen, N.M.; Hartford, D.N.D.; MacDonald, T.F.

1994-01-01

Risk assessment has received increasing attention in recent years as a means of aiding decision making on dams by providing systematic and rational methods for dealing with risk and uncertainty. Risk assessment is controversial and decisions affecting risk to life are the most controversial. Tolerable criteria, based on the risks that society is prepared to accept in order to avoid excessive costs, set bounds within which risk-based decisions may be made. The components of risk associated with dam safety are addressed on an individual basis and criteria established for each component, thereby permitting flexibility in the balance between component risk and avoiding the problems of placing a monetary value on life. The guiding principle of individual risk is that dams do not impose intolerable risks on any individual. A risk to life of 1 in 10 4 per annum is generally considered the maximum tolerable risk. When considering societal risk, the safety of a dam should be proportional to the consequences of its failure. Risks of financial losses beyond the corporation's ability to finance should be so low as to be considered negligible. 17 refs., 3 figs

9 CFR 355.21 - Products entering inspected plants.

Science.gov (United States)

2010-01-01

... INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA; INSPECTION... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Products entering inspected plants. 355.21 Section 355.21 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF...

33 CFR 3.40-15 - Sector New Orleans Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit Morgan...

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Sector New Orleans Marine....40-15 Sector New Orleans Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit Morgan City. Sector New Orleans' office is located in New Orleans, LA. A subordinate unit, Marine Safety...

30 CFR 56.4201 - Inspection.

Science.gov (United States)

2010-07-01

... Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-SURFACE METAL AND NONMETAL MINES Fire Prevention and Control... following schedules: (1) Fire extinguishers shall be inspected visually at least once a month to determine...

30 CFR 57.4201 - Inspection.

Science.gov (United States)

2010-07-01

... Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Fire Prevention and Control... following schedules: (1) Fire extinguishers shall be inspected visually at least once a month to determine...

Machine vision inspection of railroad track

Science.gov (United States)

2011-01-10

North American Railways and the United States Department of Transportation : (US DOT) Federal Railroad Administration (FRA) require periodic inspection of railway : infrastructure to ensure the safety of railway operation. This inspection is a critic...

Safety design criteria for the next generation Sodium-cooled fast reactors based on lessons learned from the Fukushima NPS accident

International Nuclear Information System (INIS)

Sakai, Takaaki

2012-01-01

In this presentation, architecture of the safety design criteria as requirements for SFR system and the activities on safety research works to establish safety evaluation methods for the next generation SFRs are summarized with the basis on lessons learned from the Fukushima NPS accident. Nuclear safety is a grovel issue which should be achieved by the international cooperation. In respect of the development for the next generation reactor, it is necessary to build the harmonized safety criteria and evaluation methods to establish the next level of safety

9 CFR 355.3 - Plants eligible for inspection.

Science.gov (United States)

2010-01-01

... INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA; INSPECTION... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Plants eligible for inspection. 355.3 Section 355.3 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE...

Computed Radiography: An Innovative Inspection Technique

International Nuclear Information System (INIS)

Klein, William A.; Councill, Donald L.

2002-01-01

Florida Power and Light Company's (FPL) Nuclear Division combined two diverse technologies to create an innovative inspection technique, Computed Radiography, that improves personnel safety and unit reliability while reducing inspection costs. This technique was pioneered in the medical field and applied in the Nuclear Division initially to detect piping degradation due to flow-accelerated corrosion. Component degradation can be detected by this additional technique. This approach permits FPL to reduce inspection costs, perform on line examinations (no generation curtailment), and to maintain or improve both personnel safety and unit reliability. Computed Radiography is a very versatile tool capable of other uses: - improving the external corrosion program by permitting inspections underneath insulation, and - diagnosing system and component problems such as valve positions, without the need to shutdown or disassemble the component. (authors)

Control of the Saclay CEA's base nuclear installations - Inspection n. INS-2010-CEASAC-0006 31 May 2010-4 June 2010 - Safety management

International Nuclear Information System (INIS)

2010-01-01

This document reports an inspection dedicated to safety management, and performed by the ASN (the French Nuclear Safety Authority) on several nuclear installations present on the CEA's Saclay site. The inspected installations have been the INBs (base nuclear installations) number 35 (STEL), 40 (Osiris), 49 (LHA), 50 (LECI), 77 (Poseidon) and 101 (Orphee), and four departments (CCSIMN, USL2TI, SP2S and DANS) involved in safety or in charge of it. The report describes the requested corrective actions about the quality of the internal diagnosis, about the follow-up of actions and directives, about internal authorizations, about the follow-up of commitments, about second level control, about the management of the return on experience, about interesting events, about the control of subcontractors. Some additional information requests are also formulated

Criteria adopted by the Argentine Nuclear Regulatory Authority for assessing digital systems related to safety

International Nuclear Information System (INIS)

Terrado, Carlos A.; Chiossi, Carlos E.; Felizia, Eduardo R.; Roca, Jose L.; Sajaroff, Pedro M.

2004-01-01

Following the technological evolution in Instrumentation and Control (I and C) design, analog components are replaced by digital in almost every industry. Due to growing challenges of obsolescence and increasing maintenance costs, licensees of nuclear and radioactive installations are increasingly upgrading or replacing their existing I and C analog systems and components. In existing installations, this involves analog to digital replacements. In new installations design, the use of digital I and C systems is being considered from the very beginning, becoming a good alternative, even in safety applications. Up to now, in Argentina, there is no specific rules for safety-related digital systems, every safety system, analog or digital, must comply with the same generic regulations. The Nuclear Regulatory Authority is now developing criteria to assess digital systems related to safety in nuclear and radioactive installations. In this paper some of those criteria, based on local research and the recognized state of the art, are explained. From a regulatory point of view, the use of digital technology often raises new technical and licensing issues, particularly for safety-related applications. Examples include new failure modes, the potential for common-cause failure of redundant components, electromagnetic interference (EMI), software verification and validation, configuration management and a more exhaustive quality assurance system. The mentioned criteria comprehend the design, operation, maintenance and acquisition of digital systems and components important to safety. The main topics covered are: requirements specifications for digital systems, planning and documentation for digital system development, effectiveness of a digital system, commercial off the shelf (COTS) treatment and considerations involving tools for software development. (author)

Pre-service inspection and in-service inspection in Japan

International Nuclear Information System (INIS)

Uebayashi, T.; Miyake, Y.

1985-01-01

To ensure the safety of nuclear power plant, pre-service inspection/in-service inspection (PSI/ISI) has an important role, and informations obtained from various inspections during plant shut-down period are contributing to establish effective preventive maintenance activities for plant facilities. It might be said that the high level of availability of Japanese light-water nuclear power plants in these two or three years has been achieved by those efforts. In case of Japan, inspections to be carried out during scheduled plant shut-down period are not limited to code requirements but include many other inspections which are mostly reflected from troubles experienced in both domestic and overseas plants. Usually, those additional inspections are performed by Ministry of Trade and Industries' (MITI's) regulator and/or tentative requirement and considered as ISI in broad meaning. To achieve high availability of plant, it is essential to avoid unscheduled shut-down and to shorten inspection period. The developments of new technology to perform effective ISI for operating plants are continued, but on the other hand it is also very important to pay a great consideration to inspectability of the plants at the stage of plant engineering. With the leadership of MITI, improvement and standardization of light-water nuclear power plant has been proceeded and newly constructed plants have great advantage from the point of view on ISI

The computer vision in the service of safety and reliability in steam generators inspection services

International Nuclear Information System (INIS)

Pineiro Fernandez, P.; Garcia Bueno, A.; Cabrera Jordan, E.

2012-01-01

The actual computational vision has matured very quickly in the last ten years by facilitating new developments in various areas of nuclear application allowing to automate and simplify processes and tasks, instead or in collaboration with the people and equipment efficiently. The current computer vision (more appropriate than the artificial vision concept) provides great possibilities of also improving in terms of the reliability and safety of NPPS inspection systems.

Thermographic inspection of pipes, tanks, and containment liners

Energy Technology Data Exchange (ETDEWEB)

Renshaw, Jeremy B., E-mail: jrenshaw@epri.com; Muthu, Nathan [Electric Power Research Institute, 1300 West WT Harris Blvd., Charlotte, NC 28262 (United States); Lhota, James R.; Shepard, Steven M., E-mail: sshepard@thermalwave.com [Thermal Wave Imaging, 845 Livernois St., Ferndale, MI 48220 (United States)

2015-03-31

Nuclear power plants are required to operate at a high level of safety. Recent industry and license renewal commitments aim to further increase safety by requiring the inspection of components that have not traditionally undergone detailed inspected in the past, such as tanks and liners. NEI 09-14 requires the inspection of buried pipes and tanks while containment liner inspections are required as a part of license renewal commitments. Containment liner inspections must inspect the carbon steel liner for defects - such as corrosion - that could threaten the pressure boundary and ideally, should be able to inspect the surrounding concrete for foreign material that could be in contact with the steel liner and potentially initiate corrosion. Such an inspection requires a simultaneous evaluation of two materials with very different material properties. Rapid, yet detailed, inspection results are required due to the massive size of the tanks and containment liners to be inspected. For this reason, thermal NDE methods were evaluated to inspect tank and containment liner mockups with simulated defects. Thermographic Signal Reconstruction (TSR) was utilized to enhance the images and provide detailed information on the sizes and shapes of the observed defects. The results show that thermographic inspection is highly sensitive to the defects of interest and is capable of rapidly inspecting large areas.

Comparison of Survival and Safety Requirements in European Union for Recreational Craft Inspections. A Spanish Case Study

Directory of Open Access Journals (Sweden)

J. Torralbo

2014-03-01

Full Text Available Statistical data shows that a large number of maritime accidents are related to recreational craft. For instance, in Spain, more than fifty percent of the emergencies are related to pleasure boats at sea. Recreational craft marketed in the EU must comply with harmonized technical safety and environmental requirements defined by Directive 94/25/EC, as amended in 2003. On 28 December 2013, the new recreational craft directive 2013/53/EU was published in the Official Journal of the European Union. EU Member States have until 18 January 2016 to amend their national legislation and transpose the new directive. The current directive 94/25/EC as amended by directive 2003/44/EC will be repealed on 18 January 2016, after the full application of the new text. Although this directive, there is not a clear coordination and equivalence among the EU countries according to the survival and safety equipment compulsory for recreational crafts. The main purpose of this paper is to analyze and compare the types of survey / inspections to be carried in pleasure craft (non-commercial use, periodicity and required safety equipment in some member states of the European Union. A case study of Spain is presented. From the results obtained, we can make clear that in the European Union there is a lack of coordination in this area and indicate the need to unify a common pattern in inspections and survival and safety requirements of recreational boats in the EU.

78 FR 28275 - Office of Commercial Space Transportation; Safety Approval Performance Criteria

Science.gov (United States)

2013-05-14

... provide as a service, scenario based physiology training, which includes hypobaric chamber training. BST may offer its scenario based physiology altitude training as a service to a prospective launch and...: Notification of criteria used to evaluate the Black Sky Training, Inc. (BST) safety approval application...

A randomised controlled study to evaluate the effectiveness of targeted occupational health and safety consultation or inspection in Ontario manufacturing workplaces.

Science.gov (United States)

Hogg-Johnson, Sheilah; Robson, Lynda; Cole, Donald C; Amick, Benjamin C; Tompa, Emile; Smith, Peter M; van Eerd, Dwayne; Mustard, Cameron

2012-12-01

From 2004 to 2008, the prevention system in Ontario, Canada ran the High Risk Firm Initiative, an injury-experience based targeted consultation or inspection programme. Our objective was to establish whether prevention system targeting of firms was effective in improving injury outcomes. Randomised controlled parallel groups. Population included all manufacturing firms registered with the Ontario Workplace Safety & Insurance Board in 2005. Firms ranked between the 2nd and 10th percentile on a composite measure of occupational health and safety performance were randomised to three study arms in 2006: targeted for Health & Safety Association (HSA) consultation, targeted for Ministry of Labour (MOL) inspection, or services as usual. Data included firm characteristics (sector, size, years in business, region, branches), work injury claims 2002-2008 and measures of consulting and inspecting activity. Negative binomial generalised estimating equations modelled claim and disability day rates by study arm and year, controlling for firm characteristics. Among 2153 firms, firm characteristics and 2002-2005 rates of work injury claims and disability days were similar across arms. Firm outcomes were significantly different from year to year, but study arm by year interactions were insignificant indicating similar trends for all three study arms. 83% of HSA targeted firms were contacted and 63% engaged while 75% of MOL targeted firms were inspected with orders written in 56%. Consultation and enforcement programmes as implemented were not sufficient to reduce work injury outcomes over 21 month follow-up. Lack of benefit could be due to non-specific firm selection methods, limited firm participation in interventions, low intervention intensity or insensitivity of available outcomes.

The role of independent inspection in verification activities

International Nuclear Information System (INIS)

Fuerste, W.

1982-01-01

Independent inspection has its origin in the early Middle Ages, when kings prescribed to textile manufacturers a quality control by authorized inspectors. Independent inspection became more important with respect to the safety of workers in the industrial era beginning in the 18th century, when the high-pressure steam engines were introduced and many accidents and explosions of steam boilers occurred. Nowadays, independent inspection is of utmost importance, because the safety of the public is endangered by industrial plants located near highly populated areas. To better understand the role of independent inspection, the paper reviews its historical development in Europe from the Middle Ages to the 20th century. Most of the independent inspection associations in European countries were established after the second half of the 19th century and began with the surveillance of steam boilers. Nowadays, organizations like the TUEVs (Technical Inspection Agencies) in the Federal Republic of Germany perform expertise and inspection on behalf of the government in various fields of industrial safety. To show how independent inspection is involved in quality assurance, the methods practised in the United States of America and the Federal Republic of Germany are compared and future trends discussed. For developing countries starting with nuclear energy, it is important to consider the information and recommendations regarding independent inspection and its regulation as laid down in a number of publications in the IAEA NUSS Programme. (author)

OHS Certification as Tool and Strategy in Labour Inspection

DEFF Research Database (Denmark)

Hendriksen, Kåre

Certification of Occupational Health and Safety as Tool and Strategy in Labour Inspection Presentation of the project Certification of Occupational Health and Safety as Tool and Strategy in Labour Inspection financed by Nordic Council of Ministers. The project has analysed the new role...... 18001. Especially in Denmark this is the case, where certified companies a. o. are exempt from primary inspection, a development that can be seen as a slight successive privatization of regulation and inspection. The focused has been the validity of certification regarding to OHS performance...

Evaluation on safety issues of SMART

International Nuclear Information System (INIS)

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

2001-01-01

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

NEA perspectives on timescales and criteria in post-closure safety of geological disposal

International Nuclear Information System (INIS)

Preter, P. de; Smith, P.; Pescatore, C.; Forinash, B.

2006-01-01

A key challenge in the development of safety cases for geological repositories is associated with the long periods of time over which radioactive wastes that are disposed of in repositories remain hazardous. The OECD Nuclear Energy Agency (NEA) has recently examined issues related to timescales in the context of two projects under the auspices of the Radioactive Waste Management Committee (RWMC): the Timescales Initiative and the Long-Term Safety Criteria (LTSC) Initiative. These projects examine, respectively, the treatment of timescales in actual safety cases and in the development of radiological protection criteria for geological disposal. They treat different aspects of timescales but have some overlap and have shown some convergence of the results achieved to date. Based on these projects, this paper examines general considerations in the handling of timescales, including ethical principles, evolution of the hazards of radioactive waste over time, and uncertainty in the evolution of repository systems (including geological features). The implications of these considerations are examined in terms of repository siting; levels of protection in regulations; planning for pre-closure and post-closure actions; and development and presentation of safety cases. A comparison is made with previous NEA work related to timescales, in order to show evolutions in current understanding. (authors)

NEA perspectives on timescales and criteria in post-closure safety of geological disposal

Energy Technology Data Exchange (ETDEWEB)

Preter, P. de [ONDRAF/NIRAS, Brussels (Belgium); Smith, P. [Safety Assessment Management Ltd, SAM Ltd. (United Kingdom); Pescatore, C.; Forinash, B. [OECD/NEA, Nuclear Energy Agency, 92 - Issy les Moulineaux (France)

2006-07-01

A key challenge in the development of safety cases for geological repositories is associated with the long periods of time over which radioactive wastes that are disposed of in repositories remain hazardous. The OECD Nuclear Energy Agency (NEA) has recently examined issues related to timescales in the context of two projects under the auspices of the Radioactive Waste Management Committee (RWMC): the Timescales Initiative and the Long-Term Safety Criteria (LTSC) Initiative. These projects examine, respectively, the treatment of timescales in actual safety cases and in the development of radiological protection criteria for geological disposal. They treat different aspects of timescales but have some overlap and have shown some convergence of the results achieved to date. Based on these projects, this paper examines general considerations in the handling of timescales, including ethical principles, evolution of the hazards of radioactive waste over time, and uncertainty in the evolution of repository systems (including geological features). The implications of these considerations are examined in terms of repository siting; levels of protection in regulations; planning for pre-closure and post-closure actions; and development and presentation of safety cases. A comparison is made with previous NEA work related to timescales, in order to show evolutions in current understanding. (authors)

77 FR 58607 - Office of Commercial Space Transportation Safety Approval Performance Criteria

Science.gov (United States)

2012-09-21

...: Notification of criteria used to evaluate the National Aerospace Training and Research (NASTAR) Center safety... approval for the ability of its Falcon 12/4 Altitude Chamber to replicate pressures experienced at altitude...). NASTAR's Falcon 12/4 Altitude Chamber is capable of replicating any pressure experienced at altitudes...

Hanford site post-NPH building inspection plan

International Nuclear Information System (INIS)

Wagenblast, G.R. Westinghouse Hanford

1996-01-01

This plan establishes consistent post-NPH building inspection procedures and defines a procedure for prioritization of buildings for inspection to ensure the safety of facilities prior to reentry. Qualification of systems for restart of operation is not included. This plan takes advantage, where possible, of existing national procedures for post-NPH inspection of buildings, of existing structural design and evaluation documentation of Hanford facilities, and current and proposed seismic instrumentation located throughout the Hanford site. A list of buildings, prioritized according to current building safety function and building vulnerability (without regard for or information about a damaging natural forces event) is provided

47 CFR 80.59 - Compulsory ship inspections.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 5 2010-10-01 2010-10-01 false Compulsory ship inspections. 80.59 Section 80... STATIONS IN THE MARITIME SERVICES Applications and Licenses § 80.59 Compulsory ship inspections. (a) Inspection of ships subject to the Communications Act or the Safety Convention. (1) The FCC will not normally...

National Dam Safety Program. Lakeview Estates Dam (MO 11004), Mississippi - Kaskaskia - St. Louis Basin, Warren County, Missouri. Phase I Inspection Report.

Science.gov (United States)

1979-09-01

ificatiozh Distributon/ Availabilit oe LAKEVIEW ESTATES DAM WARREN COUNTY, MISSOURI MISSOURI INVENTORY NO. 11004 PHASE I INSPECTION REPORT NATIONAL DAM SAFETY...and *impounds less than 1,000 acre-feet of water . Our inspection and evaluation indicates that the spill- way of Lakeview Estates Dam does not meet...not be measured because of high reservoir level, scalloping near the crest and a berm just under the water surface. Limestone riprap in sizes from sand

Radiation control in the nondestructive inspection

International Nuclear Information System (INIS)

Kariya, Yukihiro

1982-01-01

In the early days of radiation nondestructive inspection about ten years ago, the loss of radiation sources and careless radiation exposure gave the impression of radiography inspection being immediately slipshod management. In this problem, the peculiar nature of the business in this field is involved. In Nondestructive Inspection Co., Ltd., besides the safety management of radioisotopes, the radiation exposure control of personnel in the regular inspection of nuclear power plants has become increasingly important. The following matters are described: radiation utilization in nondestructive inspection (X- and #betta#-ray radiography, #betta#-ray leak test on shield), radiation control problems in nondestructive inspection business (the peculiar aspects of the business, the analysis of the incidents related with nondestructive inspection), and the practice of radiation control in nondestructive inspection in Nondestructive Inspection Co., Ltd. (Mori, K.)

Comparison of codes and standards for radiographic inspection

International Nuclear Information System (INIS)

Bingoeldag, M. M.; Aksu, M.; Akguen, A. F.

1995-01-01

This report compares the procedurel requirements and acceptance criteria for radiographic inspections specified in the relevant national and international codes and standards. In particular, detailed analysis of inspection conditions such as exposure arrangements, and contrast requirements are given

Safety analysis of ventilation and inspection operations on barrels in which spent fuel elements are stored

International Nuclear Information System (INIS)

Pavlovic, R.; Todorovic, D.; Plecas, I.

2000-01-01

Safety analysis of possible accident during performing ventilation and inspection operations on barrels in which spent fuel elements are stored has been proposed. Investigation is confined to a case when primary contamination is localized to the disposal room and controlled release of gaseous effluents to the atmosphere. 85 Kr is the most important radionuclide considered risk estimation due to release of gaseous fission products (author) [sr

Estimation of inspection effort

International Nuclear Information System (INIS)

Mullen, M.F.; Wincek, M.A.

1979-06-01

An overview of IAEA inspection activities is presented, and the problem of evaluating the effectiveness of an inspection is discussed. Two models are described - an effort model and an effectiveness model. The effort model breaks the IAEA's inspection effort into components; the amount of effort required for each component is estimated; and the total effort is determined by summing the effort for each component. The effectiveness model quantifies the effectiveness of inspections in terms of probabilities of detection and quantities of material to be detected, if diverted over a specific period. The method is applied to a 200 metric ton per year low-enriched uranium fuel fabrication facility. A description of the model plant is presented, a safeguards approach is outlined, and sampling plans are calculated. The required inspection effort is estimated and the results are compared to IAEA estimates. Some other applications of the method are discussed briefly. Examples are presented which demonstrate how the method might be useful in formulating guidelines for inspection planning and in establishing technical criteria for safeguards implementation

Reactive inspection response of NRC Region III to potential technical deficiencies identified in recent Nuclear Air Cleaning Conference papers

International Nuclear Information System (INIS)

Gill, C.F.

1987-01-01

In order to effectively meet its responsibility to protect the public health and safety, the Nuclear Regulatory Commission (NRC) nuclear power plant licensing and inspection programs respond to potential technical deficiencies identified by conference and professional society meeting papers when deemed appropriate. The NRC staff's response mechanisms for such technical deficiencies include: generic letters, Bulletins, Information Notices, Standard Review Plan (NUREG-0800) revisions, docketed Final Safety Analysis Report (FSAR) questions, special studies, special (reactive) inspection, and inspection program revisions. This paper describes reactive inspection efforts by Region III in response to potential technical deficiencies identified in recent air cleaning conference papers, including: post-accident effluent sample line deposition losses; failure to implement good engineering practices in the design, construction, and testing of Nuclear Air Treatment Systems (NATS); filter bypass via filter housing drain lines; spinster carbon degradation; use of silicone sealants and other temporary patching material in NATS; filter housing fire protection deluge system problems; lack of charcoal batch traceability; Quality Assurance records problems involving equipment, vendor, filter, and personnel qualifications; inadequate ANSI/ASME N510 acceptance criteria and tests; and failure to adequately demonstrate control room habitability per 10 CFR 50, Appendix A, General Design Criterion-19. Region III inspections indicate that many of these deficiencies appear to be prevalent. Inspection findings and utility responses to the findings are discussed. NRC Region III and Headquarters programmatic reactions to the identified generic problem areas are also discussed

In-service inspection and periodic testing

International Nuclear Information System (INIS)

Eisele, H.; Meyer, F.A.; Zipser, R.R.

1981-01-01

In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. Below, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor/PWR/ or on a boiling-water reactor/BWR/) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

In-service inspection and periodic testing

International Nuclear Information System (INIS)

Eisele, H.; Meyer, F.A.; Zipser, R.R.

1980-01-01

In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. In the present paper, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor/PWR/ or on a boiling-water reactor/BWR/) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

International Nuclear Information System (INIS)

2001-12-01

The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities: Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular Development of the short and long-term safety analysis of the Baldone repository, including: the planned increasing of capacity for disposal and long term storage, the radiological analysis for the post-closure period Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components Proposal of recommendations for future updating of radioactive waste acceptance criteria Proposal of recommendations for safety upgrades to the facility. The work programme has been developed in phases and main tasks as follows. Phase 0: Project inception, Phase 1: Establishment of current status, plans and practices (Legislation, regulation and standards, Radioactive waste management, Waste acceptance criteria), Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements. The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterization requirements), the design of an engineered cap and strategies for capping. (author)

47 CFR 80.903 - Inspection of radiotelephone installation.

Science.gov (United States)

2010-10-01

... ship passes the inspection, the technician will issue a Communications Act Safety Radiotelephony... 47 Telecommunication 5 2010-10-01 2010-10-01 false Inspection of radiotelephone installation. 80... Passenger Boats § 80.903 Inspection of radiotelephone installation. Every vessel subject to Part III of...

Periodic vehicle inspection (MOT). [previously: Periodic Vehicle Inspection of cars (MOT).

OpenAIRE

2010-01-01

In the 1980s the periodic vehicle inspection (MOT) of various categories of vehicles was introduced in the Netherlands. This fact sheet will discuss the legal framework of this measure and the research carried out into its effects on road safety, also in an international context. For instance, the technical conditions of cars at inspection as well as that of cars involved in crashes were studied. Tyre pressure will also be discussed in this fact sheet.

The United States Nuclear Regulatory Commission's vendor inspection program

International Nuclear Information System (INIS)

Grier, B.H.

1977-01-01

The NRC conducts a program of inspection at licensee contractors and vendors to assure that quality assurance programs meet applicable NRC requirements. This inspection program, which was begun in 1965 and restructured in 1974, is discussed. A trial program has recently been initiated to evaluate the use of the ASME N-stam inspection system to supplement NRC inspections. The criteria for NRC acceptance of such a third party inspection system are described in the paper. (author)

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

Energy Technology Data Exchange (ETDEWEB)

William E. Kastenberg; Edward Blandford; Lance Kim

2009-03-31

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public.

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

International Nuclear Information System (INIS)

Kastenberg, William E.; Blandford, Edward; Kim, Lance

2009-01-01

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public

Transportation of Organs by Air: Safety, Quality, and Sustainability Criteria.

Science.gov (United States)

Mantecchini, L; Paganelli, F; Morabito, V; Ricci, A; Peritore, D; Trapani, S; Montemurro, A; Rizzo, A; Del Sordo, E; Gaeta, A; Rizzato, L; Nanni Costa, A

2016-03-01

The outcomes of organ transplantation activities are greatly affected by the ability to haul organs and medical teams quickly and safely. Organ allocation and usage criteria have greatly improved over time, whereas the same result has not been achieved so far from the transport point of view. Safety and the highest level of service and efficiency must be reached to grant transplant recipients the healthiest outcome. The Italian National Transplant Centre (CNT), in partnership with the regions and the University of Bologna, has promoted a thorough analysis of all stages of organ transportation logistics chains to produce homogeneous and shared guidelines throughout the national territory, capable of ensuring safety, reliability, and sustainability at the highest levels. The mapping of all 44 transplant centers and the pertaining airport network has been implemented. An analysis of technical requirements among organ shipping agents at both national and international level has been promoted. A national campaign of real-time monitoring of organ transport activities at all stages of the supply chain has been implemented. Parameters investigated have been hospital and region of both origin and destination, number and type of organs involved, transport type (with or without medical team), stations of arrival and departure, and shipping agents, as well as actual times of activities involved. National guidelines have been issued to select organ storage units and shipping agents on the basis of evaluation of efficiency, reliability, and equipment with reference to organ type and ischemia time. Guidelines provide EU-level standards on technical equipment of aircrafts, professional requirements of shipping agencies and cabin crew, and requirements on service provision, including pricing criteria. The introduction in the Italian legislation of guidelines issuing minimum requirements on topics such as the medical team, packaging, labeling, safety and integrity, identification

A longitudinal study to assess the role of sanitary inspections in improving the hygiene and food safety of eating establishments in a tertiary care hospital of North India

Directory of Open Access Journals (Sweden)

Puja Dudeja

2017-01-01

Full Text Available Introduction: Food safety inspections serve two purposes; determine compliance with the law and gather evidence for enforcement if there is noncompliance. The present study was conducted to assess the role of regular inspections on food safety in hospital premises. Methodology: This was an intervention based before and after study. A tool was prepared based on the Food Safety and Standards Regulations (FSSR (in India 2011. This included major, critical, and highly critical domains. Each item in the tool scored between 1 and 3 (poor, satisfactory, and good. Based on this, each eating establishment (EE was given a score on conformance to FSSR 2011. Monthly inspection was made over a year and corrective actions were suggested. Results: The minimum preintervention score was (41.28%, and maximum was (77.25%. There was no significant association between type of meal services and score EE (P > 0.05. Higher proportion of EEs within the hospital building had a satisfactory and good score as compared to EEs outside the hospital building but within hospital premises (P < 0.05. Postintervention, there was a significant change (increase in the scores of EEs. There was a significant increase in mean scores of EEs under major domains namely maintenance, layout of equipment, monitoring an detection, and elimination of food sources to the pests. Under critical and highly critical domains personal cleanliness, training, and self-inspection by food business operators improved significantly. Conclusion: Regular inspections can improve the food safety standards in EEs.

A consistent approach to assess safety criteria for reactivity initiated accidents

International Nuclear Information System (INIS)

Sartoris, C.; Taisne, A.; Petit, M.; Barre, F.; Marchand, O.

2010-01-01

In the context of more and more demanding reactor managements, the fuel assembly discharge burn-up increases and raises the question of the current safety criteria relevance. In order to assess new safety criteria for reactivity initiated accidents, the IRSN is developing a consistent and original approach to assess safety. This approach is based on: -A thorough understanding of the physical mechanisms involved in each phase (PCMI and post-boiling phases) of the RIA, supported by the interpretation of the experimental database. This experimental data is constituted of global test outcomes, such as CABRI or Nuclear Safety Research Reactor (NSRR) experiments, and analytical program outcomes, such as PATRICIA tests, intending to understand some particular physical phenomena; -The development of computing codes, modelling the physical phenomena. The physical phenomena observed during the tests mentioned above were modelled in the SCANAIR code. SCANAIR is a thermal-mechanical code calculating fuel and clad temperatures and strains during RIA. The CLARIS module is used as a post-calculation tool to evaluate the clad failure risk based on critical flaw depth. These computing codes were validated by global and analytical tests results; -The development of a methodology. The first step of this methodology is the identification of all the parameters affecting the hydride rim depth. Besides, an envelope curve resulting from burst tests giving the hydride rim depth versus oxidation thickness is defined. After that, the critical flaw depth for a given energy pulse is calculated then compared to the hydride rim depth. This methodology results in an energy or enthalpy limit versus burn-up. This approach is planned to be followed for each phase of the RIA. An example of application is presented to evaluate a PCMI limit for a zircaloy-4 cladding UO 2 rod at Hot Zero Power.

Methods and criteria for safety analysis (FIN L2535)

International Nuclear Information System (INIS)

1992-12-01

In response to the NRC request for a proposal dated October 20, 1992, Westinghouse Savannah River Company (WSRC) submit this proposal to provide contractural assistance for FIN L2535, ''Methods and Criteria for Safety Analysis,'' as specified in the Statement of Work attached to the request for proposal. The Statement of Work involves development of safety analysis guidance for NRC licensees, arranging a workshop on this guidance, and revising NRC Regulatory Guide 3.52. This response to the request for proposal offers for consideration the following advantages of WSRC in performing this work: Experience, Qualification of Personnel and Resource Commitment, Technical and Organizational Approach, Mobilization Plan, Key Personnel and Resumes. In addition, attached are the following items required by the NRC: Schedule II, Savannah River Site - Job Cost Estimate, NRC Form 189, Project and Budget Proposal for NRC Work, page 1, NRC Form 189, Project and Budget Proposal for NRC Work, page 2, Project Description

30 Years of NRWG activities towards harmonization of nuclear safety criteria and requirements

International Nuclear Information System (INIS)

2002-11-01

This report describes the work performed and the results achieved by the NRWG since its creation in 1972 to advise the Commission on nuclear safety matters (safety methodologies, criteria, standards, postulated accidents inside the nuclear installations, natural hazards, man-made hazards, training of personnel and use of simulator, ALARA policy to reduce the doses to the personnel and the public, emergency planning, defence in depth and integrity of the successive barriers between the radioactive products and the environment, radiological consequences of postulated accidents, probabilistic safety analysis, severe accidents analysis and management. The report also lists a number of technical subjects where NRWG has played a leading role. (author)

Safety assessment by Euro NCAP - objective test procedures instead of subjective inspection; Die Sicherheitsbewertung durch Euro NCAP - objektive Testverfahren statt subjektiver Fahrzeuginspektion

Energy Technology Data Exchange (ETDEWEB)

Seeck, A. [Bundesanstalt fuer Strassenwesen, Bergisch Gladbach (Germany); Klanner, W. [ADAC Technik Zentrum Landsberg (Germany)

2001-07-01

Development of objective testing procedures which may be able to replace subjective inspection of a vehicle following a crash test ist being pursued by Euro NCAP to an increasing degree. Three examples were given to show the capabilities as well as the difficulties connected with description of objective criteria and test procedures. Airbag bottoming-out was described pragmatically and clearly with the aid of criteria based on acceleration measurements in the head of the dummy. These criteria could therefore already be taken into consideration in development and layout of airbags. Practical testing at Euro NCAP has shown that head side airbags can provide considerably different protective effects in terms of accident reality during pole side impact and that these effects cannot always be recorded and differentiated using the evaluation criteria defined to date. For this reason extended and new evaluation criteria have been defined which allow differentiation of such systems. However, it was also found that marginal situations can occur which are difficult to evaluate. However, since such marginal situations can be described, it should be possible for automobile manufacturers in the future to design a system which is no longer devaluated by a modifier in cases of doubt. Evaluation of the knee impact area on the dashboard has probably caused the greatest criticism from the automotive industry to date regarding subjective inspection within the scope of Euro NCAP evaluation. A new committee from Euro NCAP is presently making efforts to define an objective test procedure with which modifiers resulting from the inspection can be refuted subsequently where applicable. However, since the knee mapping situation is very complex, it will probably not be possible to find an absolutely correct test procedure. On the contrary, a pragmatic procedure will probably be found which can then supply objective and comparable readings. This would then provide a testing method which would

Survey on requirements for independent reviews and inspections of electrical and I and C equipment

International Nuclear Information System (INIS)

Byman, Karin; Groenkvist, Stefan; Egerbo, Anders; Nilsson, Thomas

2009-03-01

Agencies are involved in almost all technical issues related to the assessment of safety of installations and their operation, including licensing procedures, tests, evaluations, reviews, supervisory procedures, and inspections. The expert organisations are part of the approval processes through their evaluations provided to the authorities in, for instance, expert analysis reports. But the experts are also authorised to give their approval to certain steps of the licensing procedure. The type approval certificate is granted by an accredited inspector. The Swiss nuclear regulatory framework is domestic. General requirements for the design as well as specific criteria for the licensing procedure are provided in the Nuclear Energy Ordinace (KEV). Detailed requirements of, for example, the design, review, and inspection of different kinds of safety-related electrical and IandC equipment are found in regulatory guidelines, which are provided by the Swiss Federal Nuclear Safety Inspectorate (HSK). In Switzerland, there are no general differences between the safety licensing procedure for electrical and IandC equipment and the procedure for mechanical equipment. The licensing procedure follows the four different phases: concept, design, realisation, and installation/commissioning. HSK may, as the federal supervisory authority, seek support from an expert organisation during different steps of the safety licensing procedure for equipment and systems in Swiss nuclear power plants. There are also other examples of the involvement of independent organisations in the safety assurance process for different kinds of equipment in Swiss nuclear power plants. The accredited organisation Electrosuisse inspects electrical installations with regard to general Swiss electrical regulations for personal safety and the Swiss Association for Technical Inspections, SVTI, inspects mechanical equipment

Status on system inspection and preventive maintenance of HANARO

International Nuclear Information System (INIS)

Kim, Young-Ki; Cho, Yeong-Garp; Kwag, Byung-Ho

1999-01-01

The HANARO is a 30 MW open pool type multi-purpose research reactor with forced light water coolant/moderator flows and heavy water annular reflector. The relatively small reactor core uses a low enriched fuel and is designed to maximize the power density, thus providing the required neutron flux for various research activities. It is mainly used for radioisotope production, nuclear material testing and neutron physics experiments. The initial criticality was achieved February 1995. Considering the importance of their functionality from the safety point of view, some components and equipment are categorized into a nuclear safety grade. There are three different inspection activities for the various reactor systems and components - a Surveillance Inspection(SI) for the safety grades and a Periodic Inspection (PI) for the non-safety grades and In-Service Inspection (ISI) for the ASME Sec.III components. All of the SIs are specified and required by the safety analysis report. The SI also differs from the PI in such a point that all kinds of activities for the SIs should be accompanied by an appropriate quality assurance, while for the PIs it is not necessarily mandatory. In addition, the inspection results for the SIs should go through an examination from regulatory body every two years and specific functions of the critical components or systems are demonstrated under the witness by the governmental inspector. The ISI is required and carried out as per international codes and standards as well as Korean atomic energy regulations. There are 54 SIs, 25 PIs and 4 ISIs for the HANARO. This paper concentrates on the managing strategy and its practices for the SIs and ISIs of the safety-related components, currently being done at HANARO. Most parts of the inspections fall into a group for the periodic performance testing and/or equipment calibration. Some mechanical inspections like a torque measurement are grouped into a preventive maintenance. Lastly the ASME Sec

Documentation for initial testing and inspections of Beneficial Uses Shipping System (BUSS) Cask

International Nuclear Information System (INIS)

Lundeen, J.E.

1994-01-01

The purpose of this report is to compile data generated during the initial tests and inspections of the Beneficial Uses Shipping System (BUSS) Cask. In addition, this report will verify that the testing criteria identified in section 8.1 of the BUSS Cask Safety Analysis Report for Packaging (SARP) was met. The BUSS Cask Model R-1 is a type B shipping container used for shipment of radioactive cesium-137 and strontium-90 capsules to Waste Encapsulation and Storage Facility (WESF). The BUSS Cask body and lid are each one-piece forgings fabricated from ASTM A473, Type 304 stainless steel. The primary purpose of the BUSS Cask is to provide shielding and confinement as well as impact, puncture, and thermal protection for the capsules under both normal and accident conditions. Chapter 8 of the BUSS Cask SARP requires several acceptance tests and inspections, each intended to evaluate the performance of different components of the BUSS Cask system, to be performed before its first use. The results of the tests and inspections required are included in this document

Equipment inspection function; A funcao inspecao de equipamentos

Energy Technology Data Exchange (ETDEWEB)

Bressan, Edemir [PETROBRAS (Brazil). Refinaria Alberto Pasqualini

1994-04-01

Development of the safety engineering and equipment inspection policy in petroleum industry, with emphasis to the refineries equipment, are discussed. Presentation of the accidents percentages in petroleum plants under international researches, with details of involved equipment, kind of accident, plant and causes are reported. The start and actual stage of the safety inspection program in the PETROBRAS are also presented 5 refs., 3 figs.

Evaluation of hygiene and safety criteria in the production of a traditional Piedmont cheese

Directory of Open Access Journals (Sweden)

Sara Astegiano

2014-08-01

Full Text Available Traditional products and related processes must be safe to protect consumers’ health. The aim of this study was to evaluate microbiological criteria of a traditional Piedmont cheese, made by two different cheese producers (A and B. Three batches of each cheese were considered. The following seven samples of each batch were collected: raw milk, milk at 38°C, curd, cheese at 7, 30, 60, 90 days of ripening. During cheese making process, training activities dealing with food safety were conducted. Analyses regarding food safety and process hygiene criteria were set up according to the EC Regulation 2073/2005. Other microbiological and chemical-physical analyses [lactic streptococci, lactobacilli, pH and water activity (Aw] were performed as well. Shiga-toxin Escherichia coli, aflatoxin M1 and antimicrobial substances were considered only for raw milk. All samples resulted negative for food safety criteria; Enterobacteriaceae, E.coli and coagulase-positive staphylococci (CPS were high in the first phase of cheese production, however they decreased at the end of ripening. A high level of CPS in milk was found in producer A, likewise in some cheese samples a count of >5 Log CFU/g was reached; staphylococcal enterotoxins resulted negative. The pH and Aw values decreased during the cheese ripening period. The competition between lactic flora and potential pathogen microorganisms and decreasing of pH and Aw are considered positive factors in order to ensure safety of dairy products. Moreover, training activities play a crucial role to manage critical points and perform corrective action. Responsible application of good manufacturing practices are considered key factors to obtain a high hygienic level in dairy products.

Evaluation of Hygiene and Safety Criteria in the Production of a Traditional Piedmont Cheese.

Science.gov (United States)

Astegiano, Sara; Bellio, Alberto; Adriano, Daniela; Bianchi, Daniela Manila; Gallina, Silvia; Gorlier, Alessandra; Gramaglia, Monica; Lombardi, Giampiero; Macori, Guerrino; Zuccon, Fabio; Decastelli, Lucia

2014-08-28

Traditional products and related processes must be safe to protect consumers' health. The aim of this study was to evaluate microbiological criteria of a traditional Piedmont cheese, made by two different cheese producers (A and B). Three batches of each cheese were considered. The following seven samples of each batch were collected: raw milk, milk at 38°C, curd, cheese at 7, 30, 60, 90 days of ripening. During cheese making process, training activities dealing with food safety were conducted. Analyses regarding food safety and process hygiene criteria were set up according to the EC Regulation 2073/2005. Other microbiological and chemical-physical analyses [lactic streptococci, lactobacilli, pH and water activity (A w )] were performed as well. Shiga-toxin Escherichia coli , aflatoxin M1 and antimicrobial substances were considered only for raw milk. All samples resulted negative for food safety criteria; Enterobacteriaceae , E.coli and coagulase-positive staphylococci (CPS) were high in the first phase of cheese production, however they decreased at the end of ripening. A high level of CPS in milk was found in producer A, likewise in some cheese samples a count of >5 Log CFU/g was reached; staphylococcal enterotoxins resulted negative. The pH and A w values decreased during the cheese ripening period. The competition between lactic flora and potential pathogen microorganisms and decreasing of pH and A w are considered positive factors in order to ensure safety of dairy products. Moreover, training activities play a crucial role to manage critical points and perform corrective action. Responsible application of good manufacturing practices are considered key factors to obtain a high hygienic level in dairy products.

9 CFR 381.197 - Imported products; foreign inspection certificates required.

Science.gov (United States)

2010-01-01

... AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Imported Poultry... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Imported products; foreign inspection certificates required. 381.197 Section 381.197 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE...

Bridging of inspection with corrosion management

International Nuclear Information System (INIS)

Zamaluddin Ali; Mohd Hawari Hassan; Rohana Jaafar

2009-01-01

Formerly, Inspection and Corrosion Engineers have less interaction and sharing of information to each other even they are working in the same plant or organization. Inspection finding either from visual inspection or NDT techniques rarely shared with corrosion engineers. Similarly corrosion engineers rarely discussed their corrosion prediction and potential damage mechanism with inspection engineers. A demanding request of more holistic plant safety and asset integrity promoted the introduction and implementation of Risk Based Inspection (RBI). RBI analysis demands the input mainly from both disciplines i.e. Inspection and Corrosion Engineers. Most of RBI methodologies are once-off analysis approach which also promoted once-off interaction between Inspection and Corrosion Engineers. PETRONAS has developed a methodology with supporting software, integrating both Inspection and Corrosion disciplines. PETRONAS Risk Based Inspection (PRBI) is intended to promote continuous integration of Inspection and Corrosion management of the plant through out the whole life cycle starting from the design stage to fabrication, operation and decommissions stage. (author)

Third Joint GIF–IAEA Workshop on Safety Design Criteria for Sodium-Cooled Fast Reactors, 26-27 February 2013, Vienna, Austria. Summary Report

International Nuclear Information System (INIS)

2013-01-01

The main objectives of the meeting were to: • Present and share information on the work carried out by GIF, the IAEA and the Member States on the definition of safety design criteria for SFR, including safety approach and requirements on general plant design; • Present the document prepared by the GIF-SFR Task Force on Safety Design Criteria; • Present and discuss safety design concepts of SFRs under development in Member States, with particular emphasis on design measures against Design Basis Accidents and Design Extended Conditions, as well as the associated safety evaluations and supporting R&D; • Draft a room document which should be the basis of the discussion for the Panel on Safety Design Criteria of the FR13 Conference in Paris. • Discuss the results and agree on the future actions of the 3rd Joint GIF-IAEA Workshop on Safety of Sodium-Cooled Fast Reactors

Description of present practice concerning the safety criteria for nuclear power plants

International Nuclear Information System (INIS)

1977-01-01

In the description at hand, the authors portray how the aims defined in the safety criteria are reached, and they make proposals for improvement. Basic principles, acceptances and requirements, with which the experts of TUeV and GRS involved in licensing procedures work at the moment, are compiled. This description of present practice has to be adapted perhaps to the existing scientific knowledge at the time. In order that an optimal behaviour as regards safety is reached by the employees in nuclear power plants, criterion 2.5 requires the following measures: the places of work and the work routine in nuclear power plants are to be organized in such a way, that they offer the conditions for the optimal behaviour of employees as regards safety. (orig./HP) [de

Phase I Inspection Report. National Dam Safety Program. Round Valley South Dam, Hunterdon County, New Jersey.

Science.gov (United States)

1978-05-01

defined by the Recommended Guidelines for Safety Inspection of Dams. .M • wwM •^^^nmifgnmmmm’m •PH J.I.I MPU C. Hazard Classification - The...Conservation and Economic Development, August 1958. 3) Contract RV-1, State of New Jersey Department of Conservation and Economic Development...FIGURE 4 iymmmmr STATE OF NEW JERSEY DEPARTMENT OF CONSERVATION AND ECONOMIC DEVFl OtVNKM OF WATNt FOUCY «MO mm 1 ROUND VALLEY RESERVOIR

Monitoring and inspection techniques for long term storage of higher activity waste packages

International Nuclear Information System (INIS)

Bolton, Gary

2013-01-01

In 2009, following recent changes in United Kingdom (UK) Government Policy, the Nuclear Decommissioning Authority (NDA) identified a knowledge gap in the area of long term interim storage of waste packages. A cross-industry Integrated Project Team (IPT) for Interim Storage was created with responsibility for delivering Industry Guidance on the storage of packaged Higher Activity Waste (HAW) for the current UK civil decommissioning and clean-up programmes. This included a remit to direct research and development projects via the NDA's Direct Research Portfolio (DRP) to fill the knowledge gap. The IPT for Interim Storage published Industry Guidance in 2012 which established a method to define generic package performance criteria and made recommendations on monitoring and inspection. The package performance method consists of the following steps; identification of the package safety function, identification of evolutionary processes that may affect safety function performance, determination of measurable indicators of these evolutionary processes and calibration of the indicators into package performance zones. This article provides an overview of three projects funded by the NDA's DRP that the UK National Nuclear Laboratory (NNL) have completed to address monitoring and inspection needs of waste packages in interim storage. (orig.)

Nuclear power safety

International Nuclear Information System (INIS)

1988-01-01

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

Optimal replacement and inspection periods of safety and control boards in Wolsung nuclear power plant unit 1

International Nuclear Information System (INIS)

Mok, Jin Il

1993-02-01

upon to act when emergency conditions develop. To ensure their operability, the systems are periodically tested. In this paper, unavailability formulae for 2-out-of-3 logic configurations are developed, taking into account the probability of failure of channels tested due to human error in the simultaneous testing scheme. The probability of the channel being down due to human error is assumed to depend on the number of channel which have gone through the tests consecutively prior to the inspection of the channel under consideration. The system unavailability is the sum of unavailability due to hardware failure alone and the unavailability contribution due to human error. And we considered the probability that the reactor will be tripped during surveillance test. We determined the optimal inspection periods of safety system, taking into account both unavailability of safety system and the probability that the reactor will be tripped during surveillance test. We compared these periods with the inspection periods currently used at Wolsung NPP Unit 1. As a consequence, the inspection periods obtained using a minimum human error (8.24 x 10 -6 ) are shorter than those currently used in Wolsung NPP unit 1 while inspection periods obtained using a maximum human error is (4.44 x10 -4 ) longer than those used in Wolsung NPP unit 1

Probabilistic safety criteria on high burnup HWR fuels

International Nuclear Information System (INIS)

Marino, A.C.

2002-01-01

BACO is a code for the simulation of the thermo-mechanical and fission gas behaviour of a cylindrical fuel rod under operation conditions. Their input parameters and, therefore, output ones may include statistical dispersion. In this paper, experimental CANDU fuel rods irradiated at the NRX reactor together with experimental MOX fuel rods and the IAEA-CRP FUMEX cases are used in order to determine the sensitivity of BACO code predictions. The techniques for sensitivity analysis defined in BACO are: the 'extreme case analysis', the 'parametric analysis' and the 'probabilistic (or statistics) analysis'. We analyse the CARA and CAREM fuel rods relation between predicted performance and statistical dispersion in order of enhanced their original designs taking account probabilistic safety criteria and using the BACO's sensitivity analysis. (author)

International cooperation in production inspections

International Nuclear Information System (INIS)

Limousin, S.

2009-01-01

Nuclear pressure equipment, like the reactor pressure vessel or steam generators, are manufactured in many countries all around the world. As only few reactors were built in the 90's, most of the nuclear safety authorities have lost part of their know how in component manufacturing oversight. For these two reasons, vendor inspection is a key area for international cooperation. On the one hand, ASN has bilateral relationships with several countries (USA, Finland, China...) to fulfill specific purposes. On the other hand, ASN participates in international groups like the MDEP ( Multinational Design Evaluation Program). A MDEP working group dedicated to vendor inspection cooperation enables exchanges of informations (inspection program plan, inspection findings...) among the regulators. Join inspections are organized. International cooperation could lead in the long term to an harmonization of regulatory practices. (author)

Safety Criteria for the Private Spaceflight Industry

Science.gov (United States)

Quinn, Andy; Maropoulos, Paul

2010-09-01

The Federal Aviation Administration(FAA) Office of Commercial Space Transportation(AST) has set specific rules and generic guidelines to cover experimental and operational flights by industry forerunners such as Virgin Galactic and XCOR. One such guideline Advisory Circular(AC) 437.55-1[1] contains exemplar hazard analyses for spacecraft designers and operators to follow under an experimental permit. The FAA’s rules and guidelines have also been ratified in a report to the United States Congress, Analysis of Human Space Flight Safety[2] which cites that the industry is too immature and has ‘insufficient data’ to be proscriptive and that ‘defining a minimum set of criteria for human spaceflight service providers is potentially problematic’ in order not to ‘stifle the emerging industry’. The authors of this paper acknowledge the immaturity of the industry and discuss the problematic issues that Design Organisations and Operators now face.

75 FR 56015 - Vessel Inspection Alternatives

Science.gov (United States)

2010-09-15

... DEPARTMENT OF HOMELAND SECURITY Coast Guard 46 CFR Part 8 Vessel Inspection Alternatives CFR... Certificate; (ii) International Tonnage Certificate; (iii) Cargo Ship Safety Construction Certificate; (iv) Cargo Ship Safety Equipment Certificate; and (v) International Oil Pollution Prevention Certificate; and...

Survey on requirements for independent reviews and inspections of electrical and I and C equipment

Energy Technology Data Exchange (ETDEWEB)

Byman, Karin; Groenkvist, Stefan; Egerbo, Anders; Nilsson, Thomas (AaF Consult AB, Stockholm (Sweden))

2009-03-15

are involved in almost all technical issues related to the assessment of safety of installations and their operation, including licensing procedures, tests, evaluations, reviews, supervisory procedures, and inspections. The expert organisations are part of the approval processes through their evaluations provided to the authorities in, for instance, expert analysis reports. But the experts are also authorised to give their approval to certain steps of the licensing procedure. The type approval certificate is granted by an accredited inspector. The Swiss nuclear regulatory framework is domestic. General requirements for the design as well as specific criteria for the licensing procedure are provided in the Nuclear Energy Ordinace (KEV). Detailed requirements of the design, review, and inspection of different kinds of safety-related electrical and IandC equipment are found in regulatory guidelines, which are provided by the Swiss Federal Nuclear Safety Inspectorate (HSK).

Application of risk-informed in-service inspection approach. Pilot study on low pressure emergency core cooling system of NPP Temelin

International Nuclear Information System (INIS)

Horacek, L.; Palyza, J.; Zdarek, J.; Vizina, M.

2004-01-01

In-service inspection (ISI) programme of piping systems based on Riskinformed In-service Inspections (RI-ISI) approach represents for the WWER NPP licensee first overall systematic conceptual solution of the problems associated with design and design modifications of ISI programme for piping systems. The approach enables to consider possible savings and comparison of in-service inspection programmes according to more objective criteria including those calculated in PSA, in contrast to present much empiric experience collected by manufacturers, operators and ISI vendors in the past. Service experience has shown limited correlation between the deterministic ISI requirements and actual field failures or degradation mechanisms. Where field failures have been observed in piping, they have generally been due to either material concerns (e.g., Intergranular Stress Corrosion Cracking) or stress/cycling mechanisms not identified in the original design basis documents (e.g., thermal stratification), and therefore would not be selected for inspection under current requirements. Risk-informed in-service inspections represent integrated multidisciplinary approach to the in-service inspection programme fulfilling the enhanced requirements of the Czech Regulatory Body (SUJB) for defence in depth concept applied to weld joints of safety related components, application of qualified NDT methods/techniques and introducing of inspections for cause approach. Inspections for cause take into account analysis of both active and potential degradation mechanisms specific to piping system concerned. Simultaneously, this approach enables the licensee to reach, in cases justified from safety point of view, economic savings resulting from lowering of both number and extent of performed in-service inspections and optimisation of their performance. RI ISI pilot study based in majority on EPRI methodology implemented for WWER type reactors has been performed for LP ECCS (Low Pressure Emergency

Utilization of aging program results in plant inspections

International Nuclear Information System (INIS)

Gunther, W.; Fullwood, R.

1989-01-01

Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

Utilization of aging program results in plant inspections

International Nuclear Information System (INIS)

Gunther, W.; Fullwood, R.

1988-01-01

Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

OSE inspection of materials control and accountability: Review

International Nuclear Information System (INIS)

Coady, K.J.

1987-01-01

As part of its task to confirm that Department of Energy (DOE) field offices provide levels of security and safeguards commensurate with defined threats, the DOE Office of Security Evaluations (OSE) conducts inspections of the nuclear materials control and accountability (MC and A) systems at DOE facilities throughout the United States. Inspections are based on the DOE Safeguards and Security Standards and Criteria, tailored to the specific aspects at and threats to each individual site. This paper reviews the process of inspecting MC and A systems during the planning, preinspection, and inspection/reporting phases

Reuse inspection refort of the spent fuel cask

Energy Technology Data Exchange (ETDEWEB)

Park, S. W.; Seo, K. S.; Ku, J. H.; Lee, J. C.; Bang, K. S.; Min, D. K. [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-04-01

This is the contract result report performed by KAERI under the contract with KPS for the reuse inspection of the KSC-4 No. 2 cask to receive the license for the reuse of next 5 years. According to the revision of the atomic regulations, all type B package should receive and pass the reuse inspection for every 5 years. This report contains the summary of the reuse inspection project, the details of the inspection methods and evaluation criteria, the documents which submitted to the KINS and the license approved by the KINS. 1 tabs. (Author)

Occupational safety and health criteria for responsible development of nanotechnology

Science.gov (United States)

Schulte, P. A.; Geraci, C. L.; Murashov, V.; Kuempel, E. D.; Zumwalde, R. D.; Castranova, V.; Hoover, M. D.; Hodson, L.; Martinez, K. F.

2014-01-01

Organizations around the world have called for the responsible development of nanotechnology. The goals of this approach are to emphasize the importance of considering and controlling the potential adverse impacts of nanotechnology in order to develop its capabilities and benefits. A primary area of concern is the potential adverse impact on workers, since they are the first people in society who are exposed to the potential hazards of nanotechnology. Occupational safety and health criteria for defining what constitutes responsible development of nanotechnology are needed. This article presents five criterion actions that should be practiced by decision-makers at the business and societal levels—if nanotechnology is to be developed responsibly. These include (1) anticipate, identify, and track potentially hazardous nanomaterials in the workplace; (2) assess workers' exposures to nanomaterials; (3) assess and communicate hazards and risks to workers; (4) manage occupational safety and health risks; and (5) foster the safe development of nanotechnology and realization of its societal and commercial benefits. All these criteria are necessary for responsible development to occur. Since it is early in the commercialization of nanotechnology, there are still many unknowns and concerns about nanomaterials. Therefore, it is prudent to treat them as potentially hazardous until sufficient toxicology, and exposure data are gathered for nanomaterial-specific hazard and risk assessments. In this emergent period, it is necessary to be clear about the extent of uncertainty and the need for prudent actions.

Application of the risk based inspection in chemical and nuclear installations: a critical evaluation

International Nuclear Information System (INIS)

Sousa, Anna Leticia Barbosa de

2004-01-01

Risk-based Inspection (RBI) has arisen as an opportunity for the industry to give a specific treatment to items as equipment integrity, failures consequences and the level of risk of each piece of equipment in the inspection programs definitions. Risk-based inspection programs are replacing the traditional ones based on prescriptive requirements, for both the oil and nuclear industries. The aim of this thesis is to demonstrate how the nuclear industry has gotten over several difficulties in implementing risk-based programs considering that its safety design and regulations have traditionally been based on deterministic and prescriptive criteria and requirements. During the development of the work, the study has shown how the absence of a rigid regulation favored the dissemination of RBI diffusion in the oil industry, mainly in the USA, where such industries do not face those difficulties found by the European plants, as long as it is well known that in Europe there are complex interrelations among documents from different countries with diversity of regulation procedures. (author)

In service inspection of SUPERPHENIX 1 vessels: MIR

International Nuclear Information System (INIS)

Asty, M.; Viard, J.; Lerat, B.; Saglio, R.

1985-01-01

Although no in-service inspection constraints were imposed on the Phenix vessels, the Safety Authorities asked that the design of SUPERPHENIX 1 makes it possible to monitor throughout the lifetime of the reactor, surface and internal defects on the main vessel. A pool design and the presence of heat baffles inside the main vessel make access from the inside of the vessel impossible. Thus, an inspection can only be performed from the outside of the main vessel: the distance between the walls of the main and safety vessels is such that an inspection device can be introduced into the corresponding space. As the design of the reactor precludes radiographic inspection, the method which was selected for monitoring internal defects in the main vessel is ultrasonics. However, the anisotropic structure of austenitic stainless steel welds limits the performance of this technique. The authors present the in-service inspection device, MIR, which has been specially developed for the visual and ultrasonic examination of SUPERPHENIX 1 vessels

Inspection of the Sizewll 'B' reactor coolant pump flywheels

International Nuclear Information System (INIS)

McNulty, A.L.; Cheshire, A.

1992-01-01

The Sizewell ''B'' safety case has categorised some primary circuit items as components for which failure is considered to be incredible. These Incredibility of Failure (IOF) components are particularly critical in their safety function, and specially stringent and all embracing provisions are made in their design, manufacture, inspection and operation. These provisions are such as to limit the probability of failure to levels which are so low that it does not have to be taken into account and no steps are necessary to control the consequences. The reactor coolant pump flywheel is considered to be an IOF component. Consequently there is a need for rigorous inspection during both manufacture and in service (ISI). The ISI requirement results in the need for an automated inspection. There is therefore a prerequisite to perform a Pre-Service Inspection (PSI) for baseline fingerprinting purposes. Furthermore there is a requirement that the inspection procedure, the inspection equipment and the operators are validated at the Inspection Validation Centre (IVC) of the AEA Technology laboratories at Risley. Development work is described. (author)

Criteria for safety-related nuclear-power-plant operator actions: 1982 pressurized-water-reactor (PWR) simulator exercises

International Nuclear Information System (INIS)

Crowe, D.S.; Beare, A.N.; Kozinsky, E.J.; Haas, P.M.

1983-06-01

The primary objective of the Safety-Related Operator Action (SROA) Program at Oak Ridge National Laboratory is to provide a data base to support development of criteria for safety-related actions by nuclear power plant operators. When compared to field data collected on similar events, a base of operator performance data developed from the simulator experiments can then be used to establish safety-related operator action design evaluation criteria, evaluate the effects of performance shaping factors, and support safety/risk assessment analyses. This report presents data obtained from refresher training exercises conducted in a pressurized water reactor (PWR) power plant control room simulator. The 14 exercises were performed by 24 teams of licensed operators from one utility, and operator performance was recorded by an automatic Performance Measurement System. Data tapes were analyzed to extract operator response times (RTs) and error rate information. Demographic and subjective data were collected by means of brief questionnaires and analyzed in an attempt to evaluate the effects of selected performance shaping factors on operator performance

In-service inspection of nuclear power plants

International Nuclear Information System (INIS)

1991-01-01

This Manual is intended to provide more comprehensive considerations on the management, organization, preparation, improvement and implementation of in-service inspection activities and the related surveillance. It also gives illustrative examples of good practices and recommendations from operating and other organizations that are consistent with the requirements and recommendations of the Code and Safety Guides. The Manual is directed primarily towards plant management. This Manual should be used in conjunction with the Code and the Safety Guides, in particular with IAEA Safety Series Nos. 50-C-O, 50-SG-O2, 50-SG-05, 50-SG-07, 50-SG-08 and 50-SG-D1, which contain recommendations of a general character about maintenance activities and radiation protection in an operating power plant, and with the 'Manual on the Maintenance of Systems and Components Important to Safety'. This Manual is divided into four technical sections. The first introduces the purpose, structure and main requirements of the programme. The second section describes constituents of the programme, recommending its scope, scheduling, acceptance standards and documentation of results. The following section goes into details of the inspection programme's contents, such as the selection of components, inspection locations, defect types, applicable techniques and procedures, and the evaluation of results. The last section specifies recommended methods and techniques for inspection, such as visual, ultrasonic, eddy current, magnetic particle and others. This main part of the Manual is complemented by a number of annexes which reproduce actual national examples of established procedures, ISI programme parts, acceptance standards, personnel training programmes, testing techniques and other aspects of in-service inspection, illustrating practical implementation of the recommendations of the Manual

Update on the EPRI power generation risk-based inservice inspection pilot plant studies

International Nuclear Information System (INIS)

Gosselin, S.R.

1997-01-01

The scope for ASME Section XI ISI programs is largely based on deterministic results contained in design stress reports. These reports are normally very conservative and may not be an accurate representation of failure potential. Service experience has shown that failures are due to either corrosion or fatigue and typically occur in areas not included in the plant's ISI program. Consequently, nuclear plants are devoting significant resources to inspection programs that provide minimum benefit. As an alternative, significant industry attention has been devoted to the application of risked-based selection criteria in order to determine the scope of inservice inspection (ISI) programs at nuclear power plants. Preliminary EPRI studies indicate that the application of these techniques will allow operating nuclear plants to reduce the examination scope of current ISI programs by as much as 60 to 80%, significantly reduce costs, and continue to maintain high nuclear plant safety standards

Pickering seismic safety margin

International Nuclear Information System (INIS)

Ghobarah, A.; Heidebrecht, A.C.; Tso, W.K.

1992-06-01

A study was conducted to recommend a methodology for the seismic safety margin review of existing Canadian CANDU nuclear generating stations such as Pickering A. The purpose of the seismic safety margin review is to determine whether the nuclear plant has sufficient seismic safety margin over its design basis to assure plant safety. In this review process, it is possible to identify the weak links which might limit the seismic performance of critical structures, systems and components. The proposed methodology is a modification the EPRI (Electric Power Research Institute) approach. The methodology includes: the characterization of the site margin earthquake, the definition of the performance criteria for the elements of a success path, and the determination of the seismic withstand capacity. It is proposed that the margin earthquake be established on the basis of using historical records and the regional seismo-tectonic and site specific evaluations. The ability of the components and systems to withstand the margin earthquake is determined by database comparisons, inspection, analysis or testing. An implementation plan for the application of the methodology to the Pickering A NGS is prepared

Knowledge-Based Inspection Capabilities

National Research Council Canada - National Science Library

Marrano, Lance R; Grussing, Michael N

2006-01-01

... does not present a compelling safety hazard. Abandoning certain inspection programs to reduce costs is not a viable alternative, however, because that could degrade real property investments, soldier quality of life, and mission-readiness...

9 CFR 381.199 - Inspection of poultry products offered for entry.

Science.gov (United States)

2010-01-01

... AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Imported Poultry... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Inspection of poultry products offered for entry. 381.199 Section 381.199 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE...

33 CFR 3.40-28 - Sector Houston-Galveston Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit...

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Sector Houston-Galveston Marine....40-28 Sector Houston-Galveston Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit Port Arthur. Sector Houston-Galveston's office is located in Galena Park, TX. A subordinate unit...

The applications of risk-informed in-service-inspection

International Nuclear Information System (INIS)

Ting, K.; Ko, T.-H.; Li, Y.-C.; Wu, W.-F.; Lu, Y.-L.; Chien, F.-T.

2005-01-01

The US NRC and nuclear industry encouraged the applications of risk-informed In-Service Inspection (RI-ISI) which can be an alternative program to the ASME Section XI In-service Inspection requirements. The Implementation of RI-ISI can improve the substantial cost as well as does reductions. From the aspect of defense in depth for nuclear safety, the achievements of these procedures can identify the inspection rank to promote the integrity of the current inspection program. Thus, this study utilizes this techniques to implement risk assessment on safety class 1 recirculation piping welds where sensitized to IGSCC of Taibei BWR-6 nuclear power plant. In the evaluation process, WinPraise code is used to calculate the failure probabilities of all welds. The result of risk evaluations can be referred to the further regulatory and plant operation. (authors)

9 CFR 381.14 - Inspection concerning purportedly exempted operations.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Inspection concerning purportedly exempted operations. 381.14 Section 381.14 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE... make inspections in accordance with law to ascertain whether any of the provisions of the Act or the...

Apparative developments for inservice inspections of reactor pressure vessels

International Nuclear Information System (INIS)

Bohn, H.; Ruthrof, K.; Barbian, O.A.; Kappes, W.; Neumann, R.; Stanger, H.K.

1987-01-01

Emphasizing PWR pressure vessel (RPV) inspections, recent developments of new generations of automated and mechanized ultrasonic inspection equipment are presented. Starting from general equipment design and inservice implenentation criteria, specific examples are given. Main attention is directed to equipment realization of phased array and ALOK inspection techniques, especially in their combination. Refined aspects of subsequent computer processing and evaluation of defect detection data are described. Analytical features and potential for further developments become evident. Remote controlled RPV inspections are stressed by describing a new generation of central mast manipulators, forming an integral part of total inservice inspection system. (orig./HP)

Which follow-up by the CLIs for the 3. decennial inspections?

International Nuclear Information System (INIS)

Rollinger, Francois; Delalonde, Jean-Claude; Rousseau, Jean-Marie; Paulmaz, Xavier; Junker, R.; Sene, M.; Hubert, F.; Paulmaz, X.; Tindillere, M.; Lheureux, Y.

2010-11-01

This document contains contributions presented by representatives of the IRSN, EDF and CLIs. The first session addressed issues related to decennial inspections. The contributions proposed a presentation of the safety re-examination of EDF 900 MWe reactors at the occasion of the 3. decennial inspections, a presentation of IRSN works on skill management in electric power production nuclear plants (CNPEs), a presentation (by EDF) of these 3. decennial inspections, a presentation (by the Fessenheim CLI) of the implementation of the 3. decennial inspection in Fessenheim, and a discussion by the Blayais CLI of follow-up perspectives after a decennial inspection. The second session addressed issues not related to decennial inspections. It contains two presentations respectively made by the Gravelines CLI (an analysis of significant safety events) and Dampierre CLI (problematic of skill management in CNPEs)

What are the attributes of a good standard and associated criteria?

International Nuclear Information System (INIS)

Allentuck, J.

1987-01-01

The Department of Energy (DOE) Standards and Criteria (S and C) provide the framework upon which Office of Security Evaluations (OSE) inspections of safeguards and security at DOE facilities are conducted. The S and C were created to assure that inspections are comprehensive, standardized to the extent possible and accurately reported in meaningful terms, and that assessments are objective. With these goals in mind, the desirable attributes of a standard and its associated criteria are relevance, inspectability, and limited need for inspector judgement. 1 fig

Nuclear power plant pressure vessels. Inservice inspections

International Nuclear Information System (INIS)

1995-01-01

The requirements for the planning and reporting of inservice inspections of nuclear power plant pressure vessels are presented. The guide specifically applies to inservice inspections of Safety class 1 and 2 nuclear power plant pressure vessels, piping, pumps and valves plus their supports and reactor pressure vessel internals by non- destructive examination methods (NDE). Inservice inspections according to the Pressure Vessel Degree (549/73) are discussed separately in the guide YVL 3.0. (4 refs.)

The need to optimize inservice testing and inspection to enhance safety

International Nuclear Information System (INIS)

Perry, J.A.

1996-01-01

Welcome to the Fourth U.S. Nuclear Regulatory Commission and American Society of Mechanical Engineers (USNRC/ASME) Symposium on Valve and Pump Testing in Nuclear Power Plants. This symposium provides a forum to exchange information on technical and regulatory issues associated with the testing of valves and pumps used in nuclear power plants. Progress made since the last symposium will be discussed along with various methods for in service testing of valves and pumps. Active participation by industry representatives, regulators and consultants will entail discussion of a broad array of ideas and points of view regarding how to improve the in service testing of valves and pumps at nuclear power plants. One of the challenges faced is the need to optimize the in service testing and inspection to enhance safety, operability and reliability. The author addresses this challenge from an ASME Nuclear Codes and Standards point of view

The need to optimize inservice testing and inspection to enhance safety

Energy Technology Data Exchange (ETDEWEB)

Perry, J.A.

1996-12-01

Welcome to the Fourth U.S. Nuclear Regulatory Commission and American Society of Mechanical Engineers (USNRC/ASME) Symposium on Valve and Pump Testing in Nuclear Power Plants. This symposium provides a forum to exchange information on technical and regulatory issues associated with the testing of valves and pumps used in nuclear power plants. Progress made since the last symposium will be discussed along with various methods for in service testing of valves and pumps. Active participation by industry representatives, regulators and consultants will entail discussion of a broad array of ideas and points of view regarding how to improve the in service testing of valves and pumps at nuclear power plants. One of the challenges faced is the need to optimize the in service testing and inspection to enhance safety, operability and reliability. The author addresses this challenge from an ASME Nuclear Codes and Standards point of view.

Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide presents a coherent set of generic criteria (expressed numerically in terms of radiation dose) that form a basis for developing the operational levels needed for decision making concerning protective and response actions. The set of generic criteria addresses the requirements established in IAEA Safety Standards Series No. GS-R-2 for emergency preparedness and response, including lessons learned from responses to past emergencies, and provides an internally consistent foundation for the application of radiation protection. The publication also proposes a basis for a plain language explanation of the criteria for the public and for public officials. Contents: 1. Introduction; 2. Basic considerations; 3. Framework for emergency response criteria; 4. Guidance values for emergency workers; 5. Operational criteria; Appendix I: Dose concepts and dosimetric quantities; Appendix II: Examples of default oils for deposition, individual monitoring and contamination of food, milk and water; Appendix III: Development of EALs and example EALs for light water reactors; Appendix IV: Observables at the scene of a nuclear or radiological emergency

Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Guide (Russian Ed.)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide presents a coherent set of generic criteria (expressed numerically in terms of radiation dose) that form a basis for developing the operational levels needed for decision making concerning protective and response actions. The set of generic criteria addresses the requirements established in IAEA Safety Standards Series No. GS-R-2 for emergency preparedness and response, including lessons learned from responses to past emergencies, and provides an internally consistent foundation for the application of radiation protection. The publication also proposes a basis for a plain language explanation of the criteria for the public and for public officials. Contents: 1. Introduction; 2. Basic considerations; 3. Framework for emergency response criteria; 4. Guidance values for emergency workers; 5. Operational criteria; Appendix I: Dose concepts and dosimetric quantities; Appendix II: Examples of default oils for deposition, individual monitoring and contamination of food, milk and water; Appendix III: Development of EALs and example EALs for light water reactors; Appendix IV: Observables at the scene of a nuclear or radiological emergency.

Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Guide (Arabic Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-11-01

This Safety Guide presents a coherent set of generic criteria (expressed numerically in terms of radiation dose) that form a basis for developing the operational levels needed for decision making concerning protective and response actions. The set of generic criteria addresses the requirements established in IAEA Safety Standards Series No. GS-R-2 for emergency preparedness and response, including lessons learned from responses to past emergencies, and provides an internally consistent foundation for the application of principles of radiation protection. The publication also provides a basis for a plain language explanation of the criteria for the public and for public officials. Contents: 1. Introduction; 2. Basic considerations; 3. Framework for emergency response criteria; 4. Guidance values for emergency workers; 5. Operational criteria; Appendix I: Dose concepts and dosimetric quantities; Appendix II: Examples of default OILs for deposition, individual contamination and contamination of food, milk and water; Appendix III: Development of EALs and example EALs for light water reactors; Appendix IV: Observables on the scene of a radiological emergency.

Some reliability targets affecting the necessary provisions for in-service inspection and monitoring of LMFBR engineering components

International Nuclear Information System (INIS)

Bolt, P.R.

1980-01-01

The possible consequences of failure of primary and secondary sodium circuit components are discussed with particular reference to post incident fault diagnosis, remedial procedures and outage durations. The core support structures and steam generator units are identified as particularly important components in terms of economic consequence of their failure. Important safety considerations may also apply. Levels of reliability for core support and steam generator integrity, necessary to meet economic and certain safety criteria, are discussed and quantitative data is given. Possible failure and deterioration mechanisms which could result in unacceptable reductions in reliability are then identified for the core support and steam generator units. Following a consideration of the reliability targets and possible causes of loss of reliability, an appraisal is made of the necessary extent of in-service data to be obtained on component behaviour and condition. In-service inspection and monitoring methods that could be used to obtain this data are described. Consideration is given to UK and overseas inspection experience on LMFBR and other nuclear plant. (author)

Some reliability targets affecting the necessary provisions for in-service inspection and monitoring of LMFBR engineering components

Energy Technology Data Exchange (ETDEWEB)

Bolt, P R [Fast Reactor Engineering, Plant Engineering Department, CEGB, Barnwood, Gloucester (United Kingdom)

1980-11-01

The possible consequences of failure of primary and secondary sodium circuit components are discussed with particular reference to post incident fault diagnosis, remedial procedures and outage durations. The core support structures and steam generator units are identified as particularly important components in terms of economic consequence of their failure. Important safety considerations may also apply. Levels of reliability for core support and steam generator integrity, necessary to meet economic and certain safety criteria, are discussed and quantitative data is given. Possible failure and deterioration mechanisms which could result in unacceptable reductions in reliability are then identified for the core support and steam generator units. Following a consideration of the reliability targets and possible causes of loss of reliability, an appraisal is made of the necessary extent of in-service data to be obtained on component behaviour and condition. In-service inspection and monitoring methods that could be used to obtain this data are described. Consideration is given to UK and overseas inspection experience on LMFBR and other nuclear plant. (author)

Safety Design Criteria and Approaches to Safety Substantiation of the BN-1200

International Nuclear Information System (INIS)

Ashurko, I.

2013-01-01

Russian experience in SFR area: Activities on development of safety design criteria for SFRs of the 4th generation is carried out within the GIF framework. Although this reactor technology is considered as innovative that is relevant to the 4th generation, however, it has already a certain history. In this relation, it seems to be useful to analyze the corresponding experience that is available in various countries. 4 SFRs have been successfully operated in the USSR and in the Russian Federation: • Experimental reactor BR-5/10; • Research reactor BOR-60; • Prototype BN-350 power reactor; • Commercial BN-600 power unit at the Beloyarsk NPP. Thus, Russia gained a considerable experience of design, construction and operation of SFRs. In particular, a certain experience has been acquired on safety substantiation of reactors of this type and their licensing. Now BOR-60 and BN-600 continue their operation, BN-800 power unit is under construction, development of the commercial BN-1200 power unit, that is considered as the 4th generation reactor, has been started. Due to limited number of operating SFRs in the world, successful Russian experience in this area should be taken into account for further development and improvement of SFR SDC developed by the GIF Task Force. In particular, participation of SFR designers in this activities would be fruitful and useful

Inspection of licensed nuclear power plants in the United States

International Nuclear Information System (INIS)

Thornburg, H. D.

1977-01-01

Inspection of licensed nuclear power plants in the United States is performed by the Office of Inspection and Enforcement (IE), United States Nuclear Regulatory Commission. IE has several key functions : a) Inspection of licensees and investigation of incidents, occurrences and allegations. b) Detection and correction of safety and security problems. c) Enforcement of rules, regulations, and Commission orders. d) Feedback to the industry and others regarding safety experience. e) Informing the public and others. Major enforcement actions and events involving operating power reactors for the past several years will be summarized. (author)

75 FR 56502 - National Advisory Committee on Meat and Poultry Inspection

Science.gov (United States)

2010-09-16

... Advisory Committee on Meat and Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION... and Poultry Inspection (NACMPI) will hold a public meeting on September 29-30, 2010, to review and... disks or CD-ROMs: Send to National Advisory Committee on Meat and Poultry Inspection, USDA, FSIS, 14th...

9 CFR 355.41 - Antemortem and postmortem inspection for mules.

Science.gov (United States)

2010-01-01

... AND VOLUNTARY INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Antemortem and postmortem inspection for mules. 355.41 Section 355.41 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE...

3D optical measuring technologies for dimensional inspection

International Nuclear Information System (INIS)

Chugui, Yu V

2005-01-01

The results of the R and D activity of TDI SIE SB RAS in the field of the 3D optical measuring technologies and systems for noncontact 3D optical dimensional inspection applied to atomic and railway industry safety problems are presented. This activity includes investigations of diffraction phenomena on some 3D objects, using the original constructive calculation method, development of hole inspection method on the base of diffractive optical elements. Ensuring the safety of nuclear reactors and running trains as well as their high exploitation reliability takes a noncontact inspection of geometrical parameters of their components. For this tasks we have developed methods and produced the technical vision measuring systems LMM, CONTROL, PROFILE, and technologies for non-contact 3D dimensional inspection of grid spacers and fuel elements for the nuclear reactor VVER-1000 and VVER-440, as well as automatic laser diagnostic system COMPLEX for noncontact inspection of geometrical parameters of running freight car wheel pairs. The performances of these systems and the results of the industrial testing at atomic and railway companies are presented

A review of digital radiography technology for valve inspection

International Nuclear Information System (INIS)

Stoev, K.; Guerout, F.M.; Horn, D.

2008-01-01

There are thousands of valves in a nuclear power plant (NPP) used for control, safety and checks in various plant systems, so there is a well-identified need for fast and reliable inspection and diagnostics of valves. Digital radiography can provide considerable improvements to the inspection and testing procedures for valves in comparison to classical film radiography. These improvements can lead to significant financial advantages by providing real-time inspection results, significantly reduced inspection and decision-making time, and reduced operational cost. Digital image processing, including digital image enhancement, digital archiving, and digital communication of the images and the results, is also a considerable advantage over classical film radiography technology. Another advantage of digital radiography technology is the improved safety and the reduced environmental impact due to reduced exposure/test times, use of smaller exclusion zones, elimination of chemical processing, and absence of disposable materials. This paper reviews the existing technology and evaluates the potential of digital radiography for inspection and diagnostics of valves. Station needs and requirements are assessed, and the safety, environmental and economical constraints of digital radiography techniques estimated. The advantages and disadvantages of different digital radiography equipment are compared, and their limitations and characteristics studied. (author)

The Mechatronic System Design Of Ultrasonic Scanner For Inservice Inspection Of Research Reactor

Science.gov (United States)

Handono, Khairul; Kristedjo, K.; Awwaluddin, M.; Shobary, Ihsan

2018-02-01

The mechatronic system design of ultrasonic scanner for inservices inspection of Research Reactor has been conducted. The requirement designed must be reliable operated, safety to personnel and equipments, ease of maintenance and operation, protection of equipment mechanically, interchangeability of equipments and addition of the several model of probe immersion ultrasonic tranducer. In order to achieve the above goals and obtain the desired results, a mechatronic design based on mechanical and electronic practical experiences will be needed. In this paper consist of the mechanical design and the system mechanical movement using stepper motor control. The criteria and the methods of designs of mechanical and electronic equipments of the system have been discussed and investigated. A mechanical and instrumentation control system drawing and requirement of design will be presented as the outcome of the design. The designed of mechanical system is consequently simulated by solidwork software. The intention of the above research is to create solutions in different ways of inservice inspection of integrity of Reactor.

Advanced In-Service Inspection Approaches Applied to the Phenix Fast Breeder Reactor

International Nuclear Information System (INIS)

Guidez, J.; Martin, L.; Dupraz, R.

2006-01-01

The safety upgrading of the Phenix plant undertaken between 1994 and 1997 involved a vast inspection programme of the reactor, the external storage drum and the secondary sodium circuits in order to meet the requirements of the defence-in-depth safety approach. The three lines of defence were analysed for every safety related component: demonstration of the quality of design and construction, appropriate in-service inspection and controlling the consequences of an accident. The in-service reactor block inspection programme consisted in controlling the core support structures and the high-temperature elements. Despite the fact that limited consideration had been given to inspection constraints during the design stage of the reactor in the 1960's, as compared to more recent reactor projects such as the European Fast Reactor (EFR), all the core support line elements were able to be inspected. The three following main operations are described: Ultrasonic inspection of the upper hangers of the main vessel, using small transducers able to withstand temperatures of 130 deg. C, Inspection of the conical shell supporting the core dia-grid. A specific ultrasonic method and a special implementation technique were used to control the under sodium structure welds, located up to several meters away from the scan surface. Remote inspection of the hot pool structures, particularly the core cover plug after partial sodium drainage of the reactor vessel. Other inspections are also summarized: control of secondary sodium circuit piping, intermediate heat exchangers, primary sodium pumps, steam generator units and external storage drum. The pool type reactor concept, developed in France since the 1960's, presents several favourable safety and operational features. The feedback from the Phenix plant also shows real potential for in-service inspection. The design of future generation IV sodium fast reactors will benefit from the experience acquired from the Phenix plant. (authors)

Periodic vehicle inspection (MOT). [previously: Periodic Vehicle Inspection of cars (MOT).

NARCIS (Netherlands)

2010-01-01

In the 1980s the periodic vehicle inspection (MOT) of various categories of vehicles was introduced in the Netherlands. This fact sheet will discuss the legal framework of this measure and the research carried out into its effects on road safety, also in an international context. For instance, the

Risk-based inspection in the context of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G., E-mail: soaresw@cdtn.br, E-mail: vasconv@cdtn.br, E-mail: egr@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

Risk-based inspection in the context of nuclear power plants

International Nuclear Information System (INIS)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G.

2015-01-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

NRC program of inspection and enforcement

International Nuclear Information System (INIS)

LeDoux, J.C.; Rehfuss, C.

1978-01-01

The Nuclear Regulatory Commission (NRC) regulates civilian uses of nuclear materials to ensure the protection of the public health and safety and the environment. The Office of Inspection and Enforcement (IE) develops and implements the inspection, investigation, and enforcement programs for the NRC. The IE conducts inspection programs for reactors under construction and in operation, nuclear industry vendors, fuel facilities and users of nuclear materials, and all aspects of the safeguarding of facilities and materials. Recently the IE began implementing a program that will place inspectors on site at nuclear power reactors and will provide for national appraisal of licensee performance and for an evaluation of the effectiveness of the inspection programs

Regulatory inspection of BARC facilities

International Nuclear Information System (INIS)

Rajdeep; Jayarajan, K.

2017-01-01

Nuclear and radiation facilities are sited, constructed, commissioned, operated and decommissioned, in conformity with the current safety standards and codes. Regulatory bodies follow different means to ensure compliance of the standards for the safety of the personnel, the public and the environment. Regulatory Inspection (RI) is one of the important measures employed by regulatory bodies to obtain the safety status of a facility or project and to verify the fulfilment of the conditions stipulated in the consent

Safety indicators in different time frames for the safety assessment of underground radioactive waste repositories. First report of the INWAC subgroup on principles and criteria for radioactive waste disposal

International Nuclear Information System (INIS)

1994-10-01

Principles and criteria for the disposal of long lived radioactive waste involve issues which go beyond those normally considered in the basic system of radiation protection. Safety criteria based on radiation risk an dose limitation are commonly accepted as the principal basis for judging the acceptability of radioactive waste repositories. However, the long time-scales of interest mean that risks or doses to future individuals cannot be predicted with any certainty as they depend, amongst other things, on assumptions made about the integrity of the waste matrix, the man-made barriers, the geology, the dispersion of groundwater, etc. and future biospheric conditions and human lifestyles. This document discusses various safety indicators and their applicability in the context of the future time-scales which have to be considered in safety assessments of deep geologic repositories. Quantitative assessment are based on numerical estimates of consequences (e.g. risk or dose) and the assessment is made against numerical criteria. Qualitative assessments are based on estimates of hazard potential which are not exact or absolute and the assessment is made against criteria which may not be numerically defined. Examples of such criteria are the convenient reference values provided by levels of radionuclides in the natural environment. Refs, figs and tabs

Multiobjective optimization of the inspection intervals of a nuclear safety system: A clustering-based framework for reducing the Pareto Front

International Nuclear Information System (INIS)

Zio, E.; Bazzo, R.

2010-01-01

In this paper, a framework is developed for identifying a limited number of representative solutions of a multiobjective optimization problem concerning the inspection intervals of the components of a safety system of a nuclear power plant. Pareto Front solutions are first clustered into 'families', which are then synthetically represented by a 'head of the family' solution. Three clustering methods are analyzed. Level Diagrams are then used to represent, analyse and interpret the Pareto Fronts reduced to their head-of-the-family solutions. Two decision situations are considered: without or with decision maker preferences, the latter implying the introduction of a scoring system to rank the solutions with respect to the different objectives: a fuzzy preference assignment is then employed to this purpose. The results of the application of the framework of analysis to the problem of optimizing the inspection intervals of a nuclear power plant safety system show that the clustering-based reduction maintains the Pareto Front shape and relevant characteristics, while making it easier for the decision maker to select the final solution.

A study on safety concept and criteria of site release of nuclear installation proposed by international organizations and adopted in decommissioning practices

International Nuclear Information System (INIS)

Enokido, Yuji; Miyasaka, Yasuhiko; Ishikawa, Hironori

2008-01-01

Regulatory systems and safety criteria of site release of nuclear installation proposed by international organizations such as IAEA and applied in decommissioning in domestic and foreign countries have been studied, in order to avail them to deliberate the relevant domestic regulation and guides. In addition, the applicability of the proposal and practices to domestic legislation have been discussed. Regarding the national safety criteria, the annual individual dose constraint is optimized between 10 μSv and 300 μSv after recommendation and/or guides of IAEA etc. Unconditional release should be achieved, but the conditional and/or partial site release are possible under the same safety criteria to make the selection flexible for licensees. (author)

Inspection and test planning

International Nuclear Information System (INIS)

Miller, T.

1980-01-01

Purpose of Quality Plan - arrangement of all necessary tests or inspections as far as possible filted to certain components or systems. Subject of Quality Plan - precise determination of tests or inspections and - according to the actual safety significance - the certificates to be done. Disposition of Quality Plan - accommodation of tests to the actual state of fabrication. Application of Quality Plan - to any component or system that is regarded. Supervision of Employment - by authorized personnel of manufacturer, customer or authority providing exact employment of quality plan. Overservance of Instructions - certificates given by authorized personnel. (orig./RW)

The role of the nuclear safety regulator

International Nuclear Information System (INIS)

Mellado, I.

2007-01-01

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

77 FR 75118 - National Advisory Committee on Meat and Poultry Inspection

Science.gov (United States)

2012-12-19

... Advisory Committee on Meat and Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION... Inspection Service (FSIS) is announcing a meeting of the National Advisory Committee on Meat and Poultry... strengthening Agency verification activities and guidance concerning sanitary dressing and antimicrobial...

The KNICS approach for verification and validation of safety software

International Nuclear Information System (INIS)

Cha, Kyung Ho; Sohn, Han Seong; Lee, Jang Soo; Kim, Jang Yeol; Cheon, Se Woo; Lee, Young Joon; Hwang, In Koo; Kwon, Kee Choon

2003-01-01

This paper presents verification and validation (VV) to be approached for safety software of POSAFE-Q Programmable Logic Controller (PLC) prototype and Plant Protection System (PPS) prototype, which consists of Reactor Protection System (RPS) and Engineered Safety Features-Component Control System (ESF-CCS) in development of Korea Nuclear Instrumentation and Control System (KNICS). The SVV criteria and requirements are selected from IEEE Std. 7-4.3.2, IEEE Std. 1012, IEEE Std. 1028 and BTP-14, and they have been considered for acceptance framework to be provided within SVV procedures. SVV techniques, including Review and Inspection (R and I), Formal Verification and Theorem Proving, and Automated Testing, are applied for safety software and automated SVV tools supports SVV tasks. Software Inspection Support and Requirement Traceability (SIS-RT) supports R and I and traceability analysis, a New Symbolic Model Verifier (NuSMV), Statemate MAGNUM (STM) ModelCertifier, and Prototype Verification System (PVS) are used for formal verification, and McCabe and Cantata++ are utilized for static and dynamic software testing. In addition, dedication of Commercial-Off-The-Shelf (COTS) software and firmware, Software Safety Analysis (SSA) and evaluation of Software Configuration Management (SCM) are being performed for the PPS prototype in the software requirements phase

Implementation of in-service inspection program for HANARO

International Nuclear Information System (INIS)

Wu, J.S.; Park, Y.C.; Cho, Y.G.; Jun, B.J.

2001-01-01

HANARO, a 30 MW multi-purpose research reactor in Korea has been successfully in operation for 6 years since its initial criticality in February 1995. It is mainly used for the research areas including nuclear fuel and material irradiation tests, radioisotope production, neutron beam application, neutron activation analysis and neutron transmutation doping. HANARO was designed to perform for at least 20 years under full power operating condition. It is expected that the actual reactor lifetime will be much more than the design lifetime, due to a safety reassessment based on realistic data, preventive maintenance and appropriate in-service inspections (ISI). Since ageing may affect the overall safety of the reactor facility, it is needed to detect and evaluate the effects on aged components and systems related to safety. During the lifetime of the reactor, structures, systems and components are subjected to environmental conditions of stress, temperature and irradiation that may lead to changes in the material properties and could result in unexpected failures. Evidence of ageing problems appears progressively. A rigorous inspection and visual examination based on a periodic ISI program should be established. It is desirable that the ageing surveillance activities is scheduled as early as possible and continued throughout the operating life of the reactor. An inspection plan for safety related structures, systems and components subjected to the ageing conditions is requested by the regulatory body to assess the safety status of reactor facility. A long-term ISI program for HANARO has been established for safety-related systems and components in the context of the overall reactor ageing management. The objective of this paper is to describe the ISI program and the result of the visual inspection as the first ISI. (orig.)

Safety criteria for the next generation of European reactors

International Nuclear Information System (INIS)

Dominguez Bautista, M.T.

1995-01-01

For the next generation of reactors, European companies operating in the electricity sector have drawn up a document called European Utilities Requirement (EUR), which sets out the requirements to be met by the designers of future reactors. The main objective of these new requirements is to increase the safety in existing reactors, making good use of operating experience available and the technological developments of the last decade. This paper offers an in-depth analysis of the most significant characteristics, describing how the EUR requirements have been prepared and how they are being implemented by the designers. Areas covered are: - Combining deterministic and probabilistic criteria - Automation of control systems - Design extension for severe accidents - Containment design - Emergency plans - Autonomy versus manual operation

Extension of the service life and improvement of safety of near surface repositories of the type 'Radon'

International Nuclear Information System (INIS)

Rozdyalouvskaya, L.

2004-01-01

The paper discusses the application and implementation of the new international principles and approaches for the radioactive waste management in the existing 'Radon' type storage facilities. The characteristics of the 'Radon' facilities, their licensing, the inspection program as well as the technical assessment of the facility Puspokszilagy (Hungary) are presented. Other aspects of the safety of the facilities such as measures for modernisation implemented in some countries (Latvia, Belarus, Bulgaria and other), intervention criteria, and long term safety are also discussed

32 CFR 636.33 - Vehicle safety inspection criteria.

Science.gov (United States)

2010-07-01

... a muffler in good working order and in constant operation. (10) Mirror—every vehicle, from which the... obstructed by any sign, poster, or other nontransparent material. Windshields and rear windows will not have...

The Preliminary Review for the Cross-Cutting Issues in the US Nuclear Regulatory Inspection Framework

International Nuclear Information System (INIS)

Lee, Yong Suk; Jung, Dae Wook; Cho, Nam Chul

2008-01-01

The research for the development of risk-informed and performance-based regulatory inspection is ongoing in KINS. In the USNRC, the cross-cutting issue is one of the main components the risk-informed and performance-based regulatory inspection process as shown in figure 1, which is named as ROP (Reactor Oversight Process). The following three cross-cutting areas implicitly affect all of the safety cornerstones in ROP. In this study, the preliminary review for the inspection practices of cross-cutting issues in the US and Korean safety regulatory system were performed. The elements of the cross-cutting issues were recently modified to emphasize the importance of safety culture, and the graded approach was applied for the inspection of cross-cutting issues in USNRC. The graded approach for the inspection of cross-cutting issues will be also needed to Korean safety regulatory system in the future

The Preliminary Review for the Cross-Cutting Issues in the US Nuclear Regulatory Inspection Framework

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Suk; Jung, Dae Wook [Future and Challenges Inc., Seoul (Korea, Republic of); Cho, Nam Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2008-10-15

The research for the development of risk-informed and performance-based regulatory inspection is ongoing in KINS. In the USNRC, the cross-cutting issue is one of the main components the risk-informed and performance-based regulatory inspection process as shown in figure 1, which is named as ROP (Reactor Oversight Process). The following three cross-cutting areas implicitly affect all of the safety cornerstones in ROP. In this study, the preliminary review for the inspection practices of cross-cutting issues in the US and Korean safety regulatory system were performed. The elements of the cross-cutting issues were recently modified to emphasize the importance of safety culture, and the graded approach was applied for the inspection of cross-cutting issues in USNRC. The graded approach for the inspection of cross-cutting issues will be also needed to Korean safety regulatory system in the future.

In-service inspections of V-230 reactor

International Nuclear Information System (INIS)

Prepechal, J.

1984-01-01

It is stated that despite certain constraints the configuration of the WWER-440 is such that it allows to make in-service inspections on a fully satisfactory scale. Three factors are discussed whose existence is necessary for the implementation of in-service inspections. The program defining the scale of inspections is satisfactory with regard to the safety and reliability of reactor operation. Its further development must result in reducing time consumption and radiation burden of personnel. Regulations for the implementation and evaluation of inspections represent the weakest link in the system of in-service inspections. At present, various organizations are dealing with the said problem within international cooperation. Equipment for in-service inspections of WWER-440 reactors is relatively good. The most important knowledge is summed up gained from the ten pre-service and in-service inspections of reactors of this type made so far. (Z.M.)

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

Science.gov (United States)

2016-02-01

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

Solving the Problem of Multiple-Criteria Building Design Decisions with respect to the Fire Safety of Occupants: An Approach Based on Probabilistic Modelling

Directory of Open Access Journals (Sweden)

Egidijus Rytas Vaidogas

2015-01-01

Full Text Available The design of buildings may include a comparison of alternative architectural and structural solutions. They can be developed at different levels of design process. The alternative design solutions are compared and ranked by applying methods of multiple-criteria decision-making (MCDM. Each design is characterised by a number of criteria used in a MCDM problem. The paper discusses how to choose MCDM criteria expressing fire safety related to alternative designs. Probability of a successful evacuation of occupants from a building fire and difference between evacuation time and time to untenable conditions are suggested as the most important criteria related to fire safety. These two criteria are treated as uncertain quantities expressed by probability distributions. Monte Carlo simulation of fire and evacuation processes is natural means for an estimation of these distributions. The presence of uncertain criteria requires applying stochastic MCDM methods for ranking alternative designs. An application of the safety-related criteria is illustrated by an example which analyses three alternative architectural floor plans prepared for a reconstruction of a medical building. A MCDM method based on stochastic simulation is used to solve the example problem.

Determination of performance criteria of safety systems in a nuclear power plant via simulated annealing optimization method

International Nuclear Information System (INIS)

Jung, Woo Sik

1993-02-01

This study presents and efficient methodology that derives design alternatives and performance criteria of safety functions/systems in commercial nuclear power plants. Determination of design alternatives and intermediate-level performance criteria is posed as a reliability allocation problem. The reliability allocation is performed for determination of reliabilities of safety functions/systems from top-level performance criteria. The reliability allocation is a very difficult multi objective optimization problem (MOP) as well as a global optimization problem with many local minima. The weighted Chebyshev norm (WCN) approach in combination with an improved Metropolis algorithm of simulated annealing is developed and applied to the reliability allocation problem. The hierarchy of probabilistic safety criteria (PSC) may consist of three levels, which ranges from the overall top level (e.g., core damage frequency, acute fatality and latent cancer fatality) through the interlnediate level (e.g., unavailiability of safety system/function) to the low level (e.g., unavailability of components, component specifications or human error). In order to determine design alternatives of safety functions/systems and the intermediate-level PSC, the reliability allocation is performed from the top-level PSC. The intermediated level corresponds to an objective space and the top level is related to a risk space. The reliability allocation is performed by means of a concept of two-tier noninferior solutions in the objective and risk spaces within the top-level PSC. In this study, two kinds of towtier noninferior solutions are defined: intolerable intermediate-level PSC and desirable design alternatives of safety functions/systems that are determined from Sets 1 and 2, respectively. Set 1 is obtained by maximizing simultaneously not only safety function/system unavailabilities but also risks. Set 1 reflects safety function/system unavailabilities in the worst case. Hence, the

Safety, feasibility, and acceptability of visual inspection with acetic acid and immediate treatment with cryotherapy in rural Laos.

Science.gov (United States)

Phongsavan, Keokedthong; Phengsavanh, Alongkone; Wahlström, Rolf; Marions, Lena

2011-09-01

To assess the safety, acceptability, and feasibility of visual inspection with acetic acid (VIA) followed by immediate treatment with cryotherapy as a single-visit approach for the prevention of cervical cancer among women in rural Laos. In 2009, women from 2 provinces in Laos were recruited for cervical cancer screening using VIA. If the inspection of the cervix showed a well-defined acetowhite lesion close to the os, immediate cryotherapy was offered. Of the 1926 women who were included, 134 (7.0%) tested positive on VIA. Of these, 113 (84.3%) underwent immediate cryotherapy and none declined treatment. One year after immediate cryotherapy, 77 (68.1%) women returned for a follow-up assessment and 68 (88.3%) were now VIA-negative. There was no report of a major complication during or after treatment. The acceptance of both VIA and cryotherapy was high. Visual inspection with acetic acid is a simple test that requires minimal infrastructure and expenditure. Integration of VIA with cryotherapy at the primary care level may constitute a feasible program for the prevention of cervical cancer in Laos. Copyright © 2011 International Federation of Gynecology and Obstetrics. Published by Elsevier Ireland Ltd. All rights reserved.

Regulatory inspections in nuclear plants in the field of radiation protection

International Nuclear Information System (INIS)

Hort, M.; Fuchsova, D.

2014-01-01

State Office for Nuclear Safety executes state administration and performs inspections at peaceful use of nuclear energy and ionizing radiation in the field of radiation protection and nuclear safety. Inspections on radiation protection at nuclear power plants are secured by inspectors of the Department of Radiation Protection in Fuel Cycle, who work at the Regional centre Brno and Ceske Budejovice. (authors)

77 FR 13512 - National Advisory Committee on Meat and Poultry Inspection

Science.gov (United States)

2012-03-07

... Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION: Notice of committee meeting... Committee Act, that the National Advisory Committee on Meat and Poultry Inspection (NACMPI) will hold a public meeting on Wednesday, March 21, 2012, to discuss the proposed rule on the Modernization of Poultry...

The MCNP simulation of the X-ray leakage of X-ray security inspection equipment

International Nuclear Information System (INIS)

Wang Kai; Liu Bin; Hu Wenchao; Zhao Wei

2011-01-01

Objective: To simulate the radiation leakage of the X-ray security inspection equipment used in the subways stations. Methods: We use the MCNP4C code to simulate the X-ray leakage of the equipment during the working process. Result: the biggest amount of radiation received by the body is 8.26 μSv/a, however, if the Lead screens of the X-ray security equipment is intact, the amount of radiation received by the body is only 0.0727 μSv/a. The final. Conclusions: When the baggage get in /out the X-ray security inspection equipment, the gas in Lead screens was made, and then the amount of radiation received by human body increased; The amount of radiation received by the body is close to but still below 10 μSv/a which is the exemption criteria set by the 'safety of radiation sources of ionizing radiation protection and basic standards'(GB18871-2002). (authors)

9 CFR 381.209 - Returned United States inspected and marked poultry products; exemption.

Science.gov (United States)

2010-01-01

... PRODUCTS INSPECTION AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Returned United States inspected and marked poultry products; exemption. 381.209 Section 381.209 Animals and Animal Products FOOD SAFETY AND...

Estimated Incident Cost Savings in Shipping Due to Inspections

NARCIS (Netherlands)

S. Knapp (Sabine); G.E. Bijwaard (Govert); C. Heij (Christiaan)

2010-01-01

textabstractThe effectiveness of safety inspections has been analysed from various angles, but until now, relatively little attention has been given to translate risk reduction into incident cost savings. This paper quantifies estimated cost savings based on port state control inspections and

Machine vision system for remote inspection in hazardous environments

International Nuclear Information System (INIS)

Mukherjee, J.K.; Krishna, K.Y.V.; Wadnerkar, A.

2011-01-01

Visual Inspection of radioactive components need remote inspection systems for human safety and equipment (CCD imagers) protection from radiation. Elaborate view transport optics is required to deliver images at safe areas while maintaining fidelity of image data. Automation of the system requires robots to operate such equipment. A robotized periscope has been developed to meet the challenge of remote safe viewing and vision based inspection. (author)

Validation of statistical assessment method for the optimization of the inspection need for nuclear steam generators

International Nuclear Information System (INIS)

Wallin, K.; Voskamp, R.; Schmibauer, J.; Ostermeyer, H.; Nagel, G.

2011-01-01

The cost of steam generator inspections in nuclear power plants is high. A new quantitative assessment methodology for the accumulation of flaws due to stochastic causes like fretting has been developed for cases where limited inspection data is available. Additionally, a new quantitative assessment methodology for the accumulation of environment related flaws, caused e.g. by corrosion in steam generator tubes, has been developed. The method that combines deterministic information regarding flaw initiation and growth with stochastic elements connected to environmental aspects requires only knowledge of the experimental flaw accumulation history. The method, combining both types of flaw types, provides a complete description of the flaw accumulation and there are several possible uses of the method. The method can be used to evaluate the total life expectancy of the steam generator and simple statistically defined plugging criteria can be established based on flaw behaviour. This way the inspection interval and inspection coverage can be optimized with respect to allowable flaws and the method can recognize flaw type subsets requiring more frequent inspection intervals. The method can also be used to develop statistically realistic safety factors accounting for uncertainties in inspection flaw sizing and detection. The statistical assessment method has been showed to be robust and insensitive to different assessments of plugged tubes. Because the procedure is re-calibrated after each inspection, it reacts effectively to possible changes in the steam generator environment. Validation of the assessment method is provided for real steam generators, both in the case of stochastic damage as well as environment related flaws. (authors)

Regulatory inspection of nuclear power plants in NEA member countries

International Nuclear Information System (INIS)

Gronow, W.S.; Ilani, O.

1977-01-01

The increasing use of nuclear power and public interest in the safety controls led to the proposal by the sub-Committe on Licensing of the NEA Committee on the Safety of Nuclear Installations for a specialist meeting on regulatory inspection practices. This report which was prepared at the request of the sub-Committee to assist in the exchange of views and experience at the meeting reviews the response to a questionnaire on the systems employed, the scope and objectives and the effort involved in regulatory inspection throughout all stages of the life of a nuclear power plant. Other aspects of regulatory inspection activities are discussed including documentation, procedures for changes in technical specification and modifications to plant, powers and duties of regulatory inspection personnel and actions to be taken in the event of an accident or emergency. The report concludes with some comments on those aspects of regulatory inspection practices where further information and an exchange of experience might prove to be beneficial to Member countries. (author)

78 FR 77643 - National Advisory Committee of Meat and Poultry Inspection

Science.gov (United States)

2013-12-24

... Advisory Committee of Meat and Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION... of the National Advisory Committee on Meat and Poultry Inspection (NACMPI). The Committee is being... label on meat and poultry packages. With this input, the Agency will consider whether or not the current...

Preliminary safety criteria for organic watch list tanks at the Hanford site

International Nuclear Information System (INIS)

Webb, A.B.; Stewart, J.L.; Turner, O.A.; Plys, M.G.; Malinovic, B.; Grigsby, J.M.; Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J.

1995-11-01

Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended

Preliminary safety criteria for organic watch list tanks at the Hanford site

Energy Technology Data Exchange (ETDEWEB)

Webb, A.B.; Stewart, J.L.; Turner, O.A. [Westinghouse Hanford Co., Richland, WA (United States); Plys, M.G.; Malinovic, B. [Fauske and Associates, Inc., Burr Ridge, IL (United States); Grigsby, J.M. [G & P Consulting, Inc. (United States); Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J. [Pacific Northwest Lab., Portland, OR (United States)

1995-11-01

Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended.

Some considerations on the safety of nuclear ships

International Nuclear Information System (INIS)

Kuramoto, Masaaki

1978-01-01

For realizing the practical utilization of nuclear merchant ships, it is essential to gain their acceptance by maritime countries on an equal footing with conventional vessels, and to have the administrative procedures for their admission simplified. This, however cannot be expected to be attained overnight, and progressive measures will have to be adopted, to approach the ultimate goal step by step. The first step should be to demonstrate the safety of nuclear propulsion, for which nuclear ships must accumulate their mileages of safe service. The second important step is to simplify the procedures demanded of nuclear ships for access to ports, through the establishment of international safety standards and design criteria, the enforcement of safety measures covering the entrance of nuclear ships into ports, and the assurance of safety in he repair, inspection and refuelling operations of these ships. Among these measures, the considerations relevant to port entry are the subject of vital interest to both ship operators and port authorities

Inspection and repair of nuclear components

International Nuclear Information System (INIS)

Lahner, K.; Poetz, F.

1993-01-01

Despite careful design, manufacturing and operation, some of the important safety-relevant components show deterioration with time. Because of activation and contamination of these components, their inspection and repair has to be performed with manipulators. Some sophisticated manipulators are described, built by ABB Reaktor and used for inspection, maintenance and repair of PWR steam generators, fuel alignment pins, core baffle former bolts and reactor pressure vessel head penetrations. (Z.S.) 7 figs

Nuclear energy generation and the safety criteria for Brazilian power plants

International Nuclear Information System (INIS)

Silva, Gustavo Brandão e

2016-01-01

The purpose of this paper is to show how the use of nuclear technology can help to diversify the national electricity matrix in a sustainable and efficient way. For this, an analysis of the current situation of the Brazilian electric sector will be made, exposing its fragilities and highlighting the advantages of the nuclear source as an alternative to integrate the necessary thermoelectric base to the reliable supply of electricity in the country. In addition, the objective of the work is to detail the process of exploiting atomic energy in Brazil from raw material mining, through the stages involving the manufacture of nuclear fuel, to the current operation and situation of Brazilian power plants. By taking the Angra 2 Nuclear Power Plant as a case study, the safety criteria adopted in its design and operation will be highlighted. Particular attention will also be given to the electric supply alternatives and to the active safety systems of the plant

Inspection practice and a role of TSO

International Nuclear Information System (INIS)

Janzekovic, H.

2010-01-01

Technical and Scientific Support Organisations (TSOs) are not only expert organisations helping operators to fulfil the legal obligations but they can perform at least five tasks related to regulatory authority activities. Namely, TSOs can be an expert support when preparing legislation or guidelines. They can provide specific technical service e.g. providing independent monitoring of radioactivity in the environment or monitoring of foodstuff. They can also provide valuable data to regulatory authorities because they follow the achievements of science and technologies i.e. they are familiar with best available techniques and technologies. In many cases TSOs can be a pool of future employees of regulatory authorities and TSOs are expert or technical support at on-site inspections. Involvement of TSOs in on-site inspections either foreseen inspections or interventions requires very well defined roles of all organisations involved. Regarding the experiences of the Slovenian Nuclear Safety Administration the involvement of TSOs in on-site inspections is very beneficial to all stakeholders and leads not only to less financial and other burdens posed on the owner of sources but also basic safety requirements are implemented efficiently. (author)

Radiographic inspection on offshore platforms

International Nuclear Information System (INIS)

Soares, Sergio Damasceno; Sperandio, Augusto Gasparoni

1994-01-01

One of the great challenges for non-destructive inspection is on offshore platforms, where safety is a critical issue. Inspection by gammagraphy is practically forbidden on the platform deck due to problems to personnel safety and radiological protection. Ir-192 sources are used and the risk of an accident with loss of radioisotope must be considered. It is unfeasible to use gammagraphy, because in case of an accident the rapid evacuation from the platform would be impossible. This problem does not occur when X-ray equipment is used as the radiation source. The limited practicality and portability of the X-ray equipment have prevented its use as a replacement for the gammagraphy. This paper presents the preliminary tests to see the viable use of radiographic tests with constant potential on offshore platforms. (author). 2 refs., 1 fig., 2 tabs, 3 photos

Determining prestressing forces for inspection of prestressed concrete containments

International Nuclear Information System (INIS)

1990-07-01

General Design Criterion 53, ''Provisions for Containment Testing and Inspection,'' of Appendix A, ''General Design Criteria for Nuclear Power Plants,'' to 10 CFR Part 50, ''Domestic Licensing of Production and Utilization Facilities,'' requires, in part, that the reactor containment be designed to permit (1) periodic inspection of all important areas and (2) an appropriate surveillance program. Regulatory Guide 1.35, ''Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures,'' describes a basis acceptable to the NRC staff for developing an appropriate inservice inspection and surveillance program for ungrouted tendons in prestressed concrete containment structures of light-water-cooled reactors. This guide expands and clarifies the NRC staff position on determining prestressing forces to be used for inservice inspections of prestressed concrete containment structures

1 CFR 17.3 - Criteria for emergency publication.

Science.gov (United States)

2010-01-01

... 1 General Provisions 1 2010-01-01 2010-01-01 false Criteria for emergency publication. 17.3..., AND PROCESSING OF DOCUMENTS FILING FOR PUBLIC INSPECTION AND PUBLICATION SCHEDULES Emergency Schedule § 17.3 Criteria for emergency publication. The emergency schedule is designed to provide the fastest...

A 3D printed smartphone optosensing platform for point-of-need food safety inspection.

Science.gov (United States)

Liu, Zhonggang; Zhang, Yali; Xu, Shujia; Zhang, Heng; Tan, Yixun; Ma, Chenming; Song, Rong; Jiang, Lelun; Yi, Changqing

2017-05-08

The deficiency in rapid and in-field detection methods and portable devices that are reliable, easy-to-use, and low cost, results in the difficulties to uphold the high safety standards in China. In this study, we introduce a rapid and cost-effective smartphone-based method for point-of-need food safety inspection, which employs aptamer-conjugated AuNPs as the colorimetric indicator, and a battery-powered optosensing accessory attached to the camera of a smartphone for transmission images capture. A user-friendly and easy-to-use Android application is developed for automatic digital image processing and result reporting. Streptomycin (STR) is selected as the proof-of-concept target, and its specific quantitation can be realized with a LOD of 12.3 nM (8.97 μg kg -1 ) using the reported smartphone-based method. The quantitation of STR in honey, milk and tap water confirm the reliability and applicability of the reported method. The extremely high acceptance of smartphone in remote and metropolitan areas of China and ease-of-use of the reported method facilitate active food contaminant and toxicant screening, thus making the implementation of the whole food supply chain monitoring and surveillance possible and hence significantly improving the current Chinese food safety control system. Copyright © 2017 Elsevier B.V. All rights reserved.

Probabilistic safety assessment of the Fugen NPS

International Nuclear Information System (INIS)

Sotsu, Masutake; Iguchi, Yukihiro; Mizuno, Kouichi; Sato, Shinichirou; Shimizu, Miwako

1999-01-01

We performed a probabilistic safety assessment (PSA) on the Fugen NPS. The main topic of assessment was internal factors. We assessment core damage frequency (level 1 PSA) and containment damage frequency (level 2 PSA) during rated operation, and core damage frequency during shutdown (PSA during shutdowns). Our assessment showed that the core damage frequency of Fugen is well below the IAEA criteria for existing plants, that the conditional containment damage during shutdown is almost the target value of 0.1, and that the core damage frequency during shutdown is almost the same as that assessed during operation. These results confirm that the Fugen plant maintains a sufficient safety margin during shutdowns for regular inspections and for refueling. We developed and verified the effectiveness of an accident management plan incorporating the results of the assessment. (author)

Statement of the IRSN on the safety re-examination assessment made by EDF within the frame of the third decennial inspection of the 900 MW reactors

International Nuclear Information System (INIS)

2008-01-01

The IRSN (the French Institute of Radioprotection and Nuclear Safety) here presents an assessment of the studies performed by EDF within the frame of the safety re-examination associated to the third decennial inspections of the 900 MW reactors, and of the modifications resulting from these studies with respect to the originally defined objectives of this re-examination. The aim of this report is to allow the ASN (Autorite de Surete Nucleaire, the Nuclear Safety Authority) stating the 900 MW reactor ability to carry on their operation until the fourth decennial inspections. Different themes and studies are assessed: internal and external aggressions (flooding, explosions, fire, seismic control, and climatic aggressions), accident assessments and their radiological consequences (failure of various components, the performing of probabilistic studies, confining procedures, structures and devices, etc.), operation and design of various systems and of civil engineering works. Several documents or extracts of official reports are given in appendix, expressing notably various recommendations on the here-above topics

Promoting transparency: The Korean national inspection experience

International Nuclear Information System (INIS)

Kim, B.K.

1999-01-01

The Republic of Korea started the LAMA full-scope safeguards inspection with the TRIGA research reactor in 1976 when the nuclear industry was at its infancy. Over two decades of rapid economic growth was propelled by stable supply of electricity, substantially from nuclear energy. Today nearly half of the nations electricity comes from sixteen operating nuclear power plants (12 LWRs + 4 OLRs). Total number of facilities under IAEA inspection reaches 30 where the Agency conducts about 400 PDIs annually. Within the last decade, nuclear transparency in Korea has transformed into the international norm primarily from the needs of rapidly expanding domestic nuclear program. In addition, possibility of North/South mutual inspection helped initiate the national inspection regime in addition to the IAEA inspection. The Technology Center for Nuclear Control was established at KAERI in 1994 in order to maintain the nation's nuclear verification expertise in support of the Korean government. National inspections have been carried out simultaneously with the IAEA inspection since 1997 with trial facilities, and all domestic facilities are being inspected from this year. Necessary legal framework and working procedures were developed and field-tried for LWRs, OLRs, fuel fabrication plants and research reactor facilities. Although the inspection equipment and technology along with the safeguards criteria are quite similar to those of the Agency, it is essential to maintain the independent conclusion capabilities between IAEA and the national authority. Substantial improvements in the IAEA safeguards inspection goal attainments since 1997 are credited to the increasing safeguards awareness among operators and SSAC. Further work is necessary to develop the evaluation criteria based on the field inspection results to meet the national inspection goals. The Korean Government signed the Additional Protocol with IAEA on June, 1999 after much deliberation since it involves facilities

Improvement of foundation for inspection

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Japan Nuclear Energy Safety Organization has been carrying out improvement of inspection system for nuclear plants in Japan since 2003FY. The new inspection system was introduced into nuclear power plants in{sub -}2008FY. In this project, improvement of comprehensive plant performance assessment and management tool for the new inspection system are developed. In 2012FY, a trend analysis method of the plant performance was developed with reference to the IAEA literature. And the trend analysis was tried based on the results of the comprehensive plant performance assessment of all domestic plants except Fukushima-Daiichi Nuclear Power Station. In addition, the teaching materials for QMS training guideline were made. And improvement of a quality management system evaluation support tool was performed. (author)

Improvement of foundation for inspection

International Nuclear Information System (INIS)

2013-01-01

Japan Nuclear Energy Safety Organization has been carrying out improvement of inspection system for nuclear plants in Japan since 2003FY. The new inspection system was introduced into nuclear power plants in - 2008FY. In this project, improvement of comprehensive plant performance assessment and management tool for the new inspection system are developed. In 2012FY, a trend analysis method of the plant performance was developed with reference to the IAEA literature. And the trend analysis was tried based on the results of the comprehensive plant performance assessment of all domestic plants except Fukushima-Daiichi Nuclear Power Station. In addition, the teaching materials for QMS training guideline were made. And improvement of a quality management system evaluation support tool was performed. (author)

TIS General Safety Group Annual Report 2000

CERN Document Server

Weingarten, W

2001-01-01

This report summarises the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division (TIS) during the year 2000, and the results obtained. The different topics in which the Group is active are covered: general safety inspections and ergonomy, electrical, chemistry and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

Relative hazard potential: the basis for definition of safety criteria for fast reactors

International Nuclear Information System (INIS)

Cave, L.; Ilberg, D.

1977-02-01

One of the main safety criteria to be met for larger thermal reactors is that the probability of exceeding the dose limits imposed by 10 CRF 100 should not be greater than 10 per reactor year. The potential hazard presented by a fast reactor could be substantially greater than that due to an LWR. The potential for harm of a reactor system may be judged by the effects which would arise from a severe accident. Several different types of effects may be considered: number of latent fatal cancers; number of deaths due to acute effects; number of thyroid tumors or nodules; extent of property damage; and genetic effects. Analytical methods for comparison are employed in this paper. A second important parameter reviewed in this report is the radio-toxicity attributed to the various isotopes. It was found that the worst conceivable accident to a 1000 MW(e) fast reactor would lead to effects on health greater by an order of magnitude than the worst accident usually considered for an LWR. Therefore, some reconsideration of the need for additional safety criteria for LMFBRs, as a guide to designers in relation to the control of the effects of very severe accidents, is desirable

Study on safety evaluation for unrestricted recycling criteria of radioactive waste from dismantling operation

International Nuclear Information System (INIS)

Yoshimori, Michiro; Ohkoshi, Minoru; Abe, Masayoshi

1995-01-01

The study on safety evaluation was done, under contracting with the Science and Technology Agency, for recycling scrap metal arising from dismantling of reactor facilities. An object of this study is to contribute to the examination of establishing criteria and safety regulation for unrestricted recycling steel scrap. To define amount of market flow of iron material in Japan and the amount of radioactive waste generated from dismantling of reactor facilities, investigation had been carried out. On basis of these investigation results and data in several literature, individual doses to workers and to the members of the public have been calculated as well as collective doses. (author)

Guidelines for implementation of RCM on safety systems

International Nuclear Information System (INIS)

Kim, Tae Woon; Brijendra Singh.

1996-04-01

Reliability Centered Maintenance (RCM) methodology was originally developed by the commercial airlines industry in the early 1960s for identifying applicable and effective preventive maintenance tasks and as currently used in nuclear power industry. Effective maintenance of the systems at a nuclear power plant (NPP) is essential for its safe and reliable operation. Reliability Centered Maintenance at NPP is the program to assure that plant systems remain within an original design criteria and are not adversely affected during the plant life time. The aim of this report is to provide the guidelines to implement the RCM approach on NPP safety systems. Safety systems are usually standby and therefore, we need to periodically detect and repair failures that may have occurred since the previous activation or inspection the equipment. The RCM guidelines are intended to help identify the failure modes and related root causes and then decide the maintenance policies to achieve the high level of safety and reliability. The RCM is intended to improve or maintain high levels of system reliability and plant availability. Since the reliability of plant systems will be improved, the plant safety correspondingly will be increased. Another goal of RCM is to optimize the maintenance and surveillance tasks such that the overall level of resources required to accomplish essential tasks is kept to minimum. RCM also strives to eliminate unnecessary corrective maintenance and to select yet most cost-effective approach to maintenance, testing and inspection for system components. 9 refs. (Author) .new

Validated automated ultrasonic inspections of the Sizewell 'B' reactor pressure vessel

International Nuclear Information System (INIS)

Dikstra, B.J.; Farley, J.M.

1992-01-01

Automated ultrasonic inspection was applied extensively during manufacture of the RPV for Sizewell 'B'. This was an important element of the safety case presented at the Sizewell 'B' public enquiry. This requirement reflected concern in the United Kingdom as to the effectiveness and reliability of ultrasonic inspections. By applying automated inspections in addition to the manual ultrasonic inspection carried out by the vessel manufacturer, the overall reliability of the inspection of the vessel would be considerably enhanced. The automated inspections carried out in the manufacturer's workshops were termed 'automated shop inspections' (ASIs). The ASIs were carried out in two contracts: the first to inspect the component forgings of the RPV, the second to inspect the pressure retaining welds. (author)

LMFBR safety criteria: cost-benefit considerations under the constraint of an a priori risk criterion

International Nuclear Information System (INIS)

Hartung, J.

1979-01-01

The role of cost-benefit considerations and a priori risk criteria as determinants of Core Disruptive Accident (CDA)-related safety criteria for large LMFBR's is explored with the aid of quantitative risk and probabilistic analysis methods. A methodology is described which allows a large number of design and siting alternatives to be traded off against each other with the goal of minimizing energy generation costs subject to the constraint of both an a priori risk criterion and a cost-benefit criterion. Application of this methodology to a specific LMFBR design project is described and the results are discussed. 5 refs

Assessment of safety culture: Changing regulatory approach in Hungary

International Nuclear Information System (INIS)

Ronaky, Jozsef; Toth, Andras

2002-01-01

Hungarian Atomic Energy Authority (HAEA) is changing its inspection practice and assessment methods of safety performance and safety culture in operating nuclear facilities. The new approach emphasises integrated team inspection of safety cornerstones and systematic assessment of safety performance of operators. (author)

Probabilistic safety analysis about the radiation risk for the driver in a fast-scan container/vehicle inspection system

International Nuclear Information System (INIS)

Li Junli; Zhu Guoping; Ming Shenjin; Cao Yanfeng

2008-01-01

A new Container/Vehicle Inspection System called fast-scan inspection system has been developed and used in some countries, which has a special advantage in scanning efficiency of 200 - 400 containers per hour. However, for its unique scanning mode, the fast-scan inspection system causes some worries about the radiation risk for the truck drivers, who will drive the container truck to pass through the scanning tunnel and might be exposed by the radiation beam in accidents. A PSA analysis, which has been widely used to evaluate the safety of nuclear power plant in the past, is presented here to estimate the probability of accidental exposure to the driver and evaluate the health risk. The fault tree and event tree analysis show that the probability of accidental exposure to the driver is pretty low and the main failure contributions are human errors and scanning control devices failures, which provides some recommendations for the further improvement about this product. Furthermore, on the basic of ICRP No.60 and 76 reports, the health risk to the truck driver is only about 4.0x10 -14 /a. Compared with the exempt level of 5x10 -7 /a, it can be concluded that the fast-scan system is safe enough for the truck driver. (author)

An effective technique for the software requirements analysis of NPP safety-critical systems, based on software inspection, requirements traceability, and formal specification

International Nuclear Information System (INIS)

Koo, Seo Ryong; Seong, Poong Hyun; Yoo, Junbeom; Cha, Sung Deok; Yoo, Yeong Jae

2005-01-01

A thorough requirements analysis is indispensable for developing and implementing safety-critical software systems such as nuclear power plant (NPP) software systems because a single error in the requirements can generate serious software faults. However, it is very difficult to completely analyze system requirements. In this paper, an effective technique for the software requirements analysis is suggested. For requirements verification and validation (V and V) tasks, our technique uses software inspection, requirement traceability, and formal specification with structural decomposition. Software inspection and requirements traceability analysis are widely considered the most effective software V and V methods. Although formal methods are also considered an effective V and V activity, they are difficult to use properly in the nuclear fields as well as in other fields because of their mathematical nature. In this work, we propose an integrated environment (IE) approach for requirements, which is an integrated approach that enables easy inspection by combining requirement traceability and effective use of a formal method. The paper also introduces computer-aided tools for supporting IE approach for requirements. Called the nuclear software inspection support and requirements traceability (NuSISRT), the tool incorporates software inspection, requirement traceability, and formal specification capabilities. We designed the NuSISRT to partially automate software inspection and analysis of requirement traceability. In addition, for the formal specification and analysis, we used the formal requirements specification and analysis tool for nuclear engineering (NuSRS)

Safety criteria for the future LMFBR's in France and main safety issues for the rapide 1500 project

International Nuclear Information System (INIS)

Justin, F.; Natta, M.; Orzoni, G.

1985-04-01

The main safety criteria for future LMFBR in France and the related issues for the RAPIDE 1500 project are presented and discussed. The evolutions with respect to SUPERPHENIX options and requirements are emphasized, in particular for the concerns of the prevention of core melt accidents, fuel damage limits and related required performances of the protection system, since one main option is not to consider whole core melt accidents in the containment design. One shall also point out the advantages of some mitigating features which were nevertheless added in the containment design, although without any explicit consideration for core melt accidents

Preventing degradation and in-service inspection of NPP steam generator

International Nuclear Information System (INIS)

Ding Xunshen

1999-01-01

The author describes the degradation of steam generator tubes in initial operating stage of France NPP. The author emphatically presents the preventive measures to tackle degradation and In-service inspection of Daya Bay NPP 1 unit as a guarantee of safety operation, including secondary side water chemistry monitoring and controlling, leakage rate monitoring, eddy-current inspection, mechanical cleaning, cleanliness inspection, foreign objects removal and etc

9 CFR 590.920 - Importer to make application for inspection of imported eggs and egg products.

Science.gov (United States)

2010-01-01

... inspection of imported eggs and egg products. 590.920 Section 590.920 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE EGG PRODUCTS INSPECTION INSPECTION OF EGGS AND EGG PRODUCTS (EGG PRODUCTS INSPECTION ACT) Imports § 590.920 Importer to make application for inspection of...

49 CFR 192.241 - Inspection and test of welds.

Science.gov (United States)

2010-10-01

... NATURAL AND OTHER GAS BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Welding of Steel in Pipelines § 192.241 Inspection and test of welds. (a) Visual inspection of welding must be conducted by an individual qualified by appropriate training and experience to ensure that: (1) The welding is performed in accordance...

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

Science.gov (United States)

2015-06-01

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

Kartini reactor tank inspection using NDT method for safety improvement of the reactor operation

International Nuclear Information System (INIS)

Syarip; Sutondo, Tegas; Saleh, Chaerul; Nitiswati; Puradwi; Andryansah; Mudiharjo

2002-01-01

The inspection of Kartini reactor tank liner (TRK) by using Non Destructive Testing (NDT) methods to improve the reactor operation safety, have been done. The type of NDT used were: visual examination using an underwater camera and magnifier, replication survey using dental putty, hardness test using an Equotip D indentor, thickness test using ultrasonic probe, and dye penetrant test. The visual examination showed that the surface of TRK was in good condition. The hardness readings were considered to be consistent with the original condition of the tank and the slight hardness increase at the reactor core area consistent with the neutron fluence experienced -10 1 4 n/cm 2 . Results of ultrasonic thickness survey showed that in average the TRK thickness is between 5,0 mm - 6,5 mm, a low 2,1 mm thickness exists at the top of the TRK in the belt area (double layer aluminum plat, therefore do not influencing the safety ). The replica and dye penetrant test at the low thickness area and several suspected areas showed that it could be some defect from original manufacture. Therefore, it can be concluded that the TRK is still feasible for continued operation safely

Increasing for effectiveness of inspection of the use of radioactive substances well logging

International Nuclear Information System (INIS)

Hesty Rimadianny

2015-01-01

One of the utilization of nuclear power is the use of radioactive substances for well logging. To ensure the achievement of radiation safety and security in the use of radioactive substances for well logging activities BAPETEN carries out inspections in accordance with the mandate as sepulated in the Government Regulation No. 29 of 2008 on the Licensing Resource Utilization Ionizing Radiation and Nuclear Materials. Besides referring to the implementation of Government Regulation inspection also refers to BAPETEN Chairman Regulation No. 5 of 2009 on Radiation Safety in the Use of Radioactive material for well logging. In 2014, of 18 facilities inspected the most significant findings include the availability of equipment safety and security of radioactive substances, as well as the availability and suitability of documents and records of safety and security of radioactive substances for well logging activities. Based on these findings BAPETEN needs to make efforts to increase the effectiveness of inspections on the use of radioactive substances for well logging. Increasing the effectiveness of these inspections include a commitment for the frequency of well logging inspection, the number of qualified of inspectors in accordance with the established procedures and optimizing the law enforcement process which includes the application of administrative sanctions in the form of a written warning, license suspension, revocation until reporting to law enforcement. Besides, BAPETEN need to improve the effectiveness of outreach programs and legal guidance as a precaution in the long run. (author)

9 CFR 381.191 - Distribution of inspected products to small lot buyers.

Science.gov (United States)

2010-01-01

... small lot buyers. 381.191 Section 381.191 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE...; Exportation; or Sale of Poultry or Poultry Products § 381.191 Distribution of inspected products to small lot... small lot buyers (such as small restaurants), distributors or jobbers may remove inspected and passed...

Guidelines for evaluation of anchorage adequacy for safety-related equipment typically used on WWER-type NPPs

International Nuclear Information System (INIS)

Masopust, R.

1999-01-01

This report describes the criteria which should be met when the capacity evaluation of anchorage of safety related equipment is performed for the WWER type NPPs. It should be noted that these criteria were developed specifically for anchorage of WWER type equipment and components to the concrete or steel building structures and they cover different types of anchor bolts and other anchorage details which are typical just for the existing, constructed or reconstructed WWER type NPPs. The screening approach for verifying of equipment anchorage presented in this report is based on a combination of inspections, calculations, and engineering judgement

14 CFR 125.507 - Fuel tank system inspection program.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Fuel tank system inspection program. 125... Airworthiness and Safety Improvements § 125.507 Fuel tank system inspection program. (a) Except as provided in... fuel tank is installed under a field approval, before June 16, 2008, the certificate holder must submit...

14 CFR 91.1507 - Fuel tank system inspection program.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Fuel tank system inspection program. 91... Airworthiness and Safety Improvements § 91.1507 Fuel tank system inspection program. (a) Except as provided in... fuel tank is installed under a field approval, before June 16, 2008, the operator must submit to the...

Generic Reliability-Based Inspection Planning for Fatigue Sensitive Details

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard; Straub, Daniel; Faber, Michael Havbro

2005-01-01

of fatigue sensitive details in fixed offshore steel jacket platforms and FPSO ship structures. Inspection and maintenance activities are planned such that code based requirements to the safety of personnel and environment for the considered structure are fulfilled and at the same time such that the overall......The generic approach for planning of in-service NDT inspections is extended to cover the case where the fatigue load is modified during the design lifetime of the structure. Generic reliability-based inspection planning has been developed as a practical approach to perform inspection planning...... expected costs for design, inspections, repairs and failures are minimized. The method is based on the assumption of “no-finds” of cracks during inspections. Each fatigue sensitive detail is categorized according to their type of details (SN curves), FDF values, RSR values, inspection, repair and failure...

MIR: an in-service inspection device for Superphenix 1 vessels

International Nuclear Information System (INIS)

Asty, M.; Ceccato, S.; Lerat, B.; Viard, J.

1986-06-01

The main and safety vessels of SUPERPHENIX 1 were designed to allow in-service inspections. The remote controlled inspection device MIR was developed for this purpose. It allows both visual and ultrasonic examinations to be performed. Basically, MIR consists of a tetrahedral structure provided with four steering and traction wheels, two for each vessel. A computer assisted control system enables it to be driven to any position on either the main or safety vessels. Operating conditions are briefly reviewed and the main features of MIR presented

Strategy of Risk-Informed Inspection for Secondary Systems in NPPs

International Nuclear Information System (INIS)

Kim, So Young; Heo, Gyun Young

2012-01-01

Recently, unexpected accidents such as large-scale blackout have been occurred due to increasing demand of electricity. The unplanned trips have great influence over the economics although they rarely affect the safety of system. Because the cost for inspection and maintenance is limited, it is beneficial not only economically to take follow-up action in a timely manner to prevent plant trip but also in safety by protecting against the risk which is occurred from trip. In nuclear power plants (NPPs), the importance about risk-informed service such as inspection, maintenance and replacement is becoming on the rise. Risk-informed techniques such as in-service test, in-service inspection, design guide change and etc. are already used in nuclear field but these techniques are applied focusing on primary system for safety-related regulatory issues. It is needed to consider the optimization of inspection informed risk for entire plant including secondary system which is not applied enough. The study about risk-based inspection for boilers in thermal power field is in progress actively, but not for turbine cycle, which is similar with nuclear industry. Today, the most of inspections or tests for turbine cycle are time-based maintenance, being performed on time. It is required to perform condition-based maintenance by evaluating risk analyzing both of probability and consequence simultaneously about damage mechanisms that can be predicted by equipment or devices configuring the secondary system. Probability of failure (POF) is analyzed in terms of materials' ageing mechanisms, but consequence of failure (COF) should be evaluated in terms of thermohydraulic condition then it is needed to check power loss and period of maintenance. This paper is going to propose the idea to quantify the consequence of failure using the fault tree and simulation for secondary system, and propose quantitative risk-informed inspection by these approaches

Risk based inspection experience from the European chemical- and petrochemical industries

International Nuclear Information System (INIS)

Kristensen, Hans; Jeppesen, Leif; Larsen, Bjarne; Kim, Na Yon

2001-01-01

As an inspection vendor with 60 years of experience and with more than 25 years of experience as manufacturer of the Automated Ultrasonic NDT systems, the P-scan systems, FORCE Institute is continuously analysing the market for NDT. This is done to assure that both the equipment product line and the service mix provided by FORCE Institute are meeting the requirements from the industry today and in the future. The concept of Risk Based Inspection Programmes were adopted early by the offshore industry and has in the recent years been adopted by many other industries as a reliable and cost efficient way of maintaining a production facility. A Risk/Reliability Based Inspection Programme is a 'living organism' that constantly needs information if it shall be of any value and NDT information is only one type of information that is required. The NDT information required is normally related to corrosion/base material information and weld integrity information. NDT as an integrated part of a plants maintenance system is, in Europe, currently influenced by the following tendencies which all are related to 'Risk Based Inspection': · Increased use of Base-Line Inspections · Reduction in the use of repeated inspections(qualitative- instead of quantitative Inspections). · Inspection results are fed directly into the plant maintenance system. · Fitness-for-Purpose acceptance criteria instead of conventional acceptance criteria. As repeatability and accuracy is a key issue for the data, automated ultrasonic inspection is increasingly used as an alternative to manual ultrasonic inspection, but due to the physical size of most automated ultrasonic inspection systems the gain in productivity has not been as significant as the gain in repeatability and accuracy. In this paper some of FORCE Institute's practical experiences with examinations carried out in connection with Risk Based Inspection is used to illustrate the above described tendencies. Not only examples using automated

Optimal Inspection and Maintenance Strategies for Structural Systems

DEFF Research Database (Denmark)

Sommer, A. M.

The aim of this thesis is to give an overview of conventional and optimal reliability-based inspection and maintenance strategies and to examine for specific structures how the cost can be reduced and/or the safety can be improved by using optimal reliability-based inspection strategies....... For structures with several almost similar components it is suggested that individual inspection strategies should be determined for each component or a group of components based on the reliability of the actual component. The benefit of this procedure is assessed in connection with the structures considered....... Furthermore, in relation to the calculations performed the intention is to modify an existing program for determination of optimal inspection strategies. The main purpose of inspection and maintenance of structural systems is to prevent or delay damage or deterioration to protect people, environment...

The General Safety Group Annual Report 2001/2002

CERN Document Server

Weingarten, W

2003-01-01

This report summarizes the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division during 2001 and 2002, and the results obtained. The different topics in which the group is active are covered: general safety inspections and ergonomics, electrical, chemical and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

Safety criteria for spent-fuel transport. Final report

International Nuclear Information System (INIS)

Goldmann, K.; Gekler, W.C.

1986-10-01

The focus of this study is on the question, ''Do current regulations provide reasonable assurance of safety for a transport scenario of spent fuel, as presently anticipated by the Department of Energy, under the Nuclear Waste Policy Act.'' This question has been addressed by developing a methodology for identifying the expected frequency of Accidents Which Exceed Regulatory Conditions in Severity (AWERCS) for spent fuel transport casks and then assessing the health effects resulting from that frequency. By applying the methodology to an illustrative case of road transports, it was found that the accidental release of radioactive material from impact AWERCS would make negligible contributions to health effects associated with spent fuel transports by road. It is also concluded that the current regulatory drop test requirements in 10 CFR 71.51 which form the basis for cask design and were used to establish AWERCS screening criteria for this study are adequate, and that no basis was found to conclude that cask performance under expected road accident conditions represents an undue risk to the public

Systems engineered health and safety criteria for safety analysis reports

International Nuclear Information System (INIS)

Beitel, G.A.; Morcos, N.

1993-01-01

The world of safety analysis is filled with ambiguous words: codes and standards, consequences and risks, hazard and accident, and health and safety. These words have been subject to disparate interpretations by safety analysis report (SAR) writers, readers, and users. open-quotes Principal health and safety criteriaclose quotes has been one of the most frequently misused phrases; rarely is it used consistently or effectively. This paper offers an easily understood definition for open-quotes principal health and safety criteriaclose quotes and uses systems engineering to convert an otherwise mysterious topic into the primary means of producing an integrated SAR. This paper is based on SARs being written for environmental restoration and waste management activities for the U.S. Department of Energy (DOE). Requirements for these SARs are prescribed in DOE Order 5480-23, open-quotes Nuclear Safety Analysis Reports.close quotes

Efficiency criteria for high reliability measured system structures

International Nuclear Information System (INIS)

Sal'nikov, N.L.

2012-01-01

The procedures of structural redundancy are usually used to develop high reliability measured systems. To estimate efficiency of such structures the criteria to compare different systems has been developed. So it is possible to develop more exact system by inspection of redundant system data unit stochastic characteristics in accordance with the developed criteria [ru

Shielding repair and comprehensive safety inspection of the nuclear-powered ship Mutsu

International Nuclear Information System (INIS)

Takada, Etsuo

1982-01-01

Eight years after the radiation leakage accident, the nuclear-powered ship Mutsu returned again to its home port Ominato. During the period, for four years, the n.s. Mutsu was subjected to shielding repair and comprehensive inspection at Sasebo port. In the future, the ship will start on experimental navigation after its functional and power-up tests. The works of shielding repair and the comprehensive inspection with subsequent repair are described in technical aspects. The basic policy of the repair was two points, i.e. the usage of shielding materials excellent in shielding capacity, less in radioactivation and enduring operating temperature, and structural strength resisting ship-hull acceleration, shock and vibration, enabling easy maintenance and inspection. Comprehensive inspection was made on not only machinery integrity but also the design itself. (Mori, K.)

The operator's requirement for in service inspection at Hinkley Point 'B' power station

International Nuclear Information System (INIS)

Outram, J.F.

The subject is discussed under the following heads: the need for reactor internal inspection (safety; commercial interest); the methods available (man access inspection; remote viewing inspection); experience with man access; experience with remote viewing; reactor outage time -comparison of the two methods; contamination control; conclusions. (U.K.)

In-service inspection of nuclear power-plant pressure components

International Nuclear Information System (INIS)

Lautzenheiser, C.E.

1976-01-01

The early light-water-reactor systems for production of commercial power were designed and fabricated in accordance with the codes then being used for fossil-fired power-generating stations with some design changes for increased inspectability during fabrication. Over the past few years, major strides have been made in in-service inspection technology. Work has been under way to determine the reliability of nondestructive testing methods and to develop formal inspection programs throughout the world. The major problems associated with in-service inspection are the scarcity of qualified personnel, the variability in procedures and data recording between inspection agencies, and exposure of inspection personnel to radiation. Further work will be required to more completely mechanize piping inspections to reduce radiation exposure and to standardize inspection procedures, equipment, and certification of personnel. Worldwide attention to the requirements of the American Society of Mechanical Engineers' Boiler and Pressure Vessel Code, the size and integrity of inspection agencies, and efforts such as the development of personnel qualification and certification guides emphasize the importance of in-service inspection to nuclear safety

A Simple Semantics and Static Analysis for Stack Inspection

Directory of Open Access Journals (Sweden)

Anindya Banerjee

2013-09-01

Full Text Available The Java virtual machine and the .NET common language runtime feature an access control mechanism specified operationally in terms of run-time stack inspection. We give a denotational semantics in "eager" form, and show that it is equivalent to the "lazy" semantics using stack inspection. We give a static analysis of safety, i.e., the absence of security errors, that is simpler than previous proposals. We identify several program transformations that can be used to remove run-time checks. We give complete, detailed proofs for safety of the analysis and for the transformations, exploiting compositionality of the eager semantics.

Rail inspection of RCF defects

Directory of Open Access Journals (Sweden)

Z. Popović

2013-10-01

Full Text Available Rail defects due to rolling contact fatigue (RCF threaten the traffic safety around the world. That hazard is more distinct on railways without adequate maintenance strategy. Realization of interoperability of European railway network demands from every infrastructure manager to have a maintenance plan for the infrastructure subsystem. Besides that, this plan includes rail inspection and strategy against RCF defects. This paper emphasizes the importance of rail inspection and early detection of RCF because the most of RCF crack should be removed in rail grinding campaigns (preventive, cyclical and corrective activities during the whole rail service life.

Safety design of SNR-300

International Nuclear Information System (INIS)

Traube, K.

1976-01-01

The joint German-Belgian-Dutch loop-type 300 MW(e) LMFBR prototype is being constructed at Kalkar on the lower Rhine in Germany. Among the many arguments put forward in defense of SNR-300, that of acquiring licensing exprience has proven to be of major importance to the international breeder scene. The severity of the licensing procedures and of the safety standards imposed are unique in several respects, including timing: generally growing scepticism towards nuclear power increased severity of the licensing practice; organizational features: the procedure and criteria developed for commercial light water reactors have been applied without exemptions. This relates to the commercial-type contract under which SNR-300 is being built for private utilities by a private company; and German nuclear safety standards, known worldwide to be most stringent. The following three important areas are discussed in which SNR-300 decidedly deviates from its forerunners: protection against the hypothetical core disruptive accident (HCDA), protection against external events, and provisions for in-service inspection

Factors influencing safety in a sample of marked pedestrian crossings selected for safety inspections in the city of Oslo.

Science.gov (United States)

Elvik, Rune; Sørensen, Michael W J; Nævestad, Tor-Olav

2013-10-01

This paper reports an analysis of factors influencing safety in a sample of marked pedestrian crossings in the city of Oslo, Norway. The sample consists of 159 marked pedestrian crossings where a total of 316 accidents were recorded during a period of five years. The crossings were selected for inspection because of they were, for various reasons, regarded as sub-standard. The sample of crossings is therefore not representative of all pedestrian crossings in Oslo. Factors influencing the number of accidents were studied by means of negative binomial regression. Factors that were studied included the volume of pedestrians and vehicles, the number of traffic lanes at the crossing, the location of the crossing (midblock or junction), the type of traffic control, the share of pedestrians using the crossing and the speed of approaching vehicles. The analysis confirmed the presence of a "safety-in-numbers" effect, meaning that an increase in the number of pedestrians is associated with a lower risk of accident for each pedestrian. Crossings located in four-leg junctions or roundabouts had more accidents than crossings located in three-leg junctions or on sections between junctions. A high share of pedestrians crossing the road outside the marked crossing was associated with a high number of accidents. Increased speed was associated with an increased number of accidents. Copyright © 2013 Elsevier Ltd. All rights reserved.

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

Science.gov (United States)

2014-11-01

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

In-service inspections of the reactor cooling system of pressurized water reactors

International Nuclear Information System (INIS)

Fuerste, W.; Hohnerlein, G.; Werden, B.

1982-01-01

In order to guarantee constant safety of the components of the reactor cooling system, regular in-service inspections are carried out after commissioning of the nuclear power plant. This contribution is concerned with the components of the reactor cooling system, referring to the legal requirements, safety-related purposes and scope of the in-service inspections during the entire period of operation of a nuclear power plant. Reports are made with respect to type, examination intervals, examination technique, results and future development. The functional tests which are carried out within the scope of the in-service inspections are not part of this contribution. (orig.) [de

40 CFR 265.403 - Inspections.

Science.gov (United States)

2010-07-01

... must inspect, where present: (1) Discharge control and safety equipment (e.g., waste feed cut-off systems, by-pass systems, drainage systems, and pressure relief systems) at least once each operating day... equipment is being operated according to its design; (3) The construction materials of the treatment process...

Implementation of a Quality Management System in regulatory inspection activities

International Nuclear Information System (INIS)

Pires do Rio, Monica; Ferreira, Paulo Roberto; Cunha, Paulo G. da; Acar, Maria Elizabeth

2005-01-01

The Institute for Radioprotection and Dosimetry - IRD -, of the Brazilian National Nuclear Energy Commission, CNEN, started in 2001, the implementation of a quality management system (SGQ), in the inspection, testing and calibration activities. The SGQ was an institutional guideline and is inserted in a larger system of management of the IRD started in 1999, with the adoption of the National Quality Award criteria - PNQ, within the Project for Excellence in Technological Research of Associacao Brasileira das Instituicoes de Pesquisas Tecnologicas - ABIPTI (Brazilian Association of Technological Research institutions). The proposed quality management system and adopted at the IRD was developed and implemented in accordance with the requirements of NBR ISO/IEC 17025 - General requirements for the competence of testing and calibration laboratories, and ISO/IEC 17020 - General criteria for operation of various types of bodies performing inspections. For regulatory inspection activities, the quality system was implemented on three program inspection services of radiological protection led, respectively, by clinics and hospitals that operate radiotherapy services; industries that use nuclear gauges in their control or productive processes and power reactor operators (CNAAA) - just the environmental part. It was formed a pioneering team of inspectors for standardizing the processes, procedures and starting the implementation of the system in the areas. This work describes the implementation process steps, including difficulties, learning and advantages of the adoption of a quality management system in inspection activities

9 CFR 352.6 - Denial or withdrawal of inspection service.

Science.gov (United States)

2010-01-01

... improper means; (4) has knowingly represented that any exotic animal carcass, or exotic animal product, has... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Denial or withdrawal of inspection service. 352.6 Section 352.6 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF...

Enhancement of the reliability of automated ultrasonic inspections using tools of quantitative NDT

International Nuclear Information System (INIS)

Kappes, W.; Baehr, W.; Kroening, M.; Schmitz, V.

1994-01-01

To achieve reliable test results from automated ultrasonic inspection of safety related components, optimization and integral consideration of the various inspection stages - inspection planning, inspection performance and evaluation of results - are indispensable. For this purpose, a large potential of methods is available: advanced measurement techniques, mathematical-numerical modelling processes, artificial intelligence tools, data bases and CAD systems. The potential inherent in these methods to enhance inspection reliability is outlined by way of different applications. (orig.) [de

The maternal early warning criteria: a proposal from the national partnership for maternal safety.

Science.gov (United States)

Mhyre, Jill M; D'Oria, Robyn; Hameed, Afshan B; Lappen, Justin R; Holley, Sharon L; Hunter, Stephen K; Jones, Robin L; King, Jeffrey C; D'Alton, Mary E

2014-01-01

Case reviews of maternal death have revealed a concerning pattern of delay in recognition of hemorrhage, hypertensive crisis, sepsis, venous thromboembolism, and heart failure. Early-warning systems have been proposed to facilitate timely recognition, diagnosis, and treatment for women developing critical illness. A multidisciplinary working group convened by the National Partnership for Maternal Safety used a consensus-based approach to define The Maternal Early Warning Criteria, a list of abnormal parameters that indicate the need for urgent bedside evaluation by a clinician with the capacity to escalate care as necessary in order to pursue diagnostic and therapeutic interventions. This commentary reviews the evidence supporting the use of early-warning systems, describes The Maternal Early Warning Criteria, and provides considerations for local implementation. © 2014 AWHONN, the Association of Women's Health, Obstetric and Neonatal Nurses.

Safety advice sheets

CERN Multimedia

HSE Unit

2013-01-01

You never know when you might be faced with questions such as: when/how should I dispose of a gas canister? Where can I find an inspection report? How should I handle/store/dispose of a chemical substance…?   The SI section of the DGS/SEE Group is primarily responsible for safety inspections, evaluating the safety conditions of equipment items, premises and facilities. On top of this core task, it also regularly issues “Safety Advice Sheets” on various topics, designed to be of assistance to users but also to recall and reinforce safety rules and procedures. These clear and concise sheets, complete with illustrations, are easy to display in the appropriate areas. The following safety advice sheets have been issued so far: Other sheets will be published shortly. Suggestions are welcome and should be sent to the SI section of the DGS/SEE Group. Please send enquiries to general-safety-visits.service@cern.ch.

Application of risk-informed methods to in-service piping inspection in Framatome type nuclear power plants

International Nuclear Information System (INIS)

Kim, Jin Hoi; Lee, Jeong Seok; Yun, Eun Sub

2014-01-01

The Pressurized water reactor owners group (PWROG) developed and applied a risk-informed in-service inspection (RI-ISI) program, as an alternative to the existing ASME Section XI sampling inspection method. The RI-ISI programs enhance overall safety by focusing inspections of piping at high safety significance (HSS) locations where failure mechanisms are likely to be present. Additionally, the RI-ISI program can reduce nondestructive evaluation (NDE) exams, man-rem exposure for inspectors, and inspection time, among other benefits. The RI-ISI method of in-service piping inspection was applied to 3 units (KSNPs: Korea standard nuclear power plants) and is being deployed to the other units. In this paper, the results of RI-ISI for a Framatome type (France CPI) nuclear power plant are presented. It was concluded that application of RI-ISI to the plant could enhance and maintain plant safety, as well as provide the benefits of greater reliability.