Second periodic safety review of Angra Nuclear Power Station, unit 1

International Nuclear Information System (INIS)

Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M.; Campello, Sergio A.

2015-01-01

This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

Periodic safety re-evaluations in NPPs in EC member states, Finland and Sweden

International Nuclear Information System (INIS)

1990-01-01

The work on periodic safety re-evaluations summarized in this report was performed by a Task Force of the CEC Working Group on the Safety of Thermal Reactors. The periodic safety re-evaluations under review in this study were those that are carried out in addition to other reviews which represent the primary means of safety assurance. The periodic safety re-evaluation is broader and more comprehensive in nature. The cumulative effects of experience (national and international), advances in knowledge and analysis techniques, improvements in safety standards and operating practices, overall effects of plant ageing, and the totality of all modifications over the period in question need to be taken into account. All countries have recognized the value of such periodic reviews, and licensees, either as a regulatory requirement or as a voluntary action, are carrying them out. The scope and contents of each country's review showed many similarities of approach, any differences being explained by the age and type of reactor in operation. Many similarities emerged in the topics selected for re-evaluation and in the approach to re-evaluation itself. The overall conclusion was that while approaches may differ in some respects, for practical purposes comparable levels of safety are achieved in the periodic safety re-evaluation of nuclear power plants

The necessity of periodic fire safety review

International Nuclear Information System (INIS)

Mowrer, D.S.

1998-01-01

Effective fire safety requires the coordinated integration of many diverse elements. Clear fire safety objectives are defined by plant management and/or regulatory authorities. Extensive and time-consuming systematic analyses are performed. Fire safety features (both active and passive) are installed and maintained, and administrative programs are established and implemented to achieve the defined objectives. Personnel are rigorously trained. Given the time, effort and monetary resources expended to achieve a specific level of fire safety, conducting periodic assessments to verify that the specified level of fire safety has been achieved and is maintained is a matter of common sense. Periodic fire safety reviews and assessment play an essential role in assuring continual nuclear safety in the world's power plants

Evaluation of periodic safety status analyses

International Nuclear Information System (INIS)

Faber, C.; Staub, G.

1997-01-01

In order to carry out the evaluation of safety status analyses by the safety assessor within the periodical safety reviews of nuclear power plants safety goal oriented requirements have been formulated together with complementary evaluation criteria. Their application in an inter-disciplinary coopertion covering the subject areas involved facilitates a complete safety goal oriented assessment of the plant status. The procedure is outlined briefly by an example for the safety goal 'reactivity control' for BWRs. (orig.) [de

Periodic safety review of the HTR-10 safety analysis

International Nuclear Information System (INIS)

Chen Fubing; Zheng Yanhua; Shi Lei; Li Fu

2015-01-01

Designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, the 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first modular High Temperature Gas-cooled Reactor (HTGR) in China. According to the nuclear safety regulations of China, the periodic safety review (PSR) of the HTR-10 was initiated by INET after approved by the National Nuclear Safety Administration (NNSA) of China. Safety analysis of the HTR-10 is one of the key safety factors of the PSR. In this paper, the main contents in the review of safety analysis are summarized; meanwhile, the internal evaluation on the review results is presented by INET. (authors)

Reports on BMBF-sponsored research projects in the field of reactor safety. Reporting period 1 July - 31 December 1995

International Nuclear Information System (INIS)

1996-01-01

The Gesellschaft fuer Anlagen- und Reaktorsicherheit informs of the status of LWR tasks and projects on the safety of advanced reactors. Each progress report represents a compilation of individual reports about objectives, the work performed, the results, and the next steps of the works. The individual reports of quality assurance, safety of reactor component, emergency core cooling, lors of coolant, meltdown, fission product release, risk and reliability, are classified according to projects to the reactor safety research program. Another table uses the same classification system as applied in the nuclear safety index of the CEC. (DG)

Quarterly report on the Ferrocyanide Safety Program for the period ending June 30, 1995

International Nuclear Information System (INIS)

Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

1995-07-01

This is the seventeenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six pans of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented

Periodic safety reviews of nuclear power plants

International Nuclear Information System (INIS)

Toth, Csilla

2009-01-01

Operational nuclear power plants (NPPs) are generally subject to routine reviews of plant operation and special safety reviews following operational events. In addition, many Member States of the International Atomic Energy Agency (IAEA) have initiated systematic safety reassessment, termed periodic safety review (PSR), to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments, site specific, organizational and human aspects. These reviews include assessments of plant design and operation against current safety standards and practices. PSRs are considered an effective way of obtaining an overall view of actual plant safety, to determine reasonable and practical modifications that should be made in order to maintain a high level of safety throughout the plant's operating lifetime. PSRs can be used as a means to identify time limiting features of the plant. The trend is to use PSR as a condition for deciding whether to continue operation of the plant beyond the originally established design lifetime and for assessing the status of the plant for long term operation. To assist Member States in the implementation of PSR, the IAEA develops safety standards, technical documents and provides different services: training courses, workshops, technical meetings and safety review missions for the independent assessment of the PSR at NPPs, including the requirements for PSR, the review process and the PSR final reports. This paper describes the PSR's objectives, scopes, methods and the relationship of PSR with other plant safety related activities and recent experiences of Member States in implementation of PSRs at NPPs. (author)

Quarterly report on the Ferrocyanide Safety Program for the period ending, March 31, 1995

International Nuclear Information System (INIS)

Cash, R.J.; Meacham, J.E.; Dukelow, G.T.

1995-04-01

This quarterly report provides a status of the activities underway on the Ferrocyanide Safety Issue at the Hanford Site, including actions in response to Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 90-7 (FR 1990). In March 1991, a DNFSB implementation plan (Cash 1991) responding to the six parts of Recommendation 90-7 was prepared and sent to the DNFSB. A Ferrocyanide Safety Program Plan addressing the total Ferrocyanide Safety Program, including the six parts of DNFSB Recommendation 90-7, was released in October 1994 (DOE 1994b). Activities in the program plan are underway or have been completed, and the status of each is described in Sections 2.0 and 3.0 of this report

Exploring relationships between hospital patient safety culture and Consumer Reports safety scores.

Science.gov (United States)

Smith, Scott Alan; Yount, Naomi; Sorra, Joann

2017-02-16

A number of private and public companies calculate and publish proprietary hospital patient safety scores based on publicly available quality measures initially reported by the U.S. federal government. This study examines whether patient safety culture perceptions of U.S. hospital staff in a large national survey are related to publicly reported patient safety ratings of hospitals. The Agency for Healthcare Research and Quality Hospital Survey on Patient Safety Culture (Hospital SOPS) assesses provider and staff perceptions of hospital patient safety culture. Consumer Reports (CR), a U.S. based non-profit organization, calculates and shares with its subscribers a Hospital Safety Score calculated annually from patient experience survey data and outcomes data gathered from federal databases. Linking data collected during similar time periods, we analyzed relationships between staff perceptions of patient safety culture composites and the CR Hospital Safety Score and its five components using multiple multivariate linear regressions. We analyzed data from 164 hospitals, with patient safety culture survey responses from 140,316 providers and staff, with an average of 856 completed surveys per hospital and an average response rate per hospital of 56%. Higher overall Hospital SOPS composite average scores were significantly associated with higher overall CR Hospital Safety Scores (β = 0.24, p Consumer Reports Hospital Safety Score, which is a composite of patient experience and outcomes data from federal databases. As hospital managers allocate resources to improve patient safety culture within their organizations, their efforts may also indirectly improve consumer-focused, publicly reported hospital rating scores like the Consumer Reports Hospital Safety Score.

Aggregate analysis of regulatory authority assessors' comments to improve the quality of periodic safety update reports.

Science.gov (United States)

Jullian, Sandra; Jaskiewicz, Lukasz; Pfannkuche, Hans-Jürgen; Parker, Jeremy; Lalande-Luesink, Isabelle; Lewis, David J; Close, Philippe

2015-09-01

Marketing authorization holders (MAHs) are expected to provide high-quality periodic safety update reports (PSURs) on their pharmaceutical products to health authorities (HAs). We present a novel instrument aiming at improving quality of PSURs based on standardized analysis of PSUR assessment reports (ARs) received from the European Union HAs across products and therapeutic areas. All HA comments were classified into one of three categories: "Request for regulatory actions," "Request for medical and scientific information," or "Data deficiencies." The comments were graded according to their impact on patients' safety, the drug's benefit-risk profile, and the MAH's pharmacovigilance system. A total of 476 comments were identified through the analysis of 63 PSUR HA ARs received in 2013 and 2014; 47 (10%) were classified as "Requests for regulatory actions," 309 (65%) as "Requests for medical and scientific information," and 118 (25%) comments were related to "Data deficiencies." The most frequent comments were requests for labeling changes (35 HA comments in 19 ARs). The aggregate analysis revealed commonly raised issues and prompted changes of the MAH's procedures related to the preparation of PSURs. The authors believe that this novel instrument based on the evaluation of PSUR HA ARs serves as a valuable mechanism to enhance the quality of PSURs and decisions about optimization of the use of the products and, therefore, contributes to improve further the MAH's pharmacovigilance system and patient safety. Copyright © 2015 John Wiley & Sons, Ltd.

Quarterly report on the ferrocyanide safety program for the period ending December 31, 1994

International Nuclear Information System (INIS)

Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

1995-01-01

This is the fifteenth quarterly report on the progress of active addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 2.0 through 4.0. 60 refs

Quarterly report on the Ferrocyanide Safety Program for the period ending September 30, 1995

International Nuclear Information System (INIS)

Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

1995-10-01

This is the eighteenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented in Section 1.2. More detailed discussions of progress are located in Sections 2.0 through 4.0

Overview of the periodic safety review of nuclear power plants as practised in India

International Nuclear Information System (INIS)

Jhamb, N.K.; Chande, S.K.

1997-01-01

In India, routine and periodic safety reviews of nuclear facilities are carried out through a multitiered hierarchy of committees at the plant level, the operating organization level and the regulatory body level. In 1993, it was decided by the Atomic Energy Regulatory Board (AERB, the regulatory body) that, as a policy, authorization for operation of nuclear power plants (NPPs) shall have a validity period of 5 years, after which this authorization will have to be renewed. NPPs have to carry out a self-assessment according to an established procedure, prepare a Safety Assessment Report for Renewal of Authorization (SARRA) and submit it to the AERB for review. The procedure defines the objectives of the report and gives guidelines on the required review of the self-assessment of the operational plant safety. The paper discusses the objectives, the elements of the SARRA review, the review process, the SARRA review carried out in 1993-1994, the basis for acceptability of continued plant operation, and the lessons learned for future periodic safety reviews in India and for exchange of operating experience feedback. (author)

Research on review technology for three key safety factors of periodic safety review (PSR) and its application to Qinshan Nuclear Power Plant

International Nuclear Information System (INIS)

Xu Shoulv; Yao Weida; Dou Yikang; Lin Shaoxuan; Cao Yenan; Zhou Quanfu; Zheng Jiong; Zhang Ming

2009-04-01

In 2001, after 10 years' operation, Qinshan Nuclear Power Plant (Q1) started to carry out periodic safety review (PSR) based on a nuclear safety guideline, Periodic Safety Review for Operational Nuclear Power Plants (HAF0312), issued by National Nuclear Safety Administration of China (NNSA). Entrusted by the owner of Q1, Shanghai Nuclear Engineering Research and Design Institute (SNERDI) implemented reviews of three key safety factors including safety analysis, equipment qualification and ageing. PSR was a challenging work in China at that time and through three years' research and practice, SNERDI summarized a systematic achievement for the review including review methodology, scoping, review contents and implementation steps, etc.. During the process of review for the three safety factors, totally 148 review reports and 341 recommendations for corrections were submitted to Q1. These reports and recommendations have provided guidance for correction actions as follow-up of PSR. This paper focuses on technical aspects to carry out PSR for the above-mentioned three safety factors, including review scoping, contents, methodology and main steps. The review technology and relevant experience can be taken for reference for other NPPs to carry out PSR. (authors)

Report of the tunnel safety working group

International Nuclear Information System (INIS)

Gannon, J.

1991-04-01

On 18 February 1991 the Project Manager formed a working group to address the safety guidelines and requirements for the underground facilities during the period of accelerator construction, installation, and commissioning. The following report summarizes the research and discussions conducted by the group and the recommended guidelines for safety during this phase of the project

Sixth national report of Brazil for the nuclear safety convention

International Nuclear Information System (INIS)

2013-01-01

Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Sixth national report of Brazil for the nuclear safety convention

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations.

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

International Nuclear Information System (INIS)

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

2013-01-01

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

Krsko periodic safety review project prioritization process

International Nuclear Information System (INIS)

Basic, I.; Vrbanic, I.; Spiler, J.; Lambright, J.

2004-01-01

Definition of a Krsko Periodic Safety Review (PSR) project is a comprehensive safety review of a plant after last ten years of operation. The objective is a verification by means of a comprehensive review using current methods that Krsko NPP remains safety when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. This objective encompasses the three main criteria or goals: confirmation that the plant is as safe as originally intended, determination if there are any structures, systems or components that could limit the life of the plant in the foreseeable future, and comparison the plant against modern safety standards and to identify where improvements would be beneficial at justifiable cost. Krsko PSR project is structured in the three phases: Phase 1: Preparation of Detailed 10-years PSR Program, Phase 2: Performing of 10-years PSR Program and preparing of associated documents (2001-2003), and Phase 3: Implementation of the prioritized compensatory measures and modifications (development of associated EEAR, DMP, etc.) after agreement with the SNSA on the design, procedures and time-scales (2004-2008). This paper presents the NEK PSR results of work performed under Phase 2 focused on the ranking of safety issues and prioritization of corrective measures needed for establishing an efficient action plan. Safety issues were identified in Phase 2 during the following review processes: Periodic Safety Review (PSR) task; Krsko NPP Regulatory Compliance Program (RCP) review; Westinghouse Owner Group (WOG) catalog items screening/review; SNSA recommendations (including IAEA RAMP mission suggestions/recommendations).(author)

Periodic Safety Review of Nuclear Power Plants: Experience of Member States

International Nuclear Information System (INIS)

2010-04-01

Routine reviews of nuclear power plant operation (including modifications to hardware and procedures, operating experience, plant management and personnel competence) and special reviews following major events of safety significance are the primary means of safety verification. In addition, many Member States of the IAEA have initiated systematic safety reassessments, termed periodic safety reviews, of nuclear power plants, to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments and siting aspects. The reviews include an assessment of plant design and operation against current safety standards and practices, and they have the objective of ensuring a high level of safety throughout the plant's operating lifetime. They are complementary to the routine and special safety reviews and do not replace them. Periodic safety reviews of nuclear power plants are considered an effective way to obtain an overall view of actual plant safety, and to determine reasonable and practical modifications that should be made in order to maintain a high level of safety. They can be used as a means of identifying time limiting features of the plant in order to determine nuclear power plant operation beyond the designed lifetime. The periodic safety review process can be used to support the decision making process for long term operation or licence renewal. Since 1994, the use of periodic safety reviews by Member States has substantially broadened and confirmed its benefits. Periodic safety review results have, for example, been used by some Member States to help provide a basis for continued operation beyond the current licence term, to communicate more effectively with stakeholders regarding nuclear power plant safety, and to help identify changes to plant operation that enhance safety. This IAEA-TECDOC is intended to assist Member States in the implementation of a periodic safety review. This publication complements the

NPP Krsko periodic safety review. Safety assessment and analyses

International Nuclear Information System (INIS)

Basic, I.; Spiler, J.; Thaulez, F.

2002-01-01

Definition of a PSR (Periodic Safety Review) project is a comprehensive safety review of a plant after ten years of operation. The objective is a verification by means of a comprehensive review using current methods that the plant remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. The overall goals of the NEK PSR Program are defined in compliance with the basic role of a PSR and the current practice typical for most of the countries in EU. This practice is described in the related guides and good practice documents issued by international organizations. The overall goals of the NEK PSR are formulated as follows: to demonstrate that the plant is as safe as originally intended; to evaluate the actual plant status with respect to aging and wear-out identifying any structures, systems or components that could limit the life of the plant in the foreseeable future, and to identify appropriate corrective actions, where needed; to compare current level of safety in the light of modern standards and knowledge, and to identify where improvements would be beneficial for minimizing deviations at justifiable costs. The Krsko PSR will address the following safety factors: Operational Experience, Safety Assessment, EQ and Aging Management, Safety Culture, Emergency Planning, Environmental Impact and Radioactive Waste.(author)

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

Annual report on Reactor Safety Research Projects sponsored by the Ministry of Economics and Technology of the Federal Republic of Germany. Reporting period 1999. Progress report

International Nuclear Information System (INIS)

2000-01-01

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technologie (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to the classification system ''Joint Safety Research Index'' of the CEC (commission of the European communities). The reports are arranged in sequence of their project numbers. (orig.)

Safety technical considerations on the 2012 periodic safety verification of the Beznau nuclear power plant

International Nuclear Information System (INIS)

2016-12-01

According to nuclear legislation, the owner of an operational license for a nuclear power plant has to provide a periodic safety verification (PSU) every 10 years. The 'North Eastern Power Plants' company (NOK), today AXPO Power AG already performed such a PSU for the Beznau-2 nuclear reactor block (KKB2) in 2002. The Beznau-1 nuclear reactor block (KKB1) received its definitive operational license in October 1970, after test operation during 7 months. After the license for test operation received on July 16 th , 1971, the operational license of KKB2 was renewed several times, each time for a certain period of validity. In 1991, NOK requested a definitive operational license for KKB2, but in 1994 the Swiss Federal Council lengthened the license for only 10 years. Moreover, it laid down that NOK has to periodically report on the safety of the facility. With its letter of August 23 rd , 1998, the Federal Office of Energy defined the documents to be produced for the PSU. The extent of the PSU was defined in such a way that many documents concern the whole power plant, i.e. both nuclear reactor blocks. On December 3 rd , 2004, the Swiss Federal Council granted KKB2 an operational license of limited validity. The present report reviews the 2012 PSU, which covers the time interval from January 1 st , 2002, to December 31 st , 2011, from the point of view of safety. It contains documents for the evaluation of both reactor blocks at KKB. The Beznau interim storage pool was also taken into consideration; it is situated on the KKB site, but, according to a decision of the Swiss Federal Council of May 23 rd , 1991, it has an independent operational license. The evaluation of ageing surveillance takes the whole operational period of the facility into account, i.e. the ageing mechanisms acting as from the beginning of the operation. Moreover, important developments that occurred after the surveillance time interval have been taken into account, especially the status

Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2003. Progress report

International Nuclear Information System (INIS)

2003-01-01

The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of the investigations into the safety of nuclear power plants by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system ''Joint Safety Research Index'' of the CEC (commission of the european communities). The reports are arranged in sequence of their project numbers

Annual report on reactor safety research projects sponsored by the Ministry of Economics and Technology of the Federal Republic of Germany. Reporting period 2005. Progress report

International Nuclear Information System (INIS)

2005-01-01

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2004. Progress report

International Nuclear Information System (INIS)

2004-01-01

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2004. Progress report

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Research projects into the safety of nuclear power plants. Period covered: 01. July - 31. December 2004. Progress report

International Nuclear Information System (INIS)

2004-01-01

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Optimization of maintenance periodicity of complex of NPP safety systems

International Nuclear Information System (INIS)

Kolykhanov, V.; Skalozubov, V.; Kovrigkin, Y.

2006-01-01

The analysis of the positive and negative aspects connected to maintenance of the safety systems equipment which basically is in a standby state is executed. Tests of systems provide elimination of the latent failures and raise their reliability. Poor quality of carrying out the tests can be a source of the subsequent failures. Therefore excess frequency of tests can result in reducing reliability of safety systems. The method of optimization of maintenance periodicity of the equipment taking into account factors of its reliability and restoration procedures quality is submitted. The unavailability factor is used as a criterion of optimization of maintenance periodicity. It is offered to use parameters of reliability of the equipment and each of safety systems of NPPs received at developing PSA. And it is offered to carry out the concordance of maintenance periodicity of systems within the NPP maintenance program taking into account a significance factor of the system received on the basis of the contribution of system in CDF. Basing on the submitted method the small computer code is developed. This code allows to calculate reliability factors of a separate safety system and to determine optimum maintenance periodicity of its equipment. Optimization of maintenance periodicity of a complex of safety systems is stipulated also. As an example results of optimization of maintenance periodicity at Zaporizhzhya NPP are presented. (author)

Annual report on reactor safety research projects sponsored by the Ministry of Economics and Technology of the Federal Republic of Germany. Reporting period 2007. Progress report

International Nuclear Information System (INIS)

2007-01-01

Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Research Management Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system 'Joint Safety Research Index (JSRI)'. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Research projects into the safety of nuclear power plants. Period cover 01. January - 30. June 2017. Progress report

International Nuclear Information System (INIS)

2017-01-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fur Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/ Authority Support Division of GRS. The reports as of the year 2000 are available in the internet-based information system on results and data of reactor safety research (https://www.grs-fbw.de). The compilation of the reports is classified according to the topic areas of reactor safety research. The reports are arranged in sequence of their project numbers. Ilt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

Aging evaluation methodology of periodic safety review in Korea

International Nuclear Information System (INIS)

Park, Heung-Bae; Jung, Sung-Gyu; Jin, Tae-Eun; Jeong, Ill-Seok

2002-01-01

In Korea plant lifetime management (PLIM) study for Kori Unit 1 has been performed since 1993. Meanwhile, periodic safety review (PSR) for all operating nuclear power plants (NPPs) has been started with Kori Unit 1 since 2000 per IAEA recommendation. The evaluation period is 10 years, and safety (evaluation) factors are 11 per IAEA guidelines as represented in table 1. The relationship between PSR factors and PLIM is also represented. Among these factors evaluation of 'management of aging' is one of the most important and difficult factor. This factor is related to 'actual condition of the NPP', 'use of experience from other nuclear NPPs and of research findings', and 'management of aging'. The object of 'management of aging' is to obtain plant safety through identifying actual condition of system, structure and components (SSCs) and evaluating aging phenomena and residual life of SSCs using operating experience and research findings. The paper describes the scope and procedure of valuation of 'management of aging', such as, screening criteria of SSCs, Code and Standards, evaluation of SSCs and safety issues as represented. Evaluating SSCs are determined using final safety analysis report (FSAR) and power unit maintenance system for Nuclear Ver. III (PUMAS/N-III). The screening criteria of SSCs are safety-related items (quality class Q), safety-impact items (quality class T), backfitting rule items (fire protection (10CFR50.48), environmental qualification (10CFR50.49), pressurized thermal shock (10CFR50.61), anticipated transient without scram (10CFR50.62), and station blackout (10CFR50.63)) and regulating authority requiring items[1∼3]. The purpose of review of Code and Standards is identifying actual condition of the NPP and evaluating aging management using effective Code and Standards corresponding to reactor facilities. Code and Standards is composed of regulating laws, FSAR items, administrative actions, regulating actions, agreement items, and other

Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

International Nuclear Information System (INIS)

1987-04-01

The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

Report on safety related occurrences and reactor trips July 1, 1976-December 31, 1976

International Nuclear Information System (INIS)

Andermo, L.

1977-04-01

This is a systematically arranged report on all reported safety related occurrences and reactor trips in Swedish nuclear power plants in operation during July 1, 1976 to December 31, 1976 inclusive. The facilities involved are Oskarshamn 1 and 2, Ringhals 1 and 2 and Barsebaeck 1. During this period of the 6 months 37 safety related occurrences and 34 reactor trips have been reported to the Nuclear Power Inspectorate. As earlier experiences have shown it is to the greatest extent the conventional components which bring about the safety related occurrences or occurrences leading to outages or power reductions. However, the component errors discovered in the safety related systems have not affected the function of their redundant systems and other diverse systems have not been involved. Therefore the reactor safety has been satisfactory. The fact that even small deviations from prescribed operation results in automatic and safe shut down of the reactor, does not always imply a conflict with operational availability. The number of reactor trips are almost as low as during the last period, which is a drastic reduction compared to earlier time periods. The greatest outages are caused by occurrences without safety significance.(author)

Integrated safety assessment report, Haddam Neck Plant (Docket No. 50-213): Integrated Safety Assessment Program: Draft report

International Nuclear Information System (INIS)

1987-07-01

The integrated assessment is conducted on a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. Procedures allow for a periodic updating of the schedules to account for licensing issues that arise in the future. The Haddam Neck Plant is one of two plants being reviewed under the pilot program. This report indicates how 82 topics selected for review were addressed, and presents the staff's recommendations regarding the corrective actions to resolve the 82 topics and other actions to enhance plant safety. 135 refs., 4 figs., 5 tabs

Safety of vaccinations in patients with cryopyrin-associated periodic syndromes: a prospective registry based study

NARCIS (Netherlands)

Jaeger, Veronika K.; Hoffman, Hal M.; van der Poll, Tom; Tilson, Hugh; Seibert, Julia; Speziale, Antonio; Junge, Guido; Franke, Kristina; Vritzali, Eleni; Hawkins, Philip N.; Kuemmerle-Deschner, Jasmin; Walker, Ulrich A.

2017-01-01

Pneumococcal, tetanus and influenza vaccinations are recommended for patients with cryopyrin-associated periodic syndromes (CAPS) when treated with immunosuppressive medication. The aim of this publication is to report the safety of pneumococcal and other vaccinations in CAPS patients. All CAPS

Fifth national report of Brazil for the nuclear safety convention

International Nuclear Information System (INIS)

2010-01-01

This Fifth National Report is a new update to include relevant information for the period of 2007/2009. This document represents the national report prepared as a fulfillment of the Brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Domestic Regulation for Periodic Safety Review of Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Daesik; Ahn, Seunghoon; Auh, Geunsun; Lee, Jonghyeok

2015-01-01

The so-called Periodic Safety Review (PSR) has been carried out such safety assessment throughout its life, on a periodic basis. In January 2001, the Atomic Energy Act and related regulations were amended to adopt the PSR institutional scheme from IAEA Nuclear Safety Guide 50-SG-O12. At that time the safety assessment was made to review the plant safety on 10 safety factors, such as aging management and emergency planning, where the safety factor indicates the important aspects of safety of an operating NPP to be addressed in the PSR. According to this legislation, the domestic utility, the KHNP has conducted the PSR for the operating NPP of 10 years coming up from operating license date, starting since May 2000. Some revisions in the PSR rule were made to include the additional safety factors last year. This paper introduces the current status of the PSR review and regulation, in particular new safety factors and updated technical regulation. Comprehensive safety assessment for Korea Nuclear Power Plants have performed a reflecting design and procedure changes and considering the latest technology every 10 years. This paper also examined the PSR system changes in Korea. As of July 2015, reviews for PSR of 18 units have been completed, with 229 nuclear safety improvement items. And implementation have been completed for 165 of them. PSR system has been confirmed that it has contributed to improvement of plant safety. In addition, this paper examined the PSR system change in Korea

Patient safety incident reports related to traditional Japanese Kampo medicines: medication errors and adverse drug events in a university hospital for a ten-year period.

Science.gov (United States)

Shimada, Yutaka; Fujimoto, Makoto; Nogami, Tatsuya; Watari, Hidetoshi; Kitahara, Hideyuki; Misawa, Hiroki; Kimbara, Yoshiyuki

2017-12-21

Kampo medicine is traditional Japanese medicine, which originated in ancient traditional Chinese medicine, but was introduced and developed uniquely in Japan. Today, Kampo medicines are integrated into the Japanese national health care system. Incident reporting systems are currently being widely used to collect information about patient safety incidents that occur in hospitals. However, no investigations have been conducted regarding patient safety incident reports related to Kampo medicines. The aim of this study was to survey and analyse incident reports related to Kampo medicines in a Japanese university hospital to improve future patient safety. We selected incident reports related to Kampo medicines filed in Toyama University Hospital from May 2007 to April 2017, and investigated them in terms of medication errors and adverse drug events. Out of 21,324 total incident reports filed in the 10-year survey period, we discovered 108 Kampo medicine-related incident reports. However, five cases were redundantly reported; thus, the number of actual incidents was 103. Of those, 99 incidents were classified as medication errors (77 administration errors, 15 dispensing errors, and 7 prescribing errors), and four were adverse drug events, namely Kampo medicine-induced interstitial pneumonia. The Kampo medicine (crude drug) that was thought to induce interstitial pneumonia in all four cases was Scutellariae Radix, which is consistent with past reports. According to the incident severity classification system recommended by the National University Hospital Council of Japan, of the 99 medication errors, 10 incidents were classified as level 0 (an error occurred, but the patient was not affected) and 89 incidents were level 1 (an error occurred that affected the patient, but did not cause harm). Of the four adverse drug events, two incidents were classified as level 2 (patient was transiently harmed, but required no treatment), and two incidents were level 3b (patient was

KKP 1. Report to inform the Reactor Safety Commission

International Nuclear Information System (INIS)

1987-01-01

This report goes into details of the operation during its reporting period, giving the total activity in the primary events. Radiation exposure, activities, dose rates of persons, collective doses from activity and radioactive emission to water and waste air are given. Account is given of all modifications or extensions made on safety-related parts of the plant, on controls and regulation. (DG) [de

Safety analysis reports. Current status (third key report)

International Nuclear Information System (INIS)

1999-01-01

A review of Ukrainian regulations and laws concerned with Nuclear power and radiation safety is presented with an overview of the requirements for the Safety Analysis Report Contents. Status of Safety Analysis Reports (SAR) is listed for each particular Ukrainian NPP including SAR development schedules. Organisational scheme of SAR development works includes: general technical co-ordination on Safety Analysis Report development; list of leading organisations and utilization of technical support within international projects

Developing and Testing the Health Care Safety Hotline: A Prototype Consumer Reporting System for Patient Safety Events.

Science.gov (United States)

Schneider, Eric C; Ridgely, M Susan; Quigley, Denise D; Hunter, Lauren E; Leuschner, Kristin J; Weingart, Saul N; Weissman, Joel S; Zimmer, Karen P; Giannini, Robert C

2017-06-01

This article describes the design, development, and testing of the Health Care Safety Hotline, a prototype consumer reporting system for patient safety events. The prototype was designed and developed with ongoing review by a technical expert panel and feedback obtained during a public comment period. Two health care delivery organizations in one metropolitan area collaborated with the researchers to demonstrate and evaluate the system. The prototype was deployed and elicited information from patients, family members, and caregivers through a website or an 800 phone number. The reports were considered useful and had little overlap with information received by the health care organizations through their usual risk management, customer service, and patient safety monitoring systems. However, the frequency of reporting was lower than anticipated, suggesting that further refinements, including efforts to raise awareness by actively soliciting reports from subjects, might be necessary to substantially increase the volume of useful reports. It is possible that a single technology platform could be built to meet a variety of different patient safety objectives, but it may not be possible to achieve several objectives simultaneously through a single consumer reporting system while also establishing trust with patients, caregivers, and providers.

National Nuclear Safety Report 2001. Convention on Nuclear Safety

International Nuclear Information System (INIS)

2001-01-01

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

National nuclear safety report 2004. Convention on nuclear safety

International Nuclear Information System (INIS)

2004-01-01

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

Annual Safety Report 1981

International Nuclear Information System (INIS)

1982-09-01

A safety report from Section K (Nuclear Physics) of the Dutch National Institute for Nuclear and High Energy Physics is presented for 1981. The report begins with general matters concerning safety policy at NIKHEF, licences and expenditure. Works accidents (none of them radiological) are detailed and accident prevention considered. The measurement programme for neutron radiation in the vicinity of the accelerator is described and the results are discussed. The means and results of personnel dosimetry are also presented. The report is concluded with a list of publications concerning safety aspects at NIKHEF. (C.F.)

Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending December 31, 1992

International Nuclear Information System (INIS)

Cash, R.J.; Dukelow, G.T.; Forbes, C.J.

1993-03-01

This is the seventh quarterly report on the progress of activities addressing safety issues associated with Hanford Site high-level radioactive waste tanks that contain ferrocyanide compounds. In the presence of oxidizing materials, such as nitrates or nitrites, ferrocyanide can be made to explode in the laboratory by heating it to high temperatures [above 285 degrees C (545 degrees F)]. In the mid 1950s approximately 140 metric tons of ferrocyanide were added to 24 underground high-level radioactive waste tanks. An implementation plan (Cash 1991) responding to the Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990) was issued in March 1991 describing the activities that were planned and underway to address each of the six parts of Recommendation 90-7. A revision to the original plan was transmitted to US Department of Energy by Westinghouse Hanford Company in December 1992. Milestones completed this quarter are described in this report. Contents of this report include: Introduction; Defense Nuclear Facilities Safety Board Implementation Plan Task Activities (Defense Nuclear Facilities Safety Board Recommendation for enhanced temperature measurement, Recommendation for continuous temperature monitoring, Recommendation for cover gas monitoring, Recommendation for ferrocyanide waste characterization, Recommendation for chemical reaction studies, and Recommendation for emergency response planning); Schedules; and References. All actions recommended by the Defense Nuclear Facilities Safety Board for emergency planning by Hanford Site emergency preparedness organizations have been completed

Safety administration division business report. The first quarter of 2002

International Nuclear Information System (INIS)

Ishibashi, Takashi

2002-09-01

The business of the Safety administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, and the business of the following concerning the Tokai Works, the protection of nuclear materials, the business of the sanction, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. For the purpose of summarizing these businesses and utilizing the data concerning the businesses, the report about the businesses achievement has been periodically drawn up as quarter news since 2001, when the Safety Administration Division was established. This report describes about the business achievement of the first quarter news from April to June in 2002. (author)

Safety administration division business report. The second quarter of 2001

International Nuclear Information System (INIS)

Kanamori, Masashi

2001-12-01

The business of the Safety administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, and the business of the following concerning the Tokai Works, the protection of nuclear materials, the business of the sanction, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. For the purpose of summarizing these business and utilizing the data concerning the businesses, the report about the businesses achievement has been periodically drawn up as quarter news since 2001, when the Safety Administration Division was established. This report describes about the business achievement of the second quarter news from July to September in 2001. (author)

Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology. Reported period: July 1 to December 31, 1986. Progress report

International Nuclear Information System (INIS)

1987-05-01

Investigations on the safety of light water reactors (LWR) being performed in the framework of the research program on reactor safety (RS-projects) are sponsored by the Federal Ministry for Research and Technology (BMFT). Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks also projects on the safety of advanced reactors are sponsored by the BMFT. The individual reports are classified according to the research program on the safety of LWRs 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig.) [de

Safety evaluation status report for the prototype license application safety analysis report

International Nuclear Information System (INIS)

1989-07-01

The US Nuclear Regulatory Commission (NRC) staff and consultants reviewed a Prototype License Application Safety Analysis Report (PLASAR) submitted by the US Department of Energy (DOE) for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste disposal. The NRC reviewers relied extensively on the Standard Review Plan (SRP), Rev.1 (NUREG-1200), to evaluate the acceptability of the information provided in the EMCB PLASAR. The NRC staff selected certain review areas in the PLASAR for development of safety evaluation report input to provide examples of safety assessments that are necessary as part of a licensing review. Because of the fictitious nature of the assumed disposal site, and the decision to limit the review to essentially first-round review status, the NRC staff report is labeled a ''Safety Evaluation Status Report'' (SESR). Appendix A comprises the NRC review comments and questions on the information that DOE submitted in the PLASAR. The NRC concentrated its review on the design and operations-related portions of the EMCB PLASAR

NASA Aviation Safety Reporting System (ASRS)

Science.gov (United States)

Connell, Linda J.

2017-01-01

The NASA Aviation Safety Reporting System (ASRS) collects, analyzes, and distributes de-identified safety information provided through confidentially submitted reports from frontline aviation personnel. Since its inception in 1976, the ASRS has collected over 1.4 million reports and has never breached the identity of the people sharing their information about events or safety issues. From this volume of data, the ASRS has released over 6,000 aviation safety alerts concerning potential hazards and safety concerns. The ASRS processes these reports, evaluates the information, and provides selected de-identified report information through the online ASRS Database at http:asrs.arc.nasa.gov. The NASA ASRS is also a founding member of the International Confidential Aviation Safety Systems (ICASS) group which is a collection of other national aviation reporting systems throughout the world. The ASRS model has also been replicated for application to improving safety in railroad, medical, fire fighting, and other domains. This presentation will discuss confidential, voluntary, and non-punitive reporting systems and their advantages in providing information for safety improvements.

Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Research and Technology. Progress report. Reported period: July 1 to December 31, 1984

International Nuclear Information System (INIS)

1985-05-01

Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWRS 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in the sequence of their project numbers. (orig./HP) [de

Draft pilot report - Approaches to the resolution of safety issues

International Nuclear Information System (INIS)

2006-01-01

The purpose of this report is to present in a concise form how some safety matters associated with currently operating light water reactors have been addressed. The issues discussed in this report are common to member countries with currently operating LWRs (PWR, BWR, VVER) and, as such, have wide interest in the nuclear safety community. Accordingly, this report can serve as a reference for researchers, regulations and others (e.g., industry) interested in understanding the approach and status of issues. This report should also be useful for knowledge transfer by documenting what has been done or is planned regarding selected safety matters and as a source for identifying reference material containing additional detail. The issues addressed in this report should not be viewed as questioning the safety of operating reactors, which have reached very high operational safety record, but rather as areas where uncertainty in knowledge exists, where safety assessment has been based on conservative assumptions, and where regulatory decisions need, or will need to be confirmed. Thus, the development of sound technical bases through continuing research will improve the current knowledge and allow for more realistic safety assessment. The safety issues discussed in this initial version of the report are: - design basis accident spectrum; - severe accident issues; - reactor pressure vessel integrity; - hydrogen control; - containment integrity; - accident management; - station blackout; - high burnup fuel; - power up-rates; - ECCS strainer clogging; - boron dilution. For each issue, the scope of the issue is defined, its status discussed and planned work or research described, including schedule. This pilot version of the report is limited to input from nine countries (Belgium, Czech Republic, Finland, France, Germany, Japan, Korea, Sweden and the U.S.). An overview of this information for each issue by country is provided in the table. This document does not contain a

Fusion safety status report

International Nuclear Information System (INIS)

1986-10-01

This report includes information on a) tritium handling and safety; b) activation product generation and release; c) lithium safety; d) superconducting magnet safety; e) operational safety and shielding; f) environmental impact; g) recycling, decommissioning and waste management; and h) accident analysis. Recommendations for high priority research and development are presented, as well as the current status in each area

National nuclear safety report 2005. Convention on nuclear safety

International Nuclear Information System (INIS)

2006-01-01

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

NIKHEF-K safety report 1982

International Nuclear Information System (INIS)

1983-12-01

In this safety report, general information is offered about the safety policy at the NIKHEF-K institute Amsterdam. Costs, prevention, training courses and inspection related to (radiation) safety are briefly discussed. Small accidents are reported. Some measurements have been carried out, but no measurable increase of radiation doses have been found. (Auth.)

Safety balance: Analysis of safety systems

International Nuclear Information System (INIS)

Delage, M.; Giroux, C.

1990-12-01

Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses

RB research reactor safety report

International Nuclear Information System (INIS)

Sotic, O.; Pesic, M.; Vranic, S.

1979-04-01

This new version of the safety report is a revision of the safety report written in 1962 when the RB reactor started operation after reconstruction. The new safety report was needed because reactor systems and components have been improved and the administrative procedures were changed. the most important improvements and changes were concerned with the use of highly enriched fuel (80% enriched), construction of reactor converter outside the reactor vessel, improved control system by two measuring start-up channels, construction of system for heavy water leak detection, new inter phone connection between control room and other reactor rooms. This report includes description of reactor building with installations, rector vessel, reactor core, heavy water system, control system, safety system, dosimetry and alarm systems, experimental channels, neutron converter, reactor operation. Safety aspects contain analyses of accident reasons, method for preventing reactivity insertions, analyses of maximum hypothetical accidents for cores with natural uranium, 2% enriched and 80% enriched fuel elements. Influence of seismic events on the reactor safety and well as coupling between reactor and the converter are parts of this document

Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

International Nuclear Information System (INIS)

2007-09-01

This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-09-15

This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Non-reporting of work injuries and aspects of jobsite safety climate and behavioral-based safety elements among carpenters in Washington State.

Science.gov (United States)

Lipscomb, Hester J; Schoenfisch, Ashley L; Cameron, Wilfrid

2015-04-01

Declining work injury rates may reflect safer work conditions as well as under-reporting. Union carpenters were invited to participate in a mailed, cross-sectional survey designed to capture information about injury reporting practices. Prevalence of non-reporting and fear of repercussions for reporting were compared across exposure to behavioral-based safety elements and three domains of the Nordic Safety Climate Questionnaire (NOSACQ-50). The majority (>75%) of the 1,155 participants felt they could report work-related injuries to their supervisor without fear of retribution, and most felt that the majority of injuries on their jobsites got reported. However, nearly half indicated it was best not to report minor injuries, and felt pressures to use their private insurance for work injury care. The prevalence of non-reporting and fear of reporting increased markedly with poorer measures of management safety justice (NOSACQ-50). Formal and informal policies and practices on jobsites likely influence injury reporting. © 2015 Wiley Periodicals, Inc.

Progress report within the series of GRS-F progress reports on reactor safety, sponsored by the Federal Ministry of Economics and Labour. Period: 1 January - 30 June 2003

International Nuclear Information System (INIS)

2003-01-01

The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of the investigations into the safety of nuclear power plants by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system ''Joint Safety Research Index'' of the CEC (commission of the european communities). The reports are arranged in sequence of their project numbers. (orig.) [de

Progress report within the series of GRS-F progress reports on reactor safety, sponsored by the Federal Ministry of Economics and Labour. Period: 1 July - 31 December 2003

International Nuclear Information System (INIS)

2004-01-01

The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of the investigations into the safety of nuclear power plants by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system ''Joint Safety Research Index'' of the CEC (commission of the european communities). The reports are arranged in sequence of their project numbers. (orig.) [de

Progress report within the series of GRS-F progress reports on reactor safety, sponsored by the Federal Ministry of Economics and Technology. Period: 1 January - 30 June, 2002

International Nuclear Information System (INIS)

2002-01-01

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technologie (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order to the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Managment Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.) [de

Progress report within the series of GRS-F progress reports on reactor safety, sponsored by the Federal Ministry of Economics and Technology. Period: 1 July - 31 December 2001

International Nuclear Information System (INIS)

2002-01-01

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technologie (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order to the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Managment Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.) [de

Results of evaluation of periodic safety review for No. 1 plant in Mihama Power Station, Kansai Electric Power Co., Inc

International Nuclear Information System (INIS)

1994-01-01

No. 1 plant in Mihama Power Station started the commercial power generation in November, 1970, and has continued the operation for more than 23 years. During this period, the counter measures to troubles, periodic inspections and the maintenance by the electric power company have been carried out. These states of No. 1 plant in Mihama Power Station for more than 23 years are to be recollected from the view-points of the comprehensive evaluation of operation experiences and the reflection of latest technological knowledge, and the safety and reliability are to be further improved in the periodic safety review. Agency of Natural Resources and Energy evaluated the report of the periodic safety review for No. 1 plant in Mihama Power Station made by Kansai Electric Power Co., and summarized the results. The course of the evaluation of the report is shown. The facility utilization factor is 43.3% on the average of about 23 years, but in the last 10 years, it was improved to 69.4%. In the last five years, the rate of occurrence of unexpected shutoff was 0.6 times/year. These are the results of preventive maintenance and the improvement of the facilities and operation management. Operation management, maintenance management, fuel management, radiation control, and radioactive waste management have been carried out properly. The work plan for preventing disasters was established, and the experience of troubles and the latest technological knowledge were well reflected to improve the safety. (K.I.)

2011 NASA Range Safety Annual Report

Science.gov (United States)

Dumont, Alan G.

2012-01-01

Welcome to the 2011 edition of the NASA Range Safety Annual Report. Funded by NASA Headquarters, this report provides a NASA Range Safety overview for current and potential range users. As is typical with odd year editions, this is an abbreviated Range Safety Annual Report providing updates and links to full articles from the previous year's report. It also provides more complete articles covering new subject areas, summaries of various NASA Range Safety Program activities conducted during the past year, and information on several projects that may have a profound impact on the way business will be done in the future. Specific topics discussed and updated in the 2011 NASA Range Safety Annual Report include a program overview and 2011 highlights; Range Safety Training; Range Safety Policy revision; Independent Assessments; Support to Program Operations at all ranges conducting NASA launch/flight operations; a continuing overview of emerging range safety-related technologies; and status reports from all of the NASA Centers that have Range Safety responsibilities. Every effort has been made to include the most current information available. We recommend this report be used only for guidance and that the validity and accuracy of all articles be verified for updates. Once again the web-based format was used to present the annual report. We continually receive positive feedback on the web-based edition and hope you enjoy this year's product as well. As is the case each year, contributors to this report are too numerous to mention, but we thank individuals from the NASA Centers, the Department of Defense, and civilian organizations for their contributions. In conclusion, it has been a busy and productive year. I'd like to extend a personal Thank You to everyone who contributed to make this year a successful one, and I look forward to working with all of you in the upcoming year.

Safety Basis Report

International Nuclear Information System (INIS)

R.J. Garrett

2002-01-01

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities

Safety Basis Report

Energy Technology Data Exchange (ETDEWEB)

R.J. Garrett

2002-01-14

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

Report on nuclear safety in EU applicant countries

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

Nuclear safety in the candidate countries to the European Union is a major issue which needs to be addressed in the frame of the enlargement process. The Heads of the nuclear safety Regulatory Bodies of the European Union member states having nuclear power plants, i.e. Belgium, Finland, France, Germany, Italy, the Netherlands, Spain, Sweden and the United Kingdom thought it was their duty to offer their assistance to the European Union institutions at a moment when the expansion of the Union is being considered. As a consequence, they decided to issue a report giving their collective opinion on nuclear safety in those applicant countries having at least one nuclear power reactor (Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, Slovenia) and covering: the status of the regulatory regime and regulatory body and the nuclear power plant safety status. This report is based on the knowledge they gained through multilateral assistance programmes, in particular the Phare programmes, and also through bilateral contacts. It must be stressed that in some cases, they recognised that their current knowledge was not sufficient to express a clear and exhaustive opinion. Also, it should be pointed out that the judgements are based on widely applied Western European design standards for the defence-in-depth and associated barriers. Quantitative comparisons of Probabilistic Safety Assessments have not been used as the available results are of widely different depth and quality. They also recognised that such a report could only present the situation at a given moment and they intend to periodically update it so as to reflect the changes which may occur in these countries. At this stage, the report does not cover radioactive waste or radiation protection issues in any detail. After they had taken the decision to issue this report, they decided to create an association, the Western European Nuclear Regulators Association (WENRA) in order to increase the co

Report on nuclear safety in EU applicant countries

International Nuclear Information System (INIS)

1999-03-01

Nuclear safety in the candidate countries to the European Union is a major issue which needs to be addressed in the frame of the enlargement process. The Heads of the nuclear safety Regulatory Bodies of the European Union member states having nuclear power plants, i.e. Belgium, Finland, France, Germany, Italy, the Netherlands, Spain, Sweden and the United Kingdom thought it was their duty to offer their assistance to the European Union institutions at a moment when the expansion of the Union is being considered. As a consequence, they decided to issue a report giving their collective opinion on nuclear safety in those applicant countries having at least one nuclear power reactor (Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, Slovenia) and covering: the status of the regulatory regime and regulatory body and the nuclear power plant safety status. This report is based on the knowledge they gained through multilateral assistance programmes, in particular the Phare programmes, and also through bilateral contacts. It must be stressed that in some cases, they recognised that their current knowledge was not sufficient to express a clear and exhaustive opinion. Also, it should be pointed out that the judgements are based on widely applied Western European design standards for the defence-in-depth and associated barriers. Quantitative comparisons of Probabilistic Safety Assessments have not been used as the available results are of widely different depth and quality. They also recognised that such a report could only present the situation at a given moment and they intend to periodically update it so as to reflect the changes which may occur in these countries. At this stage, the report does not cover radioactive waste or radiation protection issues in any detail. After they had taken the decision to issue this report, they decided to create an association, the Western European Nuclear Regulators Association (WENRA) in order to increase the co

RB research reactor Safety Report

International Nuclear Information System (INIS)

Sotic, O.; Pesic, M.; Vranic, S.

1979-04-01

This RB reactor safety report is a revised and improved version of the Safety report written in 1962. It contains descriptions of: reactor building, reactor hall, control room, laboratories, reactor components, reactor control system, heavy water loop, neutron source, safety system, dosimetry system, alarm system, neutron converter, experimental channels. Safety aspects of the reactor operation include analyses of accident causes, errors during operation, measures for preventing uncontrolled activity changes, analysis of the maximum possible accident in case of different core configurations with natural uranium, slightly and highly enriched fuel; influence of possible seismic events

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

International Nuclear Information System (INIS)

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

2005-02-01

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

Safety assessment of Olkiluoto NPP units 1 and 2. Decision of the Radiation and Nuclear Safety Authority regarding the periodic safety review of the Olkiluoto NPP

International Nuclear Information System (INIS)

2010-02-01

In this safety assessment the Radiation and Nuclear Safety Authority (STUK) has evaluated the safety of the Olkiluoto Nuclear Power Plant units 1 and 2 in connection with the periodic safety review. This safety assessment provides a summary of the reviews, inspections and continuous oversight carried out by STUK. The issues addressed in the assessment and the related evaluation criteria are set forth in the nuclear energy and radiation safety legislation and the regulations issued thereunder. The provisions of the Nuclear Energy Act concerning the safe use of nuclear energy, security and emergency preparedness arrangements, and waste management are specified in more detail in the Government Decrees and Regulatory Guides issued by STUK. Based on the assessment, STUK consideres that the Olkiluoto Nuclear Power Plant units 1 and 2 meet the set safety requirements for operational nuclear power plants, the emergency preparedness arrangements are sufficient and the necessary control to prevent the proliferation of nuclear weapons has been appropriately arranged. The physical protection of the Olkiluoto nuclear power plant is not yet completely in compliance with the requirements of Government Decree 734/2008, which came into force in December 2008. Further requirements concerning this issue based also on the principle of continuous improvement were included in the decision relating to the periodic safety review. The safety of the Olkiluoto nuclear power plant was assessed in compliance with the Government Decree on the Safety of Nuclear Power Plants (733/2008), which came into force in 2008. The decree notes that existing nuclear power plants need not meet all the requirements set out for new plants. Most of the design bases pertaining to the Olkiluoto 1 and 2 nuclear power plant units were set in the 1970s. Substantial modernisations have been carried out at the Olkiluoto 1 and 2 nuclear power plant units since their commissioning to improve safety. This is in line with

Reports on research programs in the field of reactor safety sponsored by the Federal Ministry of Research and Technology. Reported period: January 1 to June 30, 1993

International Nuclear Information System (INIS)

1993-01-01

Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the research program of the safety of LWR 1977 - 1980 of the BMFT. Another table of uses the same classification system as applied in the nuclear safety index of the CEC (Commision of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig.) [de

Reports on research programs in the field of reactor safety sponsored by the Federal Ministry of Research and Technology. Reported period: January 1 to June 30, 1994

International Nuclear Information System (INIS)

1994-01-01

Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the research program of the safety of LWR 1977 - 1980 of the BMFT. Another table of uses the same classification system as applied in the nuclear safety index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig.) [de

National nuclear safety report 1998. Convention on nuclear safety

International Nuclear Information System (INIS)

1998-01-01

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

Annual report on occupational safety 1985

International Nuclear Information System (INIS)

1986-09-01

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

Progress report on safety research of high-level waste management for the period April 1986 to March 1987

International Nuclear Information System (INIS)

Nakamura, Haruto; Tashiro, Shingo

1987-08-01

Researches on high-level waste management at the High Level Waste Management Laboratory and the Waste Safety Testing Facility Operation Division of the Japan Atomic Energy Research Institute in the fiscal year of 1986 are reviewed in the report. Topics in the three sections are as follows: 1) Non-radioactive research has been continued on Synroc irradiation and modellings of waste form leaching. 2) Research results are described in the section of Safety Evaluation for Geological Disposal on engineered barriers, field tests, safety assessment models, migration, natural analogue, seabed disposal and conceptual design of a repository. 3) Adsorption behaviour of plutonium on leach-containers and migration of leached cesium in a rock column are described in the section of Safety Examination of Vitrified Forms in the Hot Cells of WASTEF. (author)

ENSI's technical view on the periodic safety review 2008 of the nuclear power plant Goesgen

International Nuclear Information System (INIS)

2012-08-01

The owner of a license for a nuclear power plant operation in Switzerland has to undergo every 10 years a comprehensive safety check called 'periodic safety review' (PSR). The regulatory authority, the Swiss Federal Nuclear Safety Inspectorate (ENSI), reviews the documents supplied by the licensee. The Goesgen power plant (KKG) obtained its operation license and started operation in 1978. A first PSR was performed in the years 1996 to 1998 (PSR 1998) and reported. KKG delivered an analysis of the safety status, an evaluation of subsystems as well as test reports. The new PSR covers the period 1998 to 2007. The basis of the evaluation by ENSI is the new nuclear energy law in force since 1 February 2005. In comparison to PSR 1998, new aspects have to be considered like the description of the safety concept, including the technical safety classification of buildings, systems and components, or consideration of the protection objective 'limitation of the radiation exposure'. The PSR 2008 is focussed on the estimate of the nuclear safety of KKG. Basically, for the operation of a nuclear power plant, a sufficient protection has to be guaranteed against the release of radioactive materials to the environment as well as the irradiation of persons, during normal operation as well as in the case of accidents. The licensee of a nuclear power plant in operation must retrofit his plant according to the experience already gained and the state-of-the-art. The purpose of the PSR is to check the quality of the plant in the domain of safety. A probabilistic safety assessment (PSA) study must prove that the probability of damages to the reactor core is smaller than 10 -5 /year. In Switzerland the life time of a nuclear power plant is not limited by a fixed maximum time of operation. On the contrary, the limitation proceeds from safety criteria. Insufficiencies in the plant design are often recognized only through the evolution of the technique or some unexpected events. Ageing

Progress report on safety research on radioactive waste management for the period April 1995 to March 1996

International Nuclear Information System (INIS)

Sekine, Keiichi; Muraoka, Susumu; Banba, Tsunetaka

1997-03-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research during the fiscal year of 1995 (April 1, 1995 - March 31, 1996). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms. 2) In the safety evaluation study for shallow land disposal, migration behavior of radionuclides in a soil layer was studied. 3) In the safety evaluation study for geological disposal, chemical behavior of radionuclides in water, nuclide migration in geosphere and groundwater flow system were studied. Migration of uranium series nuclides in uranium ore deposit was studied as a part of natural analog study. (author)

List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC. Reported period: April 1 - June 30, 1987

International Nuclear Information System (INIS)

1987-08-01

The list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

Aviation Safety Reporting System: Process and Procedures

Science.gov (United States)

Connell, Linda J.

1997-01-01

The Aviation Safety Reporting System (ASRS) was established in 1976 under an agreement between the Federal Aviation Administration (FAA) and the National Aeronautics and Space Administration (NASA). This cooperative safety program invites pilots, air traffic controllers, flight attendants, maintenance personnel, and others to voluntarily report to NASA any aviation incident or safety hazard. The FAA provides most of the program funding. NASA administers the program, sets its policies in consultation with the FAA and aviation community, and receives the reports submitted to the program. The FAA offers those who use the ASRS program two important reporting guarantees: confidentiality and limited immunity. Reports sent to ASRS are held in strict confidence. More than 350,000 reports have been submitted since the program's beginning without a single reporter's identity being revealed. ASRS removes all personal names and other potentially identifying information before entering reports into its database. This system is a very successful, proof-of-concept for gathering safety data in order to provide timely information about safety issues. The ASRS information is crucial to aviation safety efforts both nationally and internationally. It can be utilized as the first step in safety by providing the direction and content to informed policies, procedures, and research, especially human factors. The ASRS process and procedures will be presented as one model of safety reporting feedback systems.

Progress report on safety research on radioactive waste management for the period April 1993 to March 1995

Energy Technology Data Exchange (ETDEWEB)

Sekine, Keiichi; Muraoka, Susumu; Banba, Tsunetaka [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [eds.

1996-03-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research during the fiscal years of 1993 and 1994 (April 1, 1993 - March 31, 1995). The topics are as follows: (1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. (2) In the safety evaluation study for shallow land disposal, migration behaviour of nuclides in the soil layer was studied. (3) In the safety evaluation study for geological disposal, chemical behaviour of radionuclides in water, nuclide migration in geosphere and groundwater flow system were studied. Migration of uranium series nuclides in uranium ore deposit was studied as a part of natural analogue study. (author).

Progress report on safety research on radioactive waste management for the period April 1993 to March 1995

International Nuclear Information System (INIS)

Sekine, Keiichi; Muraoka, Susumu; Banba, Tsunetaka

1996-03-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research during the fiscal years of 1993 and 1994 (April 1, 1993 - March 31, 1995). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. 2) In the safety evaluation study for shallow land disposal, migration behaviour of nuclides in the soil layer was studied. 3) In the safety evaluation study for geological disposal, chemical behaviour of radionuclides in water, nuclide migration in geosphere and groundwater flow system were studied. Migration of uranium series nuclides in uranium ore deposit was studied as a part of natural analogue study. (author)

Progress report on safety research on radioactive waste management for the period April 1992 to March 1993

International Nuclear Information System (INIS)

Muraoka, Susumu; Senoo, Muneaki; Sekine, Keiichi

1994-03-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Shallow Land Migration Laboratory, Environmental Geochemistry Laboratory and Environmental Radiochemistry Laboratory of the Department of Environmental Safety Research during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. 2) In the safety evaluation study for shallow land disposal, migration behavior in the soil layer were studied. 3) In the safety evaluation study for geological disposal, chemical behavior of nuclide in water, nuclide migration and fixation in geosphere were studied. 4) Distribution of uranium and migration of uranium series nuclide in uranium ore were examined as a natural analogue study. (author)

List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC. Reported period: January 1 to June 30, 1994

International Nuclear Information System (INIS)

1994-01-01

This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesministerium fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (ISTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. (orig./HP) [de

List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC. Reported period: July 1 to December 31, 1993

International Nuclear Information System (INIS)

1993-01-01

This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesministerium fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (ISTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. (orig./HP) [de

Report on safety related occurrences and reactor trips July 1, 1977 - December 31, 1977

International Nuclear Information System (INIS)

Andermo, L.; Sundman, B.

1974-04-01

This is a systematically arranged report on all reported safety related occurrences and reactor trips in Swedish nuclear power plants in operation during July 1 to December 31, 1977 inclusive. The facilities involved are Barsebaeck 1 and 2, Oskarshamn 1 and 2 and Ringhals 1 and 2. During this period of 6 months 48 safety related occurrences and 49 reactor trips have been reported to the Nuclear Power Inspectorate. Included is also one incident June 21 in Barsebaeck 2 which was not included in the last compilation of occurrences. As earlier experiences have shown it is to the greatest extent the conventional components which bring about the safety related occurrences or occurrences leading to outages or power reductions. However, the component errors discovered in the safety related systems have not affected the function of their redundant systems and other diverse systems have not been involved. Therefore the reactor safety has been satisfactory. The total number of reactor trips have increased nearly 30% since the last period. Those occurred during power operation however, were less. More than 50% of the reactor trips happened in the shutdown condition. The fact that even small deviations from prescribed operation result in automatic and safe shut down of the reactor, does not always imply a conflict with operational availability. The greatest outages are caused by occurrences withou02068NRM 0000169 450

Safety evaluation report of the Waste Isolation Pilot Plant safety analysis report: Contact-handled transuranic waste disposal operations

International Nuclear Information System (INIS)

1997-02-01

DOE 5480.23, Nuclear Safety Analysis Reports, requires that the US Department of Energy conduct an independent, defensible, review in order to approve a Safety Analysis Report (SAR). That review and the SAR approval basis is documented in this formal Safety Evaluation Report (SER). This SER documents the DOE's review of the Waste Isolation Pilot Plant SAR and provides the Carlsbad Area Office Manager, the WIPP SAR approval authority, with the basis for approving the safety document. It concludes that the safety basis documented in the WIPP SAR is comprehensive, correct, and commensurate with hazards associated with planned waste disposal operations

Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending December 31, 1991

International Nuclear Information System (INIS)

Cash, R.J.; Dukelow, G.T.; Atwood, J.M.

1992-01-01

This quarterly report provides a status of the activities underway at the Hanford Site on the ferrocyanide safety issues as requested by the Defense Nuclear Facilities Safety Board (DNFSB) in their Recommendation 90-7 (FR 1990). In March 1991, an DNFSB Implementation Plan (Cash 1991a) was prepared and sent to the DNFSB responding to the six parts of Recommendation 90-7. All of the activities in the DNFSB Implementation Plan are underway and the status of each is described

Health and Safety Research Division progress report for the period October 1, 1991--March 31, 1993

International Nuclear Information System (INIS)

Berven, B.A.

1993-09-01

This is a progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology, Biological and Radiation Physics, Chemical Physics, Biomedical and Environmental Information Analysis, Risk Analysis, Center for Risk Management, Associate Laboratories for Excellence in Radiation Technology (ALERT), and Contributions to National and Lead Laboratory Programs and Assignments--Environmental Restoration

Health and Safety Research Division progress report for the period October 1, 1991--March 31, 1993

Energy Technology Data Exchange (ETDEWEB)

Berven, B.A.

1993-09-01

This is a progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology, Biological and Radiation Physics, Chemical Physics, Biomedical and Environmental Information Analysis, Risk Analysis, Center for Risk Management, Associate Laboratories for Excellence in Radiation Technology (ALERT), and Contributions to National and Lead Laboratory Programs and Assignments--Environmental Restoration.

Westinghouse Hanford Company health and safety performance report

International Nuclear Information System (INIS)

Rogers, L.

1996-01-01

Topping the list of WHC Safety recognition during this reporting period is a commendation received from the National Safety Council (NSC). The NSC bestowed their Award of Honor upon WHC for significant reduction of incidence rates during CY 1995. The award is based upon a reduction of 48 % or greater in cases involving days away from work, a 30 % or greater reduction in the number of days away, and a 15% or greater reduction in the total number of occupational injuries and illnesses. (page 2-1). A DOE-HQ review team representing the Office of Envirorunent, Safety and Health (EH), visited the Hanford Site during several weeks of the quarter. Ile 40-member Safety Management Evaluation Team (SMET) assessed WHC in the areas of management responsibility, comprehensive requirements, and competence commensurate with responsibility. As part of their new approach to oversight, they focused on the existence of management systems and programs (comparable approach to VPP). Plant/project areas selected for review within WHC were PFP, B Plant/WESF, Tank Farms, and K-Basins (page 2-2). Effective safety meetings, prejob safety meetings, etc., are a cornerstone of any successful safety program. In an effort to improve the reporting of safety meetings, the Safety/Security Meeting Report form was revised. It now provides a mechanism for recording and tracking safety issues (page 2-4). WHC has experienced an increase in the occupational injury and illness incidence rates during the first quarter of CY 1996. Trends show this increase can be partially attributed to inattention to workplace activities due 0999to the uncertainty Hanford employees currently face with recent reduction of force, reorganization, and reengineering efforts (page 2-7). The cumulative CY 1995 lost/restricted workday case incidence rate for the first quarter of CY 1996 (1.28) is 25% below the DOE CY 1991-93 average (1.70). However, the incidence rate increased 24% from the CY 1995 rate of 1.03 (page 2-8). The

Westinghouse Hanford Company health and safety performance report

Energy Technology Data Exchange (ETDEWEB)

Rogers, L.

1996-05-15

Topping the list of WHC Safety recognition during this reporting period is a commendation received from the National Safety Council (NSC). The NSC bestowed their Award of Honor upon WHC for significant reduction of incidence rates during CY 1995. The award is based upon a reduction of 48 % or greater in cases involving days away from work, a 30 % or greater reduction in the number of days away, and a 15% or greater reduction in the total number of occupational injuries and illnesses. (page 2-1). A DOE-HQ review team representing the Office of Envirorunent, Safety and Health (EH), visited the Hanford Site during several weeks of the quarter. Ile 40-member Safety Management Evaluation Team (SMET) assessed WHC in the areas of management responsibility, comprehensive requirements, and competence commensurate with responsibility. As part of their new approach to oversight, they focused on the existence of management systems and programs (comparable approach to VPP). Plant/project areas selected for review within WHC were PFP, B Plant/WESF, Tank Farms, and K-Basins (page 2-2). Effective safety meetings, prejob safety meetings, etc., are a cornerstone of any successful safety program. In an effort to improve the reporting of safety meetings, the Safety/Security Meeting Report form was revised. It now provides a mechanism for recording and tracking safety issues (page 2-4). WHC has experienced an increase in the occupational injury and illness incidence rates during the first quarter of CY 1996. Trends show this increase can be partially attributed to inattention to workplace activities due 0999to the uncertainty Hanford employees currently face with recent reduction of force, reorganization, and reengineering efforts (page 2-7). The cumulative CY 1995 lost/restricted workday case incidence rate for the first quarter of CY 1996 (1.28) is 25% below the DOE CY 1991-93 average (1.70). However, the incidence rate increased 24% from the CY 1995 rate of 1.03 (page 2-8). The

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

The aviation safety reporting system

Science.gov (United States)

Reynard, W. D.

1984-01-01

The aviation safety reporting system, an accident reporting system, is presented. The system identifies deficiencies and discrepancies and the data it provides are used for long term identification of problems. Data for planning and policy making are provided. The system offers training in safety education to pilots. Data and information are drawn from the available data bases.

Results of evaluation of periodic safety review for No. 1 plant in Fukushima No. 1 Nuclear Power Station, Tokyo Electric Power Co., Inc

International Nuclear Information System (INIS)

1994-01-01

No. 1 plant in Fukushima No. 1 Nuclear Power Station started the commercial power generation in March, 1971, and has continued the operation for more than 23 years. During this period, the countermeasures to troubles, periodic inspections, and the maintenance by the electric power company have been carried out. These states are to be recollected from the viewpoints of the comprehensive evaluation of the operation experiences and the reflection of the latest technological knowledge, and the safety and reliability are to be further improved in the periodic safety review. Agency of Natural Resources and Energy evaluated the report of the periodic safety review for No. 1 plant in Fukushima No. 1 Nuclear Power Station, and summarized the results. The course of the evaluation of the report is shown. The facility utilization factor was 50.1% on the average of about 23 years, but in the last 10 years, it was improved to 59.7%. In the last five years, the rate of occurrence of unexpected shutdown was 0.4 times/year. These are the results of preventive maintenance and the improvement of the facilities and operation management. Operation management, maintenance management, fuel management, radiation control, radioactive waste management and the reflection of the experience of troubles and the latest technological knowledge to the improvement of safety have been carried out properly. The work plan for disaster prevention was established. (K.I.)

Current Status of Periodic Safety Review of HANARO Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Kim, Minjin; Ahn, Guk-Hoon; Lee, Choong Sung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

A PSR for a research reactor became a legal requirement as the Nuclear Safety Act was amended and came into effect in 2014. This paper describes the current status and methodology of the first Periodic Safety Review (PSR) of HANARO that is being performed. The legal requirements, work plan, and process of implementing a PSR are described. Because this is the first PSR for a research reactor, it is our understating that the operating organization and regulatory body should communicate well with each other to complete the PSR in a timely manner. The first PSR of HANARO is under way. In order to achieve a successful result, activities of the operation organization such as scheduling, maintaining consistency in input data for review, and reviewing the PSR reports that will require intensive resources should be well planned. This means the operating organization needs to incorporate appropriate measures to ensure the transfer of knowledge and expertise arising from the PSR via a contractor to the operation organization. It is desirable for the Regulatory Body to be involved in all stage of the PSR to prevent any waste of resources and minimize the potential for a reworking of the PSR and the need for an additional assessment and review as recommended by foreign experts.

Implementation and evaluation of a prototype consumer reporting system for patient safety events.

Science.gov (United States)

Weingart, Saul N; Weissman, Joel S; Zimmer, Karen P; Giannini, Robert C; Quigley, Denise D; Hunter, Lauren E; Ridgely, M Susan; Schneider, Eric C

2017-08-01

No methodologically robust system exists for capturing consumer-generated patient safety reports. To address this challenge, we developed and pilot-tested a prototype consumer reporting system for patient safety, the Health Care Safety Hotline. Mixed methods evaluation. The Hotline was implemented in two US healthcare systems from 1 February 2014 through 30 June 2015. Patients, family members and caregivers associated with two US healthcare systems. A consumer-oriented incident reporting system for telephone or web-based administration was developed to elicit medical mistakes and care-related injuries. Key informant interviews, measurement of website traffic and analysis of completed reports. Key informants indicated that Hotline participation was motivated by senior leaders' support and alignment with existing quality and safety initiatives. During the measurement period from 1 October 2014 through 30 June 2015, the home page had 1530 visitors with a unique IP address. During its 17 months of operation, the Hotline received 37 completed reports including 20 mistakes without harm and 15 mistakes with injury. The largest category of mistake concerned problems with diagnosis or advice from a health practitioner. Hotline reports prompted quality reviews, an education intervention, and patient follow-ups. While generating fewer reports than its capacity to manage, the Health Care Safety Hotline demonstrated the feasibility of consumer-oriented patient safety reporting. Further research is needed to understand how to increase consumers' use of these systems. © The Author 2017. Published by Oxford University Press in association with the International Society for Quality in Health Care. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com

The Nirex Safety Assessment Research Programme; annual report for 1988/89

International Nuclear Information System (INIS)

Cooper, M.J.

1989-07-01

This report summarises progress of the Nirex Safety Assessment Research Programme during 1988/89, in support of assessments of the post-emplacement radiological safety of a repository for the disposal of low-level and intermediate-level radioactive waste. During this period the assessments were concentrating on a comparative study of concepts and areas for deep emplacement of waste, in order to assist in the selection of preferred sites, and the research programme was therefore focussed on providing the data necessary for broad comparisons between different options to be made. (author)

Injury & Safety Report - Legacy

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The Injury & Safety Report is a mandatory post trip legal document observers fill out to report any injuries they have incurred, illnesses they have had, or...

Annual report on occupational safety 1987

International Nuclear Information System (INIS)

1988-01-01

This report presents detailed information on occupational safety relating to the Company's employees for 1987. Data are quoted in tables and text, together with data from the previous year for comparison where available. The report is presented under the following headings: radiological and non-radiological safety, incidents, appendices (statutory dose limits, nuclear incident criteria for reporting to ministers). (author)

Reports on research programs in the field of reactor safety sponsored by the Federal Ministry for Education, Science, Research and Technology. Reported period: January 1 to June 30, 1995

International Nuclear Information System (INIS)

1995-01-01

Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Research Management Division at the GRS within the framework of general informations of progress in reactor safety research. The individual reports are classified according to projects of the reactor safety research program. Another table uses the same classification system as applied in the nuclear safety index of the CEC (Commision of the European Communities), IAEA (International Atomic Energy Agency) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig./HP) [de

Program nuclear safety research: report 2000

International Nuclear Information System (INIS)

Muehl, B.

2001-09-01

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

Revision of nuclear power plants safety systems' routine testing assigned periodicity during the design extension period

International Nuclear Information System (INIS)

Skalozubov, V.I.; Kozlov, Yi.L.; Chulkyin, O.O.

2017-01-01

When nuclear power plants safety systems thermal equipment operation extending, a necessary requirement shall rely on revising the scheduled equipment tests frequency to optimize those tests schedule taking into account the equipment remained lifespan. On the one hand, there exists a need for tests frequency increase to detect ''hidden'' failures, and on the another, frequent tests cause a premature wear of the equipment. Proposed is an original method for optimizing the frequency of NPPs safety systems thermal engineering equipment testing. Essential in the proposed method is the optimization criterion chosen: index of security system failure probability non-exceedance during the beyond-design operating period as referred to the failure probability expected considering the equipment residual resource during the design operating period. The developed method implementation when applied to NPPs safety systems operated beyond the design service life at nuclear power plants with WWER-1000 series reactors, allowed to establish that the optimal tests frequency makes half the designed one when the equipment service life is extended by five years and three times less that the designed frequency when subject lifespan extended by 10 years.

Human Factors Evaluation of Procedures for Periodic Safety Review of Yonggwang Unit no. 1, 2

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

2006-01-15

This report describes the results of human factors assessment on the plant operating procedures as part of Periodic Safety Review(PSR) of Yonggwang Nuclear Power Plant Unit no. 1, 2. The suitability of item and appropriateness of format and structure in the key operating procedures of nuclear power plants were investigated by the review of plant operating experiences and procedure documents, field survey, and experimental assessment on some part of procedures. A checklist was used to perform this assessment and record the review results. The reviewed procedures include EOP(Emergency Operating Procedures), GOP(General Operating Procedures), AOP(Abnormal Operating Procedures), and management procedures of some technical departments. As results of the assessments, any significant problem challenging the safety was not found on the human factors in the operating procedures. However, several small items to be changed and improved were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on the operating procedure.

Analytical Chemistry Division. Annual progress report for period ending December 31, 1981

International Nuclear Information System (INIS)

Lyon, W.S.

1982-04-01

The functions of the Analytical Chemistry Division fall into three general categories: (1) analytical research, development, and implementation; (2) programmatic research, development and utilization; (3) technical support. The Division is organized into five major sections each of which may carry out any type of work falling into the thre categories mentioned above. Chapters 1 through 5 of this report highlight progress within the five sections which are: analytical methodology; mass and emission spectrometry; analytical technical support; bio/organic analysis section; and nuclear and radiochemical analysis. A short summary introduces each chapter to indicate work scope. Information about quality assurance and safety programs is presented in Chapter 6, along with a tabulation of analyses rendered. Chapter 7 covers supplementary activities. Chapter 8 is on presentation of research results (publications, articles reviewed or referred for periodicals). Approximately 56 articles, 31 proceedings publications and 33 reports have been published, and 119 oral presentations given during this reporting period

Analytical Chemistry Division. Annual progress report for period ending December 31, 1981

Energy Technology Data Exchange (ETDEWEB)

Lyon, W. S. [ed.

1982-04-01

The functions of the Analytical Chemistry Division fall into three general categories: (1) analytical research, development, and implementation; (2) programmatic research, development and utilization; (3) technical support. The Division is organized into five major sections each of which may carry out any type of work falling into the thre categories mentioned above. Chapters 1 through 5 of this report highlight progress within the five sections which are: analytical methodology; mass and emission spectrometry; analytical technical support; bio/organic analysis section; and nuclear and radiochemical analysis. A short summary introduces each chapter to indicate work scope. Information about quality assurance and safety programs is presented in Chapter 6, along with a tabulation of analyses rendered. Chapter 7 covers supplementary activities. Chapter 8 is on presentation of research results (publications, articles reviewed or referred for periodicals). Approximately 56 articles, 31 proceedings publications and 33 reports have been published, and 119 oral presentations given during this reporting period.

Periodic safety review of the experimental fast reactor JOYO. Review of aging management

International Nuclear Information System (INIS)

Isozaki, Kazunori; Ogawa, To-ru; Nishino, Kazunari

2005-05-01

Periodic safety review (Review of the aging management) which consisted of ''Technical review on aging for the safety related structures, systems and components'' and ''Establishment a long term maintenance program'' was carried out up to April 2005. 1. Technical review on aging for the safety related structures, systems and components. It was technically confirmed to prevent the loss of function of the safety related structures, systems and components due to aging phenomena, which (1) irradiation damage, (2) corrosion, (3) abrasion and erosion, (4) thermal aging, (5) creep and fatigue, (6) Stress Corrosion Cracking, (7) insulation deterioration and (8) general deterioration, under the periodic monitoring or renewal of them. 2. Establishment of long term maintenance program. The long term maintenance during JFY2005 to 2014 were established based on the technical review on aging for the safety related structures, systems and components. It was evaluated that the inspection and renewal based on the long term maintenance program, in addition to the spontaneous inspection of the long term voluntary long-term inspection plan, could prevent the loss of function of the safety related structures, systems and components. (author)

Enhancing nuclear safety. Annual report 2014. Financial report 2014

International Nuclear Information System (INIS)

2015-01-01

After some introductory texts proposed by several IRSN head managers, and a brief presentation of some key data illustrating the activity, the annual report presents the main strategic orientations, notably in the field of knowledge management, and of information and communication. After some images illustrating the past year, activities are presented. They first deal with safety: Reactor safety (operating experience feedback), From decommissioning old reactors to designing those of the future, Safety of laboratories and plants, Safety regarding risks due to infrastructure near nuclear facilities, Reactor aging, Fuel: research on corrosion and deformation, Research and assessments for improved understanding of accident situations, Earthquakes: research and assessments, About defense, Geological disposal of radioactive waste. They secondly deal with security and non-proliferation (nuclear security, nuclear non-proliferation, chemical weapon ban), thirdly with radiation protection for human and environment health (environment monitoring, radionuclide transfer in the environment, radon and polluted sites, human exposure, radiation protection in the workplace, effects of low-dose chronic exposures, Organization of radiation protection at the European level, protection in health care), and fourthly with emergency and post-accident situations (emergency and post-accident preparedness and response, Emergency response tools). The next part of the activity report addresses issues related to efficiency: Real estate program (construction projects get started), Hygiene, safety, social responsibility, Human resources, Organization chart, Board of directors, Steering committee for the nuclear defense expertise Division - CODEND, Scientific council, Ethics commission composition, Nuclear safety and radiation protection Research policy committee - COR. The financial report proposes a management report, financial statements with an appendix to annual accounts, and an auditor

Template for safety reports with descriptive example

International Nuclear Information System (INIS)

1995-12-01

This report provides a template for future safety reports on long-term safety in support of important decisions and permit applications in connection with the construction of a deep repository system. The template aims at providing a uniform structure for describing long-term safety, after the repository has been closed and sealed. The availability of such a structure will simplify both preparation and review of the safety reports, and make it possible to follow how safety assessments are influenced by the progressively more detailed body of data that emerges. A separate section containing 'descriptive examples' has been appended to the template. This section illustrates what the different chapters of the template should contain. 279 refs

Template for safety reports with descriptive example

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

This report provides a template for future safety reports on long-term safety in support of important decisions and permit applications in connection with the construction of a deep repository system. The template aims at providing a uniform structure for describing long-term safety, after the repository has been closed and sealed. The availability of such a structure will simplify both preparation and review of the safety reports, and make it possible to follow how safety assessments are influenced by the progressively more detailed body of data that emerges. A separate section containing `descriptive examples` has been appended to the template. This section illustrates what the different chapters of the template should contain. 279 refs.

Mark I containment, short term program. Safety evaluation report

International Nuclear Information System (INIS)

1977-12-01

Presented is a Safety Evaluation Report (SER) prepared by the Office of Nuclear Reactor Regulation addressing the Short Term Program (STP) reassessment of the containment systems of operating Boiler Water Reactor (BWR) facilities with the Mark I containment system design. The information presented in this SER establishes the basis for the NRC staff's conclusion that licensed Mark I BWR facilities can continue to operate safely, without undue risk to the health and safety of the public, during an interim period of approximately two years while a methodical, comprehensive Long Term Program (LTP) is conducted. This SER also provides one of the basic foundations for the NRC staff review of the Mark I containment systems for facilities not yet licensed for operation

Safety and health annual report 1996

International Nuclear Information System (INIS)

1997-01-01

The 1996 report on the Health and Safety performance of the nuclear fuel cycle company BNFL at its sites in the United Kingdom demonstrates a continuing improvement. The site locations and developments are briefly described and international developments in subsidiary organisations noted. Other sections of the report cover health and safety policy, radiological and industrial safety, emergency planning, incidents, occupational health services, compensation scheme developments, transport, putting radiation in perspective, and safety and health research. Data are provided on: radioactive discharges; industrial safety of BNFL and contractors' employees; radiation dose summaries for BNFL and contractors' employees. There is evidence of the expected plateauing out of doses to BNFL employees at a level less than or similar to background radiation. (UK)

Report on the research projects into the safety of nuclear power plants in operation sponsored by Federal Ministry of Economics and Labour. Period under report: 1 January - 30 June 2004

International Nuclear Information System (INIS)

2004-01-01

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Arbeit (BMWA) (Federal Ministry of Economics and Labour) sponsors research projects into the safety of nuclear power plants in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations and to the further development of safety technology. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWA, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The reports are published by the Research Management Division of GRS. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWA does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Health and Safety Research Division progress report for period ending April 30, 1978

Energy Technology Data Exchange (ETDEWEB)

Kaye, S.V.

1978-08-01

The research goal of the Health and Safety Research Division is to conduct basic and applied research that contributes new scientific knowledge with emphasis in biophysical areas that lead to a better understanding of how alternative energy-related technologies affect man. Included in the basic research are fundamental processes that are important to understand formation, mobility, toxicity, detection, and characterization of pollutants. The applied research includes the integration of data from basic and applied studies through development of concepts and methodologies that can be used for energy-related assessments with primary focus on the health and safety of man. The division has no responsibilities for on-site health and safety.

49 CFR 385.333 - What happens at the end of the 18-month safety monitoring period?

Science.gov (United States)

2010-10-01

... SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.333 What happens at the end of the 18-month safety monitoring period? (a) If a safety audit has been performed within... the same basis as any other carrier. (d) If a safety audit or compliance review has not been performed...

Safety management as a foundation for evidence-based aeromedical standards and reporting of medical events.

Science.gov (United States)

Evans, Anthony D; Watson, Dougal B; Evans, Sally A; Hastings, John; Singh, Jarnail; Thibeault, Claude

2009-06-01

The different interpretations by States (countries) of the aeromedical standards established by the International Civil Aviation Organization has resulted in a variety of approaches to the development of national aeromedical policy, and consequently a relative lack of harmonization. However, in many areas of aviation, safety management systems have been recently introduced and may represent a way forward. A safety management system can be defined as "A systematic approach to managing safety, including the necessary organizational structures, accountabilities, policies, and procedures" (1). There are four main areas where, by applying safety management principles, it may be possible to better use aeromedical data to enhance flight safety. These are: 1) adjustment of the periodicity and content of routine medical examinations to more accurately reflect aeromedical risk; 2) improvement in reporting and analysis of routine medical examination data; 3) improvement in reporting and analysis of in-flight medical events; and 4) support for improved reporting of relevant aeromedical events through the promotion of an appropriate culture by companies and regulatory authorities. This paper explores how the principles of safety management may be applied to aeromedical systems to improve their contribution to safety.

Safety culture in design. Final report

International Nuclear Information System (INIS)

Macchi, L.; Pietikaeinen, E.; Liinasuo, M.; Savioja, P.; Reiman, T.; Wahlstroem, M.; Kahlbom, U.; Rollenhagen, C.

2013-04-01

In this report we approach design from a safety culture approach As this research area is new and understudied, we take a wide scope on the issue. Different theoretical perspectives that can be taken when improving safety of the design process are considered in this report. We suggest that in the design context the concept of safety culture should be expanded from an organizational level to the level of the network of organizations involved in the design activity. The implication of approaching the design process from a safety culture perspective are discussed and the results of the empirical part of the research are presented. In the interview study in Finland and Sweden we identified challenges and opportunities in the design process from safety culture perspective. Also, a small part of the interview study concentrated on state of the art human factors engineering (HFE) practices in Finland and the results relating to that are presented. This report provide a basis for future development of systematic good design practices and for providing guidelines that can lead to safe and robust technical solutions. (Author)

Safety culture in design. Final report

Energy Technology Data Exchange (ETDEWEB)

Macchi, L.; Pietikaeinen, E.; Liinasuo, M.; Savioja, P.; Reiman, T.; Wahlstroem, M. [VTT Technical Research Centre of Finland, Espoo (Finland); Kahlbom, U. [Risk Pilot AB, Stockholm (Sweden); Rollenhagen, C. [Vattenfall, Stockholm, (Sweden)

2013-04-15

In this report we approach design from a safety culture approach As this research area is new and understudied, we take a wide scope on the issue. Different theoretical perspectives that can be taken when improving safety of the design process are considered in this report. We suggest that in the design context the concept of safety culture should be expanded from an organizational level to the level of the network of organizations involved in the design activity. The implication of approaching the design process from a safety culture perspective are discussed and the results of the empirical part of the research are presented. In the interview study in Finland and Sweden we identified challenges and opportunities in the design process from safety culture perspective. Also, a small part of the interview study concentrated on state of the art human factors engineering (HFE) practices in Finland and the results relating to that are presented. This report provide a basis for future development of systematic good design practices and for providing guidelines that can lead to safe and robust technical solutions. (Author)

Status of safety analysis reports

Energy Technology Data Exchange (ETDEWEB)

Cserhati, A

1999-06-01

The safety regulation connected to both of the Atomic Acts from 1980 and 1996 requires preparation of the Preliminary Safety Analysis Report (PSAR) as well as Final SAR (FSAR). In this respect the licensing procedure for the construction and commissioning of Paks NPP did not formally deviate from the standards applied in developed countries; this is particularly true if comparison is made with the standards applied for commissioning NPPs in the second half of the seventies. By the time the overall development of internationally accepted safety standards and some existing deficiencies of earlier SAR made necessary a general reassessment of the plant safety (AGNES project). The carried out PSR for Paks-1 and 2 also added a valuable contribution to the SAR content, however a formal update of SAR is not made yet. A Hungarian nuclear authority decree from 1997 obligates the licensee to prepare and submit a major upgrade of FSAR until the mid of 2000, after finishing the PSR for Paks-3 and 4. From this date a periodic update of FSAR is required every year. The operational license renewal affects only the PSR but not the FSAR updating. The new Nuclear Safety Code outlines the contents of PSAR and FSAR, based on US NRC Reg. Guide 1. 70. Rev. 3. Hungary by now can fulfill the upgrading of SAR without major external technical or financial help. The AGNES project covered the safety analysis chapters of SAR. It was financed mainly by the country. In the project there have been involved in limited cases as performers the VTT (Finland), Belgatom (Belgium), GRS (Germany), etc., the IVO (Finland) fulfilled tasks of an independent reviewer for safety analysis. The AGNES had certain interconnection with the similar IAEA RER safety reassessment project for WWER-440/213. The PSR for Paks-1 and 2 have been carried out by the Paks staff from the resources of the plant. During the evaluation of several parts of Paks-3 and 4 PSR documentation the authority intends to use certain

Status of safety analysis reports

International Nuclear Information System (INIS)

Cserhati, A.

1999-01-01

The safety regulation connected to both of the Atomic Acts from 1980 and 1996 requires preparation of the Preliminary Safety Analysis Report (PSAR) as well as Final SAR (FSAR). In this respect the licensing procedure for the construction and commissioning of Paks NPP did not formally deviate from the standards applied in developed countries; this is particularly true if comparison is made with the standards applied for commissioning NPPs in the second half of the seventies. By the time the overall development of internationally accepted safety standards and some existing deficiencies of earlier SAR made necessary a general reassessment of the plant safety (AGNES project). The carried out PSR for Paks-1 and 2 also added a valuable contribution to the SAR content, however a formal update of SAR is not made yet. A Hungarian nuclear authority decree from 1997 obligates the licensee to prepare and submit a major upgrade of FSAR until the mid of 2000, after finishing the PSR for Paks-3 and 4. From this date a periodic update of FSAR is required every year. The operational license renewal affects only the PSR but not the FSAR updating. The new Nuclear Safety Code outlines the contents of PSAR and FSAR, based on US NRC Reg. Guide 1. 70. Rev. 3. Hungary by now can fulfill the upgrading of SAR without major external technical or financial help. The AGNES project covered the safety analysis chapters of SAR. It was financed mainly by the country. In the project there have been involved in limited cases as performers the VTT (Finland), Belgatom (Belgium), GRS (Germany), etc., the IVO (Finland) fulfilled tasks of an independent reviewer for safety analysis. The AGNES had certain interconnection with the similar IAEA RER safety reassessment project for WWER-440/213. The PSR for Paks-1 and 2 have been carried out by the Paks staff from the resources of the plant. During the evaluation of several parts of Paks-3 and 4 PSR documentation the authority intends to use certain

Chemical Safety Vulnerability Working Group Report

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

This report marks the culmination of a 4-month review conducted to identify chemical safety vulnerabilities existing at DOE facilities. This review is an integral part of DOE's efforts to raise its commitment to chemical safety to the same level as that for nuclear safety.

Periodic Safety Review in Interim Storage Facilities - Current Regulation and Experiences in Germany

International Nuclear Information System (INIS)

Neles, Julia Mareike; Schmidt, Gerhard

2014-01-01

Periodic safety reviews in nuclear power plants in Germany have been performed since the end of the 1980's as an indirect follow-up of the accident in Chernobyl and, in the meantime, are formally required by law. During this process the guidelines governing this review were developed in stages and reached their final form in 1996. Interim storage facilities and other nuclear facilities at that time were not included, so the guidelines were solely focused on the specific safety issues of nuclear power plants. Following IAEA's recommendations, the Western European Nuclear Regulator Association (WENRA) introduced PSRs in its safety reference levels for storage facilities (current version in WGWD report 2.1 as of Feb 2011: SRLs 59 - 61). Based on these formulations, Germany improved its regulation in 2010 with a recommendation of the Nuclear Waste Management Commission (Entsorgungskommission, ESK), an expert advisory commission for the federal regulatory body BMU. The ESK formulated these detailed requirements in the 'ESK recommendation for guides to the performance of periodic safety reviews for interim storage facilities for irradiated fuel elements and heat-generating radioactive waste'. Before finalization of the guideline a test phase was introduced, aimed to test the new regulation in practice and to later include the lessons learned in the final formulation of the guideline. The two-year test phase started in October 2011 in which the performance of a PSR will be tested at two selected interim storage facilities. Currently these recommendations are discussed with interested/concerned institutions. The results of the test phase shall be considered for improvements of the draft and during the final preparation of guidelines. Currently the PSR for the first ISF is in an advanced stage, the second facility just started the process. Preliminary conclusions from the test phase show that the implementation of the draft guideline requires interpretation. The aim of a

Safety analysis report 231-Z Building

Energy Technology Data Exchange (ETDEWEB)

Powers, C.S.

1989-03-01

This report provides an intensive review of the nuclear safety of the operation of the 231-Z Building. For background information complete descriptions of the floor plan, building services, alarm systems, and glove box systems are included in this report. In addition, references are included to The Plutonium Laboratory Radiation Work Procedures, Safety Guides, 231-Z Operating Procedures Manual and Nuclear Materials accountability Procedures. Engineered and administrative features contribute to the overall safety of personnel, the building, and environs. The consequences of credible incidents were considered and are discussed.

Hot Cell Facility (HCF) Safety Analysis Report

Energy Technology Data Exchange (ETDEWEB)

MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.; MAHN,JEFFREY A.; BERRY,DONALD T.; SCHWERS,NORMAN F.; VANDERBEEK,THOMAS E.; NAEGELI,ROBERT E.

2000-11-01

This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR.

Hot Cell Facility (HCF) Safety Analysis Report

International Nuclear Information System (INIS)

MITCHELL, GERRY W.; LONGLEY, SUSAN W.; PHILBIN, JEFFREY S.; MAHN, JEFFREY A.; BERRY, DONALD T.; SCHWERS, NORMAN F.; VANDERBEEK, THOMAS E.; NAEGELI, ROBERT E.

2000-01-01

This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR

Report on safety related occurrences and reactor trips July 1, 1979 - December 31, 1979

International Nuclear Information System (INIS)

Olsson, S.; Andermo, L.

1980-01-01

This is a report on all reported safety related occurrences and reactor trips in Swedish nuclear power plants in operation during July 1 to December 31, 1979 inclusive. The facilities involved are Barsebaeck 1 and 2, Oskarshamn 1 and 2 and Ringhals 1 and 2. During this period of 6 months 76 safety related occurrences and 27 reactor trips have been reported to the Nuclear Power Inspectorate. It is to the greatest extent conventional components such as valves and pumps which bring about the safety related occurrences or occurrences leading to outages or power reductions. However, the component errors discovered in the safety related systems have not affected the function of their redundant system and other diverse systems have not been involved. Therefore the reactor safety has been satisfactory. The total number of reactor trips are normal. The average value for these 6 months is 4.5 trips/unit. Approximetely one half of the reactor trips happened at zero or very low power operation. The fact that even small deviations from prescribed operation result in an automatic and safe shut down of the reactor, does not always imply a conflict with operational availability. The greatest outages are caused by occurrences without safety significance. (author)

Analytical Chemistry Division annual progress report for period ending December 31, 1989

International Nuclear Information System (INIS)

1990-04-01

The Analytical Chemistry Division of Oak Ridge National Laboratory (ORNL) is a large and diversified organization. As such, it serves a multitude of functions for a clientele that exists both in and outside of ORNL. These functions fall into the following general categories: Analytical Research, Development and Implementation; Programmatic Research, Development, and Utilization; and Technical Support. The Analytical Chemistry Division is organized into four major sections, each which may carry out any of the three types of work mentioned above. Chapters 1 through 4 of this report highlight progress within the four sections during the period January 1 to December 31, 1989. A brief discussion of the division's role in an especially important environmental program is given in Chapter 5. Information about quality assurance, safety, and training programs is presented in Chapter 6, along with a tabulation of analyses rendered. Publications, oral presentations, professional activities, educational programs, and seminars are cited in Chapters 7 and 8. Approximately 69 articles, 41 proceedings, and 31 reports were published, and 151 oral presentations were given during this reporting period. Some 308,981 determinations were performed

Analytical Chemistry Division annual progress report for period ending December 31, 1982

International Nuclear Information System (INIS)

Lyon, W.S.

1983-05-01

The Analytical Chemistry Dvision of Oak Ridge National laboratory (ORNL) serves a multitude of functions for a clientele that exists both in and outside ORNL. These functions fall into the following general categories: (1) analytical research, development, and implementation; (2) programmatic research, development, and utilization; and (3) technical support. The Division is organized into five major sections, each of which may carry out any type of work falling in the three categories mentioned above. Chapters 1 through 5 of this report highlight progress within the five sections (analytical methodology, mass and emission spectrometry, radioactive materials, bio/organic analysis, and general and environmental analysis) during the period January 1, 1982 to December 31, 1982. A short summary introduces each chapter to indicate work scope. Information about quality assurance and safety programs is presented in Chapter 6, along with a tabulation of analyses rendered. Publications, oral presentations, professional activities, educational programs, and seminars are cited in Chapters 7 and 8. Approximately 61 articles, 32 proceedings publications and 37 reports have been published, and 107 oral presentations were given during this reporting period

Plutonium Finishing Plant safety evaluation report

International Nuclear Information System (INIS)

1995-01-01

The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE's independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91

Safety as experienced by patients themselves: a Finnish survey of the most recent period of care.

Science.gov (United States)

Sahlström, Merja; Partanen, Pirjo; Turunen, Hannele

2014-06-01

We examined patients' experiences of patient safety and participation in promoting safe care during their most recent care period. A survey of patients (N = 175) revealed that treatment, medication, and device safety were mostly experienced as very good or excellent, but responses varied by age and experience. Patients ages 66-75 were most critical of treatment and medication safety. Device safety was rated the worst aspect of safety. Twenty percent of respondents had experienced errors at some time during their care. Patients who had experienced errors and those who were treated at inpatient wards versus a day surgery unit were most critical towards patient participation. Open and transparent error management involving patients is needed to promote treatment, medication, and especially device safety. © 2014 Wiley Periodicals, Inc.

Fusion safety program Annual report, Fiscal year 1995

International Nuclear Information System (INIS)

Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

1995-12-01

This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities

Analysis of Aviation Safety Reporting System Incident Data Associated with the Technical Challenges of the Atmospheric Environment Safety Technology Project

Science.gov (United States)

Withrow, Colleen A.; Reveley, Mary S.

2014-01-01

This study analyzed aircraft incidents in the NASA Aviation Safety Reporting System (ASRS) that apply to two of the three technical challenges (TCs) in NASA's Aviation Safety Program's Atmospheric Environment Safety Technology Project. The aircraft incidents are related to airframe icing and atmospheric hazards TCs. The study reviewed incidents that listed their primary problem as weather or environment-nonweather between 1994 and 2011 for aircraft defined by Federal Aviation Regulations (FAR) Parts 121, 135, and 91. The study investigated the phases of flight, a variety of anomalies, flight conditions, and incidents by FAR part, along with other categories. The first part of the analysis focused on airframe-icing-related incidents and found 275 incidents out of 3526 weather-related incidents over the 18-yr period. The second portion of the study focused on atmospheric hazards and found 4647 incidents over the same time period. Atmospheric hazards-related incidents included a range of conditions from clear air turbulence and wake vortex, to controlled flight toward terrain, ground encounters, and incursions.

Annual safety research report, JFY 2010

International Nuclear Information System (INIS)

2011-09-01

In the safety infrastructure research working group report, 'the effective conducting of nuclear safety infrastructure research', published by METI in March 2010, the roles of regulatory agencies and JNES and their cooperation, and the research road map for nuclear safety regulation researches were summarized. As for the regulatory issues the governments or JNES considered necessary, JNES had compiled' safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. Safety research areas, subjects and research projects were as follows: design review of nuclear power plant (4 subjects and each subject having several research projects totaled 19), control management of nuclear power plant (3 subjects and each subject having several research projects totaled 11), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 5), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 6), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 5) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 7). In JFY 2010, JNES worked on the 53 research projects of 17 subjects in 6 areas as safety researches. This annual safety research report summarized respective achievements and stage of regulatory tools necessary for solving regulatory issues according to the safety research plan, JFY 2010 Edition as well as the situation of the reflection for the safety regulations. (T. Tanaka)

Model for safety reports including descriptive examples

International Nuclear Information System (INIS)

1995-12-01

Several safety reports will be produced in the process of planning and constructing the system for disposal of high-level radioactive waste in Sweden. The present report gives a model, with detailed examples, of how these reports should be organized and what steps they should include. In the near future safety reports will deal with the encapsulation plant and the repository. Later reports will treat operation of the handling systems and the repository

Safety-related LWR research. Annual report 1993

International Nuclear Information System (INIS)

Hueper, R.

1994-06-01

The reactor safety R and D work of the Karlsruhe Nuclear Research Centre (KfK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1993 summarizes the results on LWR safety. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status at the end of 1993. (orig./HP) [de

Annual report on occupational safety 1983

International Nuclear Information System (INIS)

1984-08-01

The 1983 Annual Report on occupational safety at BNFL is presented. Data for whole-body radiation doses and skin and extremity doses are given for BNFL employees together with 1982 data for comparison. Similarly, accidental deaths and major injuries are recorded. Finally information on the frequency of both nuclear and non-nuclear incidents reported to the Health and Safety Executive is given. (U.K.)

Report on equipment availability for the ten-year period, 1966--1975

Energy Technology Data Exchange (ETDEWEB)

1976-12-01

This is an annual report of availability and outage statistics for electric power generating facilities operating in the United States. A list of utility organizations voluntarily participating in the EEI Equipment Availability Program in 1975 is located in Appendix F. All summary reports in this publication are for the 10-year period 1966-1975. Each reporting utility company has received reports on individual units for which data were submitted. Also, selected major equipment manufacturers receive copies of computer reports showing an analysis of the data for their equipment. Revised reporting instructions to incorporate Safety and Environmental Requirement Cause Codes were issued effective January 1, 1976. In addition, provisions were made for identifying major equipment manufactured outisde of the United States or under foreign license. Recognizing that an Annual Report contains only a limited amount of general outage data in selected categories, the Task Force has agreed to perform special analyses of the data bank if the cost of computer services is met by the requestor and if the required analysis conforms to some designated policy guidelines.

Patient Drug Safety Reporting: Diabetes Patients' Perceptions of Drug Safety and How to Improve Reporting of Adverse Events and Product Complaints.

Science.gov (United States)

Patel, Puja; Spears, David; Eriksen, Betina Østergaard; Lollike, Karsten; Sacco, Michael

2018-03-01

Global health care manufacturer Novo Nordisk commissioned research regarding awareness of drug safety department activities and potential to increase patient feedback. Objectives were to examine patients' knowledge of pharmaceutical manufacturers' responsibilities and efforts regarding drug safety, their perceptions and experiences related to these efforts, and how these factors influence their thoughts and behaviors. Data were collected before and after respondents read a description of a drug safety department and its practices. We conducted quantitative survey research across 608 health care consumers receiving treatment for diabetes in the United States, Germany, United Kingdom, and Italy. This research validated initial, exploratory qualitative research (across 40 comparable consumers from the same countries) which served to guide design of the larger study. Before reading a drug safety department description, 55% of respondents were unaware these departments collect safety information on products and patients. After reading the description, 34% reported the department does more than they expected to ensure drug safety, and 56% reported "more confidence" in the industry as a whole. Further, 66% reported themselves more likely to report an adverse event or product complaint, and 60% reported that they were more likely to contact a drug safety department with questions. The most preferred communication methods were websites/online forums (39%), email (27%), and telephone (25%). Learning about drug safety departments elevates consumers' confidence in manufacturers' safety efforts and establishes potential for patients to engage in increased self-monitoring and reporting. Study results reveal potentially actionable insights for the industry across patient and physician programs and communications.

Annual report on reactor safety research projects sponsored by the Ministry for Research and Technology of the Federal Republic of Germany. Reporting period 1993. Progress report

International Nuclear Information System (INIS)

1994-10-01

The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMFT, informs continuously of the status of such investigations by means of semi-annual and annual publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general information of progress in reactor safety research. The individual reports are classified according to the same classification system as applied in the nuclear index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig./HP)

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.

IRSN - Annual Report 2013. Financial Report 2013. Enhancing nuclear safety

International Nuclear Information System (INIS)

Schuler, Matthieu; Marchal, Valerie; Albert, Marc-Gerard; Aurelle, Jacques; Bigot, Marie-Pierre; Bruna, Giovanni; Charron, Sylvie; Clavelle, Stephanie; Cousinou, Patrick; Deschamps, Patrice; Delattre, Aleth; Demeillers, Didier; Dumas, Agnes; Franquard, Dominique; Laloi, Patrick; Lorthioir, Stephane; Monti, Pascale; Rollinger, Francois; Rouyer, Veronique; Rutschkovsky, Nathalie; Scott De Martinville, Edouard; Tharaud, Christine; Verpeaux, Jean-Luc; Jaunet, Camille; Hedouin, Jean-Christophe; Pascal-Heuze, Charlotte

2014-03-01

IRSN, a public entity with industrial and commercial activities, is placed under the joint authority of the Ministries of Defense, Environment, Industry, Research, and Health. It is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues. Its areas of specialization include the environment and radiological emergency response, human radiation protection in both a medical and professional capacity, and in both normal and post-accident situations, the prevention of major accidents, nuclear reactor safety, as well as safety in nuclear plants and laboratories, transport and waste treatment, and nuclear defense and security expertise. IRSN interacts with all parties concerned by these risks (public authorities, in particular nuclear safety and security authorities, local authorities, companies, research organizations, stakeholders' associations, etc.) to contribute to public policy issues relating to nuclear safety, human and environmental protection against ionizing radiation, and the protection of nuclear materials, facilities, and transport against the risk of malicious acts. This document is the 2013 issue of IRSN's activity report. Content: 1 - Organization, key figures; 2 - Strategy: Progress and main activities in 2013, Transparency and communications policy, Promoting a safety and radiation protection culture; 3 - Activities: Safety (Safety of existing facilities, Studies and researches, About defense, Conducting assessments of future facilities); Nuclear security and non-proliferation (Nuclear security activities, International non-proliferation controls); Radiation protection - environment and human health (Environmental and population exposure, Radiation protection in the workplace, Effects of chronic exposure, Protection in health care); Emergency and post-accident situations efficiency; 4 - Efficiency: Health, safety, environmental, protection and quality, Human resources

Planning report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-06-01

This document is a planning report for SKB's next assessment of long-term safety for a KBS 3 repository. The assessment, SR-Can, is to be finished by the end of 2005 and will be used for SKB's application to build an Encapsulation plant for spent nuclear fuel. Apart from outlining the methodology, the report discusses the handling in SR-Can of a number of important issues regarding the near field, the geosphere, the biosphere, the climatic evolution etc. The Swedish nuclear safety and radiation protection authorities have recently issued regulations concerning the final disposal of nuclear waste. The principal compliance criterion states that the annual risk of harmful effects must not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk. There are also a number of requirements on methodological aspects of the safety assessment as well as on the contents of a safety report. The regulations are reproduced in an Appendix to this report. The primary safety function of the KBS 3 system is to completely isolate the spent nuclear fuel within copper canisters over the entire assessment period, which will be one million years in SR-Can. Should a canister be damaged, the secondary safety function is to retard any releases from the canisters. The main steps of the assessment are the following: 1. Qualitative system description, FEP processing: This step consists of defining a system boundary and of describing the system on a format suitable for the safety assessment. Databases of relevant features, events and processes influencing long-term safety are structured and used as one starting point for the assessment. 2. Initial state descriptions. 3. Process descriptions: In this step all identified processes within the system boundary involved in the long-term evolution of the system are described in detail. 4. Description of boundary conditions: This step is a broad description of the evolution of the boundaries of the system

Patient safety event reporting in critical care: a study of three intensive care units.

Science.gov (United States)

Harris, Carolyn B; Krauss, Melissa J; Coopersmith, Craig M; Avidan, Michael; Nast, Patricia A; Kollef, Marin H; Dunagan, W Claiborne; Fraser, Victoria J

2007-04-01

To increase patient safety event reporting in three intensive care units (ICUs) using a new voluntary card-based event reporting system and to compare and evaluate observed differences in reporting among healthcare workers across ICUs. Prospective, single-center, interventional study. A medical ICU (19 beds), surgical ICU (24 beds), and cardiothoracic ICU (17 beds) at a 1,371-bed urban teaching hospital. Adult patients admitted to these three study ICUs. Use of a new, internally designed, card-based reporting program to solicit voluntary anonymous reporting of medical errors and patient safety concerns. During a 14-month period, 714 patient safety events were reported using a new card-based reporting system, reflecting a significant increase in reporting compared with pre-intervention Web-based reporting (20.4 reported events/1,000 patient days pre-intervention to 41.7 reported events/1,000 patient days postintervention; rate ratio, 2.05; 95% confidence interval, 1.79-2.34). Nurses submitted the majority of reports (nurses, 67.1%; physicians, 23.1%; other reporters, 9.5%); however, physicians experienced the greatest increase in reporting among their group (physicians, 43-fold; nurses, 1.7-fold; other reporters, 4.3-fold) relative to pre-intervention rates. There were significant differences in the reporting of harm by job description: 31.1% of reports from nurses, 36.2% from other staff, and 17.0% from physicians described events that did not reach/affect the patient (p = .001); and 33.9% of reports from physicians, 27.2% from nurses, and 13.0% from other staff described events that caused harm (p = .005). Overall reported patient safety events per 1,000 patient days differed by ICU (medical ICU = 55.5, cardiothoracic ICU = 25.3, surgical ICU = 40.2; p reporting system increased reporting significantly compared with pre-intervention Web-based reporting and revealed significant differences in reporting by healthcare worker and ICU. These differences may reveal

Fusion safety program annual report fiscal year 1997

International Nuclear Information System (INIS)

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

1998-01-01

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

Fusion safety program annual report fiscal year 1997

Energy Technology Data Exchange (ETDEWEB)

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

1998-01-01

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

Mathematics and statistics research department. Progress report, period ending June 30, 1981

Energy Technology Data Exchange (ETDEWEB)

Lever, W.E.; Kane, V.E.; Scott, D.S.; Shepherd, D.E.

1981-09-01

This report is the twenty-fourth in the series of progress reports of the Mathematics and Statistics Research Department of the Computer Sciences Division, Union Carbide Corporation - Nuclear Division (UCC-ND). Part A records research progress in biometrics research, materials science applications, model evaluation, moving boundary problems, multivariate analysis, numerical linear algebra, risk analysis, and complementary areas. Collaboration and consulting with others throughout the UCC-ND complex are recorded in Part B. Included are sections on biology and health sciences, chemistry, energy, engineering, environmental sciences, health and safety research, materials sciences, safeguards, surveys, and uranium resource evaluation. Part C summarizes the various educational activities in which the staff was engaged. Part D lists the presentations of research results, and Part E records the staff's other professional activities during the report period.

Mathematics and statistics research department. Progress report, period ending June 30, 1981

International Nuclear Information System (INIS)

Lever, W.E.; Kane, V.E.; Scott, D.S.; Shepherd, D.E.

1981-09-01

This report is the twenty-fourth in the series of progress reports of the Mathematics and Statistics Research Department of the Computer Sciences Division, Union Carbide Corporation - Nuclear Division (UCC-ND). Part A records research progress in biometrics research, materials science applications, model evaluation, moving boundary problems, multivariate analysis, numerical linear algebra, risk analysis, and complementary areas. Collaboration and consulting with others throughout the UCC-ND complex are recorded in Part B. Included are sections on biology and health sciences, chemistry, energy, engineering, environmental sciences, health and safety research, materials sciences, safeguards, surveys, and uranium resource evaluation. Part C summarizes the various educational activities in which the staff was engaged. Part D lists the presentations of research results, and Part E records the staff's other professional activities during the report period

Fusion Safety Program Annual Report, Fiscal Year 1996

International Nuclear Information System (INIS)

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

1996-12-01

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

Current status of safety analysis report for ANPP

International Nuclear Information System (INIS)

Amirjanyan, A.

1999-01-01

Current situation concerning Armenian NPP safety analysis report is considered within the frame of accepted safety practice. Licensing procedure is being developed. Technical support group was established in the Armenian Nuclear Regulatory Authority (ANRA). The task of the group is to study modern methods of NPP in depth safety analysis for technical assistance for the ANRA, and perform independent safety assessments. ANRA will be obliged to demand assistance from various foreign organisations for preparation of different parts of the Safety Analysis Report like determination though certain parts can be prepared in Armenia

Central Safety Department. Annual report 1986

International Nuclear Information System (INIS)

Kiefer, H.; Koenig, L.A.

1987-03-01

The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Central Safety Department. The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of HT in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. The report gives details of the different duties, indicates the results of 1986 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

Fusion Safety Program annual report, fiscal year 1994

International Nuclear Information System (INIS)

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

1995-03-01

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

Nuclear Safety Project. Annual report 1983

International Nuclear Information System (INIS)

1984-06-01

The annual report 1983 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1983 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig.) [de

Nuclear safety project. Annual report 1985

International Nuclear Information System (INIS)

1986-07-01

The annual report 1985 is a detailed description (in German language) of work within the nuclear safety project performed in 1985 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./HP) [de

Human factors evaluation of man-machine interface for periodic safety review of nuclear power plants

International Nuclear Information System (INIS)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang; Hwang, In Koo; Lee, Hyun Cheol; Jang, Tong Il; Ku, Jin Young; Kim, Soo Jin

2004-12-01

This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Nuclear Power Plants(NPPs). As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

Investigational new drug safety reporting requirements for human drug and biological products and safety reporting requirements for bioavailability and bioequivalence studies in humans. Final rule.

Science.gov (United States)

2010-09-29

The Food and Drug Administration (FDA) is amending its regulations governing safety reporting requirements for human drug and biological products subject to an investigational new drug application (IND). The final rule codifies the agency's expectations for timely review, evaluation, and submission of relevant and useful safety information and implements internationally harmonized definitions and reporting standards. The revisions will improve the utility of IND safety reports, reduce the number of reports that do not contribute in a meaningful way to the developing safety profile of the drug, expedite FDA's review of critical safety information, better protect human subjects enrolled in clinical trials, subject bioavailability and bioequivalence studies to safety reporting requirements, promote a consistent approach to safety reporting internationally, and enable the agency to better protect and promote public health.

Progress report on safety research of high-level waste management for the period April 1987 to March 1988

International Nuclear Information System (INIS)

Nakamura, Haruto; Tashiro, Shingo

1988-10-01

Researches on high-level waste management at the High Level Waste Management Laboratory and the Waste Safety Testing Facility Operation Division of the Japan Atomic Energy Research Institute in the fiscal year of 1987 are reviewed in the three sections of the report. The topics are as follows: 1) On performance and durability of waste forms and engineered barrier materials, accelerated alpha radiation stability of glass form and Synroc has been investigated and stress corrosion cracking of canister materials was examined under simulated conditions. 2) Sorption of 237 Np on granite samples and behavior of iron during weathering of granites were studied with respect to safety evaluation for geological disposal. 3) Actual waste was transported from the Tokai Reprocessing Plant and hot operation using the actual waste was initiated at WASTEF. (author)

Enhancing nuclear safety. Annual report 2015. Financial report 2015

International Nuclear Information System (INIS)

Le Guludec, Dominique; Niel, Jean-Christophe; Mouton, Georges-Henri; Repussard, Jacques; Schuler, Matthieu; Marchal, Valerie; Albert, Marc-Gerard; Bigot, Marie-Pierre; Brisset, Yves; Bruna, Giovanni; Charron, Sylvie; Clavelle, Stephanie; Deschamps, Patrice; Delattre, Aleth; Demeillers, Didier; Laloi, Patrick; Lorthioir, Stephane; Monti, Pascale; Rollinger, Francois; Rouyer, Veronique; Tharaud, Christine; Jaunet, Camille; Pascal-Heuze, Charlotte

2016-01-01

After some introductory texts proposed by several IRSN head managers, and a brief presentation of some key data illustrating the activity, the annual report presents the main strategic orientations, notably in the field of knowledge management, and of information and communication. After some images illustrating the past year, activities are presented. They first deal with safety: safety of civil nuclear facilities, from decommissioning old reactors to designing those of the future, reactor ageing, severe accidents, fuel, criticality and neutronics, fire and containment, safety and radiation protection of defence-related facilities and activities, geological disposal of radioactive wastes. They secondly deal with security and non-proliferation (nuclear security, nuclear non-proliferation, chemical weapon ban), thirdly with radiation protection for human and environment health (environment monitoring, radionuclide transfer in the environment, radon and polluted sites, human exposure, radiation protection in the workplace, effects of chronic exposures, protection in health care), and fourthly with emergency and post-accident situations (emergency and post-accident preparedness and response). The next part of the activity report addresses issues related to efficiency: improved economic and financial management, property, computer security, quality and corporate social responsibility, human resources, organisation chart. The financial report proposes a management report, financial statements with an appendix to annual accounts, and an auditor's report

Safety climate and self-reported injury: assessing the mediating role of employee safety control.

Science.gov (United States)

Huang, Yueng-Hsiang; Ho, Michael; Smith, Gordon S; Chen, Peter Y

2006-05-01

To further reduce injuries in the workplace, companies have begun focusing on organizational factors which may contribute to workplace safety. Safety climate is an organizational factor commonly cited as a predictor of injury occurrence. Characterized by the shared perceptions of employees, safety climate can be viewed as a snapshot of the prevailing state of safety in the organization at a discrete point in time. However, few studies have elaborated plausible mechanisms through which safety climate likely influences injury occurrence. A mediating model is proposed to link safety climate (i.e., management commitment to safety, return-to-work policies, post-injury administration, and safety training) with self-reported injury through employees' perceived control on safety. Factorial evidence substantiated that management commitment to safety, return-to-work policies, post-injury administration, and safety training are important dimensions of safety climate. In addition, the data support that safety climate is a critical factor predicting the history of a self-reported occupational injury, and that employee safety control mediates the relationship between safety climate and occupational injury. These findings highlight the importance of incorporating organizational factors and workers' characteristics in efforts to improve organizational safety performance.

Analytical Chemistry Division annual progress report for period ending December 31, 1989

Energy Technology Data Exchange (ETDEWEB)

1990-04-01

The Analytical Chemistry Division of Oak Ridge National Laboratory (ORNL) is a large and diversified organization. As such, it serves a multitude of functions for a clientele that exists both in and outside of ORNL. These functions fall into the following general categories: Analytical Research, Development and Implementation; Programmatic Research, Development, and Utilization; and Technical Support. The Analytical Chemistry Division is organized into four major sections, each which may carry out any of the three types of work mentioned above. Chapters 1 through 4 of this report highlight progress within the four sections during the period January 1 to December 31, 1989. A brief discussion of the division's role in an especially important environmental program is given in Chapter 5. Information about quality assurance, safety, and training programs is presented in Chapter 6, along with a tabulation of analyses rendered. Publications, oral presentations, professional activities, educational programs, and seminars are cited in Chapters 7 and 8. Approximately 69 articles, 41 proceedings, and 31 reports were published, and 151 oral presentations were given during this reporting period. Some 308,981 determinations were performed.

Periodic safety review of operational nuclear power plants. A publication within the NUSS programme

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide which supplements the IAEA Safety Fundamentals: The Safety of Nuclear Installations and the Code on the Safety of Nuclear Power Plants: Operation, forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes and Guides relating to nuclear power plants. A list of NUSS publications is given at the end of this book. This Guide was drafted on the basis of a systematic review approach that was endorsed by the IAEA Conference on the Safety of Nuclear Power: Strategy for the Future. The purpose of this Safety Guide is to provide guidance on the conduct of Periodic Safety Reviews (PSRs) for an operational nuclear power plant. The Guide is directed at both owners/operators and regulators. This Safety Guide deals with the PSR of an operational nuclear power plant. A PSR is a comprehensive safety review addressing all important aspects of safety, carried out at regular intervals. 22 refs, 4 figs

Revision of AESJ standard 'the code of implemnetation of periodic safety review of nuclear power plants'

International Nuclear Information System (INIS)

Hirano, Masashi; Narumiya, Yoshiyuki

2010-01-01

The Periodic Safety Review (PSR) was launched in June 1992, when the Agency for Natural Resources and Energy issued a notification that required licensees to conduct comprehensive review on the safety of each existing nuclear power plant (NPP) once approximately every ten years based on the latest technical findings for the purpose of improving the safety of the NPP. In 2006, the Standard Committee of the Atomic Energy Society of Japan established the first version of 'The Standard of Implementation for Periodic Safety Review of Nuclear Power Plants: 2006'. Taking into account developments in safety regulation of PSR after the issuance of the first version, the Standard Committee has revised the Standard. This paper summarizes background on PSR, such developments are major contents of the Standard as well as the focal points of the revision. (author)

76 FR 40648 - Safety Enhancements Part 139, Certification of Airports; Reopening of Comment Period

Science.gov (United States)

2011-07-11

... that was published on February 1, 2011. In that document, the FAA proposed several safety enhancements...-0247; Notice No. 11-01] RIN 2120-AJ70 Safety Enhancements Part 139, Certification of Airports... comment period for the NPRM published on February 1, 2011 (76 FR 5510) and reopened (76 FR 20570) April 13...

Health and safety annual report 1992

International Nuclear Information System (INIS)

1993-01-01

BNFL operates 6 sites in the United Kingdom concerned with the nuclear fuel cycle. The annual report on occupational health and safety gives information on all aspects of health and safety within BNFL with special reference to radiation doses received by the workforce and radiation protection measures taken by the company. BNFL's safety policy is set out. Radiation doses to all workers have remained low. Other industrial accidents are also listed and its safety measures for transport, radioactive effluents and in the event of an incident, are mentioned briefly. (UK)

Fusion Safety Program annual report, Fiscal Year 1993

International Nuclear Information System (INIS)

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

1993-12-01

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

List of reports on reactor safety research by BMFT, USNRC, EPRI and JSTA. Period under review: 1st January until 31st March 1978

International Nuclear Information System (INIS)

1978-05-01

This list reviews reports from the Federal Republic of Germany, from the United States of America and from Japan concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the United States Regulatory Commisssion (USNRC), the Electric Power Research Institute (EPRI), and the Japan Science and Technology Agency (JSTA) these reports are available in the Gesellschaft fuer Reaktorsicherheit. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of BMFT, reporting organisation. The list of reports appears quarterly. Requests for reports should be addressed to GRS, Forschungsbetreuung. Contractual view points have to be considered for the distribution of the reports. (orig.) [de

Nuclear safety in Slovak Republic. Safety analysis reports for WWER 440 reactors

International Nuclear Information System (INIS)

Rohar, S.

1999-01-01

Implementation of nuclear power program is connected to establishment of regulatory body for safe regulation of siting, construction, operation and decommissioning of nuclear installations. Licensing being one of the most important regulatory surveillance activity is based on independent regulatory review and assessment of information on nuclear safety for particular nuclear facility. Documents required to be submitted to the regulatory body by the licensee in Slovakia for the review and assessment usually named Safety Analysis Report (SAR) are presented in detail in this paper. Current status of Safety Analysis Reports for Bohunice V-1, Bohunice V-2 and Mochovce NPP is shown

5 CFR 2634.908 - Reporting periods.

Science.gov (United States)

2010-01-01

... DISCLOSURE, QUALIFIED TRUSTS, AND CERTIFICATES OF DIVESTITURE Confidential Financial Disclosure Reports § 2634.908 Reporting periods. (a) Incumbents. Each confidential financial disclosure report filed under... information required to be reported according to the provisions of this subpart for the preceding calendar...

Safety assessment of research reactors and preparation of the safety analysis report

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide presents guidelines, approved by international consensus, for the preparation, review and assessment of safety documentation for research reactors such as the Safety Analysis Report. While the Guide is most applicable to research reactors in the design and construction stage, it is also recommended for use during relicensing or reassessment of existing reactors

Managing change in the nuclear industry: The effects on safety. INSAG-18. A report by the International Nuclear Safety Advisory Group

International Nuclear Information System (INIS)

2003-01-01

The nuclear industry is going through a period of unprecedented change. The changes arise from the political and business environment in which the industry must operate, and from within the industry itself as it strives to become more competitive. These pressures have already led to significant changes in how nuclear enterprises are organized. The changes can be expected to continue. It is absolutely essential that throughout the period of time that organizational changes are taking place, and after the changes have occurred, very high standards of safety are maintained by all the elements that make up the industry. Changes can be made effectively and safely, and gains in efficiency and competitiveness, as well as safety, can be realized if changes are introduced carefully and managed well. Experience has shown that this is not a simple matter to achieve. Nuclear installations are complex, and it is inherently demanding to foresee all the implications that a change may have on safety. However, experience has shown very clearly that many changes have a strong potential to affect both the safety that has been built into a design and in the safety culture of an organization. Hence failure to manage change well can significantly affect the likelihood of an accident, the degree to which the assets of the company are put at risk and the company's reputation. This INSAG report is directed at members of boards of directors and senior executives who are responsible for the overall safety of an installation, who make decisions for change and who implement these decisions. It is also written for senior regulators who, on behalf of the public, ensure that boards of directors and executives meet their responsibilities for safety. This report discusses how and why change can challenge the maintenance of a high level of safety, and what can be done to control that challenge and hence reap all the benefits of change. It draws an analogy between the well established principles for

Annual report on occupational safety 1989

International Nuclear Information System (INIS)

1990-01-01

This report presents detailed information on occupational safety relating to BNFL's employees for 1989 and data compared with the previous year. Routine monitoring, non-radiological safety and 'incidents' are discussed and 'statutory' whole-body exposures, nuclear incidents, lost-time accidents, and types of injury are tabulated. (author)

76 FR 12300 - Safety Management System for Certificated Airports; Extension of Comment Period

Science.gov (United States)

2011-03-07

...-0997; Notice No. 10-14] RIN 2120-AJ38 Safety Management System for Certificated Airports; Extension of...: Background On October 7, 2010, the FAA published Notice No. 10-14, entitled ``Safety Management System for... conclusions from the safety management systems proof of concept. The FAA anticipates making this report...

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

International Nuclear Information System (INIS)

2006-01-01

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

Safety administration division business report. The fourth quarter of 2001. Document on present state of affairs

International Nuclear Information System (INIS)

Kanamori, Masashi

2002-06-01

The business of the Safety administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, and the business of the following concerning the Tokai Works, the protection of nuclear materials, the business of the sanction, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. For the purpose of summarizing these businesses and utilizing the data concerning the businesses, the report about the businesses achievement has been periodically drawn up as quarter news since 2001, when the Safety Administration Division was established. This report describes about the business achievement of the fourth quarter news from January to March in 2002. (author)

Safety administration division business report. The third quarter of 2001. Document on present state of affairs

International Nuclear Information System (INIS)

Kanamori, Masashi

2002-04-01

The business of the Safety administration Division became a wide range such as the management of a labor safety health, the crisis management, the security and the management of an entrance, and the business of the following concerning the Tokai Works, the protection of nuclear materials, the business of the sanction, the nuclear material safeguards, the transport of nuclear materials and the business of a quality assurance. For the purpose of summarizing these business and utilizing the data concerning the business, the report about the businesses achievement has been periodically drawn up as quarter news since 2001, when the Safety Administration Division was established. This report describes about the business achievement of the third quarter news from October to December in 2001. (author)

Periodic progress report, 6 months

DEFF Research Database (Denmark)

Juhl, Thomas Winther; Nielsen, Jakob Skov

This is the first progress report of the BriteEuram project named "High Power Laser Cutting for Heavy Industry" ("Powercut"). The report contains a summary of the objectives of the first period, an overview of the technical progress, a comparison between the planed and the accomplished work...

Safety balance: Analysis of safety systems; Bilans de surete: analyse par les organismes de surete

Energy Technology Data Exchange (ETDEWEB)

Delage, M; Giroux, C

1990-12-01

Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses.

Project 2nd Periodic Report - Section 2

DEFF Research Database (Denmark)

Healy, Mark; Knowles, Emma; Johnstone, Cameron

The work described in this publication has received support from the European Community - Research Infrastructure Action under the FP7 “Capacities” Specific Programme through grant agreement number 262552, MaRINET. Project Periodic Report. 2nd Period: October 2012 – March 2014 inclusive.......The work described in this publication has received support from the European Community - Research Infrastructure Action under the FP7 “Capacities” Specific Programme through grant agreement number 262552, MaRINET. Project Periodic Report. 2nd Period: October 2012 – March 2014 inclusive....

Supplement to safety analysis report. 306-W building operations safety requirement

International Nuclear Information System (INIS)

Richey, C.R.

1979-08-01

The operations safety requirements (OSRs) presented in this report define the conditions, safe boundaries, and management control needed for safely conducting operations with radioactive materials in the Pacific Northwest Laboratory (PNL) 306-W building. The safety requirements are organized in five sections. Safety limits are safety-related process variables that are observable and measurable. Limiting conditions cover: equipment and technical conditions and characteristics of the facility and operations necessary for continued safe operation. Surveillance requirements prescribe the requirements for checking systems and components that are essential to safety. Equipment design controls require that changes to process equipment and systems be independently checked and approved to assure that the changes will have no adverse effect on safety. Administrative controls describe and discuss the organization and administrative systems and procedures to be used for safe operation of the facility. Details of the implementation of the operations safety requirements are prescribed by internal PNL documents such as criticality safety specifications and radiation work procedures

Safety analysis reports - new strategies

International Nuclear Information System (INIS)

Booth, J.A.

1994-01-01

Within the past year there have been many external changes in the requirements of safety analysis reports. Now there is emphasis on open-quotes graded approachesclose quotes depending on the Hazard Classification of the project. The Energy Facility Contractors Group (EFCOG) has a Safety Analysis Working Group. The results of this group for the past year are discussed as well as the implications for EG ampersand G. New strategies include ideas for incorporating the graded approach, auditable safety documents, additional guidance for Hazard Classification per DOE-STD-1027-92. The emphasis in the paper is on those projects whose hazard classification is category three or less

An approach for Periodic Safety Review (PSR) of units 5 and 6 of Kozloduy NPP

International Nuclear Information System (INIS)

Kichev, Emil

2014-01-01

Periodic Safety Reviews (PSR) is complementary to the routine and special safety reviews and does not replaced them. It determines the level of compliance with current safety requirements and covers all safety aspects of NPP operation and all equipment (SSCs) on site. Three levels of importance are defined for the documents in PSR (towards higher conservatism): Bulgarian documents; IAEA documents; Documents of manufactures and suppliers of the equipment (SSCs). The scope and activities consists of four stages and includes 14 safety factors (SF). Cooperation with external companies and organizations in areas with proved experience is used.

Incorporation of advanced accident analysis methodology into safety analysis reports

International Nuclear Information System (INIS)

2003-05-01

also a need to update the FSAR periodically (UFSAR) for holders of an operating licence and the corresponding guidance is being developed. Objectives and scope The first objective of this report is to give a short overview of the advanced codes that are available and are currently used for accident analyses of NPPs. The main tools for the accident analyses are thermal-hydraulic system codes. The other code types used for various purposes will be also discussed briefly. The second objective is to discuss the application of such codes for the analyses to be presented in the SAR of an individual plant. The report is applicable to the advanced codes to be used in the analysis of the plants that are mainly based on light water technology and to a certain extent to the pressurized heavy water reactor designs (CANDU). The report is generally applicable to existing plants as well as to new reactor power plants. It is noted, however, that most of the examples discussed here are connected to the pressurized water reactor (PWR) technology. The report can be considered as a complementary publication to the IAEA Safety Report on Accident Analysis for Nuclear Power Plants, describing in more detail the use of computer codes for specific applications needed for the SAR. Section 2 of this report gives an overview of the existing codes for thermal-hydraulics, reactor dynamics, containment analysis, severe accident analysis and other areas included in the scope of analyses and computation to support the SARs. Section 3 describes the use of advanced methods for various transient and accident analyses to be included in the SARs. The special emphasis is on describing the methods which are used and how to achieve a reliable and conservative evaluation of safety margins

Analytical Chemistry Division annual progress report for period ending December 31, 1992

Energy Technology Data Exchange (ETDEWEB)

Shults, W.D.

1993-04-01

This report is divided into: Analytical spectroscopy (optical spectroscopy, organic mass spectrometry, inorganic mass spectrometry, secondary ion mass spectrometry), inorganic and radiochemistry (transuranium and activation analysis, low-level radiochemical analysis, inorganic analysis, radioactive materials analysis, special projects), organic chemistry (organic spectroscopy, separations and synthesis, special projects, organic analysis, ORNL/UT research program), operations (quality assurance/quality control, environmental protection, safety, analytical improvement, training, radiation control), education programs, supplementary activities, and presentation of research results. Tables are included for articles reviewed or refereed for periodicals, analytical service work, division manpower and financial summary, and organization chart; a glossary is also included.

Fusion Safety Program annual report, fiscal year 1992

International Nuclear Information System (INIS)

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

1993-01-01

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

Fusion Safety Program annual report: Fiscal year 1987

International Nuclear Information System (INIS)

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

1988-02-01

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

Reports on research projects in the field of reactor safety sponsored by the Federal Ministry for Education, Science, Research and Technology. Period covered: January 1 - June 30, 1997

International Nuclear Information System (INIS)

1997-01-01

Within the framework of its research programme on reactor safety, the Bundesministerium fuer Bildung, Wissenschaft, Forschung und Technology (BMBF) (Federal Ministry for Education, Science, Research and Technology) sponsors investigations into the safety of nuclear reactors. These investigations that are carried out within the framework of the programme are to provide fundamental knowledge, procedures and methods contributing to realistic safety assessments of nuclear facilities, the further development of safety technology, and the use of the potential of innovative safety-related approaches. Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) bmH, by order of the BMBF, continuously issues information on the status of such investigations by publishing semiannual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. (orig./SR) [de

Central Safety Department, annual report 1987

International Nuclear Information System (INIS)

Kiefer, H.; Koenig, L.A.

1988-02-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behaviour of biologically particularly active radionuclides, behaviour of HT in the air/plan/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1987 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig./HP) [de

NPP Temelin safety analysis reports and PSA status

International Nuclear Information System (INIS)

Mlady, O.

1999-01-01

To enhance the safety level of Temelin NPP, recommendations of the international reviews were implemented into the design as well as into organization of the plant construction and preparation for operation. The safety assessment of these design changes has been integrated and reflected in the Safety Analysis Reports, which follow the internationally accepted guidelines. All safety analyses within Safety Analysis Reports were repeated carefully considering technical improvements and replacements to complement preliminary safety documentation. These analyses were performed by advanced western computer codes to the depth and in the structure required by western standards. The Temelin NPP followed a systematic approach in the functional design of the Reactor Protection System and related safety analyses. Modifications of reactor protection system increase defense in depth and facilitate demonstrating that LOCA and radiological limits are met for non-LOCA events. The rigorous safety analysis methodology provides assurance that LOCA and radiological limits are met. Established and accepted safety analysis methodology and accepted criteria were applied to Temelin NPP meeting US NRC and Czech Republic requirements. IAEA guidelines and recommendations

Safety report content and development for test loop facility on MARIA reactor

International Nuclear Information System (INIS)

Konechko, A.; Shumskij, A.M.; Mikul'ahin, V.E.

1982-01-01

A 600 kW test loop facility for investigatin.o safety problems is realized on MARIA reactor in Poland together with USSR organizations. Safety reports have been developed in two steps at the designstage. The 1st report being essentially a preliminary safety analysis was developed within the scope of the feasibility study. At the engineering design stage the preliminary test loop facility safety report had been prepared considering measures excluding the possibility of the MARIA reactor damage. The test loop facility safety report is fulfilled for normal, transient and emergency operation regimes. Separate safety basing for each group of experiments will be prepared. The report presents the test loop facility safety criteria coordinated by the nuclear safety comission. They contains the preliminary reports on the test loop facility safety. At the final stage of construction and at thecommitioning stage the start-up safety report will be developed which after required correction and adding up the putting into operation data will turn into operation safety report [ru

Preliminary report of radiological safety to hydrology 1993 campaign

International Nuclear Information System (INIS)

Badano, A.; Suarez Antola, R.; Dellepere, A.; Barreiro, M.

1993-01-01

This report has been prepared based on the interaction between project managers and division radiological Protection and Nuclear Safety. In seeking to establish a basis for approval from the point of view of radiation safety practices . The idea for the audit has been provided at all times because the interest was the exchange of ideas and the use of common sense to improve the safety of radioactive substances, security of operators and public safety and environment.The above shows that in the planned radiation safety condition described in this report,the practice can be carried out according to the criteria of safety accepted .

Knowledge Representation in Patient Safety Reporting: An Ontological Approach

OpenAIRE

Liang Chen; Yang Gong

2016-01-01

Purpose: The current development of patient safety reporting systems is criticized for loss of information and low data quality due to the lack of a uniformed domain knowledge base and text processing functionality. To improve patient safety reporting, the present paper suggests an ontological representation of patient safety knowledge. Design/methodology/approach: We propose a framework for constructing an ontological knowledge base of patient safety. The present paper describes our desig...

Environment and safety research status report: 1993

International Nuclear Information System (INIS)

1993-03-01

The 1993 status report discusses ongoing and planned research activities in the GRI Environment and Safety Program. The objectives and goals, accomplishments, and strategy along with the basis for each project area are presented for the supply, end use, and gas operations subprograms. Within the context of these subprograms, contract status summaries under their conceptual titles are given for the following project areas: Gas Supply Environmental and Safety Research, Air Quality Research, End Use Equipment Safety Research, Gas Operations Safety Research, Liquefied Natural Gas, Safety Research, and Gas Operations Environmental Research

Fusion Safety Program annual report: Fiscal year 1986

International Nuclear Information System (INIS)

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

1987-06-01

This report summarizes the Fusion Safety Program's (FSP) major activities in fiscal year 1986. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and EG and G Idaho, Inc., is the prime contractor for FSP, which was initiated in 1979. Activities are conducted at the INEL and in participating facilities, including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in this report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruption, risk assessment methodology, and computer code development for reactor transients. Contributions to the Technical Planning Activity (TPA) and the ''white paper'' study by the Environmental, Safety,and Economics Committee (ESECOM) are summarized. The report also includes a summary of the safety and environmental analysis and documentation performed by the INEL for the Compact Ignition Tokamak (CIT) design project

Health and Safety Research Division progress report for the period April 1, 1990--September 30, 1991

Energy Technology Data Exchange (ETDEWEB)

Kaye, S.V.

1992-03-01

This is a brief progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology including Measurement Applications and Development, Pollutant Assessments, Measurement Systems Research, Dosimetry Applications Research, Metabolism and Dosimetry Research and Nuclear Medicine. Biological and Radiation Physics including Atomic, Molecular, and High Voltage Physics, Physics of Solids and Macromolecules, Liquid and Submicron Physics, Analytic Dosimetry and Surface Physics and Health Effects. Chemical Physics including Molecular Physics, Photophysics and Advanced Monitoring Development. Biomedical and Environmental Information Analysis including Human Genome and Toxicology, Chemical Hazard Evaluation and Communication, Environmental Regulations and Remediation and Information Management Technology. Risk Analysis including Hazardous Waste.

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.

The NASA Aviation Safety Reporting System

Science.gov (United States)

1983-01-01

This is the fourteenth in a series of reports based on safety-related incidents submitted to the NASA Aviation Safety Reporting System by pilots, controllers, and, occasionally, other participants in the National Aviation System (refs. 1-13). ASRS operates under a memorandum of agreement between the National Aviation and Space Administration and the Federal Aviation Administration. The report contains, first, a special study prepared by the ASRS Office Staff, of pilot- and controller-submitted reports related to the perceived operation of the ATC system since the 1981 walkout of the controllers' labor organization. Next is a research paper analyzing incidents occurring while single-pilot crews were conducting IFR flights. A third section presents a selection of Alert Bulletins issued by ASRS, with the responses they have elicited from FAA and others concerned. Finally, the report contains a list of publications produced by ASRS with instructions for obtaining them.

Characterization report for the ferrocyanide safety issue

International Nuclear Information System (INIS)

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

1997-06-01

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

EMS helicopter incidents reported to the NASA Aviation Safety Reporting System

Science.gov (United States)

Connell, Linda J.; Reynard, William D.

1993-01-01

The objectives of this evaluation were to: Identify the types of safety-related incidents reported to the Aviation Safety Reporting System (ASRS) in Emergency Medical Service (EMS) helicopter operations; Describe the operational conditions surrounding these incidents, such as weather, airspace, flight phase, time of day; and Assess the contribution to these incidents of selected human factors considerations, such as communication, distraction, time pressure, workload, and flight/duty impact.

Nuclear-power-safety reporting system: feasibility analysis

International Nuclear Information System (INIS)

Finlayson, F.C.; Ims, J.

1983-04-01

The US Nuclear Regulatory Commission (NRC) is evaluating the possibility of instituting a data gathering system for identifying and quantifying the factors that contribute to the occurrence of significant safety problems involving humans in nuclear power plants. This report presents the results of a brief (6 months) study of the feasibility of developing a voluntary, nonpunitive Nuclear Power Safety Reporting System (NPSRS). Reports collected by the system would be used to create a data base for documenting, analyzing and assessing the significance of the incidents. Results of The Aerospace Corporation study are presented in two volumes. This document, Volume I, contains a summary of an assessment of the Aviation Safety Reporting System (ASRS). The FAA-sponsored, NASA-managed ASRS was found to be successful, relatively low in cost, generally acceptable to all facets of the aviation community, and the source of much useful data and valuable reports on human factor problems in the nation's airways. Several significant ASRS features were found to be pertinent and applicable for adoption into a NPSRS

Summary report on safety objectives in nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

The special Task Force on Safety Objectives of the Commission of the European Communities (CEC) Working Group on the Safety of Light Water Reactors reported in May 1983 on its review of existing overall safety objectives in nuclear power plants. Since then much relevant worlwide activity has taken place. This report reviews those activities that have taken place since 1983 in European Community Member States, including more recent Members, as well as in Sweden and Finland. The report confines itself to issues related to probabilistic safety objectives, and concludes that significant progress has been made in many areas. Mutual understanding of safety objectives is leading to a convergence of views and approaches, but it is noted that much work remains to be completed

Patient involvement in patient safety: Protocol for developing an intervention using patient reports of organisational safety and patient incident reporting

Directory of Open Access Journals (Sweden)

Armitage Gerry

2011-05-01

Full Text Available Abstract Background Patients have the potential to provide a rich source of information on both organisational aspects of safety and patient safety incidents. This project aims to develop two patient safety interventions to promote organisational learning about safety - a patient measure of organisational safety (PMOS, and a patient incident reporting tool (PIRT - to help the NHS prevent patient safety incidents by learning more about when and why they occur. Methods To develop the PMOS 1 literature will be reviewed to identify similar measures and key contributory factors to error; 2 four patient focus groups will ascertain practicality and feasibility; 3 25 patient interviews will elicit approximately 60 items across 10 domains; 4 10 patient and clinician interviews will test acceptability and understanding. Qualitative data will be analysed using thematic content analysis. To develop the PIRT 1 individual and then combined patient and clinician focus groups will provide guidance for the development of three potential reporting tools; 2 nine wards across three hospital directorates will pilot each of the tools for three months. The best performing tool will be identified from the frequency, volume and quality of reports. The validity of both measures will be tested. 300 patients will be asked to complete the PMOS and PIRT during their stay in hospital. A sub-sample (N = 50 will complete the PMOS again one week later. Health professionals in participating wards will also be asked to complete the AHRQ safety culture questionnaire. Case notes for all patients will be reviewed. The psychometric properties of the PMOS will be assessed and a final valid and reliable version developed. Concurrent validity for the PIRT will be assessed by comparing reported incidents with those identified from case note review and the existing staff reporting scheme. In a subsequent study these tools will be used to provide information to wards/units about their

Chemical Technology Division progress report for the period July 1, 1988 to September 30, 1989

Energy Technology Data Exchange (ETDEWEB)

1990-03-01

This progress report summarizes the research and development efforts conducted in the Chemical Technology Division (Chem Tech) during the period July 1, 1988, through September 30, 1989. The following major areas are covered: waste management and environmental programs, the Waste Management Technology Center, radiochemical and isotope programs, basic science and technology, Nuclear Regulatory Commission and Electric Power Research Institute severe accident research programs, the Office of Safety and Operational Readiness, and administrative resources and facilities.

Annual safety research report, JFY 2012

International Nuclear Information System (INIS)

2013-08-01

As for the regulatory issues the governments or JNES considered necessary, JNES had compiled 'safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. Safety research areas, subjects and research projects were as follows: design review of nuclear power plant (5 subjects and each subject having several research projects totaled 20), control management of nuclear power plant (3 subjects and each subject having several research projects totaled 6), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 4), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 6), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 7) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 6). In addition to these 49 research projects of 18 subjects in 6 areas, JNES worked on 19 research projects of 7 subjects in added areas (specific research projects on of the disaster at Fukushima Daiichi NPP accident and other challenges JNES considered necessary) in JFY 2012. This annual safety research report summarized respective achievements and state of regulatory tools necessary for solving regulatory issues according to the safety research plan, JFY 2012 Edition as well as the situation of the reflection for the safety regulations, and also described 16 research projects of 4 subjects: examination for new safety regulation (8 research projects), development of newly necessary evaluation methods (one research project), evaluation of the validity for the work for convergence at Fukushima Daiichi NPP accident (4 research project) and horizontal development to other nuclear power plants (3 research projects), and 3 research projects of 3 subjects as other challenges. A list of JNES

Knowledge Representation in Patient Safety Reporting: An Ontological Approach

Directory of Open Access Journals (Sweden)

Liang Chen

2016-10-01

Full Text Available Purpose: The current development of patient safety reporting systems is criticized for loss of information and low data quality due to the lack of a uniformed domain knowledge base and text processing functionality. To improve patient safety reporting, the present paper suggests an ontological representation of patient safety knowledge. Design/methodology/approach: We propose a framework for constructing an ontological knowledge base of patient safety. The present paper describes our design, implementation, and evaluation of the ontology at its initial stage. Findings: We describe the design and initial outcomes of the ontology implementation. The evaluation results demonstrate the clinical validity of the ontology by a self-developed survey measurement. Research limitations: The proposed ontology was developed and evaluated using a small number of information sources. Presently, US data are used, but they are not essential for the ultimate structure of the ontology. Practical implications: The goal of improving patient safety can be aided through investigating patient safety reports and providing actionable knowledge to clinical practitioners. As such, constructing a domain specific ontology for patient safety reports serves as a cornerstone in information collection and text mining methods. Originality/value: The use of ontologies provides abstracted representation of semantic information and enables a wealth of applications in a reporting system. Therefore, constructing such a knowledge base is recognized as a high priority in health care.

Safety technical considerations on the 2012 periodic safety verification of the Beznau nuclear power plant; Sicherheitstechnische Stellungnahme zur Periodischen Sicherheitsüberprüfung 2012 des Kernkraftwerks Beznau

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-12-15

According to nuclear legislation, the owner of an operational license for a nuclear power plant has to provide a periodic safety verification (PSU) every 10 years. The 'North Eastern Power Plants' company (NOK), today AXPO Power AG already performed such a PSU for the Beznau-2 nuclear reactor block (KKB2) in 2002. The Beznau-1 nuclear reactor block (KKB1) received its definitive operational license in October 1970, after test operation during 7 months. After the license for test operation received on July 16{sup th}, 1971, the operational license of KKB2 was renewed several times, each time for a certain period of validity. In 1991, NOK requested a definitive operational license for KKB2, but in 1994 the Swiss Federal Council lengthened the license for only 10 years. Moreover, it laid down that NOK has to periodically report on the safety of the facility. With its letter of August 23{sup rd}, 1998, the Federal Office of Energy defined the documents to be produced for the PSU. The extent of the PSU was defined in such a way that many documents concern the whole power plant, i.e. both nuclear reactor blocks. On December 3{sup rd}, 2004, the Swiss Federal Council granted KKB2 an operational license of limited validity. The present report reviews the 2012 PSU, which covers the time interval from January 1{sup st}, 2002, to December 31{sup st}, 2011, from the point of view of safety. It contains documents for the evaluation of both reactor blocks at KKB. The Beznau interim storage pool was also taken into consideration; it is situated on the KKB site, but, according to a decision of the Swiss Federal Council of May 23{sup rd}, 1991, it has an independent operational license. The evaluation of ageing surveillance takes the whole operational period of the facility into account, i.e. the ageing mechanisms acting as from the beginning of the operation. Moreover, important developments that occurred after the surveillance time interval have been taken into account

Report on nuclear and radiological safety in 1994

International Nuclear Information System (INIS)

Lovincic, D.

1995-01-01

The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate, prepared the Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1994 as part of its regular practice of reporting on its activities to the Government and the Parliament of the Republic of Slovenia. The report is divided into seven thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activities of the Agency for Radwaste Management (ARAO), the activities of international safety missions in Slovenia, environmental radioactivity monitoring in Slovenia, ionizing radiation sources control by Slovenian Health Inspectorate and review of the operation of nuclear facilities around the world.

77 FR 21782 - International Conference on Harmonisation; Draft Guidance for Industry on E2C(R2) Periodic...

Science.gov (United States)

2012-04-11

... Safety Data Management: Periodic Safety Update Reports for Marketed Drugs'' (E2C guidance) and ``Addendum to E2C Clinical Safety Data Management: Periodic Safety Update Reports for Marketed Drugs'' (addendum....regulations.gov . Submit written comments to the Division of Dockets Management (HFA-305), Food and Drug...

Improving the safety of LWR power plants. Final report

International Nuclear Information System (INIS)

1980-04-01

This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs

Geosphere process report for the safety assessment SR-Site

International Nuclear Information System (INIS)

Skagius, Kristina

2010-11-01

This report documents geosphere processes identified as relevant to the long-term safety of a KBS-3 repository, and forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Geosphere process report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

Skagius, Kristina (ed.) (Kemakta Konsult AB, Stockholm (Sweden))

2010-11-15

This report documents geosphere processes identified as relevant to the long-term safety of a KBS-3 repository, and forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Work stress and patient safety: observer-rated work stressors as predictors of characteristics of safety-related events reported by young nurses.

Science.gov (United States)

Elfering, A; Semmer, N K; Grebner, S

This study investigates the link between workplace stress and the 'non-singularity' of patient safety-related incidents in the hospital setting. Over a period of 2 working weeks 23 young nurses from 19 hospitals in Switzerland documented 314 daily stressful events using a self-observation method (pocket diaries); 62 events were related to patient safety. Familiarity of safety-related events and probability of recurrence, as indicators of non-singularity, were the dependent variables in multilevel regression analyses. Predictor variables were both situational (self-reported situational control, safety compliance) and chronic variables (job stressors such as time pressure, or concentration demands and job control). Chronic work characteristics were rated by trained observers. The most frequent safety-related stressful events included incomplete or incorrect documentation (40.3%), medication errors (near misses 21%), delays in delivery of patient care (9.7%), and violent patients (9.7%). Familiarity of events and probability of recurrence were significantly predicted by chronic job stressors and low job control in multilevel regression analyses. Job stressors and low job control were shown to be risk factors for patient safety. The results suggest that job redesign to enhance job control and decrease job stressors may be an important intervention to increase patient safety.

Safety Review Committee - Annual Report 1991-1992

International Nuclear Information System (INIS)

1993-01-01

During the year under review. The Safety Review Committee (SRC) assessed the safety of ANSTO's operations. This was done by site visits, examination of documentation and briefing by ANSTO officers responsible for particular operations, and includes HIFAR and Moata reactors, radioisotope production, packing and dispatch, radioactive waste management practices, occupational health and safety activities and ANSTO's arrangements for public health and safety beyond the site. This report describes the activities and findings of the SRC during the year ending 30 June 1992. 8 figs., ills

Safety report on WWR-S reactor

International Nuclear Information System (INIS)

Horyna, J.; Kaisler, L.; Listik, E.

1981-04-01

The present Safety Report of the WWR-S reactor summarizes findings obtained during the trial and partially also permanent operation of the reactor after two stages of its reconstruction implemented between 1974 and 1976. Most data are presented necessary for assessing probable risks of possible accident conditions whose consequences pose health hazards to individuals of the population, radiation personnel and the facilities themselves. Attention is devoted to the description of the locality, to components and systems, heat removal from the core, design aspects, the quality of new and old parts of the technological circuits, the systems of protection and control, the emergency core cooling system, the problems of radiation safety, and to the safety analyses of the abnormal states envisaged. The Report was compiled with regard to IAEA and CMEA recommendations concerning safe operation of research reactors and to the recommendations and binding decisions of the Czechoslovak Atomic Energy Commission. (author)

14 CFR 91.25 - Aviation Safety Reporting Program: Prohibition against use of reports for enforcement purposes.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Aviation Safety Reporting Program... GENERAL OPERATING AND FLIGHT RULES General § 91.25 Aviation Safety Reporting Program: Prohibition against... to the National Aeronautics and Space Administration under the Aviation Safety Reporting Program (or...

Fusion Safety Program. Annual report, FY 1982

International Nuclear Information System (INIS)

Crocker, J.G.; Cohen, S.

1983-07-01

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

Nuclear Safety Research Department annual report 2000

DEFF Research Database (Denmark)

Majborn, B.; Nielsen, Sven Poul; Damkjær, A.

2001-01-01

The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and "Radioecology andTracer Studies". In addtion the department...

Nuclear Safety Research Department annual report 2001

DEFF Research Database (Denmark)

Majborn, B.; Damkjær, A.; Nielsen, Sven Poul

2002-01-01

The report presents a summary of the work of the Nuclear Safety Research Department in 2001. The department's research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and "Radioecology andTracer Studies". In addition the department...

Designing a Safety Reporting Smartphone Application to Improve Patient Safety After Total Hip Arthroplasty.

Science.gov (United States)

Krumsvik, Ole Andreas; Babic, Ankica

2017-01-01

This paper presents a safety reporting smartphone application which is expected to reduce the occurrence of postoperative adverse events after total hip arthroplasty (THA). A user-centered design approach was utilized to facilitate optimal user experience. Two main implemented functionalities capture patient pain levels and well-being, the two dimensions of patient status that are intuitive and commonly checked. For these and other functionalities, mobile technology could enable timely safety reporting and collection of patient data out of a hospital setting. The HCI expert, and healthcare professionals from the Haukeland University Hospital in Bergen have assessed the design with respect to the interaction flow, information content, and self-reporting functionalities. They have found it to be practical, intuitive, sufficient and simple for users. Patient self-reporting could help recognizing safety issues and adverse events.

The President's Report on Occupational Safety and Health.

Science.gov (United States)

Department of Health, Education, and Welfare, Washington, DC.

This report describes what has been done to implement the Occupational Safety and Health Act of 1970 during its first year of operation. The report examines the responsibilities of the Department of Labor for setting safety and health standards and also explores the activities of the Department of Health, Education, and Welfare in research and…

Selection of detailed items for periodic safety review on PWR radwaste management system

Energy Technology Data Exchange (ETDEWEB)

Sung, K. B.; Ahn, Y. S.; Park, Y. S.; Kim, S. H.; Kim, J. T. [Korea Hydric and Nuclear Power Company, Taejon (Korea, Republic of)

2003-10-01

Selection of detailed-items for Periodic Safety Review on PWR radwaste management system, the main component could be faithfully clarified according to the purpose of establishment on each system and basic purpose. It is proper to select detailed-items those of radioactivities in the reactor coolant activity levels and the released volume of liquid and gaseous radioactive material on safety performance. It's also proper to select solid radwaste production quantities as detailed-item that it would be predict the next ten years trends after PSR.

Managing change in the nuclear industry: The effects on safety. INSAG-18. A report by the International Nuclear Safety Advisory Group (Russian Edition)

International Nuclear Information System (INIS)

2015-01-01

The nuclear industry is going through a period of unprecedented change. The changes arise from the political and business environment in which the industry must operate, and from within the industry itself as it strives to become more competitive. These pressures have already led to significant changes in how nuclear enterprises are organized. The changes can be expected to continue. It is absolutely essential that throughout the period of time that organizational changes are taking place, and after the changes have occurred, very high standards of safety are maintained by all the elements that make up the industry. Changes can be made effectively and safely, and gains in efficiency and competitiveness, as well as safety, can be realized if changes are introduced carefully and managed well. Experience has shown that this is not a simple matter to achieve. Nuclear installations are complex, and it is inherently demanding to foresee all the implications that a change may have on safety. However, experience has shown very clearly that many changes have a strong potential to affect both the safety that has been built into a design and in the safety culture of an organization. Hence failure to manage change well can significantly affect the likelihood of an accident, the degree to which the assets of the company are put at risk and the company's reputation. This INSAG report is directed at members of boards of directors and senior executives who are responsible for the overall safety of an installation, who make decisions for change and who implement these decisions. It is also written for senior regulators who, on behalf of the public, ensure that boards of directors and executives meet their responsibilities for safety. This report discusses how and why change can challenge the maintenance of a high level of safety, and what can be done to control that challenge and hence reap all the benefits of change. It draws an analogy between the well established principles

Nuclear safety research project. Annual report 1995

International Nuclear Information System (INIS)

Hueper, R.

1996-08-01

The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1995 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1996. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

Interim process report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Sellin, Patrick

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses

Interim process report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

Sellin, Patrick (ed.)

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses.

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

Science.gov (United States)

Corkern, Walter H.; Munchausen, Linda L.

1983-01-01

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

Re-assessment of seismic loads in conjunction with periodic safety review

International Nuclear Information System (INIS)

Jonczyk, Josef

2002-01-01

The objective of this paper is the fundamental consideration of a safeguard-aim-oriented approach for use in the re-assessment of seismic events with regard to the periodic safety review (PSR) of nuclear power plants (NPP). The re-assessment aspects of site-specific design earthquakes (DEQ), specially the procedure for seismic hazard analysis, will not, however, be considered in detail here. The proposed assessment concept clearly presents a general approach for safety assessments. The approach is based on a successive screening review of components that are considered sufficiently earthquake-resistant. In this respect, the principle of maximum practical application of the design documentation has been considered in the re-assessment process. On the other hand, the safeguard-aim-oriented evaluation will also be applied with regard to whether the requirements of the safety regulations are fulfilled with respect to the safety goals. The review in conjunction with PSR does not, however, attempt to perform this under all technical aspects. Moreover, it is possible to make extensive use of experimental knowledge and engineering judgement with regard to the structural capacity behaviour in case of a seismic event. Compared with design procedures, however, this proposed approach differs from the one applied in licensing procedures, in which such assessment freedom will not usually be exhausted. (author)

Safety Analysis Report for Ignalina NPP

International Nuclear Information System (INIS)

Negrivoda, G.

1997-01-01

In December 1994 an agreement was signed between the European Bank for Reconstruction and Development and the Republic of Lithuania for the grant of 32.86 MECU for the safety Improvement at Ignalina NPP. One of the conditions for the provision of the grant, was a requirement for an in-depth analysis of the safety level at Ignalina NPP in the scope and according to the standards acceptable for a western nuclear power plant, and to publish a Safety Analysis Report (SAR). The report should investigate and analyze any factor that could limit a safe operation of the plant, and provide recommendations for actual safety improvements. According to the agreement, Lithuania had to finalize the SAR until 31 December, 1995. The bank has also organized and financed investigation of safety at Ignalina NPP and preparation of the SAR. EBRD made an agreement with Sweden's Vattenfall, which subcontracted well-known companies from Canada, USA, Germany, etc., and also the Russian Research and Development Institute of Power Engineering (NIKIET), reactor designer of Ignalina NPP. The SAR is a very comprehensive document and contains about 8000 pages of text, diagrams and tables. The main findings of the SAR are provided in the article. A large number of discrepancies with modern rules and western practices was detected, but they were not proved to be serious enough to require reactors shutdown. Based on the recommendations of the SAR Ignalina NPP has worked out Safety Improvement Program No. 2 (SIP-2), which is planned for three years and will cost 486 MLT. (author)

Nuclear Safety Project - annual report 1980

International Nuclear Information System (INIS)

1981-08-01

The Annual Report 1980 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1980 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work completed, essential results, plans for the near future. (orig./RW) [de

Health and Safety annual report 1993

International Nuclear Information System (INIS)

1994-01-01

In the 1993 Health and Safety Report for BNFL, data showing improvements in radiological and conventional safety are given. Other aspects discussed are emergency planning, the level of incidents, occupational health services, litigation and the compensation scheme, the transport of radioactive materials, research covering transgenerational epidemiology, mortality and cancer studies, genetics and radiobiology, and dosimetry, and finally a summary of radioactive discharges and environmental data. (UK)

Annual report on occupational safety

International Nuclear Information System (INIS)

1985-09-01

A report is given on the occupational safety relating to BNFL's employees for the year 1984 and the results compared to those obtained in 1983. Data are presented for each of the Company's Sites on whole body exposures, accidental deaths and major injuries and nuclear and non-nuclear incidents. The results show that the Company average body dose continues to be less than 5mSv, there were no accidental deaths but 15 major injuries. One nuclear incident and 9 non-nuclear incidents were notified to the Health and Safety Executive. (UK)

Annual report ''nuclear safety in France''

International Nuclear Information System (INIS)

2001-01-01

This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

78 FR 5866 - Pipeline Safety: Annual Reports and Validation

Science.gov (United States)

2013-01-28

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID PHMSA-2012-0319] Pipeline Safety: Annual Reports and Validation AGENCY: Pipeline and Hazardous Materials... 2012 gas transmission and gathering annual reports, remind pipeline owners and operators to validate...

Nuclear and radiation safety in Slovenia. Annual report 1997

International Nuclear Information System (INIS)

1998-01-01

The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 1997. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. Contributions to the report were furthermore prepared by competent authorities in the field of nuclear safety: the Agency for Radwaste Management (ARAO), the Milan Copic Nuclear Training Centre, etc. The report contains 17 chapters. (author)

Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group

International Nuclear Information System (INIS)

2002-01-01

This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

78 FR 14877 - Pipeline Safety: Incident and Accident Reports

Science.gov (United States)

2013-03-07

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID PHMSA-2013-0028] Pipeline Safety: Incident and Accident Reports AGENCY: Pipeline and Hazardous Materials... PHMSA F 7100.2--Incident Report--Natural and Other Gas Transmission and Gathering Pipeline Systems and...

Planning report for the safety assessment SR-Can

International Nuclear Information System (INIS)

2003-06-01

This document is a planning report for SKB's next assessment of long-term safety for a KBS 3 repository. The assessment, SR-Can, is to be finished by the end of 2005 and will be used for SKB's application to build an Encapsulation plant for spent nuclear fuel. Apart from outlining the methodology, the report discusses the handling in SR-Can of a number of important issues regarding the near field, the geosphere, the biosphere, the climatic evolution etc. The Swedish nuclear safety and radiation protection authorities have recently issued regulations concerning the final disposal of nuclear waste. The principal compliance criterion states that the annual risk of harmful effects must not exceed 10 -6 for a representative individual in the group exposed to the greatest risk. There are also a number of requirements on methodological aspects of the safety assessment as well as on the contents of a safety report. The regulations are reproduced in an Appendix to this report. The primary safety function of the KBS 3 system is to completely isolate the spent nuclear fuel within copper canisters over the entire assessment period, which will be one million years in SR-Can. Should a canister be damaged, the secondary safety function is to retard any releases from the canisters. The main steps of the assessment are the following: 1. Qualitative system description, FEP processing: This step consists of defining a system boundary and of describing the system on a format suitable for the safety assessment. Databases of relevant features, events and processes influencing long-term safety are structured and used as one starting point for the assessment. 2. Initial state descriptions. 3. Process descriptions: In this step all identified processes within the system boundary involved in the long-term evolution of the system are described in detail. 4. Description of boundary conditions: This step is a broad description of the evolution of the boundaries of the system, focussing mainly

Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

International Nuclear Information System (INIS)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang

2006-01-01

This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

2006-01-15

This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area.

Organizational safety culture and medical error reporting by Israeli nurses.

Science.gov (United States)

Kagan, Ilya; Barnoy, Sivia

2013-09-01

To investigate the association between patient safety culture (PSC) and the incidence and reporting rate of medical errors by Israeli nurses. Self-administered structured questionnaires were distributed to a convenience sample of 247 registered nurses enrolled in training programs at Tel Aviv University (response rate = 91%). The questionnaire's three sections examined the incidence of medication mistakes in clinical practice, the reporting rate for these errors, and the participants' views and perceptions of the safety culture in their workplace at three levels (organizational, departmental, and individual performance). Pearson correlation coefficients, t tests, and multiple regression analysis were used to analyze the data. Most nurses encountered medical errors from a daily to a weekly basis. Six percent of the sample never reported their own errors, while half reported their own errors "rarely or sometimes." The level of PSC was positively and significantly correlated with the error reporting rate. PSC, place of birth, error incidence, and not having an academic nursing degree were significant predictors of error reporting, together explaining 28% of variance. This study confirms the influence of an organizational safety climate on readiness to report errors. Senior healthcare executives and managers can make a major impact on safety culture development by creating and promoting a vision and strategy for quality and safety and fostering their employees' motivation to implement improvement programs at the departmental and individual level. A positive, carefully designed organizational safety culture can encourage error reporting by staff and so improve patient safety. © 2013 Sigma Theta Tau International.

The complexity of patient safety reporting systems in UK dentistry.

Science.gov (United States)

Renton, T; Master, S

2016-10-21

Since the 'Francis Report', UK regulation focusing on patient safety has significantly changed. Healthcare workers are increasingly involved in NHS England patient safety initiatives aimed at improving reporting and learning from patient safety incidents (PSIs). Unfortunately, dentistry remains 'isolated' from these main events and continues to have a poor record for reporting and learning from PSIs and other events, thus limiting improvement of patient safety in dentistry. The reasons for this situation are complex.This paper provides a review of the complexities of the existing systems and procedures in relation to patient safety in dentistry. It highlights the conflicting advice which is available and which further complicates an overly burdensome process. Recommendations are made to address these problems with systems and procedures supporting patient safety development in dentistry.

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

International Nuclear Information System (INIS)

2013-07-01

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

Health and safety annual report 1988

International Nuclear Information System (INIS)

1989-01-01

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

Report on safety and the environment 1992-93

International Nuclear Information System (INIS)

1993-09-01

The steps taken by AEA Technology to implement high safety and environmental standards and performance levels achieved are summarized. AEA's policy on safety and the environment is stated. The way that safety is organised, how plant safety cases are made, plant operations and safety 1992-93 and decommissioning work at several of AEA's plants are reported. Radiological doses for AEA plants are shown to have fallen since 1990. General industrial and office safety, what is learned from accidents and incidents, how the environment is protected, the occupational health services provided and the emergency arrangements in operation are also mentioned briefly. (UK)

Psychological safety and error reporting within Veterans Health Administration hospitals.

Science.gov (United States)

Derickson, Ryan; Fishman, Jonathan; Osatuke, Katerine; Teclaw, Robert; Ramsel, Dee

2015-03-01

In psychologically safe workplaces, employees feel comfortable taking interpersonal risks, such as pointing out errors. Previous research suggested that psychologically safe climate optimizes organizational outcomes. We evaluated psychological safety levels in Veterans Health Administration (VHA) hospitals and assessed their relationship to employee willingness of reporting medical errors. We conducted an ANOVA on psychological safety scores from a VHA employees census survey (n = 185,879), assessing variability of means across racial and supervisory levels. We examined organizational climate assessment interviews (n = 374) evaluating how many employees asserted willingness to report errors (or not) and their stated reasons. Finally, based on survey data, we identified 2 (psychologically safe versus unsafe) hospitals and compared their number of employees who would be willing/unwilling to report an error. Psychological safety increased with supervisory level (P hospital (71% would report, 13% would not) were less willing to report an error than at the psychologically safe hospital (91% would, 0% would not). A substantial minority would not report an error and were willing to admit so in a private interview setting. Their stated reasons as well as higher psychological safety means for supervisory employees both suggest power as an important determinant. Intentions to report were associated with psychological safety, strongly suggesting this climate aspect as instrumental to improving patient safety and reducing costs.

Task Group on Safety Margins Action Plan (SMAP). Safety Margins Action Plan - Final Report

International Nuclear Information System (INIS)

Hrehor, Miroslav; Gavrilas, Mirela; Belac, Josef; Sairanen, Risto; Bruna, Giovanni; Reocreux, Michel; Touboul, Francoise; Krzykacz-Hausmann, B.; Park, Jong Seuk; Prosek, Andrej; Hortal, Javier; Sandervaag, Odbjoern; Zimmerman, Martin

2007-01-01

The international nuclear community has expressed concern that some changes in existing plants could challenge safety margins while fulfilling all the regulatory requirements. In 1998, NEA published a report by the Committee on Nuclear Regulatory Activities on Future Nuclear Regulatory Challenges. The report recognized 'Safety margins during more exacting operating modes' as a technical issue with potential regulatory impact. Examples of plant changes that can cause such exacting operating modes include power up-rates, life extension or increased fuel burnup. In addition, the community recognized that the cumulative effects of simultaneous changes in a plant could be larger than the accumulation of the individual effects of each change. In response to these concerns, CSNI constituted the safety margins action plan (SMAP) task group with the following objectives: 'To agree on a framework for integrated assessments of the changes to the overall safety of the plant as a result of simultaneous changes in plant operation / condition; To develop a CSNI document which can be used by member countries to assess the effect of plant change on the overall safety of the plant; To share information and experience.' The two approaches to safety analysis, deterministic and probabilistic, use different methods and have been developed mostly independently of each other. This makes it difficult to assure consistency between them. As the trend to use information on risk (where the term risk means results of the PSA/PRA analysis) to support regulatory decisions is growing in many countries, it is necessary to develop a method of evaluating safety margin sufficiency that is applicable to both approaches and, whenever possible, integrated in a consistent way. Chapter 2 elaborates on the traditional view of safety margins and the means by which they are currently treated in deterministic analyses. This chapter also discusses the technical basis for safety limits as they are used today

Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

Energy Technology Data Exchange (ETDEWEB)

Baum, J W; Boccio, J L; Diamond, D; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Hall, R E; Higgins, J C; Weiss, A J [comp.

1988-12-01

This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1987.

Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, October 1--December 31, 1988

Energy Technology Data Exchange (ETDEWEB)

Weiss, A J; Azarm, A; Baum, J W; Boccio, J L; Carew, J; Diamond, D J; Fitzpatrick, R; Ginsberg, T; Greene, G A; Guppy, J G; Haber, S B

1989-07-01

This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through September 30, 1988.

Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--June 30, 1988

International Nuclear Information System (INIS)

Baum, J.W.; Boccio, J.L.; Diamond, D.

1988-12-01

This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1987

Report on nuclear and radiological safety in 1995

International Nuclear Information System (INIS)

Lovincic, D.

1996-07-01

The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate of the Republic of Slovenia and the Administration for Rescue and Disaster Relief (URSZR) has prepared a Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1995. The report is presenting: the activities of the SNSA; the operation of nuclear facilities; monitoring of radioactivity; control of ionizing radiation and nuclear electricity generation.

Preparing a Safety Analysis Report using the building block approach

International Nuclear Information System (INIS)

Herrington, C.C.

1990-01-01

The credibility of the applicant in a licensing proceeding is severely impacted by the quality of the license application, particularly the Safety Analysis Report. To ensure the highest possible credibility, the building block approach was devised to support the development of a quality Safety Analysis Report. The approach incorporates a comprehensive planning scheme that logically ties together all levels of the investigation and provides the direction necessary to prepare a superior Safety Analysis Report

Interim summary report of the safety case 2009

International Nuclear Information System (INIS)

2010-03-01

Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy), Posiva is preparing to submit a construction license application for the final disposal spent nuclear fuel at the Olkiluoto site, Finland, by the end of the year 2012. Disposal will take place in a geological repository implemented according to the KBS-3 method. The long-term safety section supporting the license application will be based on a safety case that, according to the internationally adopted definition, will be a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository. The present Interim Summary Report represents a major contribution to the development of this safety case. The report has been compiled in accordance with Posiva's current plan for preparing this safety case. A full safety case for the KBS-3V variant will be developed to support the Preliminary Safety Assessment Report (PSAR) in 2012. The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository. Current understanding of the evolution of the disposal system indicates that, except a few unlikely circumstances affecting a small number of canisters, spent fuel will remain isolated, and the radionuclides contained within the canisters, for hundreds of thousands of years or more, in accordance with the base scenario. Confidence in this base scenario derives, in the first place, from the

Nuclear safety research project (PSF). 1999 annual report

International Nuclear Information System (INIS)

Muehl, B.

2000-08-01

The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report summarizes the R and D results of PSF during 1999. The research tasks cover three main topics: Light Water Reactor safety, innovative systems, and studies related to the transmutation of actinides. The importance of the Light Water Reactor safety, however, has decreased during the last year in favour of the transmutation of actinides. Numerous institutes of the research centre contribute to the PSF programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2000. (orig.) [de

New Automated System Available for Reporting Safety Concerns | Poster

Science.gov (United States)

A new system has been developed for reporting safety issues in the workplace. The Environment, Health, and Safety’s (EHS’) Safety Inspection and Issue Management System (SIIMS) is an online resource where any employee can report a problem or issue, said Siobhan Tierney, program manager at EHS.

Nordic nuclear safety research. Summary report for 1995. Plans for 1996 and 1997

International Nuclear Information System (INIS)

1996-04-01

NKS (Nordic Nuclear Safety Research) is a cooperative body in nuclear safety and radiation protection. Its purpose is to carry out cost-effective Nordic projects, thus producing research results, exercises, information, recommendations, manuals and other types of background material, to be used by decision makers and other concerned staff members at authorities and within the nuclear industry. This is the annual report for 1995. The report also contains plans for the rest of the program period. The program comprises four major fields of research: reactor safety; radioactive waste; radioecology; and emergency preparedness. Finland and Sweden presently operate a total of 16 power producing reactors. Denmark, Norway and Sweden operate research reactors. There is a plant for nuclear fuel manufacture in Sweden. All five Nordic countries have intermediate waste storage facilities. In addition, there are a number of power, research and naval reactors and other nuclear installations in Nordic surroundings, both in Eastern and Western Europe. Hence, nuclear safety, radiation protection, waste management, environmental impact and emergency preparedness issues are of common interest to all Nordic countries. Environmental impact of radioactive releases is studied in two radioecology projects. The project on marine radioecology, including sediment research (EKO-1), includes sampling, analysis and modeling. These are also key issues in the project on long ecological half-lives in semi-natural systems (EKO-2). The transfer of the seven presently ongoing projects are summarized in this report by the project leaders, both in terms of results in 1995 and plans for 1996/97. (EG)

A report on developing a checklist to assess company plans focused on improving safety awareness, safe behaviour and safety culture: final report

NARCIS (Netherlands)

Steijger, N.; Starren, H.; Keus, M.; Gort, J.; Vervoort, M.

2003-01-01

This report describes the process of developing a checklist to asses company plans focused on improving safety awareness, safe behaviour and safety culture. These plans are part of a programme initiated by the Ministry of Social Affairs and Employment aiming at improving the safety performance of

Analysis of doses reported to the Health and Safety Executive's Central Index of Dose Information

International Nuclear Information System (INIS)

1993-01-01

This publication analyses the occupational exposure summary information reported to the UK Health and Safety Executive for the years 1986-91. In particular, it considers evidence pointing to the relative success of employers in restricting occupational exposure to ionising radiation over this period. Exposure in the nuclear industry, industrial radiography, non-coal miners underground, medicine, dentistry and the transport sector is discussed. (UK)

KIT safety management. Annual report 2012

International Nuclear Information System (INIS)

Frank, Gerhard

2013-01-01

The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for - licensing procedures, - industrial safety organization, - control of environmental protection measures, - planning and implementation of emergency preparedness and response, - operation of radiological laboratories and measurement stations, - extensive radiation protection support and the - the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its industrial safety management is certified by the VBG as ''AMS-Arbeitsschutz mit System'' and, hence, fulfills the requirements of NLF / ISO-OSH 2001. KSM laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2012. Status figures in principle reflect the status at the end of the year 2012. The processes described cover the areas of competence of KSM.

Engineered safeguards and passive safety features (safety analysis detailed report no. 6)

Energy Technology Data Exchange (ETDEWEB)

1988-01-15

The Safety-Analysis Summary lists the reactor's safety aspects for passive and active prevention of severe accidents and mitigation of accident consequences, i.e., intrinsic and passive protections of the plant; intrinsic and passive protections of the core; inherent decay-heat removal systems; rapid-shutdown systems; four physical containment barriers. This report goes into further details regarding some of this aspects.

National report of Brazil. Nuclear Safety Convention

International Nuclear Information System (INIS)

1998-09-01

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

Electronic clinical safety reporting system: a benefits evaluation.

Science.gov (United States)

Elliott, Pamela; Martin, Desmond; Neville, Doreen

2014-06-11

Eastern Health, a large health care organization in Newfoundland and Labrador (NL), started a staged implementation of an electronic occurrence reporting system (used interchangeably with "clinical safety reporting system") in 2008, completing Phase One in 2009. The electronic clinical safety reporting system (CSRS) was designed to replace a paper-based system. The CSRS involves reporting on occurrences such as falls, safety/security issues, medication errors, treatment and procedural mishaps, medical equipment malfunctions, and close calls. The electronic system was purchased from a vendor in the United Kingdom that had implemented the system in the United Kingdom and other places, such as British Columbia. The main objective of the new system was to improve the reporting process with the goal of improving clinical safety. The project was funded jointly by Eastern Health and Canada Health Infoway. The objectives of the evaluation were to: (1) assess the CSRS on achieving its stated objectives (particularly, the benefits realized and lessons learned), and (2) identify contributions, if any, that can be made to the emerging field of electronic clinical safety reporting. The evaluation involved mixed methods, including extensive stakeholder participation, pre/post comparative study design, and triangulation of data where possible. The data were collected from several sources, such as project documentation, occurrence reporting records, stakeholder workshops, surveys, focus groups, and key informant interviews. The findings provided evidence that frontline staff and managers support the CSRS, identifying both benefits and areas for improvement. Many benefits were realized, such as increases in the number of occurrences reported, in occurrences reported within 48 hours, in occurrences reported by staff other than registered nurses, in close calls reported, and improved timelines for notification. There was also user satisfaction with the tool regarding ease of use

Fusion Safety Program annual report, fiscal year 1984

International Nuclear Information System (INIS)

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

1985-06-01

This report summarizes the Fusion Safety Program major activities in fiscal year 1984. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. A report section titled ''Activities at the INEL'' includes progress reports on the tritium implantation experiment, tritium blanket permeation, volatilization of reactor alloys, plasma disruptions, a comparative blanket safety assessment, transient code development, and a discussion of the INEL's participation in the Tokamak Fusion Core Experiment (TFCX) design study. The report section titled ''Outside Contracts'' includes progress reports on tritium conversion by the Oak Ridge National Laboratory (ORNL), lithium-lead reactions by the Hanford Engineering Development Laboratory (HEDL) and the University of Wisconsin, magnet safety by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) and Argonne National Laboratory (ANL), risk assessment by MIT, tritium retention by the University of Virginia, and activation product release by GA Technologies. A list of publications produced during the year and brief descriptions of activities planned for FY-1985 are also included

2007 motor vehicle occupant safety survey. Volume 3, air bags report

Science.gov (United States)

2008-11-01

The 2007 Motor Vehicle Occupant Safety Survey was the sixth in a series of periodic national telephone surveys on occupant : protection issues conducted for the National Highway Traffic Safety Administration (NHTSA). Data collection was conducted : b...

1978 annual report of the safety department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.

1979-04-01

The Safety Officer and the Security Officer, respectively, are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the security of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH. (KfK). To fulfill these functions they rely on the assitance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project and the Nuclear Safeguards Project. The centers of interest of r and d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, implementation of nuclear fuel safequarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1978 routine tasks, and reports about new results of investigations and developments of the working groups of the Department. (orig.) [de

Annual Report 1979 of the Safety Department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.; Koenig, L.A.

1980-04-01

The Safety Officer and the Security Officer, respectively, are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the security of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH. (KfK). To fulfill these functions they rely on the assistance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project and the Nuclear Safeguards Project. The centers of interest of r and d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, implemantation of nuclear fuel safeguarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1979 routine tasks, and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

Energy Technology Data Exchange (ETDEWEB)

Weiss, A J [comp.

1989-02-01

This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through June 30, 1988. 71 figs., 24 tabs.

Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, July 1--September 30, 1988

International Nuclear Information System (INIS)

Weiss, A.J.

1989-02-01

This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through June 30, 1988. 71 figs., 24 tabs

Research program on regulatory safety research - Synthesis report 2008

International Nuclear Information System (INIS)

Mailaender, R

2009-06-01

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

The Interagency Nuclear Safety Review Panel's Galileo safety evaluation report

International Nuclear Information System (INIS)

Nelson, R.C.; Gray, L.B.; Huff, D.A.

1989-01-01

The safety evaluation report (SER) for Galileo was prepared by the Interagency Nuclear Safety Review Panel (INSRP) coordinators in accordance with Presidential directive/National Security Council memorandum 25. The INSRP consists of three coordinators appointed by their respective agencies, the Department of Defense, the Department of Energy (DOE), and the National Aeronautics and Space Administration (NASA). These individuals are independent of the program being evaluated and depend on independent experts drawn from the national technical community to serve on the five INSRP subpanels. The Galileo SER is based on input provided by the NASA Galileo Program Office, review and assessment of the final safety analysis report prepared by the Office of Special Applications of the DOE under a memorandum of understanding between NASA and the DOE, as well as other related data and analyses. The SER was prepared for use by the agencies and the Office of Science and Technology Policy, Executive Office of the Present for use in their launch decision-making process. Although more than 20 nuclear-powered space missions have been previously reviewed via the INSRP process, the Galileo review constituted the first review of a nuclear power source associated with launch aboard the Space Transportation System

Review of safety reports involving electronic flight bags

Science.gov (United States)

2009-04-27

Electronic Flight Bags (EFBs) are a relatively new device used by pilots. Even so, 37 safety-related events involving EFBs were identified from the public online Aviation Safety Reporting System (ASRS) database as of June 2008. In addition, two accid...

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)

Status of Ignalina's safety analysis reports

International Nuclear Information System (INIS)

Uspuras, E.

1999-01-01

Ignalina NPP is unique among RBMK type reactors in the scope and comprehensiveness of international studies which have been performed to verify its design parameters and analyze risk levels. International assistance took several forms, a very valuable mod of assistance utilized the knowledge of international experts in extensive international studies whose purpose was: collection, systematization and verification of plant design data; analysis of risk levels; recommendations leading to improvements in the safety lave; transfer of state of the art analytical methodology to Lithuanian specialists. The major large scale international studies include: probabilistic risk analysis; extensive international study meant to provide comprehensive overview of plant status with special emphasis on safety aspects; an extensive review of the Safety Analysis Report by an independent group of international experts. In spite of the safety improvements and analyses which have been performed at the Ignalina NPP, much remains to be done in the nearest future

Research projects into the safety of nuclear power plants. Period cover 01. January - 30. June 2016. Progress report; Forschungsvorhaben auf dem Gebiet der Reaktorsicherheit. Berichtszeitraum 01. Januar - 30. Juni 2016. Fortschrittsbericht

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-07-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/ Authority Support Division of GRS. The reports as of the year 2000 are available in the internet-based information system on results and data of reactor safety research (https://www.grs-fbw.de). The compilation of the reports is classified according to general topics related to reactor safety research as well as to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

Research projects into the safety of nuclear power plants. Period cover 01. July - 31. December 2016. Progress report; Forschungsvorhaben auf dem Gebiet der Reaktorsicherheit. Berichtszeitraum 01. Juli - 31. Dezember 2016. Fortschrittsbericht

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-07-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fur Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/ Authority Support Division of GRS. The reports as of the year 2000 are available in the internet-based information system on results and data of reactor safety research (https://www.grs-fbw.de). The compilation of the reports is classified according to general topics related to reactor safety research as well as to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. lt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

Regulatory Aspect of Periodic Safety Review Performed in Nuclear Power Plants in the Slovak Republic

International Nuclear Information System (INIS)

Baszo, Z.

2010-01-01

The paper deals with the regulatory aspect of Nuclear Power Plant (NPP) Periodic Safety Review (PSR) as a part of license renewal process in the Slovak Republic. It summarizes the history of activities similar to PSR performed in the past for NPPs operated in the Slovak Republic. Furthermore, it describes both the requirements involved in the current Slovak legislation to be met by licensee in the Slovak Republic in this field and the procedures concerning the PSR as well. The objective and rules of PSR to be performed for NPPs in the Slovak Republic were derived from the internationally accepted International Atomic Energy Agency (IAEA) document and have been implemented into national legislation. PSR of two twin units located in Bohunice NPP and Mochovce NPP, respectively, has been initiated in the Slovak Republic based on evaluation of each area to be reviewed (safety factors) using recent methodology and practice. Other significant factors, such as ageing, modifications of NPP and the safe operation for a specified future period, have to be assessed in the frame of PSR. Report on performed PSR outlines the results of review for each area, the corrective plan, which considering mutual relations between assessed areas specifies the issues to be solved with the aim to eliminate shortcomings identified in the frame of PSR and to adopt safety improvements. The findings from PSR in the evaluated areas also serve as a source of information for updating of all documents to be attached to the written application of licensee for renewal of a nuclear power plant operating license. The presented procedure describes how the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) has reviewed the documents submitted during PSR. Based on results of submitted documents evaluation and licensee application for license renewal the license for next 10 years operation has been issued for Bohunice NPP. At present, similar procedure for Mochovce NPP unit 1 and 2 is underway.(author).

Safety evaluation review of the prototype license application safety analysis report

International Nuclear Information System (INIS)

1991-08-01

The US Nuclear Regulatory Commission (NRC) staff and consultants reviewed a Prototype License Application Safety Analysis Report (PLASAR) submitted by the US Department of Energy (DOE) for the belowground vault (BGV) alternative method of low-level radioactive waste disposal. In Volume 1 of NUREG-1375, the NRC staff provided the safety review results for an earth-mounded concrete bunker PLASAR. In the current report, the staff focused its review on the design, construction, and operational aspects of the BGV PLASAR. The staff developed review comments and questions using the Standard Review Plan (SRP), Rev. 1 (NUREG-1200) as the basis for evaluating the acceptability of the information provided in the BGV PLASAR. The detailed review comments provided in this report are intended to be useful guidance to facility developers and State regulators in addressing issues likely to be encountered in the review of a license application for a low-level-waste disposal facility. 44 refs

Code development incorporating environmental, safety, and economic aspects of fusion reactors (FY 92--94). Final report

International Nuclear Information System (INIS)

Ho, S.K.; Fowler, T.K.; Holdren, J.P.

1994-01-01

This is the Final Report for a three-year (FY 92--94) study of the Environmental, Safety, and Economic (ESE) aspects of fusion energy systems, emphasizing development of computerized approaches suitable for incorporation as modules in fusion system design codes. First, as is reported in Section 2, the authors now have operating a simplified but complete environment and safety evaluation code, BESAFE. The first tests of BESAFE as a module of the SUPERCODE, a design optimization systems code at LLNL, are reported in Section 3. Secondly, as reported in Section 4, the authors have maintained a strong effort in developing fast calculational schemes for activation inventory evaluation. In addition to these major accomplishments, considerable progress has been made on research on specific topics as follows. A tritium modeling code TRIDYN was developed in collaboration with the TSTA group at LANL and the Fusion Nuclear Technology group at UCLA. A simplified algorithm has been derived to calculate the transient temperature profiles in the blanket during accidents. The scheme solves iteratively a system of non-linear ordinary differential equations describing about 10 regions of the blanket by preserving energy balance. The authors have studied the physics and engineering aspects of divertor modeling for safety applications. Several modifications in the automation and characterization of environmental and safety indices have been made. They have applied this work to the environmental and safety comparisons of stainless steel with alternative structural materials for fusion reactors. A methodology in decision analysis utilizing influence and decision diagrams has been developed to model fusion reactor design problems. Most of the work during this funding period has been reported in 26 publications including theses, journal publications, conference papers, and technical reports, as listed in Section 11

Final safety analysis report (FSAR) for waste receiving and processing (WRAP) facility

International Nuclear Information System (INIS)

Weidert, J.R.

1997-01-01

This safety analysis report provides a summary description of the WRAP Facility, focusing on significant safety-related characteristics of the location and facility design. This report demonstrates that adherence to the safety basis wi11 ensure necessary operational safety considerations have been addressed sufficiently and justifies the adequacy of the safety basis in protecting the health and safety of the public, workers, and the environment

Research projects into the safety of nuclear power plants. Period covered: 01. July - 31. Dezember 2004. Progress report; Forschungsvorhaben auf dem Gebiet der Reaktorsicherheit. Berichtszeitraum: 01. Juli - 31. Dezember 2004. Fortschrittsbericht

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

National report of Brazil: nuclear safety convention - September 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The last chapter describes plans and future activities to further enhance the safety of nuclear installations in Brazil.

National report of Brazil: nuclear safety convention - September 1998

International Nuclear Information System (INIS)

1998-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The last chapter describes plans and future activities to further enhance the safety of nuclear installations in Brazil

Preliminary safety analysis report for the Waste Characterization Facility

International Nuclear Information System (INIS)

1994-10-01

This safety analysis report outlines the safety concerns associated with the Waste Characterization Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are to: define and document a safety basis for the Waste Characterization Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume. 142 refs., 38 figs., 39 tabs

Nuclear Reactor RA Safety Report, Format and Contents

International Nuclear Information System (INIS)

1986-11-01

This is a new complete version of the safety report of nuclear reactor RA is made according to the recommendations of the IAEA. Report includes all the relevant data needed for evaluation of safe operation of this nuclear facility. Each of seven volumes of this report cover separate topics as follows: (1) introduction; (2) Site characteristics; (3) description of the reactor building and installations; (4) description of the reactor; (5) description of the coolant system; (6) description of the regulation and safety instrumentation; (7) description of the power supply system; (8) description of the auxiliary systems; (9) radiation protection issues; (10) radioactive waste management (11) reactor operation; (12) accident analysis during previous operation; (13) analysis of possible accident causes; (14) safety analysis and preventive actions: (15) analysis of significant accidents; (16) analysis of maximum possible accident; (17) environmental impact analysis in case of accident [sr

Bowtie Risk Management methodology and Modern Nuclear Safety Reports

International Nuclear Information System (INIS)

Ilizastigui Pérez, F.

2016-01-01

The Safety Report (SR) plays a crucial role within the nuclear licensing regime as the principal means for demonstrating the adequacy of safety analysis for a nuclear facility to ensure that it can be constructed, operated, maintained, shut down, and decommissioned safely and in compliance with applicable laws and regulations. It serves as the basis for granting authorizations for the commencement of the main stages of the facility’s life cycle as well as decision-making processes related to safety. Historically, the majority of nuclear safety reports have operated under rather prescriptive regimes, with emphasis placed on demonstrations of the robustness of the facility’s design (design safety) against prescriptive technical requirements set by the regulatory body, and less attention paid to demonstrating the adequacy and effectiveness of Operator’s management system for managing risks to daily operation.

Report on nuclear and radiation safety in Slovenia in 1997

International Nuclear Information System (INIS)

1998-06-01

The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 1997. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. Contributions to the report were furthermore prepared by competent authorities in the field of nuclear safety: the Agency for Radwaste Management (ARAO), the Milan Copic Nuclear Training Centre, etc. The report contains 19 chapters.

Ignalina Safety Analysis Group's report for the year 1998

International Nuclear Information System (INIS)

Uspuras, E.; Augutis, J.; Bubelis, E.; Cesna, B.; Kaliatka, A.

1999-02-01

Results of Ignalina NPP Safety Analysis Group's research are presented. The main fields of group's activities in 1998 were following: safety analysis of reactor's cooling system, safety analysis of accident localization system, investigation of the problem graphite - fuel channel, reactor core modelling, assistance to the regulatory body VATESI in drafting regulations and reviewing safety reports presented by Ignalina NPP during the process of licensing of unit 1

Nuclear safety

International Nuclear Information System (INIS)

Tarride, Bruno

2015-10-01

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

Nuclear Safety Project. Annual report 1986

International Nuclear Information System (INIS)

1987-09-01

The annual report 1986 is a detailed description of work within the Nuclear Safety Project performed in 1986 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes individual research activities on dynamic loads and strains of reactor components under accident conditions, fuel behaviour under accident conditions, investigation and control of LWR core-meltdown accidents, improvement of fission product retention and reduction of radiation exposure, and on behaviour, impact and removal of released pollutants. (DG)

The Impact of a Patient Safety Program on Medical Error Reporting

Science.gov (United States)

2005-05-01

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

JET-ISX-B beryllium limiter experiment safety analysis report and operational safety requirements

International Nuclear Information System (INIS)

Edmonds, P.H.

1985-09-01

An experiment to evaluate the suitability of beryllium as a limiter material has been completed on the ISX-B tokamak. The experiment consisted of two phases: (1) the initial operation and characterization in the ISX experiment, and a period of continued operation to the specified surface fluence (10 22 atoms/cm 2 ) of hydrogen ions; and (2) the disassembly, decontamination, or disposal of the ISX facility. During these two phases of the project, the possibility existed for beryllium and/or beryllium oxide powder to be produced inside the vacuum vessel. Beryllium dust is a highly toxic material, and extensive precautions are required to prevent the release of the beryllium into the experimental work area and to prevent the contamination of personnel working on the device. Details of the health hazards associated with beryllium and the appropriate precautions are presented. Also described in appendixes to this report are the various operational safety requirements for the project

Research projects into the safety of nuclear power plants. Period cover 01. January - 30. June 2017. Progress report; Forschungsvorhaben auf dem Gebiet der Reaktorsicherheit. Berichtszeitraum 01. Januar - 30. Juni 2017. Fortschrittsbericht

Energy Technology Data Exchange (ETDEWEB)

NONE

2017-07-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fur Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/ Authority Support Division of GRS. The reports as of the year 2000 are available in the internet-based information system on results and data of reactor safety research (https://www.grs-fbw.de). The compilation of the reports is classified according to the topic areas of reactor safety research. The reports are arranged in sequence of their project numbers. Ilt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

HTGR safety research program. Progress report, April--June 1975

International Nuclear Information System (INIS)

Kirk, W.L.

1975-09-01

Progress in HTGR safety research is reported under the following headings: fission product technology; primary coolant impurities; structural investigation; safety instrumentation and control systems; phenomena modeling and systems analysis. (JWR)

Saclay transparency and nuclear safety report 2009

International Nuclear Information System (INIS)

2006-01-01

After a general presentation of the Saclay CEA Centre, this report presents the various safety arrangements in the different basic nuclear installations it possesses. These arrangements can be administrative, technical, or related to emergency situations or to inspections. It describes the organisation of radioprotection in the Saclay CEA Centre, indicates highlights for 2009, and gives results of dose measurements performed on the personnel. It reports significant events regarding nuclear safety and radioprotection in the various installations, gives and comments release measurements results and their impact on the environment (gaseous and liquid releases). It gives an overview of radioactive wastes stored in the different installations

26 CFR 301.6059-1 - Periodic report of actuary.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 18 2010-04-01 2010-04-01 false Periodic report of actuary. 301.6059-1 Section...-1 Periodic report of actuary. (a) In general. The actuarial report described in this section must be... funding deficiency (as defined in section 412(a)) to zero, (4) A statement by the enrolled actuary signing...

Health and Safety Research Division progress report, October 1, 1988--March 31, 1990

International Nuclear Information System (INIS)

1990-09-01

The Health and Safety Research Division (HASRD) of the Oak Ridge National Laboratory (ORNL) continues to maintain an outstanding program of basic and applied research displaying a high level of creativity and achievement as documented by awards, publications, professional service, and successful completion of variety of projects. Our focus is on human health and the scientific basis for measurement and assessment of health-related impacts of energy technologies. It is our custom to publish a division progress report every 18 months that summarizes our programmatic progress and other measures of achievement over the reporting period. Since it is not feasible to summarize in detail all of our work over the period covered by this report (October 1, 1988, to March 30, 1990), we intend this document to point the way to the expensive open literature that documents our findings. During the reporting period the Division continued to maintain strong programs in its traditional areas of R ampersand D, but also achieved noteworthy progress in other areas. Much of the Division's work on site characterization, development of new field instruments, compilation of data bases, and methodology development fits into this initiative. Other new work in tunneling microscopy in support of DOE's Human Genome Program and the comprehensive R ampersand D work related to surface-enhanced Raman spectroscopy have attained new and exciting results. These examples of our progress and numerous other activities are highlighted in this report

Health and Safety Research Division progress report, October 1, 1988--March 31, 1990

Energy Technology Data Exchange (ETDEWEB)

1990-09-01

The Health and Safety Research Division (HASRD) of the Oak Ridge National Laboratory (ORNL) continues to maintain an outstanding program of basic and applied research displaying a high level of creativity and achievement as documented by awards, publications, professional service, and successful completion of variety of projects. Our focus is on human health and the scientific basis for measurement and assessment of health-related impacts of energy technologies. It is our custom to publish a division progress report every 18 months that summarizes our programmatic progress and other measures of achievement over the reporting period. Since it is not feasible to summarize in detail all of our work over the period covered by this report (October 1, 1988, to March 30, 1990), we intend this document to point the way to the expensive open literature that documents our findings. During the reporting period the Division continued to maintain strong programs in its traditional areas of R D, but also achieved noteworthy progress in other areas. Much of the Division's work on site characterization, development of new field instruments, compilation of data bases, and methodology development fits into this initiative. Other new work in tunneling microscopy in support of DOE's Human Genome Program and the comprehensive R D work related to surface-enhanced Raman spectroscopy have attained new and exciting results. These examples of our progress and numerous other activities are highlighted in this report.

Guidance for identifying, reporting and tracking nuclear safety noncompliances

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

This document provides Department of Energy (DOE) contractors, subcontractors and suppliers with guidance in the effective use of DOE`s Price-Anderson nuclear safety Noncompliance Tracking System (NTS). Prompt contractor identification, reporting to DOE, and correction of nuclear safety noncompliances provides DOE with a basis to exercise enforcement discretion to mitigate civil penalties, and suspend the issuance of Notices of Violation for certain violations. Use of this reporting methodology is elective by contractors; however, this methodology is intended to reflect DOE`s philosophy on effective identification and reporting of nuclear safety noncompliances. To the extent that these expectations are met for particular noncompliances, DOE intends to appropriately exercise its enforcement discretion in considering whether, and to what extent, to undertake enforcement action.

Annual report 1988 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.; Urban, M.

1989-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1988 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig./HP) [de

Annual report 1991 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.

1992-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Annual report 1990 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.; Urban, M.

1991-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

NASA aviation safety reporting system

Science.gov (United States)

1981-01-01

Aviation safety reports that relate to loss of control in flight, problems that occur as a result of similar sounding alphanumerics, and pilot incapacitation are presented. Problems related to the go around maneuver in air carrier operations, and bulletins (and FAA responses to them) that pertain to air traffic control systems and procedures are included.

Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group [Russian Edition

International Nuclear Information System (INIS)

2015-01-01

This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

Can Patient Safety Incident Reports Be Used to Compare Hospital Safety? Results from a Quantitative Analysis of the English National Reporting and Learning System Data.

Science.gov (United States)

Howell, Ann-Marie; Burns, Elaine M; Bouras, George; Donaldson, Liam J; Athanasiou, Thanos; Darzi, Ara

2015-01-01

The National Reporting and Learning System (NRLS) collects reports about patient safety incidents in England. Government regulators use NRLS data to assess the safety of hospitals. This study aims to examine whether annual hospital incident reporting rates can be used as a surrogate indicator of individual hospital safety. Secondly assesses which hospital characteristics are correlated with high incident reporting rates and whether a high reporting hospital is safer than those lower reporting hospitals. Finally, it assesses which health-care professionals report more incidents of patient harm, which report more near miss incidents and what hospital factors encourage reporting. These findings may suggest methods for increasing the utility of reporting systems. This study used a mix methods approach for assessing NRLS data. The data were investigated using Pareto analysis and regression models to establish which patients are most vulnerable to reported harm. Hospital factors were correlated with institutional reporting rates over one year to examine what factors influenced reporting. Staff survey findings regarding hospital safety culture were correlated with reported rates of incidents causing harm; no harm and death to understand what barriers influence error disclosure. 5,879,954 incident reports were collected from acute hospitals over the decade. 70.3% of incidents produced no harm to the patient and 0.9% were judged by the reporter to have caused severe harm or death. Obstetrics and Gynaecology reported the most no harm events [OR 1.61(95%CI: 1.12 to 2.27), p<0.01] and pharmacy was the hospital location where most near-misses were captured [OR 3.03(95%CI: 2.04 to 4.55), p<0.01]. Clinicians were significantly more likely to report death than other staff [OR 3.04(95%CI: 2.43 to 3.80) p<0.01]. A higher ratio of clinicians to beds correlated with reduced rate of harm reported [RR = -1.78(95%Cl: -3.33 to -0.23), p = 0.03]. Litigation claims per bed were

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

International Nuclear Information System (INIS)

2014-01-01

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

Report on nuclear and radiation safety in Slovenia in 1999

International Nuclear Information System (INIS)

Lovincic, D.

2000-09-01

The Slovenian Nuclear Safety Administration (SNSA) has prepared Report on Nuclear and Radiation Safety in Slovenia in 1999. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia.

DOE Safety Metrics Indicator Program (SMIP) Fiscal Year 2000 Annual Report of Packaging- and Transportation-related Occurrences

International Nuclear Information System (INIS)

Dickerson, L.S.

2001-01-01

The U.S. Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS) is an interactive computer system designed to support DOE-owned or -operated facilities in reporting and processing information concerning occurrences related to facility operations. The Oak Ridge National Laboratory has been charged by the DOE National Transportation Program Albuquerque (NTPA) with the responsibility of retrieving reports and information pertaining to packaging and transportation (P and T) incidents from the centralized ORPS database. These selected reports are analyzed for safety concerns, trends, potential impact on P and T operations, and ''lessons learned'' in P and T safety. To support this analysis and trending, the Safety Metrics Indicator Program (SMIP) was established by the NTPA in fiscal year (FY) 1998. Its chief goal is to augment historical reporting of occurrence-based information by providing (1) management notification of those incidents that require attention, (2) an accurate picture of contractors' P and T-related performance, and (3) meaningful statistics on occurrences at particular sites, including comparisons among different contractor sites and between DOE and the private sector. This annual report contains information on those P and T-related occurrences reported to the ORPS during the period from October 1, 1999, through September 30, 2000. Only those incidents that occur in preparation for transport, during transport, and during unloading of hazardous material are considered as packaging- or transportation-related occurrences

Research projects into the safety of nuclear power plants. Period cover 01. July 2015 - 31. December 2015. Progress report; Forschungsvorhaben auf dem Gebiet der Reaktorsicherheit. Berichtszeitraum 01. Juli - 31. Dezember 2015. Fortschrittsbericht

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-07-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/ Authority Support Division of GRS. The reports as of the year 2000 are available in the internet-based information system on results and data of reactor safety research (https://www.grs-fbw.de). The compilation of the reports is classified according to general topics related to reactor safety research as well as to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

RB research reactor safety report; Izvestaj o sigurnsti istrazivackog reaktora RB

Energy Technology Data Exchange (ETDEWEB)

Sotic, O; Pesic, M; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

1979-04-15

This new version of the safety report is a revision of the safety report written in 1962 when the RB reactor started operation after reconstruction. The new safety report was needed because reactor systems and components have been improved and the administrative procedures were changed. the most important improvements and changes were concerned with the use of highly enriched fuel (80% enriched), construction of reactor converter outside the reactor vessel, improved control system by two measuring start-up channels, construction of system for heavy water leak detection, new inter phone connection between control room and other reactor rooms. This report includes description of reactor building with installations, rector vessel, reactor core, heavy water system, control system, safety system, dosimetry and alarm systems, experimental channels, neutron converter, reactor operation. Safety aspects contain analyses of accident reasons, method for preventing reactivity insertions, analyses of maximum hypothetical accidents for cores with natural uranium, 2% enriched and 80% enriched fuel elements. Influence of seismic events on the reactor safety and well as coupling between reactor and the converter are parts of this document.

Progress report - list of reports from BMFT, CEA, EPRI, JSTA and USNRC reactor safety research

International Nuclear Information System (INIS)

1982-10-01

This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

Reports about Occurrence of Events with Effect on Aviation Safety

Directory of Open Access Journals (Sweden)

Vladimír Plos

2014-07-01

Full Text Available This article deals with a system, that is established to report the events with effect on safety. This system is based on requirements published in Annex 13 to the Chicago Convention and legislative foundations laid down in Regulation L13, Regulation of the European Parliament and of the Council (EU No 376/2014, Decree No. 359/2006 Sb. and Act No. 49/1997 Sb. Standards and legislative rules precisely define the types of events that are subject of reporting and also define the structure and content of the reporting message. This content is consists mainly of the identification data about the airplane and crew, information about the route and a short description of the damage to the airplane. In the following, we discuss the possible use of such a system of mandatory reporting for the needs of safety indicators. Then there are proposals of changes in the content of the reporting message for the need of safety indicators. The present knowledge indicates that the use of all opportunities provided by the law for the reporting of events can lead to a creating of sufficient basis for safety indicators.

AEA Technology safety report 1990

International Nuclear Information System (INIS)

1991-12-01

AEA Technology is the trading name of the United Kingdom Atomic Energy Authority. Work in support of nuclear power at home and abroad continues to be an important part of our business but as nuclear power has matured AEA Technology has looked beyond its traditional role to other markets worldwide. We are a major commercial enterprise, with an annual turnover of Pound 450 million, selling a variety of technical services and products to customers worldwide. The scope of the business lies in the closely related fields of energy, environment and safety, targeted at both nuclear and non-nuclear markets. We also have a major role in providing innovative technology solutions to assist manufacturing industry. The 1990 report on safety within the Authority is presented here. (author)

AEA Technology safety report 1990

Energy Technology Data Exchange (ETDEWEB)

1991-12-01

AEA Technology is the trading name of the United Kingdom Atomic Energy Authority. Work in support of nuclear power at home and abroad continues to be an important part of our business but as nuclear power has matured AEA Technology has looked beyond its traditional role to other markets worldwide. We are a major commercial enterprise, with an annual turnover of Pound 450 million, selling a variety of technical services and products to customers worldwide. The scope of the business lies in the closely related fields of energy, environment and safety, targeted at both nuclear and non-nuclear markets. We also have a major role in providing innovative technology solutions to assist manufacturing industry. The 1990 report on safety within the Authority is presented here. (author).

Applied Health Physics and Safety annual report for 1975

International Nuclear Information System (INIS)

1976-08-01

This report describes and summarizes the activities of the applied sections and/or groups of the Health Physics Division. Projects and activities covered include personnel monitoring, environmental monitoring, radiation and safety surveys, and industrial safety

Annual report 1982 of the Central Safety Department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.; Koenig, L.A.

1983-04-01

The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project. The centers of interest of r + d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1982 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

The safety indicators program in Taiwan, China : a six-year trend

International Nuclear Information System (INIS)

Hsu, Mingte

1998-01-01

This paper presents data on the current operating status and the safety indicators (SI) of the six nuclear power units in Taiwan. Analysis of the data collected in a six-year period has been made to obtain trends for each safety indicator. An overview of the trends of the plant operational data during the same period are also provided and discussed. On the whole, the trends of safety indicators are improving during the observed period 1991-1996. The plant operational data have depicted coherent improvement with the safety indicator trends. This result supports the premise that improvements in safety performance and in operational reliability are correspondingly inter-dependent. Both the safety indicators quarterly report and the annual report are available to the public. The public can also approach this information from the AEC's World Wide Web site (http://www.aec.gov.tw). (author)

Fuel and canister process report for the safety assessment SR-Site

International Nuclear Information System (INIS)

Werme, Lars; Lilja, Christina

2010-12-01

This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Fuel and canister process report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

Werme, Lars; Lilja, Christina (eds.)

2010-12-15

This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

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

International Nuclear Information System (INIS)

Kliem, S.

2010-01-01

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

KfK Nuclear Safety Project. First semiannual report 1985

International Nuclear Information System (INIS)

1985-11-01

The semiannual progress report 1985/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1985 in the nuclear safety field by KfK institutes and departements and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics: work performed, results obtained and plans for future work. (orig./HP) [de

Nuclear Safety Research Department annual report 2000

International Nuclear Information System (INIS)

Majborn, B.; Damkjaer, A.; Nielsen, S.P.; Nonboel, E.

2001-08-01

The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. In addition the department was responsible for the tasks 'Applied Health Physics and Emergency Preparedness', 'Dosimetry', 'Environmental Monitoring', and Irradiation and Isotope Services'. Lists of publications, committee memberships and staff members are included. (au)

Safety analysis report for the Waste Storage Facility. Revision 2

Energy Technology Data Exchange (ETDEWEB)

Bengston, S.J.

1994-05-01

This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

Safety and Effectiveness of Natalizumab: First Report of Interim Results of Post-Marketing Surveillance in Japan.

Science.gov (United States)

Saida, Takahiko; Yokoyama, Kazumasa; Sato, Ryusuke; Makioka, Haruki; Iizuka, Yukihiko; Hase, Masakazu; Ling, Yan; Torii, Shinichi

2017-12-01

Natalizumab, a humanized anti-α4 integrin monoclonal antibody, received marketing approval in Japan in 2014 for the treatment of multiple sclerosis (MS). Because the previous large-scale clinical trials of natalizumab were mainly conducted in Europe and North American countries, and data in patients with MS from Japan were limited, we conducted an all-case post-marketing surveillance of natalizumab-treated MS patients from Japan to investigate the safety and effectiveness of natalizumab in a real-world clinical setting in Japan. Here, we report the results of an interim analysis. During the observation period of 2 years, all patients who were treated with natalizumab subsequent to its approval in Japan were followed. The effectiveness of natalizumab was assessed by examining the changes in expanded disability status scale (EDSS) score and annualized relapse rate (ARR) from baseline. Safety was assessed by analyzing the incidence of adverse drug reactions (ADRs). The safety analysis included 106 patients (mean age 39.3 years; women 62.3%) whose data were collected until the data lock point (February 7, 2016). The effectiveness analysis included 75 patients. The majority of patients had relapsing-remitting MS (93/106 patients; 87.7%). The mean length of treatment exposure in the present study was 6.6 months. During the 2-year observation period, no significant change in the EDSS was observed, while the ARR decreased significantly from baseline (72.9% reduction, p = 0.001). ADRs and serious ADRs were observed in 11.3% and 3.8% of patients, respectively; however, no new safety concerns were detected. No patient had progressive multifocal leukoencephalopathy (PML) during the present study period. The safety and effectiveness of natalizumab were confirmed in Japanese patients with MS in clinical practice. Nevertheless, potential risks including PML require continuous, careful observation. Biogen Japan Ltd (Tokyo, Japan).

MedWatch, the FDA Safety Information and Adverse Event Reporting Program

Science.gov (United States)

... Reporting Program MedWatch: The FDA Safety Information and Adverse Event Reporting Program Share Tweet Linkedin Pin it ... approved information that can help patients avoid serious adverse events. Potential Signals of Serious Risks/New Safety ...

HERBE final safety report; HERBE Finalni sigurnosni izvestaj

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-07-01

The Final safety report of HERBE system constructed at the RB reactor consists of 13 chapters, as follows. Chapter 0 includes a summary and the contents of the Final safety report, fundamental characteristics of the system and conclusion remarks, with the license agreement of the Safety Committee of the Boris Kidric Institute. Chapter 1 describes and analyzes the site of the HERBE system, including demography, topography, meteorology, hydrology, geology, seismicity, ecology. Chapter 3 covers technical characteristics of the system, Chapter 4 deals with safety analysis, Chapter 5 describes organisation of construction and preliminary operational testing of the system. Chapter 6 deals with organisation and program of test and regular operation, relevant procedures. Chapter 7 defines operational conditions and constraints, Chapter 8 and describe methods and means of radiation protection and radioactive materials management respectively. Chapter 10 contains a review of emergency plans, measures and procedures for nuclear accident protection. Chapters 11 and 12 are concerned with quality assurance program and physical protection of the HERBE system and related nuclear material.

Regulatory control of nuclear safety in Finland. Annual report 2008

International Nuclear Information System (INIS)

Kainulainen, E.

2009-06-01

This report covers the regulatory control of nuclear safety in 2008, including the design, construction and operation of nuclear facilities, as well as nuclear waste management and nuclear materials. The control of nuclear facilities and nuclear waste management, as well as nuclear non-proliferation, concern two STUK departments: Nuclear Reactor Regulation and Nuclear Waste and Material Regulation. It constitutes the report on regulatory control in the field of nuclear energy, which the Radiation and Nuclear Safety Authority (STUK) is required to submit to the Ministry of Employment and the Economy pursuant to section 121 of the Finnish Nuclear Energy Decree. The first parts of the report explain the basics of the nuclear safety regulation included as part of STUK's responsibilities, as well as the objectives of the operations, and briefly introduce the objects of regulation. The chapter concerning the development and implementation of legislation and regulations describes changes in nuclear legislation, as well as the progress of STUK's YVL Guide revision. The chapter also includes a summary of the application of the updated YVL Guides to nuclear facilities. The section concerning the regulation of nuclear facilities contains a complete safety assessment of the nuclear facilities currently in operation or under construction. For the nuclear facilities in operation, the section describes plant operation, events during operation, annual maintenance, development of the plants and their safety, and observations made during monitoring. Data and observations gained during regulatory activities are reviewed with a focus on ensuring the safety functions of nuclear facilities and the integrity of structures and components. The report also includes a description of the oversight of the operations and quality management of organisations, oversight of operational experience feedback activities, and the results of these oversight activities. The radiation safety of nuclear

Guidance for preparation of safety analysis reports for nonreactor facilities and operations

International Nuclear Information System (INIS)

1992-01-01

Department of Energy (DOE) Orders 5480.23, ''Nuclear Safety Analysis Reports,'' and 5481.1B, ''Safety Analysis and Review System'' require the preparation of appropriate safety analyses for each DOE operation and subsequent significant modifications including decommissioning, and independent review of each safety analysis. The purpose of this guide is to assist in the preparation and review of safety documentation for Oak Ridge Field Office (OR) nonreactor facilities and operation. Appendix A lists DOE Orders, NRC Regulatory Guides and other documents applicable to the preparation of safety analysis reports

1982 annual status report: reactor safety

International Nuclear Information System (INIS)

1982-01-01

This report presents the projects of the Reactor Safety Program at the JRC: 1) Reliability and risk evolution; 2) LWR loss of coolant accident studies; 3) Primary system integrity; 4) LMFBR core accident initiation and transition phase; and, 5) LMFBR accident post disassembly phase

Nuclear and radiation safety in Slovenia. Annual report 2000

International Nuclear Information System (INIS)

Lovincic, D.

2001-09-01

The Slovenian Nuclear Safety Administration (SNSA), in co-operation with the Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiation Safety in the Republic of Slovenia for 2000. This is one of the regular forms of reporting on the work of the Administration to the Government and National Assembly of the Republic of Slovenia. (author)

Monitoring product safety in the postmarketing environment.

Science.gov (United States)

Sharrar, Robert G; Dieck, Gretchen S

2013-10-01

The safety profile of a medicinal product may change in the postmarketing environment. Safety issues not identified in clinical development may be seen and need to be evaluated. Methods of evaluating spontaneous adverse experience reports and identifying new safety risks include a review of individual reports, a review of a frequency distribution of a list of the adverse experiences, the development and analysis of a case series, and various ways of examining the database for signals of disproportionality, which may suggest a possible association. Regulatory agencies monitor product safety through a variety of mechanisms including signal detection of the adverse experience safety reports in databases and by requiring and monitoring risk management plans, periodic safety update reports and postauthorization safety studies. The United States Food and Drug Administration is working with public, academic and private entities to develop methods for using large electronic databases to actively monitor product safety. Important identified risks will have to be evaluated through observational studies and registries.

Safety-related LWR research. Annual report 1989

International Nuclear Information System (INIS)

1990-11-01

The main topics in this annual report 1989 are phenomena of heavy fuel damage and single aspects of a core meltdown accident. The examined single aspects refer to aerosol behavior and filter engineering and to methods for assessment and minimization of the radiological consequences of reactor accidents. Different contributions to selected, safety-related problems of an advanced pressurized-water reactor complete the topic spectrum. The annual report 1989 describes the progress of the research work wich was carried out in the area of safety research by institutes and departments of the KfK, and on behalf of the KfK by external institutions. The individual contributions represent the status of work at the end of the year under review, 1989. (orig./HP) [de

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

International Nuclear Information System (INIS)

2011-01-01

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

12 CFR 563g.18 - Current and periodic reports.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Current and periodic reports. 563g.18 Section 563g.18 Banks and Banking OFFICE OF THRIFT SUPERVISION, DEPARTMENT OF THE TREASURY SECURITIES OFFERINGS § 563g.18 Current and periodic reports. (a) Each savings association which files an offering circular...

Survey of reportable incidents in nuclear power plant in the Federal Republic of Germany. Period covered: 4th quarter 1992

International Nuclear Information System (INIS)

1993-01-01

There was no radioactivity release exceeding the limits set by law, and there was no hazard to man or the environment in the period under review. 58 events reported belonged to the lowest reporting category, N (normal notification), one event to category E (immediate notification, and there was none belonging to category S (emergency) notification. According to the INES evaluation scale, 56 events belonged to category 0, (no safety or radiological impact), and there were 3 events of INES scale 1 (malfunction). (orig./HP) [de

Research projects into the safety of nuclear power plants. Period cover 01. January 2014 - 30. June 2014. Progress report; Forschungsvorhaben auf dem Gebiet der Reaktorsicherheit. Berichtszeitraum 01. Januar 2014 - 30. Juni 2014. Fortschrittsbericht

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi), formerly Federal Ministry of Economics and Technology, sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/ Authority Support Division of GRS. The reports as of the 1st half-year 2000 are available in the internet-based information system on results and data of reactor safety research (https://www.grs-fbw.de). The compilation of the reports is classified according to general topics related to reactor safety research as well as to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

Storm water monitoring report for the 1995 reporting period

International Nuclear Information System (INIS)

Braun, D.R.; Brock, T.A.

1995-10-01

This report includes sampling results and other relevant information gathered in the past year by LITCO's Environmental Monitoring and Water Resources Unit. This report presents analytical data collected from storm water discharges as a part of the Environmental Monitoring Storm Water Monitoring Program for 1994--1995 for facilities located on the Idaho National Engineering Laboratory (INEL). The 1995 reporting period is October 1, 1994 through September 30, 1995. The storm water monitoring program tracks information about types and amounts of pollutants present. Data are required for the Environmental Protection Agency and are transmitted via Discharge Monitoring Reports. Additional information resulting from the program contributes to Best Management Practice to control pollution in runoff as well as Storm Water Pollution Prevention Plans

Data report for the safety assessment SR-Site

International Nuclear Information System (INIS)

2010-12-01

This report compiles, documents, and qualifies input data identified as essential for the long-term safety assessment of a KBS-3 repository, and forms an important part of the reporting of the safety assessment project SR-Site. The input data concern the repository system, broadly defined as the deposited spent nuclear fuel, the engineered barriers surrounding it, the host rock, and the biosphere in the proximity of the repository. The input data also concern external influences acting on the system, in terms of climate related data. Data are provided for a selection of relevant conditions and are qualified through traceable standardised procedures

Data report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

2010-12-15

This report compiles, documents, and qualifies input data identified as essential for the long-term safety assessment of a KBS-3 repository, and forms an important part of the reporting of the safety assessment project SR-Site. The input data concern the repository system, broadly defined as the deposited spent nuclear fuel, the engineered barriers surrounding it, the host rock, and the biosphere in the proximity of the repository. The input data also concern external influences acting on the system, in terms of climate related data. Data are provided for a selection of relevant conditions and are qualified through traceable standardised procedures

Progress report on safety research on radioactive waste management for the period April 1996 to March 1998

International Nuclear Information System (INIS)

Ohnuki, Toshihiko; Muraoka, Susumu; Banba, Tsunetaka

1998-10-01

This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research, JAERI during the fiscal year of 1996 and 1997 (April 1, 1996 - March 31, 1998). The topics are as follows: (1) In the research and development of waste forms and engineered barrier, studies on development of ceramic waste forms, the leaching behaviors from glass waste at reduced condition and sorption behaviors on backfill materials have been carried out. (2) In studies on shallow land disposal, studies on the migration behaviors of radionuclides in the presence of humic acid have been carried out. (3) In the studies on geological disposal, the studies on diffusivity in rock formation, in-situ migration and diffusion experiments, sorption mechanism, fixation mechanism, natural analogue study and geochronology have been carried out. (author)

Project Guarantee 1985. Final repository for low- and intermediate level radioactive wastes: Safety report

International Nuclear Information System (INIS)

Anon.

1985-01-01

Storage of radioactive waste must delay the return of radionuclides to the biosphere for a long period of time and must maintain the release rates at a sufficiently low level for all time. This is achieved with the aid of a series of safety barriers which consist, on the one hand, of technical barriers in the repository and, on the other hand , of natural geological barriers as they occur at the repository location. In order to assess the efficiency of the barriers, the working methods of the technical barriers and the host rock must be understood. This understanding is transferred into quantitative models in order to calculate the safety of the repository. The individual barriers and the methods used to modelling their functions were described in volume NGB 85-07 of the Project Guarantee 1985 report series and the data necessary for modelling were given. The models and data are used in the safety analysis, the results of which are contained in the present report. Safety considerations show that models are available in Switzerland which allow, in principle, an assessment of the long-term behaviour of a repository for low- and intermediate-level waste. The evaluation of earlier studies and experimental work, suitable laboratory measurements and results from field research enable compilation of a representative data-set so that the requirements for quantitative statements on safety of final disposal are met from this side also. The safety calculations show that the radiation doses calculated for a base case scenario with realistic/conservative parameter values are negligibly low. Also, radiation doses which are clearly under the protection standard of 10 mrem per year result for conservative values and the cumulation of several conservative assumptions. Even assuming exposure of the repository by erosion, a radiotoxicity of the soil formed results which is under natural values

Sizewell 'B' PWR pre-construction safety report

International Nuclear Information System (INIS)

1982-04-01

The Pre-Construction Safety Report (PCSR) for a PWR power station to be constructed as Sizewell 'B' is presented in 13 volumes containing 16 chapters. The PCSR has been submitted to the Nuclear Installations Inspectorate in support of the Central Electricity Generating Board's application for consent to the extension at Sizewell. It describes the design and provides the safety case for the proposed station, which comprises a 4-loop pressurized water reactor with associated generating plant and supporting auxiliary equipment. A general description of the station and its site is given. The strategy for ensuring nuclear safety is set out and the general design aspects of systems and plant outlined. The plant and systems, including their safety design bases and the fault analyses carried out for the design are described. Finally the way in which the plant will be decommissioned at the end of its useful life is outlined. (U.K.)

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

International Nuclear Information System (INIS)

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

1997-05-01

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

Shutdown Safety in NEK

International Nuclear Information System (INIS)

Gluhak, Mario; Senegovic, Marko

2014-01-01

Industry performance analysis since 2004 has revealed that 23% of the events reported to WANO occurred during outage periods. Given the fact that a plant is in the outage only 5 percent of the time, this emphasizes the importance of shutdown safety and measures station staffs undertake to maintain effective barriers to safety margins during the outage. Back in 1990s, the industry adopted guidance to meet safety requirements by focusing on safety functions. Both WANO and INPO released various documents, reports and guidelines to help accomplish those requirements. However, in the last decade inadequate 'defence in depth' has led to several events affecting shutdown safety and challenging one of the most important nuclear safety principles: 'The special characteristics of nuclear technology are taken into account in all decisions and actions. Reactivity control, continuity of core cooling, and integrity of fission product barriers are valued as essential, distinguishing attributes of nuclear station work environment'. NEK has recognized the importance of 'defence in depth'Industry performance analysis since 2004 has revealed that 23% of the events reported to WANO occurred during outage periods. Given the fact that a plant is in the outage only 5 percent of the time, this emphasizes the importance of shutdown safety and measures station staffs undertake to maintain effective barriers to safety margins during the outage. Back in 1990s, the industry adopted guidance to meet safety requirements by focusing on safety functions. Both WANO and INPO released various documents, reports and guidelines to help accomplish those requirements. However, in the last decade inadequate 'defence in depth' has led to several events affecting shutdown safety and challenging one of the most important nuclear safety principles: 'The special characteristics of nuclear technology are taken into account in all decisions and actions. Reactivity

Complementary safety assessments - Report by the French Nuclear Safety Authority

International Nuclear Information System (INIS)

2011-12-01

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

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

Science.gov (United States)

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

2009-02-01

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

Preliminary Safety Analysis Report for the Tokamak Physics Experiment

International Nuclear Information System (INIS)

Motloch, C.G.; Bonney, R.F.; Levine, J.D.; Masson, L.S.; Commander, J.C.

1995-04-01

This Preliminary Safety Analysis Report (PSAR), includes an indication of the magnitude of facility hazards, complexity of facility operations, and the stage of the facility life-cycle. It presents the results of safety analyses, safety assurance programs, identified vulnerabilities, compensatory measures, and, in general, the rationale describing why the Tokamak Physics Experiment (TPX) can be safely operated. It discusses application of the graded approach to the TPX safety analysis, including the basis for using Department of Energy (DOE) Order 5480.23 and DOE-STD-3009-94 in the development of the PSAR

Standard model for the safety analysis report of nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

1980-02-01

This norm establishes the Standard Model for the Safety Analysis Report of Nuclear Fuel Reprocessing Plants, comprehending the presentation format, the detailing level of the minimum information required by the CNEN for evaluation the requests of Construction License or Operation Authorization, in accordance with the legislation in force. This regulation applies to the following basic reports: Preliminary Safety Analysis Report - PSAR, integrating part of the requirement of Construction License; and Final Safety Analysis Report (FSAR) which is the integrating part of the requirement for Operation Authorization

Progress report - reports on reactor safety research programs sponsored by the Federal Ministry for Research and Technology

International Nuclear Information System (INIS)

1982-09-01

Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the GRS, within the framework of general information of progress in reactor safety research. The individual reports are classified according to the research program on the safety of LWRs 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the nuclear safety index of the CEC and the OECD. The reports are arranged in the sequence of their project numbers. (orig./HP) [de