Safety review advisor

International Nuclear Information System (INIS)

Boshers, J.A.; Alguindigue, I.E.; Uhrig, R.E.

1989-01-01

The University of Tennessee's Nuclear Engineering Department, in cooperation with the Tennessee Valley Authority (TVA), is evaluating the feasibility of utilizing an expert system to aid in 10CFR50.59 evaluations. This paper discusses the history of 10CFR50.59 reviews, and details the development approach used in the construction of a prototype Safety Review Advisor (SRA). The goals for this expert system prototype are to (1) aid the engineer in the evaluation process by directing his attention to the appropriate critical issues, (2) increase the efficiency, consistency, and thoroughness of the evaluation process, and (3) provide a foundation of appropriate Safety Analysis Report (SAR) references for the reviewer. 6 refs., 2 figs

ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

Reviewing industrial safety in nuclear power plants

International Nuclear Information System (INIS)

1990-02-01

This document contains guidance and reference materials for Operational Safety Review Team (OSART) experts, in addition to the OSART Guidelines (TECDOC-449), for use in the review of industrial safety activities at nuclear power plants. It sets out objectives for an excellent industrial safety programme, and suggests investigations which should be made in evaluating industrial safety programmes. The attributes of an excellent industrial safety programme are listed as examples for comparison. Practical hints for reviewing industrial safety are discussed, so that the necessary information can be obtained effectively through a review of documents and records, discussions with counterparts, and field observations. There are several annexes. These deal with major features of industrial safety programmes such as safety committees, reporting and investigation systems and first aid and medical facilities. They include some examples which are considered commendable. The document should be taken into account not only when reviewing management, organization and administration but also in the review of related areas, such as maintenance and operations, so that all aspects of industrial safety in an operating nuclear power plant are covered

Development of web-based safety review advisory system

International Nuclear Information System (INIS)

Kim, M. W.; Lee, H. C.; Park, S. O.; Lee, K. H.; Hur, K. Y.; Lee, S. J.; Choi, S. S.; Kang, C. M.

2002-01-01

For the development of an expert system supporting the safety review of nuclear power plants, the application was implemented after gathering necessary theoretical background and practical requirements. The general and the detail functional specifications were established, and they are investigated by KINS (Korea Institute of Nuclear Safety). The Safety Review Advisory System(SRAS), this application on web-server environment was developed according to the above specifications. Reviews can do their safety reviewing regardless of their speciality or reviewing experiences because SRAS is operated by the safety review plans which are converted to standardized format. When the safety reviewing is carried out by using SRAS, the results of safety reviewing are accumulated in the database and may be utilized later usefully, and we can grasp safety reviewing progress. Users of SRAS are categorized into four groups, administrator, project manager, project reviewer and general reviewer. Each user group is delegated appropriate access capability. The function and some screen shots of SRAS are described

Development of web-based safety review advisory system

International Nuclear Information System (INIS)

Kim, M. W.; Hur, K. Y.; Lee, S. J.; Choi, S. J.

2002-01-01

For the development of an expert system supporting the safety review of nuclear power plants, the application was implemented after gathering necessary theoretical background and practical requirements. The general and the detail functional specifications were established, and they are investigated by KINS. Safety Review Advisory System (SRAS), this application on web-server environment was developed according to the above specifications. Reviews can do their safety reviewing regardless of their speciality or reviewing experiences because SRAS is operated by the safety review plans which are converted to standardized format. When the safety reviewing is carried out by using SRAS, the results of safety reviewing are accumulated in the database and may be utilized later usefully, and we can grasp safety reviewing progress. Users of SRAS are categorized into four groups, administrator, project manager, project reviewer and general reviewer. Each user group is delegated appropriate access capability. The function and some screen shots of SRAS are described

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)

Ongoing and planned fuel safety research in NEA member states - Compiled from SEGFSM Members' Contributions

International Nuclear Information System (INIS)

2002-10-01

This report is in response to an action placed on SEGFSM members to compile ongoing and planned fuel safety research in NEA member states with the aim of providing CSNI an overview on related R and D international programmes and projects, along with the identification of current and future needs and priorities. A questionnaire was distributed to SEGFSM members on 18 October 2000, requesting them to identify fuel safety research programmes and to provide information on achievements and future plans. The questionnaire required respondents to provide information on the ongoing R and D programmes under the following headings: Title; Research Laboratory/Sponsor(s); Objectives/Goals; Status of Work; Brief description/presentation of the main results achieved; Future plans; References. Replies were received from organizations in the following countries: Belgium, Canada, Czech Republic, France, Germany, Hungary, Japan, Korea, Norway (Halden Reactor Project), Sweden, Switzerland, United Kingdom, USA. The report is based on the information provided in the replies received, as a consequence it cannot be viewed as comprehensive; programmes may well be in progress in addition to those detailed here. It is also possible that the detailed results of some programmes may remain proprietary and therefore not available in the short term. The report is organized in topic sections relating to: fuel and clad studies, integral fuel rod tests and PIE, LOCA and RIA studies including whole rods and bundles as well as single effects studies of fuel and cladding, code development for both steady state and transient fuel behaviour, thermal hydraulics, reactor physics codes and finally severe accident studies. The main issues for the current generation of reactors are those of high burn-up performance in normal operations, LOCA and RIA conditions and the main goal for the industry is to consolidate the safety issues to bring all countries up to a licensed discharge burn-up of ∼60 MWd/kg in

Ongoing development of digital radiotherapy plan review tools

International Nuclear Information System (INIS)

Ebert, M.A.; Hatton, J.; Cornes, D.

2011-01-01

Full text: To describe ongoing development of software to support the review of radiotherapy treatment planning system (TPS) data. The 'SWAN' software program was conceived in 2000 and initially developed for the RADAR (TROG 03.04) prostate radiotherapy trial. Validation of the SWAN program has been occurring via implementation by TROG in support of multiple clinical trials. Development has continued and the SWAN software program is now supported by modular components which comprise the 'SW AN system'. This provides a comprehensive set of tools for the review, analysis and archive of TPS exports. The SWAN system has now been used in support of over 20 radiotherapy trials and to review the plans of over 2,000 trial participants. The use of the system for the RADAR trial is now culminating in the derivation of dose-outcomes indices for prostate treatment toxicity. Newly developed SWAN tools include enhanced remote data archive/retrieval, display of dose in both relative and absolute modes, and interfacing to a Matlab-based add-on ('VAST') that allows quantitative analysis of delineated volumes including regional overlap statistics for multi-observer studies. Efforts are continuing to develop the SWAN system in the context of international collaboration aimed at harmonising the quality-assurance activities of collaborative trials groups. Tools such as the SWAN system are essential for ensuring the collection of accurate and reliable evidence to guide future radiotherapy treatments. One of the principal challenges of developing such a tool is establishing a development path that will ensure its validity and applicability well into the future.

Nuclear safety review for the year 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-08-01

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

Nuclear safety review for the year 2002

International Nuclear Information System (INIS)

2003-08-01

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

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)

Nuclear Safety Review for the Year 2003

International Nuclear Information System (INIS)

2004-08-01

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

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)

Krsko NPP Periodic Safety Review program

International Nuclear Information System (INIS)

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

2001-01-01

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

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)

Lift truck safety review

Energy Technology Data Exchange (ETDEWEB)

Cadwallader, L.C.

1997-03-01

This report presents safety information about powered industrial trucks. The basic lift truck, the counterbalanced sit down rider truck, is the primary focus of the report. Lift truck engineering is briefly described, then a hazard analysis is performed on the lift truck. Case histories and accident statistics are also given. Rules and regulations about lift trucks, such as the US Occupational Safety an Health Administration laws and the Underwriter`s Laboratories standards, are discussed. Safety issues with lift trucks are reviewed, and lift truck safety and reliability are discussed. Some quantitative reliability values are given.

Lift truck safety review

International Nuclear Information System (INIS)

Cadwallader, L.C.

1997-03-01

This report presents safety information about powered industrial trucks. The basic lift truck, the counterbalanced sit down rider truck, is the primary focus of the report. Lift truck engineering is briefly described, then a hazard analysis is performed on the lift truck. Case histories and accident statistics are also given. Rules and regulations about lift trucks, such as the US Occupational Safety an Health Administration laws and the Underwriter's Laboratories standards, are discussed. Safety issues with lift trucks are reviewed, and lift truck safety and reliability are discussed. Some quantitative reliability values are given

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)

49 CFR 659.27 - Internal safety and security reviews.

Science.gov (United States)

2010-10-01

... 49 Transportation 7 2010-10-01 2010-10-01 false Internal safety and security reviews. 659.27... State Oversight Agency § 659.27 Internal safety and security reviews. (a) The oversight agency shall... safety and security reviews in its system safety program plan. (b) The internal safety and security...

Development of Safety Review Guidance for Research and Training Reactors

International Nuclear Information System (INIS)

Oh, Kju-Myeng; Shin, Dae-Soo; Ahn, Sang-Kyu; Lee, Hoon-Joo

2007-01-01

The KINS already issued the safety review guidance for pressurized LWRs. But the safety review guidance for research and training reactors were not developed. So, the technical standard including safety review guidance for domestic research and training reactors has been applied mutates mutandis to those of nuclear power plants. It is often difficult for the staff to effectively perform the safety review of applications for the permit by the licensee, based on peculiar safety review guidance. The NRC and NSC provide the safety review guidance for test and research reactors and European countries refer to IAEA safety requirements and guides. The safety review guide (SRG) of research and training reactors was developed considering descriptions of the NUREG- 1537 Part 2, previous experiences of safety review and domestic regulations for related facilities. This study provided the safety review guidance for research and training reactors and surveyed the difference of major acceptance criteria or characteristics between the SRG of pressurized light water reactor and research and training reactors

Development of safety review advisory system for nuclear power plants

International Nuclear Information System (INIS)

Kim, M. W.; Lee, H. C.; Park, S. O.; Park, W. J.; Lee, J. I.; Hur, K. Y.; Choi, S. S.; Lee, S. J.; Kang, C. M.

2001-01-01

For the development of an expert system supporting the safety review of nuclear power plants, the application program was implemented after gathering necessary theoretical background and practical requirements. The general and the detail functional specifications were established, and they were investigated by the safety review experts at KINS. Safety Review Advisory System (SRAS), the windows application on client-server environment was developed according to the above specifications. Reviewers can do their safety reviewing regardless of speciality or reviewing experiences because SRAS is operated by the safety review plans which are converted to standardized format. When the safety reviewing is carried out by using SRAS, the results of safety reviewing are accumulated in the database and may be utilized later usefully, and we can grasp safety reviewing progress. Users of SRAS are categorized into three groups, administrator, project manager, and reviewer. Each user group has appropriate access capability. The function and some screen shots of SRAS are described in this paper

Conducting organizational safety reviews - requirements, methods and experience

International Nuclear Information System (INIS)

Reiman, T.; Oedewald, P.; Wahlstroem, B.; Rollenhagen, C.; Kahlbom, U.

2008-03-01

Organizational safety reviews are part of the safety management process of power plants. They are typically performed after major reorganizations, significant incidents or according to specified review programs. Organizational reviews can also be a part of a benchmarking between organizations that aims to improve work practices. Thus, they are important instruments in proactive safety management and safety culture. Most methods that have been used for organizational reviews are based more on practical considerations than a sound scientific theory of how various organizational or technical issues influence safety. Review practices and methods also vary considerably. The objective of this research is to promote understanding on approaches used in organizational safety reviews as well as to initiate discussion on criteria and methods of organizational assessment. The research identified a set of issues that need to be taken into account when planning and conducting organizational safety reviews. Examples of the issues are definition of appropriate criteria for evaluation, the expertise needed in the assessment and the organizational motivation for conducting the assessment. The study indicates that organizational safety assessments involve plenty of issues and situations where choices have to be made regarding what is considered valid information and a balance has to be struck between focus on various organizational phenomena. It is very important that these choices are based on a sound theoretical framework and that these choices can later be evaluated together with the assessment findings. The research concludes that at its best, the organizational safety reviews can be utilised as a source of information concerning the changing vulnerabilities and the actual safety performance of the organization. In order to do this, certain basic organizational phenomena and assessment issues have to be acknowledged and considered. The research concludes with recommendations on

Conducting organizational safety reviews - requirements, methods and experience

Energy Technology Data Exchange (ETDEWEB)

Reiman, T.; Oedewald, P.; Wahlstroem, B. [Technical Research Centre of Finland, VTT (Finland); Rollenhagen, C. [Royal Institute of Technology, KTH, (Sweden); Kahlbom, U. [RiskPilot (Sweden)

2008-03-15

Organizational safety reviews are part of the safety management process of power plants. They are typically performed after major reorganizations, significant incidents or according to specified review programs. Organizational reviews can also be a part of a benchmarking between organizations that aims to improve work practices. Thus, they are important instruments in proactive safety management and safety culture. Most methods that have been used for organizational reviews are based more on practical considerations than a sound scientific theory of how various organizational or technical issues influence safety. Review practices and methods also vary considerably. The objective of this research is to promote understanding on approaches used in organizational safety reviews as well as to initiate discussion on criteria and methods of organizational assessment. The research identified a set of issues that need to be taken into account when planning and conducting organizational safety reviews. Examples of the issues are definition of appropriate criteria for evaluation, the expertise needed in the assessment and the organizational motivation for conducting the assessment. The study indicates that organizational safety assessments involve plenty of issues and situations where choices have to be made regarding what is considered valid information and a balance has to be struck between focus on various organizational phenomena. It is very important that these choices are based on a sound theoretical framework and that these choices can later be evaluated together with the assessment findings. The research concludes that at its best, the organizational safety reviews can be utilised as a source of information concerning the changing vulnerabilities and the actual safety performance of the organization. In order to do this, certain basic organizational phenomena and assessment issues have to be acknowledged and considered. The research concludes with recommendations on

International Expert Review of Sr-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can

International Nuclear Information System (INIS)

Sagar, Budhi; Egan, Michael; Roehlig, Klaus-Juergen; Chapman, Neil; Wilmot, Roger

2008-03-01

recognising that a long-term safety case needs to provide a broad, integrated view of the various issues that will support the further refinement and development of confidence in post-closure safety performance for the repository (IAEA, 2006; NEA, 2004). Although the focus of the evaluation presented here was on the methodology for safety assessment, it is evident from the review team's terms of reference (not least the reference to SKB's 'strategy for safety demonstration') that SKI's and SSI's interests extend beyond the structure and composition of the assessment itself. By itself, safety assessment is but one thread of the wider strategy for building confidence in implementation of KBS-3 for deep disposal, which also includes ongoing R and D, engineering demonstration, monitoring and inspection, management systems, etc. It is the linkage between such issues and the safety assessment in relation to building an integrated safety case that is perhaps one of the weaker aspects of SR-Can. This underlines the importance of framing the assessment itself, its inputs and outputs, within the wider context of what will be required to support the licence application. In view of the above, and the fact that SKB has acknowledged that some further development work remains to be done, the SAM review team believes that it remains a challenge for SKB to conduct and present a safety case of suitable quality within the currently proposed timescale for delivery of the SR-Can assessment and the 2009 licence application

Nuclear Safety Review for 2015

International Nuclear Information System (INIS)

2015-06-01

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

Internal safety review team at Comanche Peak SES

Energy Technology Data Exchange (ETDEWEB)

Davis, D [Comanche Peak Steam Electric Staion, Texas Utilities, TX (United States)

1997-09-01

The presentations describes the following issues: levels of defense in depth; internal safety review organizations; methods used to perform safety assessment; safety committee review; quality verification; root cause analysis; human performance program; industry operating experience.

Safety Review Services, Site Review Services and IRRS

International Nuclear Information System (INIS)

Yllera, Javier

2010-01-01

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

Striking balance between expedited review and expecting efficacious anticancer drug and biologics: An ongoing challenge

Directory of Open Access Journals (Sweden)

Krishnan Vengadaragava Chary

2017-01-01

Full Text Available Objective: The objective of this study is to assess the postmarketing status: Efficacy and safety drugs and biologics related with cancer approved under expedited review. Methods: This observational, analytical study was carried between January and April 2016 by the Department of Pharmacology and Medical Oncology, Saveetha Medical College. Drugs approved under expedited review, fast-track status and its association with anti-cancer effects, postmarketing efficacy and safety, propensity to induce the second tumor was noted. Drug approval status and average time of review process were obtained from the United States-Food and Drug Administration (FDA, Center for Drugs and Biologics Center (Center for Drug Evaluation and Research and Center for Biologics Evaluation and Research. Postmarketing adverse events and safety issues were collected FDA adverse effects reporting system. Further, evidence efficacy and safety of drugs were taken from various meta-analysis, reports on BioMed journals, and Cochrane systematic reviews. Results: In the last 5 years, 166 products were approved by expedited review. Out of 166, 48 (28.9% drugs/biologics are anticancer drugs and drugs used in precancerous conditions. The average time of review varies from19 months to 8.2 months. Out of these 48 molecules, 37 (77% molecules received serious adverse event alert. Positive correlation is seen between average time of review and number of adverse events reported. Seven (14.5% drugs were proven to induce second tumor among receivers. Conclusion: Although expedited review facilitates faster approval of drugs; selection and assessment criteria should be stringent to prevent clinical failure, serious adverse effects of such drugs exposed to many individuals. Focus should be given developing chemosensitizing molecule and evaluation of metronomic regimen which is being more optimistic in current cancer therapeutics.

Nuclear Safety Review for the Year 2012

International Nuclear Information System (INIS)

2012-07-01

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

Use of site specific data from Aespoe - preliminary results from the on-going safety analysis SR 97

International Nuclear Information System (INIS)

Stroem, A.; Selroos, J.O.; Andersson, Johan

1998-01-01

This paper discusses an on-going safety assessment study of SKB as well as the use of field data from Aespoe for obtaining input parameters for flow and radionuclide transport modelling in the geosphere. In the on-going Safety Assessment study SR 97, three individual sites in Sweden are used for exemplifying site specific conditions on overall repository performance. Thus, models capable of reproducing site specific characteristics are utilised. This is primarily obtained by implementing the geologic structural models in suitable conceptual models for groundwater flow on both regional and local scales. The models for flow incorporate observed and/or inferred water conducting features as well as other site-specific characteristics necessary for realistic descriptions of flow at the sites. The flow modelling thus aims at realism; the results obtained for present day conditions should not in any serious aspect conflict with observations at the site. Agreement between observed and modelled entities provides confidence in that a sound understanding of the site is obtained. Aespoe is one of the three sites providing site-specific conditions in SR 97. Transport is subsequently modelled using a stream tube approach where the 'travel times', for non-sorbing species, and discharge locations of a set of one-dimensional stream tubes are obtained from particle tracking in the flow model. The resulting distribution of 'travel times' in a single model realisation reflects the spatial variability and spatial extent of the repository, whereas the ensemble travel time distribution (over several realisations) for a given canister location reflects the uncertainty in travel time. The actual transport paths used in the transport modelling are thus dependent on site specific information such as e.g. existence of water conductive features. Other input parameters to the transport model are based on more generic and/or conservative arguments. However, the goal in a safety assessment

Nuclear safety review for 1984

International Nuclear Information System (INIS)

1985-08-01

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

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

Internet Safety and Security Surveys - A Review

DEFF Research Database (Denmark)

Sharp, Robin

This report gives a review of investigations into Internet safety and security over the last 10 years. The review covers a number of surveys of Internet usage, of Internet security in general, and of Internet users' awareness of issues related to safety and security. The focus and approach...... of the various surveys is considered, and is related to more general proposals for investigating the issues involved. A variety of proposals for how to improve levels of Internet safety and security are also described, and they are reviewed in the light of studies of motivational factors which affect the degree...

International Expert Review of Sr-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can

Energy Technology Data Exchange (ETDEWEB)

Sagar, Budhi (Center for Nuclear Waste Regulatory Analyses, Southwest Research Inst., San Antonio, TX (US)); Egan, Michael (Quintessa Limited, Henley-on-Thames (GB)); Roehlig, Klaus-Juergen (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (DE)); Chapman, Neil (Independent Consultant (XX)); Wilmot, Roger (Galson Sciences Limited, Oakham (GB))

2008-03-15

convincing overall safety case. In this context it is worth recognising that a long-term safety case needs to provide a broad, integrated view of the various issues that will support the further refinement and development of confidence in post-closure safety performance for the repository (IAEA, 2006; NEA, 2004). Although the focus of the evaluation presented here was on the methodology for safety assessment, it is evident from the review team's terms of reference (not least the reference to SKB's 'strategy for safety demonstration') that SKI's and SSI's interests extend beyond the structure and composition of the assessment itself. By itself, safety assessment is but one thread of the wider strategy for building confidence in implementation of KBS-3 for deep disposal, which also includes ongoing R and D, engineering demonstration, monitoring and inspection, management systems, etc.

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

Safety Review related to Commercial Grade Digital Equipment in Safety System

International Nuclear Information System (INIS)

Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

2013-01-01

The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

INSAG's ongoing work on nuclear, radiation and waste safety

International Nuclear Information System (INIS)

Baer, A.J.

1999-01-01

The International Nuclear Safety Advisory Group (INSAG) is an advisory group to the Director General of the IAEA. It identifies current nuclear safety issues, draws conclusions from its analyses and gives advice on those issues. INSAG is currently working on four documents: a complete revision of INSAG-3, the classical paper on safety principles for nuclear plants, published in 1988; 'Safety Management', the effective system for the management of operational strategy; 'Safe Management of the Life Cycle of Nuclear Power Plants'; and the fourth document in preparation entitled 'The Safe Management of Sources of Radiation: Principles and Strategies'. The fourth document is aimed primarily at political decision makers who have no knowledge of radiation safety or of nuclear matters generally but are called upon to make important decisions in this field. INSAG has attempted to present them with a 'unified doctrine' of the management of all radiation sources, even though, for historical reasons radiation protection and nuclear safety have evolved largely independently of each other. The major conclusion to be drawn from the paper is that a systematic application of protection and safety principles, and of appropriate strategies, goes a long way towards ensuring the safe management of technologies involving radiation. Furthermore, the management of sources of radiation could benefit from the experience accumulated in other industries facing comparable challenges

Nuclear Safety Review for 2014

International Nuclear Information System (INIS)

2014-07-01

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

Results of the 3rd Review Meeting of the Convention on Nuclear Safety and Preparatory Works for the 4th Meeting

International Nuclear Information System (INIS)

Choi, Young Sung; Choi, Kwang Sik; Kim, Woong Sik

2006-01-01

The 3 rd Review Meeting of the Convention on Nuclear Safety (CNS) took place from April 11-22, 2005. Fifty out of fifty-five Contracting Parties (CPs) participated with over 500 delegates in attendance. It was concluded that all CPs in attendance were in compliance with the requirements of the CNS. It was also noted that although the focus tends to be on the triennial national reports and review meetings, the CNS should emphasize an ongoing process that continually promotes the advancement of nuclear safety. With regard to this continuity process, the President of the 3 rd Review Meeting sent to all the CPs a message to remind of the lessons offered and learned from the Meeting and to put them into action as well. The president also asked that the CPs start in earnest later this year their preparations for the Forth Meeting in 2008. This paper introduces the results of the 3 rd Review Meeting and presents some suggestions on preparatory works that should be done for the next Review Meeting

Review of the Tritium Extraction Facility design

International Nuclear Information System (INIS)

Barton, R.W.; Bamdad, F.; Blackman, J.

2000-01-01

The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the US Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

Review of the Tritium Extraction Facility Design

International Nuclear Information System (INIS)

Ronald W. Barton; Farid Bamdad; Joel Blackman

2000-01-01

The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the U.S. Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

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)

Activity of safety review for the facilities using nuclear material (2). Safety review results and maintenance experiences for hot laboratories

International Nuclear Information System (INIS)

Amagai, Tomio; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Ohmori, Tsuyoshi

2009-01-01

In the site of O-arai Research and Development Center of Japan Atomic Energy Agency (JAEA), five hot laboratories for post-irradiation examination and development of plutonium fuels are operated more than 30 years. A safety review method for preventive maintenance on these hot laboratories includes test facilities and devices are established in 2003. After that, the safety review of these facilities and devices are done and taken the necessary maintenance based on the results in each year. In 2008, 372 test facilities and devices in these hot laboratories were checked and reviewed by this method. As a results of the safety review, repair issues of 38 facilities of above 372 facilities were resolved. This report shows the review results and maintenance experiences based on the results. (author)

Lessons learned from the Galileo and Ulysses flight safety review experience

International Nuclear Information System (INIS)

Bennett, Gary L.

1998-01-01

In preparation for the launches of the Galileo and Ulysses spacecraft, a very comprehensive aerospace nuclear safety program and flight safety review were conducted. A review of this work has highlighted a number of important lessons which should be considered in the safety analysis and review of future space nuclear systems. These lessons have been grouped into six general categories: (1) establishment of the purpose, objectives and scope of the safety process; (2) establishment of charters defining the roles of the various participants; (3) provision of adequate resources; (4) provision of timely peer-reviewed information to support the safety program; (5) establishment of general ground rules for the safety review; and (6) agreement on the kinds of information to be provided from the safety review process

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

Treatment of intracerebral haemorrhage with tranexamic acid – A review of current evidence and ongoing trials

DEFF Research Database (Denmark)

Law, Zhe Kang; Meretoja, Atte; Engelter, Stefan T

2017-01-01

Purpose Haematoma expansion is a devastating complication of intracerebral haemorrhage (ICH) with no established treatment. Tranexamic acid had been an effective haemostatic agent in reducing post-operative and traumatic bleeding. We review current evidence examining the efficacy of tranexamic acid...... in improving clinical outcome after ICH. Method We searched MEDLINE, EMBASE, CENTRAL and clinical trial registers for studies using search strategies incorporating the terms ‘intracerebral haemorrhage’, ‘tranexamic acid’ and ‘antifibrinolytic’. Authors of ongoing clinical trials were contacted for further...... details. Findings We screened 268 publications and retrieved 17 articles after screening. Unpublished information from three ongoing clinical trials was obtained. We found five completed studies. Of these, two randomised controlled trials (RCTs) comparing intravenous tranexamic acid to placebo (n = 54...

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

The transport safety programme

International Nuclear Information System (INIS)

Selling, H.A.

1994-01-01

The transport safety programme is one of the smaller technical sub-programmes in the Radiation Safety Section of the Division of Nuclear Safety, in terms of both regular budget and professional staff allocations. The overall aim of the programme is to promote the safe movement of radioactive material worldwide. The specific objectives are the development, review and maintenance of the Regulations for the Safe Transport of Radioactive Material, Safety Series No 6, and its supporting documents Safety Series Nos 7, 37 and 80 and the assistance to Member States and International Organizations in the proper implementation of the Regulations. One of the important issues that emerged during an ongoing Review/Revision process is the transport of Low-Specific Activity (LSA) material and Surface Contaminated Objects (SCO). Many of the radioactive waste materials fall in one of these categories. The subject has gained substance because it is expected that in the next decade radioactive waste could become available in so far unprecedented quantities and volumes due to decontamination and decommissioning of nuclear facilities. (author)

A literature review of safety culture.

Energy Technology Data Exchange (ETDEWEB)

Cole, Kerstan Suzanne; Stevens-Adams, Susan Marie; Wenner, Caren A.

2013-03-01

Workplace safety has been historically neglected by organizations in order to enhance profitability. Over the past 30 years, safety concerns and attention to safety have increased due to a series of disastrous events occurring across many different industries (e.g., Chernobyl, Upper Big-Branch Mine, Davis-Besse etc.). Many organizations have focused on promoting a healthy safety culture as a way to understand past incidents, and to prevent future disasters. There is an extensive academic literature devoted to safety culture, and the Department of Energy has also published a significant number of documents related to safety culture. The purpose of the current endeavor was to conduct a review of the safety culture literature in order to understand definitions, methodologies, models, and successful interventions for improving safety culture. After reviewing the literature, we observed four emerging themes. First, it was apparent that although safety culture is a valuable construct, it has some inherent weaknesses. For example, there is no common definition of safety culture and no standard way for assessing the construct. Second, it is apparent that researchers know how to measure particular components of safety culture, with specific focus on individual and organizational factors. Such existing methodologies can be leveraged for future assessments. Third, based on the published literature, the relationship between safety culture and performance is tenuous at best. There are few empirical studies that examine the relationship between safety culture and safety performance metrics. Further, most of these studies do not include a description of the implementation of interventions to improve safety culture, or do not measure the effect of these interventions on safety culture or performance. Fourth, safety culture is best viewed as a dynamic, multi-faceted overall system composed of individual, engineered and organizational models. By addressing all three components of

Safety review and approval process for the TFTR

International Nuclear Information System (INIS)

Levine, J.D.; Howe, H.J.; Howe, K.E.

1983-01-01

The design, construction, and operation of the Tokamak Fusion Test Reactor (TFTR) has undergone an extensive safety and enviromental analysis involving Princeton Plasma Physics Laboratory (PPPL), the U.S. Department of Energy (DOE), the Ebasco/Grumman Industrial Subcontractor Team, and other organizations. This analysis, which is continuing during the TFTR operational phase, has been facilitated by the preparation, review and approval of several documents, including an Environmental Statement (Draft and Final), a Preliminary Safety Analysis Report (PSAR), a Final Safety Analysis Report (FSAR), Operations Safety Requirements (OSRs) and Safety Requirements (SRs), and various Operating and Maintenance Manuals. Through TFTR Safety Group participation in formal system design evaluations, change control boards, and reviews of project procurement and installation documentation, the TFTR Management Configuration Control System assures that all aspects of the project, including proposed design, installation and operational changes, receive prompt and thorough safety analyses. These efforts will continue as the TFTR Program moves into the neutral beam and D-T operational phases. The safety review and approval experience that has been acquired on the TFTR Project should serve as a foundation for similar efforts on future fusion devices

Medication safety programs in primary care: a scoping review.

Science.gov (United States)

Khalil, Hanan; Shahid, Monica; Roughead, Libby

2017-10-01

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

An international nuclear safety regime

International Nuclear Information System (INIS)

Rosen, M.

1995-01-01

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

The Nordic program for nuclear safety 1990-1993

International Nuclear Information System (INIS)

1991-02-01

The status of ongoing projects under The Nordic Program for Nuclear Safety (NKS) 1990-1993, and the economy of the programme is presented. A review of projects, projects managers and coordinators, and a list of members of NKS and associated members is included. (CLS)

49 CFR 659.29 - Oversight agency safety and security reviews.

Science.gov (United States)

2010-10-01

... 49 Transportation 7 2010-10-01 2010-10-01 false Oversight agency safety and security reviews. 659... Role of the State Oversight Agency § 659.29 Oversight agency safety and security reviews. At least... safety program plan and system security plan. Alternatively, the on-site review may be conducted in an on...

Nuclear safety review for the year 1997

International Nuclear Information System (INIS)

1998-12-01

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

Operational safety review programmes for nuclear power plants. Guidelines for assessment

International Nuclear Information System (INIS)

2002-01-01

The IAEA has been offering the Operational Safety Review Team (OSART) programme to provide advice and assistance to Member States in enhancing the operational safety of nuclear power plants (NPPs). Simultaneously, the IAEA has encouraged self-assessment and review by Member States of their own nuclear power plants to continuously improve nuclear safety. Currently, some utilities have been implementing safety review programmes to independently review their own plants. Corporate or national operational safety review programmes may be compliance or performance based. Successful utilities have found that both techniques are necessary to provide assurance that (i) as a minimum the NPP meets specific corporate and legal requirements and (ii) management at the NPP is encouraged to pursue continuous improvement principles. These programmes can bring nuclear safety benefits to the plants and utilities. The IAEA has conducted two pilot missions to assess the effectiveness of the operational review programme. Based on these missions and on the experience gained during OSART missions, this document has been developed to provide guidance on and broaden national/corporate safety review programmes in Member States, and to assist in maximizing their benefits. These guidelines are intended primarily for the IAEA team to conduct assessment of a national/corporate safety review programme. However, this report may also be used by a country or utility to establish its own national/corporate safety review programme. The guidelines may likewise be used for self-assessment or for establishing a baseline when benchmarking other safety review programmes. This report consists of four parts. Section 2 addresses the planning and preparation of an IAEA assessment mission and Sections 3 and 4 deal with specific guidelines for conducting the assessment mission itself

Safety reviews of next-generation light-water reactors

International Nuclear Information System (INIS)

Kudrick, J.A.; Wilson, J.N.

1997-01-01

The Nuclear Regulatory Commission (NRC) is reviewing three applications for design certification under its new licensing process. The U.S. Advanced Boiling Water Reactor (ABWR) and System 80+ designs have received final design approvals. The AP600 design review is continuing. The goals of design certification are to achieve early resolution of safety issues and to provide a more stable and predictable licensing process. NRC also reviewed the Utility Requirements Document (URD) of the Electric Power Research Institute (EPRI) and determined that its guidance does not conflict with NRC requirements. This review led to the identification and resolution of many generic safety issues. The NRC determined that next-generation reactor designs should achieve a higher level of safety for selected technical and severe accident issues. Accordingly, NRC developed new review standards for these designs based on (1) operating experience, including the accident at Three Mile Island, Unit 2; (2) the results of probabilistic risk assessments of current and next-generation reactor designs; (3) early efforts on severe accident rulemaking; and (4) research conducted to address previously identified generic safety issues. The additional standards were used during the individual design reviews and the resolutions are documented in the design certification rules. 12 refs

The relation of ongoing brain activity, evoked neural responses, and cognition

Directory of Open Access Journals (Sweden)

Sepideh Sadaghiani

2010-06-01

Full Text Available Ongoing brain activity has been observed since the earliest neurophysiological recordings and is found over a wide range of temporal and spatial scales. It is characterized by remarkably large spontaneous modulations. Here, we review evidence for the functional role of these ongoing activity fluctuations and argue that they constitute an essential property of the neural architecture underlying cognition. The role of spontaneous activity fluctuations is probably best understood when considering both their spatiotemporal structure and their functional impact on cognition. We first briefly argue against a ‘segregationist’ view on ongoing activity, both in time and space, countering this view with an emphasis on integration within a hierarchical spatiotemporal organization of intrinsic activity. We then highlight the flexibility and context-sensitivity of intrinsic functional connectivity that suggest its involvement in functionally relevant information processing. This role in information processing is pursued by reviewing how ongoing brain activity interacts with afferent and efferent information exchange of the brain with its environment. We focus on the relationship between the variability of ongoing and evoked brain activity, and review recent reports that tie ongoing brain activity fluctuations to variability in human perception and behavior. Finally, these observations are discussed within the framework of the free-energy principle which – applied to human brain function - provides a theoretical account for a non-random, coordinated interaction of ongoing and evoked activity in perception and behaviour.

Improved tank car design development : ongoing studies on sandwich structures

Science.gov (United States)

2009-03-02

The Government and industry have a common interest in : improving the safety performance of railroad tank cars carrying : hazardous materials. Research is ongoing to develop strategies : to maintain the structural integrity of railroad tank cars carr...

On some aspects of nuclear safety surveillance and review

International Nuclear Information System (INIS)

Li Ganjie; Zhu Hong; Zhou Shanyuan

2004-01-01

Five aspects of the nuclear safety surveillance and review are discussed: Strict implementation of nuclear safety regulation, making the nuclear safety surveillance and review more normalization, procedurization, scientific decision-making; Strictly requiring the applicant to comply with the requirements of codes, do not allowing the utilization of mixing of codes; Properly controlling the strictness for the review on significant non-conformance; Strengthening the co-operation between regional offices and technical support units, Properly treat the relations between administrational management unit and technical support units. (authors)

A review of models relevant to road safety.

Science.gov (United States)

Hughes, B P; Newstead, S; Anund, A; Shu, C C; Falkmer, T

2015-01-01

It is estimated that more than 1.2 million people die worldwide as a result of road traffic crashes and some 50 million are injured per annum. At present some Western countries' road safety strategies and countermeasures claim to have developed into 'Safe Systems' models to address the effects of road related crashes. Well-constructed models encourage effective strategies to improve road safety. This review aimed to identify and summarise concise descriptions, or 'models' of safety. The review covers information from a wide variety of fields and contexts including transport, occupational safety, food industry, education, construction and health. The information from 2620 candidate references were selected and summarised in 121 examples of different types of model and contents. The language of safety models and systems was found to be inconsistent. Each model provided additional information regarding style, purpose, complexity and diversity. In total, seven types of models were identified. The categorisation of models was done on a high level with a variation of details in each group and without a complete, simple and rational description. The models identified in this review are likely to be adaptable to road safety and some of them have previously been used. None of systems theory, safety management systems, the risk management approach, or safety culture was commonly or thoroughly applied to road safety. It is concluded that these approaches have the potential to reduce road trauma. Copyright © 2014 Elsevier Ltd. All rights reserved.

IRSN safety research carried out for reviewing geological disposal safety case

International Nuclear Information System (INIS)

Serres, Christophe; Besnus, Francois; Gay, Didier

2010-01-01

The Radiation Protection and Nuclear Safety Institute develops a research programme on scientific issues related to geological disposal safety in order to supporting the technical assessment carried out in the framework of the regulatory review process. This research programme is organised along key safety questions that deal with various scientific disciplines as geology, hydrogeology, mechanics, geochemistry or physics and is implemented in national and international partnerships. It aims at providing IRSN with sufficient independent knowledge and scientific skills in order to be able to assess whether the scientific results gained by the waste management organisation and their integration for demonstrating the safety of the geological disposal are acceptable with regard to the safety issues to be dealt with in the Safety Case. (author)

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

Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

Energy Technology Data Exchange (ETDEWEB)

Chopra, Omesh K. [Argonne National Lab., IL (United States). Environmental Science Division; Diercks, Dwight R. [Argonne National Lab., IL (United States). Nuclear Engineering Division; Ma, David Chia-Chiun [Argonne National Lab., IL (United States). Environmental Science Division; Garud, Yogendra S. [Argonne National Lab., IL (United States). Environmental Science Division

2013-12-17

At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commission (NRC) incorporate lessons learned from periodic safety reviews (PSRs) performed in other countries as an input to the NRC’s assessment processes. In the U.S., commercial nuclear power plants (NPPs) are granted an initial 40-year operating license, which may be renewed for additional 20-year periods, subject to complying with regulatory requirements. The NRC has established a framework through its inspection, and operational experience processes to ensure the safe operation of licensed nuclear facilities on an ongoing basis. In contrast, most other countries do not impose a specific time limit on the operating licenses for NPPs, they instead require that the utility operating the plant perform PSRs, typically at approximately 10-year intervals, to assure continued safe operation until the next assessment. The staff contracted with Argonne National Laboratory (Argonne) to perform a pilot review of selected translated PSR assessment reports and related documentation from foreign nuclear regulatory authorities to identify any potential new regulatory insights regarding license renewal-related topics and NPP operating experience (OpE). A total of 14 PSR assessment documents from 9 countries were reviewed. For all of the countries except France, individual reports were provided for each of the plants reviewed. In the case of France, three reports were provided that reviewed the performance assessment of thirty-four 900-MWe reactors of similar design commissioned between 1978

Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

International Nuclear Information System (INIS)

Chopra, Omesh K.; Diercks, Dwight R.; Ma, David Chia-Chiun; Garud, Yogendra S.

2013-01-01

At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commission (NRC) incorporate lessons learned from periodic safety reviews (PSRs) performed in other countries as an input to the NRC's assessment processes. In the U.S., commercial nuclear power plants (NPPs) are granted an initial 40-year operating license, which may be renewed for additional 20-year periods, subject to complying with regulatory requirements. The NRC has established a framework through its inspection, and operational experience processes to ensure the safe operation of licensed nuclear facilities on an ongoing basis. In contrast, most other countries do not impose a specific time limit on the operating licenses for NPPs, they instead require that the utility operating the plant perform PSRs, typically at approximately 10-year intervals, to assure continued safe operation until the next assessment. The staff contracted with Argonne National Laboratory (Argonne) to perform a pilot review of selected translated PSR assessment reports and related documentation from foreign nuclear regulatory authorities to identify any potential new regulatory insights regarding license renewal-related topics and NPP operating experience (OpE). A total of 14 PSR assessment documents from 9 countries were reviewed. For all of the countries except France, individual reports were provided for each of the plants reviewed. In the case of France, three reports were provided that reviewed the performance assessment of thirty-four 900-MWe reactors of similar design commissioned between 1978 and

Nuclear safety review for the year 2001

International Nuclear Information System (INIS)

2002-07-01

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

Interagency Nuclear Safety Review Panel Power System Subpanel review for the Ulysses mission

International Nuclear Information System (INIS)

McCulloch, W.H.

1991-01-01

As part of the Interagency Nuclear Safety Review Panel's assessment of the nuclear safety of NASA's Ulysses Mission to investigate properties of the sun, the Power System Subpanel has reviewed the safety analyses and risk evaluations done for the General Purpose Heat Source-Radioisotope Thermoelectric Generator which provides on-board electrical power for the spacecraft. This paper summarizes the activities and results of that review. In general, the approach taken in the primary analysis, executed by the General Electric Company under contract to the Department of Energy, and the resulting conclusions were confirmed by the review. However, the Subpanel took some exceptions and modified the calculations accordingly, producing an independent evaluation of potential releases of radioactive fuel in launch and reentry accidents. Some of the more important of these exceptions are described briefly

Guidelines for the review research reactor safety. Reference document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

International Nuclear Information System (INIS)

1997-01-01

In 1992, the IAEA published new safety standards for research reactors as part of the set of publications considered by its Research Reactor Safety Programme (RRSP). This set also includes publications giving guidance for all safety aspects related to the lifetime of a research reactor. In addition, the IAEA has also revised the Safety Standards for radiation protection. Consequently, it was considered advisable to revise the Integrated Safety Assessment of Research Reactors (INSARR) procedures to incorporate the new requirements and guidance as well as to extend the scope of the safety reviews to currently operating research reactors. The present report is the result of this revision. The purpose of this report is to give guidance on the preparation, execution, reporting and follow-up of safety review mission to research reactors as conducted by the IAEA under its INSARR missions safety service. However, it will also be of assistance to operators and regulators in conducting: (a) ad hoc safety assessments of research reactors to address individual issues such as ageing or safety culture; and (b) other types of safety reviews such as internal and peer reviews and regulatory inspections

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

Guidelines for the Review of Research Reactor Safety: Revised Edition. Reference Document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

International Nuclear Information System (INIS)

2013-01-01

The Integrated Safety Assessment of Research Reactors (INSARR) is an IAEA safety review service available to Member States with the objective of supporting them in ensuring and enhancing the safety of their research reactors. This service consists of performing a comprehensive peer review and an assessment of the safety of the respective research reactor. The reviews are based on IAEA safety standards and on the provisions of the Code of Conduct on the Safety of Research Reactors. The INSARR can benefit both the operating organizations and the regulatory bodies of the requesting Member States, and can include new research reactors under design or operating research reactors, including those which are under a Project and Supply Agreement with the IAEA. The first IAEA safety evaluation of a research reactor operated by a Member State was completed in October 1959 and involved the Swiss 20 MW DIORIT research reactor. Since then, and in accordance with its programme on research reactor safety, the IAEA has conducted safety review missions in its Member States to enhance the safety of their research reactor facilities through the application of the Code of Conduct on the Safety of Research Reactors and the relevant IAEA safety standards. About 320 missions in 51 Member States were undertaken between 1972 and 2012. The INSARR missions and other limited scope safety review missions are conducted following the guidelines presented in this publication, which is a revision of Guidelines for the Review of Research Reactor Safety (IAEA Services Series No. 1), published in December 1997. This publication details those IAEA safety standards and guidance publications relevant to the safety of research reactors that have been revised or published since 1997. The purpose of this publication is to give guidance on the preparation, implementation, reporting and follow-up of safety review missions. It is also intended to be of assistance to operators and regulators in conducting

Post Chernobyl safety review at Ontario Hydro

International Nuclear Information System (INIS)

Frescura, G.M.; Luxat, J.C.; Jobe, C.

1991-01-01

It is generally recognized that the Chernobyl Unit 4 accident did not reveal any new phenomena which had not been previously identified in safety analyses. However, the accident provided a tragic reminder of the potential consequences of reactivity initiated accidents (RIAs) and stimulated nuclear plant operators to review their safety analyses, operating procedures and various operational and management aspects of nuclear safety. Concerning Ontario Hydro, the review of the accident performed by the corporate body responsible for nuclear safety policy and by the Atomic Energy Control Board (the Regulatory Body) led to a number of specific recommendations for further action by various design, analysis and operation groups. These recommendations are very comprehensive in terms of reactor safety issues considered. The general conclusion of the various studies carried out in response to the recommendations, is that the CANDU safety design and the procedures in place to identify and mitigate the consequences of accidents are adequate. Improvements to the reliability of the Pickering NGSA shutdown system and to some aspects of safety management and staff training, although not essential, are possible and would be pursued. In support of this conclusion, the paper describes some of the studies that were carried out and discusses the findings. The first part of the paper deals with safety design aspects. While the second is concerned with operational aspects

Radiation safety in nuclear medicine procedures

International Nuclear Information System (INIS)

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

2017-01-01

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

Radiation safety in nuclear medicine procedures

Energy Technology Data Exchange (ETDEWEB)

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

2017-03-15

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

Review of Public Safety in Viewpoint of Complex Networks

International Nuclear Information System (INIS)

Gai Chengcheng; Weng Wenguo; Yuan Hongyong

2010-01-01

In this paper, a brief review of public safety in viewpoint of complex networks is presented. Public safety incidents are divided into four categories: natural disasters, industry accidents, public health and social security, in which the complex network approaches and theories are need. We review how the complex network methods was developed and used in the studies of the three kinds of public safety incidents. The typical public safety incidents studied by the complex network methods in this paper are introduced, including the natural disaster chains, blackouts on electric power grids and epidemic spreading. Finally, we look ahead to the application prospects of the complex network theory on public safety.

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

Nuclear Safety Review for the Year 2008

International Nuclear Information System (INIS)

2009-07-01

's Response Assistance Network. In July 2008, an emergency exercise, hosted by Mexico and known as ConvEx3 (2008), tested the international response to a simulated accident at a nuclear power plant. The Agency used its Incident and during the exercise. The importance of having effective civil liability mechanisms in place to insure against harm to human health and the environment, as well as actual economic loss caused by nuclear damage, receives continued attention among Member States. The deposit by the USA of its instrument of ratification of the Convention on Supplementary Compensation for Nuclear Damage (CSC) marked an important milestone towards bringing the entry into force of the CSC. The International Expert Group on Nuclear Liability (INLEX) continues to serve as the Agency's main forum dealing with questions related to nuclear liability. In 2008, INLEX discussed, inter alia, outreach activities and the ongoing European Commission's impact assessment on nuclear liability. Nuclear power plant operators continued to show strong safety performance in 2008, with no serious accidents or significant radiation exposure to workers or the public to report. During the Agency's International Conference on Topical Issues in Nuclear Installation Safety, held in Mumbai, India in November 2008, participants concluded that an integrated nuclear safety approach based on the defence in depth principle and deterministic criteria, when properly applied and complemented with probabilistic analyses and operational experience feedback, continues to be successful. The reevaluation of the integrity of existing nuclear installations, taking into account the increased magnitude observed during recent severe earthquakes and extreme natural events, has begun. At the request of Member States, the Agency has conducted generic reactor safety reviews to assess new nuclear power plant designs for consistency with the Agency's safety standards.

Nuclear safety review for the year 2000

International Nuclear Information System (INIS)

2001-06-01

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

Fuel safety criteria technical review - Results of OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria

International Nuclear Information System (INIS)

Hollasky, N.; Valtonen, K.; Hache, G.; Gross, H.; Bakker, K.; Recio, M.; Bart, G.; Zimmermann, M.; Van Doesburg, W.; Killeen, J.; Meyer, R.O.; Speis, T.

2000-01-01

of the assessment of the safety criteria, the TF members looked at various issues, as they relate to one or more criteria, that have become of special interest. These topics included high burnup, core management, MOX, mixed cores, incomplete control rod insertion, and axial offset anomaly. Also, an attempt was made to assess the current level of methods and codes, which are used to verify the criteria and margins. As code development activities are widespread, the Task Force could not identify all such activities but focused on those needed to adequately analyse the effects of new design elements. The Task Force did not extensively review all ongoing and future research programs. However, a few examples of research programs are given that contribute to investigating the phenomena and mechanisms of fuel behavior under transient / accident conditions. These include hot-cell testing at Argonne National Laboratory in the U.S., the Halden Reactor Project in Norway, research and development work by Belgonucleaire in Belgium, the Cabri test reactor and related programs in France, and the Nuclear Safety Research Reactor program in Japan. As a result of all above assessments, the Task Force considers that the current framework of fuel safety criteria remains generally applicable, being largely unaffected by the 'new' or modern design elements; the levels (numbers) in the individual safety criteria may, however, change in accordance with the particular fuel and core design features. Some of these levels have already been - or are continuously being - adjusted; level adjustments of several other criteria (RIA, LOCA) also appear to be needed, on the basis of experimental data and the analysis thereof. For this (re)assessment of fuel safety criteria, the following process is recommended: (a) Continue to develop best-estimate (nominal) analysis methods, together with a suitable uncertainty analysis, in all areas of safety analysis (b) Continue to perform experimental verification

Occupational Safety Review of High Technology Facilities

Energy Technology Data Exchange (ETDEWEB)

Lee Cadwallader

2005-01-31

This report contains reviews of operating experiences, selected accident events, and industrial safety performance indicators that document the performance of the major US DOE magnetic fusion experiments and particle accelerators. These data are useful to form a basis for the occupational safety level at matured research facilities with known sets of safety rules and regulations. Some of the issues discussed are radiation safety, electromagnetic energy exposure events, and some of the more widespread issues of working at height, equipment fires, confined space work, electrical work, and other industrial hazards. Nuclear power plant industrial safety data are also included for comparison.

Nuclear Safety Bureau. Annual Report 1996-1997

International Nuclear Information System (INIS)

1997-01-01

Throughout the year the Nuclear Safety Bureau (NSB) continued its regulatory approach to monitor and review the safety of nuclear plant operated by the Australian Nuclear Science and Technology Organisation (ANSTO). This included an ongoing regime of safety audits against the authorised arrangements in ANSTO's safety documentation and the bureau's expectations for nuclear plant drawn from international best practice. The NSB invited the participation of officers of the Australian Radiation Laboratory in these audits. Aspects of ANSTO's operation of nuclear plant reviewed by the NSB included training and accreditation of operations staff, abnormal occurrences, modifications to plant and emergency arrangements and exercises for the Lucas Heights Science and Technology Centre. Audits of HIFAR were also conducted on operating logs, radiation protection and radioactive discharges. Based on the reviews and audits conducted by the NSB, and ANSTO's actions in responding to the bureau's requests and requirements for actions, the NSB concluded that ANSTO's nuclear plant operated safely throughout the year, and that risks to on-site personnel and the public were maintained at acceptably low levels

IAEA Operational Safety Team Reviews Cattenom Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has reviewed operational safety at France's Cattenom Nuclear Power Plant (NPP) noting a series of good practices as well as recommendations and suggestions to reinforce them. The IAEA assembled an international team of experts at the request of the Government of France to conduct an Operational Safety Review (OSART) of Cattenom NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review of the plant from 14 November to 1 December 2011. The team was made up of experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Japan, Russia, Slovakia, South Africa, Sweden, Ukraine, the United Kingdom and the IAEA. The team at Cattenom conducted an in-depth review of the aspects essential to the safe operation of the NPP, which is largely under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. Cattenom is the first plant in Europe to voluntarily undertake a Severe Accident Management review during an OSART review. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: Sheets are displayed in storage areas where combustible material is present - these sheets are updated readily and accurately by the area owner to ensure that the fire limits are complied with; A simple container is attached to the neutron source handling device to ensure ease and safety of operations and reduce possible radiation exposure during use

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

International Nuclear Information System (INIS)

1992-02-01

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

Desonide: a review of formulations, efficacy and safety.

Science.gov (United States)

Kahanek, Nr; Gelbard, Cg; Hebert, Aa

2008-07-01

Desonide is a low-potency topical corticosteroid that has been used for decades in the treatment of steroid-responsive dermatoses. The favorable safety profile of this topical agent makes it ideal for patients of all ages. This article provides a review of desonide's history, pharmacodynamic properties, vehicle technology, efficacy and safety. Randomized controlled trials, as well as open-label and non-comparative studies, case series and reports, experimental models, and data from the Galderma pharmacovigiliance program were reviewed in order to address the clinical efficacy and safety of desonide. Clinical efficacy and safety have been proven in multiple clinical trials. In addition to cream, lotion and ointment formulations, the recently developed hydrogel and foam preparations have increased desonide's versatility and patient tolerability.

78 FR 11902 - Review of Gun Safety Technologies

Science.gov (United States)

2013-02-20

... DEPARTMENT OF JUSTICE Office of Justice Programs [OJP (NIJ) Docket No. 1615] Review of Gun Safety...'s Plan to reduce gun violence released on January 16, 2013, the U.S. Department of Justice, Office... emerging gun safety technologies and plans to issue a report on the availability and use of those...

Packaging review guide for reviewing safety analysis reports for packagings: Revision 1

International Nuclear Information System (INIS)

Fisher, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

1988-10-01

The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. The principal purpose of this document is to assure the quality and uniformity of PCS reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The Packaging Review Guide (PRG) also sets forth solutions and approaches determined to be acceptable in the past in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented. It is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 77 refs., 16 figs., 15 tabs

Safety review of experiments at Albuquerque Operations Office

International Nuclear Information System (INIS)

Elliott, K.

1984-01-01

The Department of Energy (DOE) Albuquerque Operations Office is responsible for the safety overview of nuclear reactor and critical assembly facilities at Sandia National Laboratories, Los Alamos National Laboratory, and the Rocky Flats Plant. The important safety concerns with these facilities involve the complex experiments that are performed, and that is the area emphasized. A determination is made by the Albuquerque Office (AL) with assistance from DOE/OMA whether or not a proposed experiment is an unreviewed safety question. Meetings are held with the contractor to resolve and clarify questions that are generated during the review of the proposed experiment. The AL safety evaluation report is completed and any recommendations are discussed. Prior to the experiment a preoperational appraisal is performed to assure that personnel, procedures, and equipment are in readiness for operations. During the experiment, any abnormal condition is reviewed in detail to determine any safety concerns

Review of fuel safety criteria in France

Energy Technology Data Exchange (ETDEWEB)

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

2018-01-15

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

Review of fuel safety criteria in France

International Nuclear Information System (INIS)

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

2018-01-01

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

Standard review plan for reviewing safety analysis reports for dry metallic spent fuel storage casks

International Nuclear Information System (INIS)

1988-01-01

The Cask Standard Review Plan (CSRP) has been prepared as guidance to be used in the review of Cask Safety Analysis Reports (CSARs) for storage packages. The principal purpose of the CSRP is to assure the quality and uniformity of storage cask reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The CSRP also sets forth solutions and approaches determined to be acceptable in the past by the NRC staff in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a CSAR does not have to follow the solutions or approaches presented in the CSRP. However, applicants should recognize that the NRC staff has spent substantial time and effort in reviewing and developing their positions for the issues. A corresponding amount of time and effort will probably be required to review and accept new or different solutions and approaches

Severe accident mitigation strategy for the generation II PWRs in France. Some outcomes of the on-going periodic safety review of the French 1300 MWe PWR series

Energy Technology Data Exchange (ETDEWEB)

Cenerino, G.; Rahni, N.; Chevrier, P.; Dubreuil, M.; Guigueno, Y.; Raimond, E.; Bonnet, J.M. [IRSN/PSN-RES/SAG (France)

2013-07-01

The 3{sup rd} Periodic Safety Review of the French 1300 MWe PWRs series includes some modifications to increase their robustness in case of a severe accident. Their review is based on both deterministic and probabilistic approaches, keeping in mind that severe accidents frequencies and radiological consequences should be as low as reasonably practicable, severe accidents management strategies should be as safe as possible and the robustness of equipment used for severe accident management should be ensured. Consequently, the IRSN level 2 probabilistic safety assessment (L2 PSA) studies for the 1300 MWe reactors have been used to re-assess the results of the utility's L2 PSA and rank them to identify the containment failure modes contributing the most to the global risk. This ranking helped the review of plant modifications. Regarding strategies for accident management, the EDF management of water in the reactor cavity during a severe accident for the 1300 MWe PWRs is presented as well as the IRSN position on this strategy: this is an example where the optimal severe accident management strategy choice is not so easy to define. Regarding the robustness of equipment used for severe accident management, the interest of a diversification or redundancy of the French emergency filtered containment venting opening is one example among many others. (orig.)

Packaging review guide for reviewing safety analysis reports for packagings: Revision 0

International Nuclear Information System (INIS)

Fischer, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

1987-09-01

The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. These certification review policies and procedures are established to ensure that DOE packaging designs and operations meet safety criteria at least equivalent to the standards prescribed by the Nuclear Regulatory Commission (NRC) certification process for packaging. The Packaging Review Guide (PRG) is not a DOE order, but has been prepared as guidance for the Packaging Certification Staff (PCS) under the Certifying Official, Office of Security Evaluations, or designated representatives. The principal purpose of the PRG is to assure the quality and uniformity of PCS reviews, and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The PRG also sets forth solutions and approaches determined to be acceptable in the past by the PCS in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented in the PRG. However, applicants should recognize that the PCS has spent substantial time and effort in reviewing and developing their positions for the issues. A corresponding amount of time and effort will probably be required to review and accept new or different solutions and approaches. Finally, it is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 7 refs., 15 figs., 14 tabs

Systematic review of economic analyses in patient safety: a protocol designed to measure development in the scope and quality of evidence.

Science.gov (United States)

Carter, Alexander W; Mandavia, Rishi; Mayer, Erik; Marti, Joachim; Mossialos, Elias; Darzi, Ara

2017-08-18

Recent avoidable failures in patient care highlight the ongoing need for evidence to support improvements in patient safety. According to the most recent reviews, there is a dearth of economic evidence related to patient safety. These reviews characterise an evidence gap in terms of the scope and quality of evidence available to support resource allocation decisions. This protocol is designed to update and improve on the reviews previously conducted to determine the extent of methodological progress in economic analyses in patient safety. A broad search strategy with two core themes for original research (excluding opinion pieces and systematic reviews) in 'patient safety' and 'economic analyses' has been developed. Medline, Econlit and National Health Service Economic Evaluation Database bibliographic databases will be searched from January 2007 using a combination of medical subject headings terms and research-derived search terms (see table 1). The method is informed by previous reviews on this topic, published in 2012. Screening, risk of bias assessment (using the Cochrane collaboration tool) and economic evaluation quality assessment (using the Drummond checklist) will be conducted by two independent reviewers, with arbitration by a third reviewer as needed. Studies with a low risk of bias will be assessed using the Drummond checklist. High-quality economic evaluations are those that score >20/35. A qualitative synthesis of evidence will be performed using a data collection tool to capture the study design(s) employed, population(s), setting(s), disease area(s), intervention(s) and outcome(s) studied. Methodological quality scores will be compared with previous reviews where possible. Effect size(s) and estimate uncertainty will be captured and used in a quantitative synthesis of high-quality evidence, where possible. Formal ethical approval is not required as primary data will not be collected. The results will be disseminated through a peer-reviewed

Review on JMTR safety design for LEU core conversion

International Nuclear Information System (INIS)

Komori, Yoshihiro; Yokokawa, Makoto; Saruta, Toru; Inada, Seiji; Sakurai, Fumio; Yamamoto, Katsumune; Oyamada, Rokuro; Saito, Minoru

1993-12-01

Safety of the JMTR was fully reviewed for the core conversion to low enriched uranium fuel. Fundamental policies for the JMTR safety design were reconsidered based on the examination guide for safety design of test and research reactors, and safety of the JMTR was confirmed. This report describes the safety design of the JMTR from the viewpoint of major functions for reactor safety. (author)

[Improving patient safety through voluntary peer review].

Science.gov (United States)

Kluge, S; Bause, H

2015-01-01

The intensive care unit (ICU) is one area of the hospital in which processes and communication are of primary importance. Errors in intensive care units can lead to serious adverse events with significant consequences for patients. Therefore quality and risk-management are important measures when treating critically ill patients. A pragmatic approach to support quality and safety in intensive care is peer review. This approach has gained significant acceptance over the past years. It consists of mutual visits by colleagues who conduct standardised peer reviews. These reviews focus on the systematic evaluation of the quality of an ICU's structure, its processes and outcome. Together with different associations, the State Chambers of Physicians and the German Medical Association have developed peer review as a standardized tool for quality improvement. The common goal of all stakeholders is the continuous and sustainable improvement in intensive care with peer reviews significantly increasing and improving communication between professions and disciplines. Peer reviews secure the sustainability of planned change processes and consequently lead the way to an improved culture of quality and safety.

Using systematic review in occupational safety and health.

Science.gov (United States)

Howard, John; Piacentino, John; MacMahon, Kathleen; Schulte, Paul

2017-11-01

Evaluation of scientific evidence is critical in developing recommendations to reduce risk. Healthcare was the first scientific field to employ a systematic review approach for synthesizing research findings to support evidence-based decision-making and it is still the largest producer and consumer of systematic reviews. Systematic reviews in the field of occupational safety and health are being conducted, but more widespread use and adoption would strengthen assessments. In 2016, NIOSH asked RAND to develop a framework for applying the traditional systematic review elements to the field of occupational safety and health. This paper describes how essential systematic review elements can be adapted for use in occupational systematic reviews to enhance their scientific quality, objectivity, transparency, reliability, utility, and acceptability. Published 2017. This article is a U.S. Government work and is in the public domain in the USA.

Safety and efficacy of pharmacologic thromboprophylaxis following blunt head injury: a systematic review.

Science.gov (United States)

Reeves, Fairleigh; Batty, Lachlan; Pitt, Veronica; Chau, Marisa; Pattuwage, Loyal; Gruen, Russell L

2013-10-01

Patients with blunt head injury are at high risk of venous thromboembolism. However, pharmacologic thromboprophylaxis (PTP) may cause progression of intracranial hemorrhage, and clinicians must often weigh up the risks and benefits. This review aimed to determine whether adding PTP to mechanical prophylaxis confers net benefit or harm and the optimal timing, dose, and agent for PTP in patients with blunt head injury. We searched MEDLINE, EMBASE, The Cochrane Library Central Register of Controlled Trials (CENTRAL), and www.clinicaltrials.gov on April 24, 2013, to identify controlled studies and ongoing trials that assessed the efficacy or safety of thromboprophylaxis interventions in the early management of head-injured patients. Studies were classified based on types of interventions and comparisons, and the quality of included studies was assessed using Cochrane risk-of-bias tool and the Newcastle-Ottawa Quality Assessment Scale. We intended to undertake a meta-analysis if studies were sufficiently similar. Sixteen studies met the inclusion criteria, including four randomized controlled trials. At least two randomized controlled trials were at high risk of bias owing to inadequate randomization and concealment of allocation, and observational studies were potentially confounded by substantial differences between comparison groups. Heterogeneity of included studies precluded meta-analysis. Results were mixed, with some studies supporting and others refuting addition of PTP to mechanical interventions. Little evidence was available about dose or choice of agent. The safety and efficacy of early PTP in patients without early progression of hemorrhage is unclear. There is currently insufficient evidence to guide thromboprophylaxis in patients with blunt head injury. Standardized definitions and outcome measurements would facilitate comparison of outcomes across future studies. Studies in mixed populations should report head-injured specific subgroup data. Future

Efficacy and Safety Data of Subsequent Entry Biologics Pertinent to Nephrology Practice: A Systematic Review

Directory of Open Access Journals (Sweden)

Judith Genevieve Marin

2014-12-01

Full Text Available Background: Subsequent entry biologics (SEBs may soon be a reality in Canadian nephrology practice. Understanding the worldwide experience with these agents will be valuable to Canadian clinicians. Objectives: To compare the efficacy and safety data between SEBs used in nephrology practice and their reference biologic. Design: Systematic review. Sources of information: Ovid MEDLINE, EMBASE, Cochrane Database of Systematic Reviews, Database of Abstracts of Review of Effects, Cochrane Central Register of Controlled Trials. Patients: Adult patients with chronic kidney disease (CKD. Methods: Our systematic review follows the process outlined by Cochrane Reviews. For efficacy data, all randomized controlled trials (RCTs, quasi-RCTs and observational trials in nephrology practice were included. For safety data, case series, case reports, review articles in nephrology practice and pharmacovigilance programs were included as well. Results: Only epoetin SEBs trials were published in the literature. Ten studies involving three different epoetin SEBs (epoetin zeta, HX575 and epoetin theta were included. The mean epoetin dose used did not differ significantly between the SEBs and the reference product. For epoetin zeta and epoetin theta, the mean hemoglobin levels achieved in the studies were similar between the SEBs and the reference epoetin. The HX 575 studies reported a mean absolute change in hemoglobin within the predefined equivalence margin, when compared with the reference biologic. In terms of safety data, 2 cases of pure-red-cell aplasia were linked to the subcutaneous administration of HX 575. Otherwise, the rate of adverse drug reactions was similar when epoetin SEBs were compared with the reference biologic. Limitations: Our analysis is limited by the paucity of information available on SEB use in nephrology with the exception of epoetin SEBs. Methodological flaw was found in one of the epoetin zeta studies which accounted for 45% of pooled

Standard Review Plan for the review of safety analysis reports for nuclear power plants: LWR edition

International Nuclear Information System (INIS)

1987-06-01

The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. It is also a purpose of the SRP to make information about regulatory matters widely available and to improve communication and understanding of the staff review process by interested members of the public and the nuclear power industry. The safety review is primarily based on the information provided by an applicant in a Safety Analysis Report (SAR). The SAR must be sufficiently detailed to permit the staff to determine whether the plant can be built and operated without undue risk to the health and safety of the public. The SAR is the principal document in which the applicant provides the information needed to understand the basis upon which this conclusion has been reached. The individual SRP sections address, in detail, who performs the review, the matters that are reviewed, the basis for review, how the review is accomplished, and the conclusions that are sought. The safety review is performed by 25 primary branches. One of the objectives of the SRP is to assign the review responsibilities to the various branches and to define the sometimes complex interfaces between them. Each SRP section identifies the branch that has the primary review responsibility for that section. In some review areas the primary branch may require support, and the branches that are assigned these secondary review responsibilities are also identified for each SRP section

Immunization safety review: influenza vaccines and neurological complications

National Research Council Canada - National Science Library

Stratton, Kathleen R

..., unlike other vaccines. The Immunization Safety Review committee reviewed the data on influenza vaccine and neurological conditions and concluded that the evidence favored rejection of a causal relationship...

IAEA Completes First Ever Corporate Safety Review, at Czech Republic's CEZ

International Nuclear Information System (INIS)

2013-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) today completed a review of corporate safety performance at CEZ a.s., the largest national electricity company in the Czech Republic. For the first time since the Agency launched its Operational Safety Review Team (OSART) missions in 1982, the team addressed corporate aspects of a company in relation to nuclear safety. The team noted a series of good practices and proposed recommendations to strengthen some safety measures. Assembled at the request of the Government of the Czech Republic, the first ''Corporate OSART'' review, which ran from 30 September to 9 October 2013, addressed corporate aspects necessary to ensure the safe operation of the Dukovany and Temelin Nuclear Power Plants (NPPs). The mission included experts from Finland, France, Romania, USA and the IAEA. OSART services aim to improve operational safety at nuclear facilities by objectively assessing safety performance using the IAEA's Safety Standards and proposing recommendations for improvement where appropriate. The missions serve as a channel to exchange information and experience and provide Member States with good practices. A ''Corporate OSART'' is an OSART mission organized to review those centralized functions of the corporate organization of a utility with multiple nuclear plant sites and conventional plant sites that affect all the operational safety aspects of the nuclear power plants of this utility. ''OSART missions are one of the most important tools of the Agency to ensure better and wider implementation of the IAEA Safety Standards,'' said Denis Flory, Deputy Director General in the IAEA Department of Nuclear Safety and Security. ''Since 1982, we have conducted close to 200 safety review missions around the globe; however, this mission is the first of its kind because we focused on the corporate performance that is a necessity for a safe operation of NPPs,'' Flory added

Review of probabilistic safety assessments by regulatory bodies

International Nuclear Information System (INIS)

2002-01-01

This report provides guidance to assist regulatory bodies in carrying out reviews of the PSAs produced by utilities. In following this guidance, it is important that the regulatory body is able to satisfy itself that the PSA has been carried out to an acceptable standard and that it can be used for its intended applications. The review process becomes an important phase in determining the acceptability of the PSA since this provides a degree of assurance of the PSA scope, validity and limitations, as well as a better understanding of plants themselves. This report is also intended to assist technical experts managing or performing PSA reviews. A particular aim is to promote a standardized framework, terminology and form of documentation for the results of PSA reviews. The information presented in this report supports IAEA Safety Guide No. GS-G-1.2. Recommendations on the scope and methods to be used by the utility in the preparation of a PSA study is provided in IAEA Safety Guide No. NSG- 1.2. Information on these Safety Guides and other IAEA safety standards for nuclear power plants can be found on the following Internet site: http://www.iaea.org/ns/coordinet. The scope of this report covers the review of Level 1, 2 and 3 PSAs for event sequences occurring in all modes of plant operation (including full power, low power and shutdown). Where the scope of the analysis is narrower than this, a subset of the guidance can be identified and used. Information is provided on carrying out the review of a PSA throughout the PSA production process, i.e. from the initial decision to carry out the PSA through to the completion of the study and the production of the final PSA report. However, the same procedure can be applied to a completed PSA or to one already in progress. As a result of the performance of a PSA, changes to the design or operation of the plant are often identified that would increase the level of safety. This might include the addition of further safety

IAEA Concludes Safety Review at Gravelines Nuclear Power Plant, France

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA-led international team of nuclear safety experts noted a series of good practices and made recommendations to reinforce some safety measures during a review of operational safety at France's Gravelines Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 12 November 2012, focused on aspects essential to the safe operation of the NPP. The team was composed of experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain, Ukraine and the IAEA. The review covered the areas of management, organization and administration; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their possible use elsewhere. Examples include the following: - The Power Plant uses a staff-skills mapping process that significantly enhances knowledge of the facility's collective and individual skills and provides proactive management to address the loss of such skills; - As a measure to reduce the risk of workers' radiation exposure, the Power Plant uses a system to ensure that dose rate measurements are carried out at a precise distance from the source of radiation; and - Flood protection of the Power Plant is supported by special technical guidance documents and associated arrangements. The team identified a number of proposals for improvements to operational safety at Gravelines NPP. Examples include the following: - The Power Plant should reinforce its measures to prevent foreign objects from entering plant systems; - The Power Plant should ensure the 24-hour presence of an operator

Patient safety culture in care homes for older people: a scoping review

Directory of Open Access Journals (Sweden)

Emily Gartshore

2017-11-01

Full Text Available Abstract Background In recent years, there has been an increasing focus on the role of safety culture in preventing incidents such as medication errors and falls. However, research and developments in safety culture has predominantly taken place in hospital settings, with relatively less attention given to establishing a safety culture in care homes. Despite safety culture being accepted as an important quality indicator across all health and social care settings, the understanding of culture within social care settings remains far less developed than within hospitals. It is therefore important that the existing evidence base is gathered and reviewed in order to understand safety culture in care homes. Methods A scoping review was undertaken to describe the availability of evidence related to care homes’ patient safety culture, what these studies focused on, and identify any knowledge gaps within the existing literature. Included papers were each reviewed by two authors for eligibility and to draw out information relevant to the scoping review. Results Twenty-four empirical papers and one literature review were included within the scoping review. The collective evidence demonstrated that safety culture research is largely based in the USA, within Nursing Homes rather than Residential Home settings. Moreover, the scoping review revealed that empirical evidence has predominantly used quantitative measures, and therefore the deeper levels of culture have not been captured in the evidence base. Conclusions Safety culture in care homes is a topic that has not been extensively researched. The review highlights a number of key gaps in the evidence base, which future research into safety culture in care home should attempt to address.

IAEA Completes Safety Review at Czech Nuclear Power Plant

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts, led by the International Atomic Energy Agency (IAEA), today completed a review of safety practices at Temelin Nuclear Power Station in the Czech Republic. The team highlighted the Power Plant's good practices and also recommended improvements to some safety measures. At the request of the Government of the Czech Republic, the IAEA assembled a team of nuclear installation safety experts to send an Operational Safety Review Team (OSART) to the Power Plant, and the mission was conducted from 5 to 22 November 2012. The team was comprised of experts from Brazil, Hungary, Slovakia, South Africa, Sweden, Ukraine and the United Kingdom. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the Plant's overall safety status. The team at Temelin conducted an in-depth review of the functions essential to the safe operation of the Power Plant, which are under the responsibility of the site's management. The review covered the areas of management, organization and administration; operations; maintenance; technical support; operating experience; radiation protection; chemistry; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of potential application elsewhere. Examples include the following: - The Power Plant has adopted effective computer software to improve the efficiency of the plant to prepare and isolate equipment for maintenance; - The Power Plant undertakes measures to control precisely the chemical parameters that limit corrosion in the reactor's coolant system, which in turn reduce radiation exposure to the workforce; and - The Temelin

Independent peer review of nuclear safety computer codes

International Nuclear Information System (INIS)

Boyack, B.E.; Jenks, R.P.

1993-01-01

A structured, independent computer code peer-review process has been developed to assist the US Nuclear Regulatory Commission (NRC) and the US Department of Energy in their nuclear safety missions. This paper describes a structured process of independent code peer review, benefits associated with a code-independent peer review, as well as the authors' recent peer-review experience. The NRC adheres to the principle that safety of plant design, construction, and operation are the responsibility of the licensee. Nevertheless, NRC staff must have the ability to independently assess plant designs and safety analyses submitted by license applicants. According to Ref. 1, open-quotes this requires that a sound understanding be obtained of the important physical phenomena that may occur during transients in operating power plants.close quotes The NRC concluded that computer codes are the principal products to open-quotes understand and predict plant response to deviations from normal operating conditionsclose quotes and has developed several codes for that purpose. However, codes cannot be used blindly; they must be assessed and found adequate for the purposes they are intended. A key part of the qualification process can be accomplished through code peer reviews; this approach has been adopted by the NRC

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

International Nuclear Information System (INIS)

Rzentkowski, G.

2016-01-01

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

Safety Commission databases support

CERN Document Server

Petit, S; CERN. Geneva. TS Department

2005-01-01

A collaboration project between the Safety Commission (SC) and the Controls, Safety and Engineering databases group (TS/CSE) started last year. The aim of this collaboration is to transfer several SC applications from their local environments onto the D7i-MTF EDMS framework, for which the TS/CSE group is responsible. Different domains of activity and projects have been defined in the areas of equipment management, safety inspections, accidents and risks management. Priorities have been established in collaboration with SC. This paper presents the new Safety Inspections Management system (SIM) which will be put in production before the summer 2005 and reviews the constraints of both the users and the development and operational framework that needed to be taken into account. The technical solutions adopted to assure a successful production start-up and operation of the SIM system are described. Progress on other on-going projects and plans for the next year are also reported.

Ongoing Space Physics - Astrophysics Connections

OpenAIRE

Eichler, David

2005-01-01

I review several ongoing connections between space physics and astrophysics: a) Measurements of energetic particle spectra have confirmed theoretical prediction of the highest energy to which shocks can accelerate particles, and this has direct bearing on the origin of the highest energy cosmic rays. b) Mass ejection in solar flares may help us understand photon ejection in the giant flares of magnetar outbursts. c) Measurements of electron heat fluxes in the solar wind can help us understand...

Organization and conduct of IAEA fire safety reviews at nuclear power plants

International Nuclear Information System (INIS)

1998-01-01

The importance of fire safety in the safe and productive operation of nuclear power plants is recognized worldwide. Lessons learned from experience in nuclear power plants indicate that fire poses a real threat to nuclear safety and that its significance extends far beyond the scope of a conventional fire hazard. With a growing understanding of the close correlation between the fire hazard in nuclear power plants and nuclear safety, backfitting for fire safety has become necessary for a number of operating plants. However, it has been recognized that the expertise necessary for a systematic independent assessment of fire safety of a NPP may not always be available to a number of Member States. In order to assist in enhancing fire safety, the IAEA has already started to offer various services to Member States in the area of fire safety. At the request of a Member State, the IAEA may provide a team of experts to conduct fire safety reviews of varying scope to evaluate the adequacy of fire safety at a specific nuclear power plant during various phases such as construction, operation and decommissioning. The IAEA nuclear safety publications related to fire protection and fire safety form a common basis for these reviews. This report provides guidance for the experts involved in the organization and conduct of fire safety review services to ensure consistency and comprehensiveness of the reviews

Nulcear Safety: Technical progress review, October--December 1988

Energy Technology Data Exchange (ETDEWEB)

Silver, E G [ed.

1988-01-01

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

Design review report for modifications to RMCS safety class equipment

International Nuclear Information System (INIS)

Corbett, J.E.

1997-01-01

This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable

Design review report for modifications to RMCS safety class equipment

Energy Technology Data Exchange (ETDEWEB)

Corbett, J.E.

1997-05-30

This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable.

Women's journey to safety - the Transtheoretical model in clinical practice when working with women experiencing Intimate Partner Violence: a scientific review and clinical guidance.

Science.gov (United States)

Reisenhofer, Sonia; Taft, Angela

2013-12-01

Review the applicability of the Transtheoretical model and provide updated guidance for clinicians working with women experiencing intimate partner violence. Critical review of related primary research conducted from 1990 to March 2013. Women's experiences of creating change within abusive relationships can be located within a stages of change continuum by identifying dominant behavioral clusters. The processes of change and constructs of decisional-balance and turning-points are evident in women's decision-making when they engage in change. Clinicians can use the stages of change to provide a means of assessing women's movement toward their nominated outcomes, and the processes of change, decisional-balance and turning-points, to enhance understanding of, and promote women's movement across stages in their journey to safety. Clinicians should assess women individually for immediate and ongoing safety and well-being, and identify their overarching stage of change. Clinicians can support women in identifying and implementing their personal objectives to enhance self-efficacy and create positive change movement across stages. The three primary objectives identified for clinician support are: 1. Minimizing harm and promoting well-being within an abusive relationship, 2. Achieving safety and well-being within the relationship; halting the abuse, or 3. Achieving safety by ending/leaving intimate relationships. Copyright © 2013 Elsevier Ireland Ltd. All rights reserved.

49 CFR 209.501 - Review of rail transportation safety and security route analysis.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Review of rail transportation safety and security....820 § 209.501 Review of rail transportation safety and security route analysis. (a) Review of route... establish that the route chosen by the carrier poses the least overall safety and security risk, the...

SALTO Peer Review Guidelines. Guidelines for Peer Review of Safety Aspects of Long Term Operation of Nuclear Power Plants

International Nuclear Information System (INIS)

2014-01-01

International peer review is a useful tool for Member States to exchange experiences, learn from each other and apply good practices in the long term operation (LTO) of nuclear power plants (NPPs). The peer review is also an important mechanism through which the IAEA supports Member States in enhancing the safety of NPPs. The IAEA has conducted various types of safety review that indirectly address aspects of LTO, including safety reviews for design, engineering, operation and external hazards. Operational Safety Review Team (OSART) services include review of ageing management programmes. In addition, several Member States have requested Ageing Management Assessment Team (AMAT) missions. Through these experiences, it was recognized that a comprehensive peer review on LTO would be very useful to Member States. The Safety Aspects of Long Term Operation (SALTO) peer review addresses strategy and key elements for the safe LTO of NPPs, which includes AMAT objectives and complements OSART reviews. The SALTO peer review is designed to assist operating organizations in adopting a proper approach to LTP including implementing appropriate activities to ensure that plant safety will be maintained during the LTO period. The SALTO peer review can be tailored to focus on ageing management programmes (AMPs) or on other activities related to LTO to support the Member State in enhancing the safety of its NPPs. The SALTO peer review can also support regulators in establishing or improving regulatory and licensing strategies for the LTO of NPPs. The guidelines in this publication are primarily intended for members of a SALTO review team and provide a basic structure and common reference for peer reviews of LTO. Additionally, the guidelines also provide useful information to the operating organizations of NPPs (or technical support organizations) for carrying out their own self-assessments or comprehensive programme reviews. The guidelines are intended to be generic, as there are

Preparation of NPP Dukovany periodic safety review

International Nuclear Information System (INIS)

Dubsky, L.; Vymazal, P.

2004-01-01

Dukovany NPP in Czech Republic performs a periodic safety review for the second time after approximately 20 years of operation. The history of the Safety Report and its transformation into an internationally accepted form complying with IAEA standards is described. The deterministic and probabilistic assessment of the plant's safety-related design and state is applied to determine whether and to what extend the relevant protective goals are fulfilled by the existing plant design. A description of the step-by-step process is presented together with the creation of methods and criteria for PSR evaluation prepared by Nuclear Research Institute Rez

IAEA Concludes Safety Review at Chooz Nuclear Power Plant in France

International Nuclear Information System (INIS)

2013-01-01

Full text: An IAEA-led international team of nuclear safety experts noted good practices and made recommendations to reinforce safety measures during a review of operational safety at France's Chooz Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 17 June, focused on aspects essential to the safe operation of the NPP. The team comprised experts from Switzerland, Belgium, Germany, China, India, United Kingdom, Czech Republic, Canada, Hungary and the IAEA. The review covered the areas of management, organization and administration; training and qualification of personnel; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team identified good plant practices that will be shared with the rest of the nuclear industry for consideration. Examples include: The plant has a professional development programme as part of a joint employment effort shared by the plant and its contractors. This enables trainees to develop professional capability, understand practices and gain experience from other nuclear power plants in terms of work planning and coordination; The plant has built a strong relationship between the on-shift response team of the plant and the local fire brigade to improve firefighting and rescue operations; Self-assessment groups discuss and resolve specific issues within operations, empowering operations personnel to take ownership of improvement programmes; and The plant has improved warnings at entrances to all o range zones , areas of elevated dose rates to which only authorized staff have access. The team identified a number of improvements to operational safety at Chooz NPP. Examples include: The plant should review its process for the

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Patient Safety and Workplace Bullying: An Integrative Review.

Science.gov (United States)

Houck, Noreen M; Colbert, Alison M

Workplace bullying is strongly associated with negative nursing outcomes, such as work dissatisfaction, turnover, and intent to leave; however, results of studies examining associations with specific patient safety outcomes are limited or nonspecific. This integrative review explores and synthesizes the published articles that address the impact of workplace nurse bullying on patient safety.

Monitoring and reviewing research reactor safety in Australia

International Nuclear Information System (INIS)

Cairns, R.C.; Greenslade, G.K.

1990-01-01

Th research reactors operated by the Australian Nuclear Science and Technology Organization (ANSTO) comprise the 10 MW reactor HIFAR and the 100 kW reactor Moata. Although there are no power reactors in Australia the problems and issues of public concern which arise in the operation of research reactors are similar to those of power reactors although on a smaller scale. The need for independent safety surveillance has been recognized by the Australian Government and the ANSTO Act, 1987, required the Board of ANSTO to establish a Nuclear Safety Bureau (NSB) with responsibility to the Minister for monitoring and reviewing the safety of nuclear plant operated by ANSTO. The Executive Director of ANSTO operates HIFAR subject to compliance with requirements and arrangements contained in a formal Authorization from the Board of ANSTO. A Ministerial Direction to the Board of ANSTO requires the NSB to report to him, on a quarterly basis, matters relating to its functions of monitoring and reviewing the safety of ANSTO's nuclear plant. Experience has shown that the Authorization provides a suitable framework for the operational requirements and arrangements to be organised in a disciplined and effective manner, and also provides a basis for audits by the NSB by which compliance with the Board's safety requirements are monitored. Examples of the way in which the NSB undertakes its monitoring and reviewing role are given. Moata, which has a much lower operating power level and fission product inventory than HIFAR, has not been subject to a formal Authorization to date but one is under preparation

International Nuclear Officials Discuss IAEA Peer Reviews of Nuclear Safety Regulations

International Nuclear Information System (INIS)

2011-01-01

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

Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

International Nuclear Information System (INIS)

Wilmot, Roger D.

2011-02-01

The workshop described here was organised to address more general issues regarding regulatory review of SKB's safety assessment and overall review strategy. The objectives of the workshop were: - to learn from other programmes' experiences on planning and review of a license application for a nuclear waste repository, - to offer newly employed SSM staff an opportunity to learn more about selected safety assessment issues, and - to identify and document recommendations and ideas for SSM's further planning of the licensing review

Healthcare Staff Wellbeing, Burnout, and Patient Safety: A Systematic Review

Science.gov (United States)

Hall, Louise H.; Johnson, Judith; Watt, Ian; Tsipa, Anastasia; O’Connor, Daryl B.

2016-01-01

Objective To determine whether there is an association between healthcare professionals’ wellbeing and burnout, with patient safety. Design Systematic research review. Data Sources PsychInfo (1806 to July 2015), Medline (1946 to July 2015), Embase (1947 to July 2015) and Scopus (1823 to July 2015) were searched, along with reference lists of eligible articles. Eligibility Criteria for Selecting Studies Quantitative, empirical studies that included i) either a measure of wellbeing or burnout, and ii) patient safety, in healthcare staff populations. Results Forty-six studies were identified. Sixteen out of the 27 studies that measured wellbeing found a significant correlation between poor wellbeing and worse patient safety, with six additional studies finding an association with some but not all scales used, and one study finding a significant association but in the opposite direction to the majority of studies. Twenty-one out of the 30 studies that measured burnout found a significant association between burnout and patient safety, whilst a further four studies found an association between one or more (but not all) subscales of the burnout measures employed, and patient safety. Conclusions Poor wellbeing and moderate to high levels of burnout are associated, in the majority of studies reviewed, with poor patient safety outcomes such as medical errors, however the lack of prospective studies reduces the ability to determine causality. Further prospective studies, research in primary care, conducted within the UK, and a clearer definition of healthcare staff wellbeing are needed. Implications This review illustrates the need for healthcare organisations to consider improving employees’ mental health as well as creating safer work environments when planning interventions to improve patient safety. Systematic Review Registration PROSPERO registration number: CRD42015023340. PMID:27391946

Nuclear Safety: Technical progress review, January--March 1989

Energy Technology Data Exchange (ETDEWEB)

Silver, E. G. [ed.

1989-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M., E-mail: ottoncf@tecnatom.com.br, E-mail: emfreire46@gmail.com, E-mail: robcrepaldi@hotmail.com [Tecnatom do Brasil Engenharia e Servicos Ltda, Rio de Janeiro, RJ (Brazil); Campello, Sergio A., E-mail: sacampe@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

2015-07-01

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)

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)

Use of FPGA and CPLD in nuclear reactor safety systems and its regulatory review requirements for reactor safety

International Nuclear Information System (INIS)

Roy, Suvadip; Biswas, Animesh; Pradhan, S.K.

2015-01-01

Field Programmable Gate Arrays (FPGA) and Complex Programmable Logic Devices (CPLD) is being used widely in safety critical and safety related systems in nuclear power plans like in trip logic units, Engineered Safety Feature (ESF) actuation decision logic and neutronic signal processing for their reprogrammability feature and compact design. These HDL Programmable devices (HPD) are complex devices consisting of both hardware and software which is used to implement the logic on the FPGA. It is observed that these Programmable devices suffer from various modes of failure and the major failures in these devices are due to Single Event Upset (SEU), where a highly energetic ionizing radiation may lead to device failure which can even occur in radiologically benign environment. Other failures can occur during steps of developing the hardware using software tools like during Synthesis and placement and routing of the desired hardware. Here a study on use of such devices in Nuclear Reactors, study on mode of failures of these devices, way to tackle such failure and development of review guidelines for review of such devices used in safety critical and safety related systems with special emphasis on choice of software tools, way to mitigate effects of SEU and simulation and hardware testing results to be reviewed by regulatory body during design safety review is done. (author)

SKI's and SSI's review of SKB's safety report SR-Can

International Nuclear Information System (INIS)

Dverstorp, Bjoern; Stroemberg, Bo

2008-03-01

This report summarises SKI's and SSI's joint review of the Swedish Nuclear Fuel and Waste Management Co's (SKB) safety report SR-Can (SKB TR-06-09). SR-Can is the first assessment of post-closure safety for a KBS-3 spent nuclear fuel repository at the candidate sites Forsmark and Laxemar, respectively. The analysis builds on data from the initial stage of SKB's surface-based site investigations and on data from full-scale manufacturing and testing of buffer and copper canisters. SR-Can can be regarded as a preliminary version of the safety report that will be required in connection with SKB's planned licence application for a final repository in late 2009. The main purpose of the authorities' review is to provide feedback to SKB on their safety reporting as part of the pre-licensing consultation process. However, SR-Can is not part of the formal licensing process. In support of the authorities' review three international peer review teams were set up to make independent reviews of SR-Can from three perspectives, namely integration of site data, representation of the engineered barriers and safety assessment methodology, respectively. Further, several external experts and consultants have been engaged to review detailed technical and scientific issues in SR-Can. The municipalities of Oesthammar and Oskarshamn where SKB is conducting site investigations, as well NGOs involved in SKB's programme, have been invited to provide their views on SR-Can as input to the authorities' review. Finally, the authorities themselves, and with the help of consultants, have used independent models to reproduce part of SKB's calculations and to make complementary calculations. All supporting review documents are published in SKI's and SSI's report series. The main findings of the review are: -SKB's safety assessment methodology is overall in accordance with applicable regulations, but part of the methodology needs to be further developed for the licence application. -SKB's quality

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

Fuel safety criteria and review by OECD / CSNI task force

International Nuclear Information System (INIS)

Van Doesburg, W.

1999-01-01

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

Economic evaluation in patient safety: a literature review of methods.

Science.gov (United States)

de Rezende, Bruna Alves; Or, Zeynep; Com-Ruelle, Laure; Michel, Philippe

2012-06-01

Patient safety practices, targeting organisational changes for improving patient safety, are implemented worldwide but their costs are rarely evaluated. This paper provides a review of the methods used in economic evaluation of such practices. International medical and economics databases were searched for peer-reviewed publications on economic evaluations of patient safety between 2000 and 2010 in English and French. This was complemented by a manual search of the reference lists of relevant papers. Grey literature was excluded. Studies were described using a standardised template and assessed independently by two researchers according to six quality criteria. 33 articles were reviewed that were representative of different patient safety domains, data types and evaluation methods. 18 estimated the economic burden of adverse events, 3 measured the costs of patient safety practices and 12 provided complete economic evaluations. Healthcare-associated infections were the most common subject of evaluation, followed by medication-related errors and all types of adverse events. Of these, 10 were selected that had adequately fulfilled one or several key quality criteria for illustration. This review shows that full cost-benefit/utility evaluations are rarely completed as they are resource intensive and often require unavailable data; some overcome these difficulties by performing stochastic modelling and by using secondary sources. Low methodological transparency can be a problem for building evidence from available economic evaluations. Investing in the economic design and reporting of studies with more emphasis on defining study perspectives, data collection and methodological choices could be helpful for strengthening our knowledge base on practices for improving patient safety.

78 FR 25476 - Meeting of the Public Safety Officer Medal of Valor Review Board

Science.gov (United States)

2013-05-01

... Safety Officer Medal of Valor Review Board AGENCY: Bureau of Justice Assistance (BJA), Department of...) of the Public Safety Officer Medal of Valor Review Board to consider a range of issues of [email protected] . SUPPLEMENTARY INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out...

77 FR 26790 - Meeting of the Public Safety Officer Medal of Valor Review Board

Science.gov (United States)

2012-05-07

... Safety Officer Medal of Valor Review Board AGENCY: Office of Justice Programs (OJP), Bureau of Justice... meeting (via conference call-in) of the Public Safety Officer Medal of Valor Review Board (``Board'') to... INFORMATION: The Public Safety Officer Medal of Valor Review Board carries out those advisory functions...

SRTC criticality safety technical review: Nuclear Criticality Safety Evaluation 93-04 enriched uranium receipt

International Nuclear Information System (INIS)

Rathbun, R.

1993-01-01

Review of NMP-NCS-930087, open-quotes Nuclear Criticality Safety Evaluation 93-04 Enriched Uranium Receipt (U), July 30, 1993, close quotes was requested of SRTC (Savannah River Technology Center) Applied Physics Group. The NCSE is a criticality assessment to determine the mass limit for Engineered Low Level Trench (ELLT) waste uranium burial. The intent is to bury uranium in pits that would be separated by a specified amount of undisturbed soil. The scope of the technical review, documented in this report, consisted of (1) an independent check of the methods and models employed, (2) independent HRXN/KENO-V.a calculations of alternate configurations, (3) application of ANSI/ANS 8.1, and (4) verification of WSRC Nuclear Criticality Safety Manual procedures. The NCSE under review concludes that a 500 gram limit per burial position is acceptable to ensure the burial site remains in a critically safe configuration for all normal and single credible abnormal conditions. This reviewer agrees with that conclusion

Guide for reviewing safety analysis reports for packaging: Review of quality assurance requirements

International Nuclear Information System (INIS)

Moon, D.W.

1988-10-01

This review section describes quality assurance requirements applying to design, purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, and modification of components of packaging which are important to safety. The design effort, operation's plans, and quality assurance requirements should be integrated to achieve a system in which the independent QA program is not overly stringent and the application of QA requirements is commensurate with safety significance. The reviewer must verify that the applicant's QA section in the SARP contains package-specific QA information required by DOE Orders and federal regulations that demonstrate compliance. 8 refs

Nuclear Fuel Safety Criteria Technical Review - Second edition

International Nuclear Information System (INIS)

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

2012-01-01

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

Safety review on unit testing of safety system software of nuclear power plant

International Nuclear Information System (INIS)

Liu Le; Zhang Qi

2013-01-01

Software unit testing has an important place in the testing of safety system software of nuclear power plants, and in the wider scope of the verification and validation. It is a comprehensive, systematic process, and its documentation shall meet the related requirements. When reviewing software unit testing, attention should be paid to the coverage of software safety requirements, the coverage of software internal structure, and the independence of the work. (authors)

Integrated Plant Safety Assessment, Systematic Evaluation Program: Yankee Nuclear Power Station (Docket No. 50-29)

International Nuclear Information System (INIS)

1987-10-01

The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0825), under the scope of the Systematic Evaluation Program (SEP), for Yankee Atomic Electric Company's Yankee Nuclear Power Station located in Rowe, Massachusetts. The SEP was initiated by the NRC to review the design of older operating nuclear power plants to reconfirm and document their safety. This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Yankee plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when Yankee was licensed, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. 2 tabs

Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

Energy Technology Data Exchange (ETDEWEB)

Wilmot, Roger D. (Galson Sciences Limited (United Kingdom))

2011-02-15

The workshop described here was organised to address more general issues regarding regulatory review of SKB's safety assessment and overall review strategy. The objectives of the workshop were: - to learn from other programmes' experiences on planning and review of a license application for a nuclear waste repository, - to offer newly employed SSM staff an opportunity to learn more about selected safety assessment issues, and - to identify and document recommendations and ideas for SSM's further planning of the licensing review

Integrated Plant Safety Assessment, Systematic Evaluation Program, Palisades Plant (Docket No. 50-255)

International Nuclear Information System (INIS)

1983-11-01

This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Palisades Plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when the Palisades Plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when the supplement to the Final IPSAR and the Safety Evaluation Report for converting the license from a provisional to a full-term license have been issued. The Final IPSAR and its supplement will form part of the bases for considering the conversion of the provisional operating license to a full-term operating license

Safety review for human factors engineering and control rooms of nuclear power plants

International Nuclear Information System (INIS)

Yang Mengzhuo

1998-01-01

Safety review for human factors engineering and control rooms of nuclear power plants (NPP) is in a forward position of science and technology, which began at American TMI severe accident and had been implemented in China. The importance and the significance of the safety review are expounded, the requirements of its scope and profundity are explained in detail. In addition, the situation of the technical document system for nuclear safety regulation on human factors engineering and control rooms of NPP in China is introduced briefly, on which the safety review is based

Regulatory system reform of occupational health and safety in China.

Science.gov (United States)

Wu, Fenghong; Chi, Yan

2015-01-01

With the explosive economic growth and social development, China's regulatory system of occupational health and safety now faces more and more challenges. This article reviews the history of regulatory system of occupational health and safety in China, as well as the current reform of this regulatory system in the country. Comprehensive, a range of laws, regulations and standards that promulgated by Chinese government, duties and responsibilities of the regulatory departments are described. Problems of current regulatory system, the ongoing adjustments and changes for modifying and improving regulatory system are discussed. The aim of reform and the incentives to drive forward more health and safety conditions in workplaces are also outlined.

The periodic safety review of nuclear power plants. Practices in OECD countries

International Nuclear Information System (INIS)

1992-01-01

This report gives an overview of the regulatory concepts and practices for the periodic safety review of nuclear power plants in OECD countries with nuclear power programmes. The statutory bases for such reviews, their objectives and the processes adopted are summarised against the background of each country's regulatory practices. Although periodic safety reviews are now, or will soon be, part of the regulatory process in the majority of countries, the national approaches to these reviews still differ considerably. This report includes numerous examples of the different concepts and practices in OECD countries, thereby illustrating the variety of ways adopted to reach the common goal of maintaining and improving nuclear safety

29 CFR 2200.108 - Official Seal of the Occupational Safety and Health Review Commission.

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false Official Seal of the Occupational Safety and Health Review... Occupational Safety and Health Review Commission. The seal of the Commission shall consist of: A gold eagle... background, encircled by a white band edged in black and inscribed “Occupational Safety and Health Review...

IAEA Operational Safety Team Reviews Saint-Alban Nuclear Power Plant, France

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed safety practices at France's Saint-Alban Nuclear Power Plant (NPP) and has highlighted a set of strong practices as well as a series of recommendations to reinforce them. The IAEA assembled the team at the request of the Government of France to conduct an Operational Safety Review (OSART) of the Saint-Alban NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review from 20 September to 6 October 2010. The team was made up of experts from Belgium, Canada, the Czech Republic, Germany, Lithuania, the Netherlands, Slovakia, Sweden and the USA. An OSART mission is designed to review programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at Saint-Alban conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely are under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; and Emergency Planning and Preparedness. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: A safety guideline for outages; The use of remote video surveillance of fuel inspection and handling activities; A motivational tool for plant staff regarding the benefits of operating experience and associated corrective actions; and Use of a sophisticated key control system

IAEA Operational Safety Team Review Bohunice Nuclear Power Plant, Slovak Republic

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed Slovakia's Bohunice Nuclear Power Plant (BNPP) for its safety practices and has noted a series of good practices as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of Slovak Republic to conduct an Operational Safety Review (OSART) of Bohunice NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 1 to 18 November 2010. The team was made up of experts from Belgium, Canada, China, the Czech Republic, France, Sweden, the United Kingdom and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at BNPP conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely is under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. Long Term Operation assessment has been requested by the plant in addition to the standard OSART program. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: BNPP has implemented a comprehensive set of technical and organizational measures which have significantly reduced the production of liquid radioactive waste; BNPP has developed an automatic transfer of dosimetry data

Effect of electronic device use on pedestrian safety : a literature review.

Science.gov (United States)

2016-04-01

This literature review on the effect of electronic device use on pedestrian safety is part of a research project sponsored by the Office of Behavioral Safety Research in the National Highway Traffic Safety Administration (NHTSA). An extensive literat...

Reactor safety review of permanent changes

International Nuclear Information System (INIS)

Lam, K.F.

1997-01-01

Operational compliance engineers review all changes as part of a change control process. Each change, permanent or temporary, is required to undergo an intricate review process to ensure that the benefits associated with the change outweigh the risk. For permanent changes, it is necessary to ensure that the proposed design meets the nuclear safety requirements, conforms to the licensing requirements and complies with regulatory requirements. In addition, during installation of the permanent change and prior to in-service, a configuration management process is in place to align the change with operating and maintenance documents. (author)

Uncertain safety: allocating responsibilities for safety

National Research Council Canada - National Science Library

2009-01-01

Flood prevention, food safety, the transport of hazardous substances, infectious diseases, the risk of new Technologies and many other threats to public health and the environment call for ongoing public alertness...

Nuclear Safety: Volume 29, No. 3: Technical progress review

Energy Technology Data Exchange (ETDEWEB)

Silver, E G [ed.

1988-07-01

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

SCART guidelines. Reference report for IAEA Safety Culture Assessment Review Team (SCART)

International Nuclear Information System (INIS)

2008-01-01

The IAEA Director General stressed the role of safety culture in his concluding remarks at the Meeting of the Contracting Parties to the Convention on Nuclear Safety in 2002: 'As we have learned in other areas, it is not enough simply to have a structure; it is not enough to say that we have the necessary laws and the appropriate regulatory bodies. All these are important, but equally important is that we have in place a safety culture that gives effect to the structure that we have developed. To me, effectiveness and transparency are keys. So, it is an issue which I am pleased to see, you are giving the attention it deserves and we will continue to work with you in clarifying, developing and applying safety culture through our programmes and through our technical cooperation activities.' The concept of safety culture was initially developed by the International Nuclear Safety Advisory Group (INSAG) after the Chernobyl accident in 1986. Since then the IAEA's perspective of safety culture has expanded with time as its recognition of the complexities of the concept developed. Safety culture is considered to be specific organizational culture in all types of organizations with activities that give rise to radiation risks. The aim is to make safety culture strong and sustainable, so that safety becomes a primary focus for all activities in such organizations, even for those, which might not look safety-related at first. SCART (Safety Culture Assessment Review Team) is a safety review service, which reflects the expressed interest of Members States for methods and tools for safety culture assessment. It is a replacement for the earlier service ASCOT (Assessment of Safety Culture in Organizations Team). The IAEA Safety Fundamentals, Requirements and Guides (Safety Standards) are the basis for the SCART Safety Review Service. The reports of INSAG, identifying important current nuclear safety issues, serve also as references during a SCART mission. SCART missions are based

The work of the Operational Safety Review Team (OSART)

International Nuclear Information System (INIS)

Hide, K.W.

1996-01-01

The Operational Safety Review Team (OSART) programme was set up by the IAEA in 1982 to assist Member States to enhance the operational safety of nuclear power plants. Each team is staffed by senior experts in the relevant fields. The review team discusses with plant staff the existing operational programmes for plant which may be under construction, being commissioned or already operating. Following a detailed examination of a safety programme, the OSART team lists strengths and weaknesses and makes recommendations on how to overcome the latter. Since their conclusions are based on the best prevailing international practice, they may be more stringent than those based on national criteria. The results of the 77 missions conducted at 62 plants in 28 countries by the end of 1994 are summarised. (UK)

Russian Minatom nuclear safety research strategic plan. An international review

International Nuclear Information System (INIS)

Royen, J.

1999-01-01

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

Healthcare Staff Wellbeing, Burnout, and Patient Safety: A Systematic Review.

Science.gov (United States)

Hall, Louise H; Johnson, Judith; Watt, Ian; Tsipa, Anastasia; O'Connor, Daryl B

2016-01-01

To determine whether there is an association between healthcare professionals' wellbeing and burnout, with patient safety. Systematic research review. PsychInfo (1806 to July 2015), Medline (1946 to July 2015), Embase (1947 to July 2015) and Scopus (1823 to July 2015) were searched, along with reference lists of eligible articles. Quantitative, empirical studies that included i) either a measure of wellbeing or burnout, and ii) patient safety, in healthcare staff populations. Forty-six studies were identified. Sixteen out of the 27 studies that measured wellbeing found a significant correlation between poor wellbeing and worse patient safety, with six additional studies finding an association with some but not all scales used, and one study finding a significant association but in the opposite direction to the majority of studies. Twenty-one out of the 30 studies that measured burnout found a significant association between burnout and patient safety, whilst a further four studies found an association between one or more (but not all) subscales of the burnout measures employed, and patient safety. Poor wellbeing and moderate to high levels of burnout are associated, in the majority of studies reviewed, with poor patient safety outcomes such as medical errors, however the lack of prospective studies reduces the ability to determine causality. Further prospective studies, research in primary care, conducted within the UK, and a clearer definition of healthcare staff wellbeing are needed. This review illustrates the need for healthcare organisations to consider improving employees' mental health as well as creating safer work environments when planning interventions to improve patient safety. PROSPERO registration number: CRD42015023340.

Patient participation in patient safety and nursing input - a systematic review.

Science.gov (United States)

Vaismoradi, Mojtaba; Jordan, Sue; Kangasniemi, Mari

2015-03-01

This systematic review aims to synthesise the existing research on how patients participate in patient safety initiatives. Ambiguities remain about how patients participate in routine measures designed to promote patient safety. Systematic review using integrative methods. Electronic databases were searched using keywords describing patient involvement, nursing input and patient safety initiatives to retrieve empirical research published between 2007 and 2013. Findings were synthesized using the theoretical domains of Vincent's framework for analysing risk and safety in clinical practice: "patient", "healthcare provider", "task", "work environment", "organisation & management". We identified 17 empirical research papers: four qualitative, one mixed-method and 12 quantitative designs. All 17 papers indicated that patients can participate in safety initiatives. Improving patient participation in patient safety necessitates considering the patient as a person, the nurse as healthcare provider, the task of participation and the clinical environment. Patients' knowledge, health conditions, beliefs and experiences influence their decisions to engage in patient safety initiatives. An important component of the management of long-term conditions is to ensure that patients have sufficient knowledge to participate. Healthcare providers may need further professional development in patient education and patient care management to promote patient involvement in patient safety, and ensure that patients understand that they are 'allowed' to inform nurses of adverse events or errors. A healthcare system characterised by patient-centredness and mutual acknowledgement will support patient participation in safety practices. Further research is required to improve international knowledge of patient participation in patient safety in different disciplines, contexts and cultures. Patients have a significant role to play in enhancing their own safety while receiving hospital care. This

The occupational health and safety of flight attendants.

Science.gov (United States)

Griffiths, Robin F; Powell, David M C

2012-05-01

In order to perform safety-critical roles in emergency situations, flight attendants should meet minimum health standards and not be impaired by factors such as fatigue. In addition, the unique occupational and environmental characteristics of flight attendant employment may have consequential occupational health and safety implications, including radiation exposure, cancer, mental ill-health, musculoskeletal injury, reproductive disorders, and symptoms from cabin air contamination. The respective roles of governments and employers in managing these are controversial. A structured literature review was undertaken to identify key themes for promoting a future agenda for flight attendant health and safety. Recommendations include breast cancer health promotion, implementation of Fatigue Risk Management Systems, standardization of data collection on radiation exposure and health outcomes, and more coordinated approaches to occupational health and safety risk management. Research is ongoing into cabin air contamination incidents, cancer, and fatigue as health and safety concerns. Concerns are raised that statutory medical certification for flight attendants will not benefit either flight safety or occupational health.

A LITERATURE REVIEW ON GLOBAL OCCUPATIONAL SAFETY AND HEALTH PRACTICE & ACCIDENTS SEVERITY

Directory of Open Access Journals (Sweden)

Kassu Jilcha

2016-06-01

Full Text Available This literature review focuses on researches undertaken since 1980s onwards. The purpose of the study is to identify existing gaps on workplace safety and health management and propose future research areas. The review adds value to existing electronic database through integration of researches' results. To identify existing gaps, a systematic literature review approach has been used. The reviews were undertaken through keywords and safety related topics. In the literature, various characteristics of workplace safety and health problems were found emanating from the lack of operational activities of the employees, internal working environment and external environment those impose hazards on employee temporarily, permanently and on working environments. The integration of multidisciplinary approaches and collaborative model of hub and peripheral industries to protect workplace safety hazards to develop multilevel model has been undermined in many researches. The other face of finding is that knowledge transfer mechanism and industrial topology factors are left. Some researches finding showed that they have focused on single problems related to health and health factors leaving universal improving workplace safety. In general, this literature reviews compare various studies output based on their research method and findings to fills gap and add value to a body of knowledge.

Second review meeting of the Contracting Parties to the Convention on Nuclear Safety

International Nuclear Information System (INIS)

Rafferty, Barbara

2002-01-01

The Second Review Meeting of the Contracting Parties to the Convention on Nuclear Safety was held in the Headquarters of the International Atomic Energy Agency in Vienna from 15-26 April 2002, under the chairmanship of the President, Mr Miroslav Gregoric, Director of the Slovenian Nuclear Safety Authority. The Convention on Nuclear Safety entered into force in October 1996, has been signed by sixty-five States and ratified by fifty-four, bringing within its scope 428 of the 448 nuclear reactors worldwide. The Convention aims to achieve and maintain a high level of nuclear safety worldwide, through inter alia enhancement of national measures and international co-operation. Obligations on Contracting Parties in accordance with the Convention include: the establishment and maintenance of a legislative and regulatory framework to govern the safety of land-based civil nuclear installations; the allocation of adequate financial and human resources to support the safety objectives; ensuring that all reasonably practicable improvements to safety are made as a matter of urgency. Adherence to this Convention entails two basic commitments by each Contracting Party: to prepare and make available a national report for review; and to subject its national report to a peer review by the other Contracting Parties. Thus, being a Contracting Party to this Convention involves: including in the national report a self-assessment of steps and measures already taken and in progress to implement the Convention obligations; taking an active part in an open and transparent review of its national report and the Reports of other Contracting Parties; and a commitment to a continuous learning and improving process, something which is a key element of a strong safety culture. The peer review of national reports takes place every three years, the first having been held in 1999. The Second Review Meeting was attended by delegates from 46 contracting parties. During the review certain issues were

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

A review of the nuclear safety activities in Italy

International Nuclear Information System (INIS)

Merelli, A.

1989-01-01

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

Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings

Energy Technology Data Exchange (ETDEWEB)

DiSabatino, A; Biswas, D; DeMicco, M; Fisher, L E; Hafner, R; Haslam, J; Mok, G; Patel, C; Russell, E

2007-04-12

This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE Order 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his or her review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. This PRG is generally organized at the section level in a format similar to that recommended in Regulatory Guide 7.9 (RG 7.9). One notable exception is the addition of Section 9 (Quality Assurance), which is not included as a separate chapter in RG 7.9. Within each section, this PRG addresses the technical and regulatory bases for the review, the manner in which the review is accomplished, and findings that are generally applicable for a package that meets the approval standards. This Packaging Review Guide (PRG) provides guidance for DOE review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE O 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. The primary objectives of this PRG are to: (1) Summarize the regulatory requirements for package approval; (2) Describe the technical review procedures by which DOE determines that these requirements have been satisfied; (3) Establish and maintain the quality and uniformity of reviews; (4) Define the base from which to evaluate proposed changes in scope

Survey of systems safety analysis methods and their application to nuclear waste management systems

International Nuclear Information System (INIS)

Pelto, P.J.; Winegardner, W.K.; Gallucci, R.H.V.

1981-11-01

This report reviews system safety analysis methods and examines their application to nuclear waste management systems. The safety analysis methods examined include expert opinion, maximum credible accident approach, design basis accidents approach, hazard indices, preliminary hazards analysis, failure modes and effects analysis, fault trees, event trees, cause-consequence diagrams, G0 methodology, Markov modeling, and a general category of consequence analysis models. Previous and ongoing studies on the safety of waste management systems are discussed along with their limitations and potential improvements. The major safety methods and waste management safety related studies are surveyed. This survey provides information on what safety methods are available, what waste management safety areas have been analyzed, and what are potential areas for future study

Survey of systems safety analysis methods and their application to nuclear waste management systems

Energy Technology Data Exchange (ETDEWEB)

Pelto, P.J.; Winegardner, W.K.; Gallucci, R.H.V.

1981-11-01

This report reviews system safety analysis methods and examines their application to nuclear waste management systems. The safety analysis methods examined include expert opinion, maximum credible accident approach, design basis accidents approach, hazard indices, preliminary hazards analysis, failure modes and effects analysis, fault trees, event trees, cause-consequence diagrams, G0 methodology, Markov modeling, and a general category of consequence analysis models. Previous and ongoing studies on the safety of waste management systems are discussed along with their limitations and potential improvements. The major safety methods and waste management safety related studies are surveyed. This survey provides information on what safety methods are available, what waste management safety areas have been analyzed, and what are potential areas for future study.

Healthcare Staff Wellbeing, Burnout, and Patient Safety: A Systematic Review.

Directory of Open Access Journals (Sweden)

Louise H Hall

Full Text Available To determine whether there is an association between healthcare professionals' wellbeing and burnout, with patient safety.Systematic research review.PsychInfo (1806 to July 2015, Medline (1946 to July 2015, Embase (1947 to July 2015 and Scopus (1823 to July 2015 were searched, along with reference lists of eligible articles.Quantitative, empirical studies that included i either a measure of wellbeing or burnout, and ii patient safety, in healthcare staff populations.Forty-six studies were identified. Sixteen out of the 27 studies that measured wellbeing found a significant correlation between poor wellbeing and worse patient safety, with six additional studies finding an association with some but not all scales used, and one study finding a significant association but in the opposite direction to the majority of studies. Twenty-one out of the 30 studies that measured burnout found a significant association between burnout and patient safety, whilst a further four studies found an association between one or more (but not all subscales of the burnout measures employed, and patient safety.Poor wellbeing and moderate to high levels of burnout are associated, in the majority of studies reviewed, with poor patient safety outcomes such as medical errors, however the lack of prospective studies reduces the ability to determine causality. Further prospective studies, research in primary care, conducted within the UK, and a clearer definition of healthcare staff wellbeing are needed.This review illustrates the need for healthcare organisations to consider improving employees' mental health as well as creating safer work environments when planning interventions to improve patient safety.PROSPERO registration number: CRD42015023340.

Regulatory system reform of occupational health and safety in China

Science.gov (United States)

WU, Fenghong; CHI, Yan

2015-01-01

With the explosive economic growth and social development, China’s regulatory system of occupational health and safety now faces more and more challenges. This article reviews the history of regulatory system of occupational health and safety in China, as well as the current reform of this regulatory system in the country. Comprehensive, a range of laws, regulations and standards that promulgated by Chinese government, duties and responsibilities of the regulatory departments are described. Problems of current regulatory system, the ongoing adjustments and changes for modifying and improving regulatory system are discussed. The aim of reform and the incentives to drive forward more health and safety conditions in workplaces are also outlined. PMID:25843565

Comprehensive review of the maritime safety regimes.

NARCIS (Netherlands)

S. Knapp (Sabine); Ph.H.B.F. Franses (Philip Hans)

2007-01-01

textabstractThis report presents a comprehensive review of the maritime safety regimes and provides recommendations on how to improve the system. The results show a complex legal framework which generates a high amount of inspections and overlapping of inspection areas where no cross-recognition is

SRTC criticality safety technical review of SRT-CMA-930039

International Nuclear Information System (INIS)

Rathbun, R.

1993-01-01

Review of SRT-CMA-930039, ''Nuclear Criticality Safety Evaluation (NCSE): DWPF Melter-Batch 1,'' December 1, 1993, has been performed by the Savannah River Technical Center (SRTC) Applied Physics Group. The NCSE is a criticality assessment of the Melt Cell in the DWPF. Additionally, this pertains only to Batch 1 operation, which differs from batches to follow. Plans for subsequent batch operations call for fissile material in the Salt Cell feed-stream, which necessitates a separate criticality evaluation in the future. The NCSE under review concludes that the process is safe from criticality events, even in the event that all lithium and boron neutron poisons are lost, provided uranium enrichments are less than 40%. Furthermore, if all the lithium and as much as 98% of the boron would be lost, uranium enrichments of 100% would be allowable. After a thorough review of the NCSE, this reviewer agrees with that conclusion. This technical review consisted of: an independent check of the methods and models employed, independent calculations application of ANSI/ANS 8.1, verification of WSRC Nuclear Criticality Safety Manual( 2 ) procedures

Plant safety review from mass criticality accident

International Nuclear Information System (INIS)

Susanto, B.G.

2000-01-01

The review has been done to understand the resent status of the plant in facing postulated mass criticality accident. From the design concept of the plant all the components in the system including functional groups have been designed based on favorable mass/geometry safety principle. The criticality safety for each component is guaranteed because all the dimensions relevant to criticality of the components are smaller than dimensions of 'favorable mass/geometry'. The procedures covering all aspects affecting quality including the safety related are developed and adhered to at all times. Staff are indoctrinated periodically in short training session to warn the important of the safety in process of production. The plant is fully equipped with 6 (six) criticality detectors in strategic places to alert employees whenever the postulated mass criticality accident occur. In the event of Nuclear Emergency Preparedness, PT BATAN TEKNOLOGI has also proposed the organization structure how promptly to report the crisis to Nuclear Energy Control Board (BAPETEN) Indonesia. (author)

Tank waste remediation system nuclear criticality safety program management review

International Nuclear Information System (INIS)

BRADY RAAP, M.C.

1999-01-01

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

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

Science.gov (United States)

Boyd, Douglas D

2017-07-01

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

International experts conclude IAEA peer review of Iran's safety regulation of Bushehr NPP

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear safety experts today completed an IAEA mission to review the effectiveness of Iran's safety regulation of its first nuclear power plant and to identify possible improvements before the plant begins operation. Upon invitation of the Islamic Republic of Iran, the International Atomic Energy Agency (IAEA) assembled a team of senior regulators from seven Member States for an Integrated Regulatory Review Service (IRRS) mission. The scope of the mission was limited to the safety regulation of Bushehr nuclear power plant (BNPP-1). The IRRS review took place from 20 February to 2 March at the INRA offices in Tehran and included a technical visit to the BNPP-1 site. The mission was an objective peer review based on IAEA safety standards, and was neither an inspection, nor an audit. Ms. Olena Mykolaichuk, IRRS Team Leader and Head of the State Nuclear Regulatory Committee of Ukraine, commended her INRA counterparts: 'The regulatory work performed on the Bushehr construction and in preparation for commissioning has demonstrated significant progress of INRA as a nuclear regulatory authority,' she said. Philippe Jamet, Director of the IAEA's Nuclear Installation Safety Division, added: 'Through this IRRS mission, both Iran and the international experts contribute to the enhancement of nuclear safety and worldwide experience sharing.' In the course of its review the IRRS team identified the following strengths: - INRA has a dedicated, conscientious staff, demonstrating clear commitments to further improvements. - INRA clearly recognizes the value of peer reviews and international cooperation regarding nuclear safety. - Despite a shortage of staff, INRA demonstrated strong leadership while performing both review and assessment and inspection tasks during the BNPP-1 construction and pre-commissioning. - INRA has developed an excellent computerized documentation control system. Recommendations and suggestions to improve INRA's regulatory

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2001-01-01

This publication supports the Safety Requirements on the Safety of Nuclear Power Plants: Design. This Safety Guide was prepared on the basis of a systematic review of all the relevant publications including the Safety Fundamentals, Safety of Nuclear Power Plants: Design, current and ongoing revisions of other Safety Guides, INSAG reports and other publications that have addressed the safety of nuclear power plants. This Safety Guide also provides guidance for Contracting Parties to the Convention on Nuclear Safety in meeting their obligations under Article 14 on Assessment and Verification of Safety. The Safety Requirements publication entitled Safety of Nuclear Power Plants: Design states that a comprehensive safety assessment and an independent verification of the safety assessment shall be carried out before the design is submitted to the regulatory body. This publication provides guidance on how this requirement should be met. This Safety Guide provides recommendations to designers for carrying out a safety assessment during the initial design process and design modifications, as well as to the operating organization in carrying out independent verification of the safety assessment of new nuclear power plants with a new or already existing design. The recommendations for performing a safety assessment are suitable also as guidance for the safety review of an existing plant. The objective of reviewing existing plants against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The methods and the recommendations of this Safety Guide can also be used by regulatory bodies for the conduct of the regulatory review and assessment. Although most recommendations of this Safety Guide are general and applicable to all types of nuclear reactors, some specific recommendations and examples apply mostly to water cooled reactors. Terms such as 'safety assessment', 'safety analysis' and 'independent

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

International Nuclear Information System (INIS)

Frescura, G.

2001-01-01

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

OSART Guidelines. 2015 Edition. Reference Report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2016-01-01

The IAEA works to provide a global nuclear safety and security framework for the protection of people and the environment from the effects of ionizing radiation, the minimization of the likelihood of accidents that could endanger life and property, and effective mitigation of the effects of any such events, should they occur. The strategic approach to achieving such a framework involves continual improvement in four areas: national and international safety infrastructures; the establishment and global acceptance of IAEA safety standards; an integrated approach to the provision for the application of the safety standards; and a global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. Conservative design, careful manufacture and sound construction are all prerequisites for the safe operation of nuclear power plants. However, the safety of the plant also depends ultimately on: sound management, policies, procedures, processes and practices; the capability and reliability of commissioning and operating personnel; comprehensive instructions; sound accident management and emergency preparedness; and adequate resources. Finally, a positive attitude and conscientiousness on the part of all staff in discharging their responsibilities is important to safety. The OSART programme is based on the safety standards applicable to nuclear power plants. IAEA safety standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Group identify important current nuclear safety issues and also serve as references during an OSART review. The publication OSART Guidelines provides overall guidance on the conduct of OSART

Review of actinide nitride properties with focus on safety aspects

Energy Technology Data Exchange (ETDEWEB)

Albiol, Thierry [CEA Cadarache, St Paul Lez Durance Cedex (France); Arai, Yasuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-12-01

This report provides a review of the potential advantages of using actinide nitrides as fuels and/or targets for nuclear waste transmutation. Then a summary of available properties of actinide nitrides is given. Results from irradiation experiments are reviewed and safety relevant aspects of nitride fuels are discussed, including design basis accidents (transients) and severe (core disruptive) accidents. Anyway, as rather few safety studies are currently available and as many basic physical data are still missing for some actinide nitrides, complementary studies are proposed. (author)

Safety research activities on radioactive waste management in JNES

International Nuclear Information System (INIS)

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

2010-01-01

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

Aviation and healthcare: a comparative review with implications for patient safety.

Science.gov (United States)

Kapur, Narinder; Parand, Anam; Soukup, Tayana; Reader, Tom; Sevdalis, Nick

2016-01-01

Safety in aviation has often been compared with safety in healthcare. Following a recent article in this journal, the UK government set up an Independent Patient Safety Investigation Service, to emulate a similar well-established body in aviation. On the basis of a detailed review of relevant publications that examine patient safety in the context of aviation practice, we have drawn up a table of comparative features and a conceptual framework for patient safety. Convergence and divergence of safety-related behaviours across aviation and healthcare were derived and documented. Key safety-related domains that emerged included Checklists, Training, Crew Resource Management, Sterile Cockpit, Investigation and Reporting of Incidents and Organisational Culture. We conclude that whilst healthcare has much to learn from aviation in certain key domains, the transfer of lessons from aviation to healthcare needs to be nuanced, with the specific characteristics and needs of healthcare borne in mind. On the basis of this review, it is recommended that healthcare should emulate aviation in its resourcing of staff who specialise in human factors and related psychological aspects of patient safety and staff wellbeing. Professional and post-qualification staff training could specifically include Cognitive Bias Avoidance Training, as this appears to play a key part in many errors relating to patient safety and staff wellbeing.

Classification of antecedents towards safety use of health information technology: A systematic review.

Science.gov (United States)

Salahuddin, Lizawati; Ismail, Zuraini

2015-11-01

This paper provides a systematic review of safety use of health information technology (IT). The first objective is to identify the antecedents towards safety use of health IT by conducting systematic literature review (SLR). The second objective is to classify the identified antecedents based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model and an extension of DeLone and McLean (D&M) information system (IS) success model. A systematic literature review (SLR) was conducted from peer-reviewed scholarly publications between January 2000 and July 2014. SLR was carried out and reported based on the preferred reporting items for systematic reviews and meta-analyses (PRISMA) statement. The related articles were identified by searching the articles published in Science Direct, Medline, EMBASE, and CINAHL databases. Data extracted from the resultant studies included are to be analysed based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model, and also from the extended DeLone and McLean (D&M) information system (IS) success model. 55 articles delineated to be antecedents that influenced the safety use of health IT were included for review. Antecedents were identified and then classified into five key categories. The categories are (1) person, (2) technology, (3) tasks, (4) organization, and (5) environment. Specifically, person is attributed by competence while technology is associated to system quality, information quality, and service quality. Tasks are attributed by task-related stressor. Organisation is related to training, organisation resources, and teamwork. Lastly, environment is attributed by physical layout, and noise. This review provides evidence that the antecedents for safety use of health IT originated from both social and technical aspects. However, inappropriate health IT usage potentially increases the incidence of errors and produces new safety risks. The review cautions future

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

Science.gov (United States)

2010-07-01

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

Nuclear health and safety

International Nuclear Information System (INIS)

1991-08-01

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

Idaho National Laboratory Integrated Safety Management System FY 2012 Effectiveness Review and Declaration Report

Energy Technology Data Exchange (ETDEWEB)

Farren Hunt

2012-12-01

Idaho National Laboratory (INL) performed an Annual Effectiveness Review of the Integrated Safety Management System (ISMS), per 48 Code of Federal Regulations (CFR) 970.5223 1, “Integration of Environment, Safety and Health into Work Planning and Execution.” The annual review assessed Integrated Safety Management (ISM) effectiveness, provided feedback to maintain system integrity, and identified target areas for focused improvements and assessments for fiscal year (FY) 2013. Results of the FY 2012 annual effectiveness review demonstrated that the INL’s ISMS program was significantly strengthened. Actions implemented by the INL demonstrate that the overall Integrated Safety Management System is sound and ensures safe and successful performance of work while protecting workers, the public, and environment. This report also provides several opportunities for improvement that will help further strengthen the ISM Program and the pursuit of safety excellence. Demonstrated leadership and commitment, continued surveillance, and dedicated resources have been instrumental in maturing a sound ISMS program. Based upon interviews with personnel, reviews of assurance activities, and analysis of ISMS process implementation, this effectiveness review concludes that ISM is institutionalized and is “Effective”.

75 FR 54915 - Meeting of the Public Safety Officer Medal of Valor Review Board

Science.gov (United States)

2010-09-09

... Safety Officer Medal of Valor Review Board AGENCY: Office of Justice Programs (OJP), Justice. ACTION... Officer Medal of Valor Review Board to vote on recommendations for the 2009-2010 Medal of Valor... Public Safety Officer Medal of Valor Review Board carries out those advisory functions specified in 42 U...

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)

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

International Nuclear Information System (INIS)

2012-01-01

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

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards; - Integrated approach to the provision for the application of safety standards; and - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices; on the capability and reliability of the commissioning and operating personnel; on comprehensive instructions; and on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2007-01-01

The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2008-01-01

The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

SSI and SKI's Review of SKB's Updated Final Safety Report for SFR 1. Review Report

International Nuclear Information System (INIS)

2003-10-01

The Repository for Radioactive Operational Waste (SFR 1) is now the object of a new review by the Swedish Radiation Protection Authority (SSI) and the Swedish Nuclear Power Inspectorate (SKI). One of the stipulations for operating SFR 1 was that a new assessment of the long-term performance and environmental consequences of the repository should be conducted once every 10 years by the licensee, the Swedish Nuclear Fuel and Waste Management Co (SKB). During the time that SFR 1 has been in operation, experience has been gained of operating the facility and new knowledge of long-term performance of SFR 1 has been obtained. New regulations for nuclear facilities have been promulgated since SFR 1 was taken into operation (1988). A review committee comprising employees from SKI and SSI has conducted the review of SSR 2001. This review report has resulted in the committee's evaluation of the safety of SFR 1 and is the basis of the regulatory authorities' decision concerning any amendments to the stipulations for the operation of SFR 1. However, the review has found deficiencies in the follow up of the development of design basis norms since the facility was constructed as well as deficiencies in learning from operating experience. However, the overall evaluation is that the facility is being operated in an acceptable manner from the standpoint of safety. With respect to the long-term performance of the repository, it is a deficiency that SSR 2001 does not describe how compliance with the stipulated radiation protection requirements on optimisation and use of the best available technology (BAT) is achieved during operation. In the opinion of the review committee, issues relating to occupational radiation protection are being handled satisfactorily and the operational releases of radioactive substances are very small. Safety and Radiation Protection after Closure SKB's long-term repository performance assessment contains essential updates and improvements compared with the

A Review of Research on Driving Styles and Road Safety.

Science.gov (United States)

Sagberg, Fridulv; Selpi; Piccinini, Giulio Francesco Bianchi; Engström, Johan

2015-11-01

The aim of this study was to outline a conceptual framework for understanding driving style and, on this basis, review the state-of-the-art research on driving styles in relation to road safety. Previous research has indicated a relationship between the driving styles adopted by drivers and their crash involvement. However, a comprehensive literature review of driving style research is lacking. A systematic literature search was conducted, including empirical, theoretical, and methodological research, on driving styles related to road safety. A conceptual framework was proposed whereby driving styles are viewed in terms of driving habits established as a result of individual dispositions as well as social norms and cultural values. Moreover, a general scheme for categorizing and operationalizing driving styles was suggested. On this basis, existing literature on driving styles and indicators was reviewed. Links between driving styles and road safety were identified and individual and sociocultural factors influencing driving style were reviewed. Existing studies have addressed a wide variety of driving styles, and there is an acute need for a unifying conceptual framework in order to synthesize these results and make useful generalizations. There is a considerable potential for increasing road safety by means of behavior modification. Naturalistic driving observations represent particularly promising approaches to future research on driving styles. Knowledge about driving styles can be applied in programs for modifying driver behavior and in the context of usage-based insurance. It may also be used as a means for driver identification and for the development of driver assistance systems. © 2015, Human Factors and Ergonomics Society.

Immunization Safety Review: Thimerosal - Containing Vaccines and Neurodevelopmental Disorders

National Research Council Canada - National Science Library

Stratton, Kathleen; Gable, Alicia; McCormick, Marie C

2001-01-01

In this report, the Immunization Safety Review committee examines the hypothesis of whether or not the use of vaccines containing the preservative thimerosal can cause neurodevelopmental disorders (NDDs...

Review of SKB's Safety Assessment SR-Can: Contributions in Support of SKI's and SSI's Review by External Consultants

International Nuclear Information System (INIS)

2008-03-01

The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety report, SR-Site, on the repository's long-term safety and radiological consequences. As a preparation for SR-Site, SKB published the preliminary safety assessment SR-Can in November 2006. The purposes were to document a first evaluation of long-term safety for the two candidate sites at Forsmark and Laxemar and to provide feedback to SKB's future programme of work. An important objective of the authorities' review of SR-Can is to provide guidance to SKB on the complete safety reporting for the license application. The authorities have engaged external experts for independent modelling, analysis and review, with the aim to provide a range of expert opinions related to the sufficiency and appropriateness of various aspects of SR-Can. The conclusions and judgments in this report are those of the authors and may not necessarily coincide with those of SKI and SSI. The authorities own review will be published separately (SKI Report 2008:23, SSI Report 2008:04 E). This report compiles contributions from several specific research projects. The separate reviews cover topics regarding the engineered barrier system, the quality assurance, the climate evolution and its effects, and the ecosystems and environmental impacts. All contributions are in English apart from the review concerning ecosystems and environmental impacts, which is presented in Swedish

A probabilistic safety assessment PEER review: Case study on the use of probabilistic safety assessment for safety decisions

International Nuclear Information System (INIS)

1989-10-01

The purpose of this case study is to illustrate, using an actual example, the organizing and carrying out of an independent peer review of a draft full-scope (level 3) probabilistic safety assessment. The specific findings of the peer review are of less importance than the approach taken, the interaction between sponsor and study team, and the technical and administrative issues that can arise during a peer review. This case study will examine the following issues: how the scope of the peer review was established, based on how it was to be used by the review sponsoring body; how the level of effort was determined, and what this determination meant for the technical quality of the review; how the team of peer reviewers was selected; how the review itself was carried out; what findings were made; what was done with these findings by both the review sponsoring body and the PSA analysis team. 9 refs, 2 figs, 1 tab

Recommendations and comments on the report of the Ontario Nuclear Safety Review

International Nuclear Information System (INIS)

1988-12-01

The report of the Ontario Nuclear Safety Review (ONSR) prepared by Dr. F. Kenneth Hare in March 1988, is reviewed by the Advisory Committee on Nuclear Safety (ACNS) to assess for the Atomic Energy Control Board the relevance and importance of the ONSR recommendations and comments. The ACNS conclusions from this study are embodied in nineteen recommendations, as well as several suggestions and some specific comments

IAEA Team Concludes Peer Review of Greece's Regulatory Framework for Radiation Safety

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of senior nuclear safety and radiation protection experts yesterday concluded an 11-day mission to review the regulatory framework for nuclear and radiation safety in Greece. The Integrated Regulatory Review Service (IRRS) mission, which was conducted at the request of the Government of the Hellenic Republic, noted good practices in the country's nuclear regulatory system and also identified issues for improvement for the Greek Atomic Energy Commission (GAEC) and the Greek competent authorities. These are aimed at strengthening the effectiveness of the country's regulatory framework and functions in line with IAEA Safety Standards. ''The IRRS team enjoyed excellent cooperation from the GAEC throughout its mission,'' said Tom Ryan, mission leader and Director of Regulations and Information Management at the Radiological Protection Institute of Ireland. ''The GAEC staff were very open and candid in their discussions and provided the fullest practicable assistance.'' The main observations of the IRRS Review team included: While the Greek Government's commitment to safety is being demonstrated through its actions, the development of a comprehensive national policy and strategy expressed in a consolidated statement would provide a valuable framework and guidance for future actions in terms of safety; and GAEC has effective independence. The Greek government has ensured that GAEC is effectively independent in its safety-related decision-making and that it has functional separation from entities having responsibility or interests that could unduly influence its decision making. Strengths and good practices identified by the IRRS team included: Greece actively participates in the global safety regime including all relevant safety conventions; The nation's radiation monitoring system for the detection of illicit trafficking contributes significantly to identifying potential radiation emergencies due to events within or outside the country

Grasping at Straws: Comments on the Alberta Pipeline Safety Review

Directory of Open Access Journals (Sweden)

Jennifer Winter

2013-09-01

Full Text Available The release last month of the Alberta Pipeline Safety Review was meant to be a symbol of the province’s renewed commitment to environmental responsibility as it aims for new export markets. The report’s authors, Group 10 Engineering, submitted 17 recommendations covering public safety and pipeline incidents, pipeline integrity management and pipeline safety near bodies of water — and many of them run the gamut from the obvious to the unhelpful to the contradictory. That the energy regulator ought to be staffed to do its job should go without saying; in fact, staffing levels were never identified as an issue. The recommendation that record retention and transfer requirements be defined for mergers and acquisitions, sales and takeovers is moot. There is no reason a purchasing party would not want all relevant documents, and no real way to enforce transparency if the seller opts to withhold information. Harmonizing regulations between provinces could reduce companies’ cost of doing business, but could also prove challenging if different jurisdictions use performance-based regulations — which is what the Review recommended Alberta consider. This very brief paper pries apart the Review’s flaws and recommends that the province go back to the drawing board. Safety is a serious issue; a genuine statistical review linking pipeline characteristics to failures and risk-mitigation activities would be a better alternative by far.

Setting the standard: The IAEA safety standards set the global reference

International Nuclear Information System (INIS)

Williams, L.

2003-01-01

For the IAEA, setting and promoting standards for nuclear radiation, waste, and transport safety have been priorities from the start, rooted in the Agency's 1957 Statute. Today, a corpus of international standards are in place that national regulators and industries in many countries are applying, and more are being encouraged and assisted to follow them. Considerable work is done to keep safety standards updated and authoritative. They cover five main areas: the safety of nuclear facilities; radiation protection and safety of radiation sources; safe management of radioactive waste; safe transport of radioactive material; and thematic safety areas, such as emergency preparedness or legal infrastructures. Overall, the safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment. All IAEA Member States can nominate experts for the Agency standards committees and provide comments on draft standards. Through this ongoing cycle of review and feedback, the standards are refined, updated, and extended where needed

The internationalization of nuclear safety

International Nuclear Information System (INIS)

Rosen, M.

1989-01-01

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

[Evidence-based effectiveness of road safety interventions: a literature review].

Science.gov (United States)

Novoa, Ana M; Pérez, Katherine; Borrell, Carme

2009-01-01

Only road safety interventions with scientific evidence supporting their effectiveness should be implemented. The objective of this study was to identify and summarize the available evidence on the effectiveness of road safety interventions in reducing road traffic collisions, injuries and deaths. All literature reviews published in scientific journals that assessed the effectiveness of one or more road safety interventions and whose outcome measure was road traffic crashes, injuries or fatalities were included. An exhaustive search was performed in scientific literature databases. The interventions were classified according to the evidence of their effectiveness in reducing road traffic injuries (effective interventions, insufficient evidence of effectiveness, ineffective interventions) following the structure of the Haddon matrix. Fifty-four reviews were included. Effective interventions were found before, during and after the collision, and across all factors: a) the individual: the graduated licensing system (31% road traffic injury reduction); b) the vehicle: electronic stability control system (2 to 41% reduction); c) the infrastructure: area-wide traffic calming (0 to 20%), and d) the social environment: speed cameras (7 to 30%). Certain road safety interventions are ineffective, mostly road safety education, and others require further investigation. The most successful interventions are those that reduce or eliminate the hazard and do not depend on changes in road users' behavior or on their knowledge of road safety issues. Interventions based exclusively on education are ineffective in reducing road traffic injuries.

Trends in HFE Methods and Tools and Their Applicability to Safety Reviews

Energy Technology Data Exchange (ETDEWEB)

O' Hara, J.M.; Plott, C.; Milanski, J.; Ronan, A.; Scheff, S.; Laux, L.; and Bzostek, J.

2009-09-30

The U.S. Nuclear Regulatory Commission's (NRC) conducts human factors engineering (HFE) safety reviews of applicant submittals for new plants and for changes to existing plants. The reviews include the evaluation of the methods and tools (M&T) used by applicants as part of their HFE program. The technology used to perform HFE activities has been rapidly evolving, resulting in a whole new generation of HFE M&Ts. The objectives of this research were to identify the current trends in HFE methods and tools, determine their applicability to NRC safety reviews, and identify topics for which the NRC may need additional guidance to support the NRC's safety reviews. We conducted a survey that identified over 100 new HFE M&Ts. The M&Ts were assessed to identify general trends. Seven trends were identified: Computer Applications for Performing Traditional Analyses, Computer-Aided Design, Integration of HFE Methods and Tools, Rapid Development Engineering, Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. We assessed each trend to determine its applicability to the NRC's review by considering (1) whether the nuclear industry is making use of M&Ts for each trend, and (2) whether M&Ts reflecting the trend can be reviewed using the current design review guidance. We concluded that M&T trends that are applicable to the commercial nuclear industry and are expected to impact safety reviews may be considered for review guidance development. Three trends fell into this category: Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. The other trends do not need to be addressed at this time.

Trends in HFE Methods and Tools and Their Applicability to Safety Reviews

International Nuclear Information System (INIS)

O'Hara, J.M.; Plott, C.; Milanski, J.; Ronan, A.; Scheff, S.; Laux, L.; Bzostek, J.

2009-01-01

The U.S. Nuclear Regulatory Commission's (NRC) conducts human factors engineering (HFE) safety reviews of applicant submittals for new plants and for changes to existing plants. The reviews include the evaluation of the methods and tools (M and T) used by applicants as part of their HFE program. The technology used to perform HFE activities has been rapidly evolving, resulting in a whole new generation of HFE M and Ts. The objectives of this research were to identify the current trends in HFE methods and tools, determine their applicability to NRC safety reviews, and identify topics for which the NRC may need additional guidance to support the NRC's safety reviews. We conducted a survey that identified over 100 new HFE M and Ts. The M and Ts were assessed to identify general trends. Seven trends were identified: Computer Applications for Performing Traditional Analyses, Computer-Aided Design, Integration of HFE Methods and Tools, Rapid Development Engineering, Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. We assessed each trend to determine its applicability to the NRC's review by considering (1) whether the nuclear industry is making use of M and Ts for each trend, and (2) whether M and Ts reflecting the trend can be reviewed using the current design review guidance. We concluded that M and T trends that are applicable to the commercial nuclear industry and are expected to impact safety reviews may be considered for review guidance development. Three trends fell into this category: Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. The other trends do not need to be addressed at this time.

Nuclear Safety Review for the Year 2007

International Nuclear Information System (INIS)

2008-07-01

In 2007, the 50th anniversary year of the Agency, the safety performance of the nuclear industry, on the whole, remained high, although incidents and accidents with no significant impact on public health and safety continue to make news headlines and challenge operators and regulators. It is therefore essential to maintain vigilance, continuously improve safety culture and enhance the international sharing and utilization of operating and other safety experience, including that resulting from natural events. The establishment and sustainability of infrastructures for all aspects of nuclear, radiation, transport and waste safety will remain a high priority. Member States embarking on nuclear power programmes will need to be active participants in the global nuclear safety regime. Harmonized safety standards, the peer review mechanism among contracting parties of the safety conventions, and sharing safety knowledge and best practices through networking are key elements for the continuous strengthening of the global nuclear safety regime. Technical and scientific support organizations (TSOs), whether part of the regulatory body or a separate organization, are gaining increased importance by providing the technical and scientific basis for safety related decisions and activities. There is a need for enhanced interaction and cooperation between TSOs. Academic and industrial expert communities also play a vital role in improving safety cooperation and capacity building. Countries embarking on nuclear power programmes, as well as countries expanding existing programmes, have to meet the challenge of building a technically qualified workforce. A vigorous knowledge transfer programme is key to capacity building - particularly in view of the ageing of experienced professionals in the nuclear field. National and regional safety networks, and ultimately a global safety network will greatly help these efforts. Changes in world markets and technology are having an impact on both

Measures to strengthen international co-operation in nuclear, radiation and transport safety and waste management. Nuclear safety review for the year 2003

International Nuclear Information System (INIS)

2004-01-01

The Nuclear Safety Review for the Year 2003 presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety during 2003. As in 2002 the overview is supported by more detailed Notes by the Secretariat: Safety Related Events and Issues Worldwide during 2003 (document 2004/Note 6), The Agency's Safety Standards: Activities during 2003 (document 2004/Note 7) and Providing for the Application of the Safety Standards (document 2004/Note 8). In January 2003, the Agency implemented an organization change and developed an integrated approach to reflect a broader assignment of nuclear safety and nuclear security and to better exploit synergy between them. The Office of Physical Protection and Material Security renamed to Office of Nuclear Security was transferred from the Department of Safeguards to the Department of Nuclear Safety, which became the Department of Nuclear Safety and Security to reflect the change. This Review provides information primarily on nuclear safety, and nuclear security will be addressed in a separate report

Preliminary standard review guide for Environmental Restoration/Decontamination and Decommissioning safety analyses

International Nuclear Information System (INIS)

Ellingson, D.R.

1993-06-01

The review guide is based on the shared experiences, approaches, and philosophies of the Environmental Restoration/Decontamination and Decommissioning (ER/D ampersand D) subgroup members. It is presented in the form of a review guide to maximize the benefit to both the safety analyses practitioner and reviewer. The guide focuses on those challenges that tend to be unique to ER/D ampersand D cleanup activities. Some of these experiences, approaches, and philosophies may find application or be beneficial to a broader spectrum of activities such as terminal cleanout or even new operations. Challenges unique to ER/D ampersand D activities include (1) consent agreements requiring activity startup on designated dates; (2) the increased uncertainty of specific hazards; and (3) the highly variable activities covered under the broad category of ER/D ampersand D. These unique challenges are in addition to the challenges encountered in all activities; e.g., new and changing requirements and multiple interpretations. The experiences in approaches, methods, and solutions to the challenges are documented from the practitioner and reviewer's perspective, thereby providing the viewpoints on why a direction was taken and the concerns expressed. Site cleanup consent agreements with predetermined dates for restoration activity startup add the dimension of imposed punitive actions for failure to meet the date. Approval of the safety analysis is a prerequisite to startup. Actions that increase expediency are (1) assuring activity safety; (2) documenting that assurance; and (3) acquiring the necessary approvals. These actions increase the timeliness of startup and decrease the potential for punitive action. Improvement in expediency has been achieved by using safety analysis techniques to provide input to the line management decision process rather than as a review of line management decisions. Expediency is also improved by sharing the safety input and resultant decisions with

REVIEW OF SAFETY AND TOLERANCE OF OMALIZUMAB

Directory of Open Access Journals (Sweden)

A.V. Emel'yanov

2008-01-01

Full Text Available The review of safety of monoclonal anti-ige-antibodies (xolair — a new medication for the treatment of severe allergic bronchial asthma is presented. Local and system adverse events, originating after injection of medicament in clinical studies and following administration in patients are discussed.Key words: children, bronchial asthma, monoclonal anti Ige antibodies.

Experience in the review of utility control room design review and safety parameter display system programs

International Nuclear Information System (INIS)

Moore, V.A.

1985-01-01

The Detailed Control Room Design Review (DCRDR) and the Safety Parameter Display System (SPDS) had their origins in the studies and investigations conducted as the result of the TMI-2 accident. The President's Commission (Kemeny Commission) critized NRC for not examining the man-machine interface, over-emphasizing equipment, ignoring human beings, and tolerating outdated technology in control rooms. The Commission's Special Inquiry Group (Rogovin Report) recommended greater application of human factors engineering including better instrumentation displays and improved control room design. The NRC Lessons Learned Task Force concluded that licensees should review and improve control rooms using NRC Human engineering guidelines, and install safety parameter display systems (then called the safety staff vector). The TMI Action Plan Item I.D.1 and I.D.2 were based on these recommendations

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

Occupational health and safety issues affecting young workers: a literature review.

Science.gov (United States)

Laberge, Marie; Ledoux, Elise

2011-01-01

Many overview articles, reports, book chapters and literature reviews have examined the health and safety of young workers. These sources discuss the relationships between the work conditions of young workers and the various indicators of accidents and occupational diseases. Breslin et al. [12,13] conducted two literature reviews of quantitative studies to determine which factors best predicted work accidents and occupational disorders in young people. The present article proposes a review of young people's occupational health and safety (OHS) factors (e.g., demographic, individual, professional, organizational, temporal and operational factors) in both qualitative and quantitative studies. Five types of problems were analyzed in greater depth, namely MSD symptoms, respiratory, allergy and toxicological problems, mental health and well-being, alcohol and drug consumption, and fatigue. This review likewise examines related dimensions that allow us to adopt a more global perspective on this subject by considering such elements as young people's values, their knowledge and attitudes, safety practices in companies, the safe integration of young people, and rehabilitation. A total of 189 scientific articles were selected on the basis of certain criteria. These articles came from refereed OHS journals published between 1994 and 2005.

Patient Safety Learning Systems: A Systematic Review and Qualitative Synthesis.

Science.gov (United States)

2017-01-01

A patient safety learning system (sometimes called a critical incident reporting system) refers to structured reporting, collation, and analysis of critical incidents. To inform a provincial working group's recommendations for an Ontario Patient Safety Event Learning System, a systematic review was undertaken to determine design features that would optimize its adoption into the health care system and would inform implementation strategies. The objective of this review was to address two research questions: (a) what are the barriers to and facilitators of successful adoption of a patient safety learning system reported by health professionals and (b) what design components maximize successful adoption and implementation? To answer the first question, we used a published systematic review. To answer the second question, we used scoping study methodology. Common barriers reported in the literature by health care professionals included fear of blame, legal penalties, the perception that incident reporting does not improve patient safety, lack of organizational support, inadequate feedback, lack of knowledge about incident reporting systems, and lack of understanding about what constitutes an error. Common facilitators included a non-accusatory environment, the perception that incident reporting improves safety, clarification of the route of reporting and of how the system uses reports, enhanced feedback, role models (such as managers) using and promoting reporting, legislated protection of those who report, ability to report anonymously, education and training opportunities, and clear guidelines on what to report. Components of a patient safety learning system that increased successful adoption and implementation were emphasis on a blame-free culture that encourages reporting and learning, clear guidelines on how and what to report, making sure the system is user-friendly, organizational development support for data analysis to generate meaningful learning outcomes

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

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of senior nuclear safety experts concluded today a two-week mission to review the regulatory framework for nuclear safety in the Republic of Korea. The team identified good practices and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of Korea, while the final report will be submitted by the end of summer 2011. At the request of the Korean Government, the IAEA assembled a team of 16 senior regulatory experts from 14 nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Korean Ministry for Education, Science and Technology (MEST) and the Korean Institute for Nuclear Safety (KINS). The mission is a peer-review based on the IAEA Safety Standards. ''This was the first IRRS mission organized after Japan's Fukushima Daiichi nuclear accident and it included a review of the regulatory implications of that event,' explains Denis Flory, IAEA Deputy Director General and Head of the Department of Nuclear Safety and Security. William Borchardt, Executive Director of Operations from the US Nuclear Regulatory Commission and Team Leader of this mission commended the Korean authorities for their openness and commitment to sharing their experience with the world's nuclear safety community. ''IRRS missions such as the one that was just concluded here in the Republic of Korea are crucial to the enhancement of nuclear safety worldwide,'' he said. The IRRS team reviewed Korea's current regulatory framework while acknowledging the fact that the country's Government has already decided to establish, as of October 2011, a new independent regulatory body to be called Nuclear Safety Commission (NSC). As a consequence, KINS role will be as a regulatory expert organization reporting to the NSC, while MEST's role will be restricted to promoting the utilization of nuclear energy. The IRRS team identified particular strengths in the Korean regulatory system

Nuclear Safety Research Review Committee

International Nuclear Information System (INIS)

Todreas, N.E.

1990-01-01

The Nuclear Safety Research Review Committee has had a fundamental difficulty because of the atmosphere that has existed since it was created. It came into existence at a time of decreasing budgets. For any Committee the easiest thing is to tell the Director what additional to do. That does not really help him a lot in this atmosphere of reduced budgets which he reviewed for you on Monday. Concurrently the research arm of Nuclear Regulatory Commission has recognized that the scope of its activity needed to be increased rather than decreased. In the last two-and-a-half-year period, human factors work was reinstated, radiation and health effects investigations were reinvigorated, research in the waste area was given significant acceleration. Further, accident management came into being, and the NRC finally got back into the TMI-2 area. So with all of those activities being added to the program at the same time that the research budget was going down, the situation has become very strained. What that leads to regarding Committee membership is a need for technically competent generalists who will be able to sit as the Division Directors come in, as the contractors come in, and sort the wheat from the chaff. The Committee needs people who are interested in and have a broad perspective on what regulatory needs are and specifically how safety research activities can contribute to them. The author summarizes the history of the Committee, the current status, and plans for the future

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

International Nuclear Information System (INIS)

2016-01-01

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

Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report

International Nuclear Information System (INIS)

Herborn, D.I.

1991-10-01

The requirements for Westinghouse Hanford independent review of the Preliminary Safety Analysis Report (PSAR) are contained in Section 1.0, Subsection 4.3 of WCH-CM-4-46. Specifically, this manual requires the following: (1) Formal functional reviews of the HWVP PSAR by the future operating organization (HWVP Operations), and the independent review organizations (HWVP and Environmental Safety Assurance, Environmental Assurance, and Quality Assurance); and (2) Review and approval of the HWVP PSAR by the Tank Waste Disposal (TWD) Subcouncil of the Safety and Environmental Advisory Council (SEAC), which provides independent advice to the Westinghouse Hanford President and executives on matters of safety and environmental protection. 7 refs

RAF/9/049: Enhancing and Sustaining the National Regulatory Bodies for safety

International Nuclear Information System (INIS)

Keter, C.J.

2017-01-01

The main objective of this project is to enhance regulatory infrastructure, sustainability and cooperation among national regulatory bodies. This will support strengthening of the existing regulatory framework and capacity building in the region. Self-Assessment using the Self-Assessment Regulatory Infrastructure for Safety (SARIS) was completed on 26th May 2016. Changes made to the legislation is ongoing. The Nuclear Regulatory Bill 2017 is at an advanced stage and about to be tabled to Cabinet. The project objectives shall be addressed under a new project, RAF/9/058 – Improving the Regulatory Framework for the Control of Radiation Sources in Member States. Two major tasks for Kenya to focus include Review of regulations on waste safety, radiation sources and on safety of NPP and advising on drafting of radiation safety guides

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)

The safety of available and emerging options for emergency contraception.

Science.gov (United States)

Lee, Jessica K; Schwarz, Eleanor Bimla

2017-10-01

Emergency contraception (EC) is a way to significantly reduce the chance of becoming pregnant after an episode of unprotected intercourse. Considerable data support the safety of all available and emerging options for EC. Areas covered: This review presents a comprehensive summary of the literature regarding the safety of EC as well as directions for further study. PubMed was searched for all relevant studies published prior to June 2017. Expertopinion: All available methods of EC (i.e., ulipristal acetate pills, levonorgestrel pills, and the copper-IUD), carry only mild side effects and serious adverse events are essentially unknown. The copper IUD has the highest efficacy of EC methods. Given the excellent safety profiles of mifepristone and the levonorgestrel IUD, research is ongoing related to use of these products for EC.

Ongoing contraception after use of emergency contraception from a specialist contraceptive service.

Science.gov (United States)

Cameron, Sharon T; Glasier, Anna; Johnstone, Anne; Rae, Leanne

2011-10-01

A consultation for emergency contraception (EC) gives way to an opportunity to provide women with an ongoing effective method of contraception. A review of the case notes of women seeking EC from a large family planning clinic in Edinburgh, Scotland, was conducted to determine what percentage of women were provided with an effective method of ongoing contraception. Case notes of 460 women presenting for EC over a 2-year period were reviewed. Women were of mean age 26 years (range 15-49 years) and presented because they had used no contraception (47%), experienced condom failure (42%) or missed oral contraceptive pills (9%). Only 2% (n=11) were given an intrauterine device for EC. All women who had missed contraceptive pills prior to taking EC opted to continue this method. Only 23% (n=89) of women using no method or condoms at EC received supplies of an effective contraceptive method (pills, patch, injectable). Two thirds (n=263) of the women chose condoms for ongoing contraception. Research is required to develop strategies to improve the uptake of effective contraception after EC. Copyright © 2011 Elsevier Inc. All rights reserved.

Development of a draft of human factors safety review procedures for the Korean Next Generation Reactor

International Nuclear Information System (INIS)

Lee, Jung Woon; Moon, B. S.; Park, J. C.; Lee, Y. H.; Oh, I. S.; Lee, H. C.

2000-02-01

In this study, a draft of Human Factors Engineering (HFE) Safety Review Procedures (SRP) was developed for the safety review of KNGR based on HFE Safety and Regulatory Requirements and Guidelines (SRRG). This draft includes acceptance criteria, review procedure, and evaluation findings for the areas of review including HFE program management, human factors analyses, human factors design, and HFE verification and validation, based on section 15.1 'human factors engineering design process' and 15.2 'control room human factors engineering' of KNGR specific safety requirements and chapter 15 'human factors engineering' of KNGR safety regulatory guides. For the effective review, human factors concerns or issues related to advanced HSI design that have been reported so far should be extensively examined. In this study, a total of 384 human factors issues related to the advanced HSI design were collected through our review of a total of 145 documents. A summary of each issue was described and the issues were identified by specific features of HSI design. These results were implemented into a database system

Regulatory review of probabilistic safety assessment (PSA) Level 2

International Nuclear Information System (INIS)

2001-07-01

Probabilistic safety assessment (PSA) is increasingly being used as part of the decision making process to assess the level of safety of nuclear power plants. The methodologies in use are maturing and the insights gained from the PSAs are being used along with those from deterministic analysis. Many regulatory authorities consider the current state of the art in PSA to be sufficiently well developed for results to be used centrally in the regulatory decision making process-referred to as risk informed regulation. For these applications to be successful, it will be necessary for the regulatory authority to have a high degree of confidence in the PSA. However, at the 1994 IAEA Technical Committee Meeting on Use of PSA in the Regulatory Process and at the OECD Nuclear Energy Agency Committee for Nuclear Regulatory Activities (CNRA) 'Special Issues' meeting in 1997 on Review Procedures and Criteria for Different Regulatory Applications of PSA, it was recognized that formal regulatory review guidance for PSA did not exist. The senior regulators noted that there was a need to produce some international guidance for reviewing PSAs to establish an agreed basis for assessing whether important technological and methodological issues in PSAs are treated adequately and to verify that conclusions reached are appropriate. In 1997, the IAEA and OECD Nuclear Energy Agency agreed to produce, in cooperation, guidance on Regulatory Review of PSA. This led to the publication of IAEA-TECDOC-1135 on the Regulatory Review of Probabilistic Safety Assessment (PSA) Level 1, which gives advice for the review of Level 1 PSA for initiating events occurring at power plants. This TECDOC extends the coverage to address the regulatory review of Level 2 PSA.These publications are intended to provide guidance to regulatory authorities on how to review the PSA for a nuclear power plant to gain confidence that it has been carried out to an acceptable level of quality so that it can be used as the

Results of 6th Review Meeting and Perspective of the 7th Review Meeting of the Convention on Nuclear Safety

International Nuclear Information System (INIS)

Lee, Sukho; Kim, Manwoong; You, Jeongwon; Lee, Youngeal

2017-01-01

This paper highlighted the objective and role of the Convention on Nuclear Safety organized by the IAEA. The Convention provides Member States to demonstrate and share how to maintain and improve the level of nuclear safety. The results of the 6 th review meeting were implemented for safety improvements and to prepare for 7 th national report. Seven and a half months before the 7 th Review Meeting, the National Report has submitted on steps and measures taken to implement Convention obligations. The Contracting Parties reviewed each other’s reports, and exchanged written questions, written answers and comments. The discussions in the Country Group sessions were generally good with a lively and frank exchange of information. The Country Groups noted the significant measures taken by Contracting Parties to improve nuclear safety and identified a number of good practices to be shared with all Contracting Parties.

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views [fr

Guidelines regarding the review process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2002-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views

Guidelines regarding the review process under the convention on nuclear safety

International Nuclear Information System (INIS)

1998-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing national reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of national reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views

Guidelines regarding the review process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

1999-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing national reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of national reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views [es

Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

International Nuclear Information System (INIS)

Zull, Lawrence M.; Yeniscavich, William

2008-01-01

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

Regulatory instrument review: Management of aging of LWR [light water reactor] major safety-related components

International Nuclear Information System (INIS)

Werry, E.V.

1990-10-01

This report comprises Volume 1 of a review of US nuclear plant regulatory instruments to determine the amount and kind of information they contain on managing the aging of safety-related components in US nuclear power plants. The review was conducted for the US Nuclear Regulatory Commission (NRC) by the Pacific Northwest Laboratory (PNL) under the NRC Nuclear Plant Aging Research (NPAR) Program. Eight selected regulatory instruments, e.g., NRC Regulatory Guides and the Code of Federal Regulations, were reviewed for safety-related information on five selected components: reactor pressure vessels, steam generators, primary piping, pressurizers, and emergency diesel generators. Volume 2 will be concluded in FY 1991 and will also cover selected major safety-related components, e.g., pumps, valves and cables. The focus of the review was on 26 NPAR-defined safety-related aging issues, including examination, inspection, and maintenance and repair; excessive/harsh testing; and irradiation embrittlement. The major conclusion of the review is that safety-related regulatory instruments do provide implicit guidance for aging management, but include little explicit guidance. The major recommendation is that the instruments be revised or augmented to explicitly address the management of aging

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

Energy Technology Data Exchange (ETDEWEB)

Kim, J. Y.

1998-02-01

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

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.

A Review of Interventions To Increase Driving Safety among Teenage Drivers.

Science.gov (United States)

Mattox, John R., II

Young drivers across the United States represent a persistent traffic safety problem. Many interventions have been imposed on these drivers but few studies have evaluated the impact of these interventions on risky behaviors or traffic safety measures. To fill this gap, a review was undertaken to examine the most rigorous methodological evaluations…

Key regulatory and safety issues emerging NEA activities. Lessons Learned from Fukushima Dai-ichi NPS Accident - Key Regulatory and Safety Issues

International Nuclear Information System (INIS)

Nakoski, John

2013-01-01

A presentation was provided on the key safety and regulatory issues and an update of activities undertaken by the NEA and its members in response to the accident at the Fukushima Daiichi nuclear power stations (NPS) on 11 March 2011. An overview of the accident sequence and the consequences was provided that identified the safety functions that were lost (electrical power, core cooling, and primary containment) that lead to units 1, 2, and 3 being in severe accident conditions with large off-site releases. Key areas identified for which activities of the NEA and member countries are in progress include accident management; defence-in-depth; crisis communication; initiating events; operating experience; deterministic and probabilistic assessments; regulatory infrastructure; radiological protection and public health; and decontamination and recovery. For each of these areas, a brief description of the on-going and planned NEA activities was provided within the three standing technical committees of the NEA with safety and regulatory mandates (the Committee on Nuclear Regulatory Activities - CNRA, the Committee on the Safety of Nuclear Installations - CSNI, and the Committee on Radiation Protection and Public Health - CRPPH). On-going activities of CNRA include a review of enhancement being made to the regulatory aspects for the oversight of on-site accident management strategies and processes in light of the lessons learned from the accident; providing guidance to regulators on crisis communication; and supporting the peer review of the safety assessments of risk-significant research reactor facilities in light of the accident. Within the scope of the CSNI mandate, activities are being undertaken to better understand accident progression; characteristics of new fuel designs; and a benchmarking study of fast-running software for estimating source term under severe accident conditions to support protective measure recommendations. CSNI also has ongoing work in human

Safety of human papillomavirus vaccines: a review.

Science.gov (United States)

Stillo, Michela; Carrillo Santisteve, Paloma; Lopalco, Pier Luigi

2015-05-01

Between 2006 and 2009, two different human papillomavirus virus (HPV) vaccines were licensed for use: a quadrivalent (qHPVv) and a bivalent (bHPVv) vaccine. Since 2008, HPV vaccination programmes have been implemented in the majority of the industrialized countries. Since 2013, HPV vaccination has been part of the national programs of 66 countries including almost all countries in North America and Western Europe. Despite all the efforts made by individual countries, coverage rates are lower than expected. Vaccine safety represents one of the main concerns associated with the lack of acceptance of HPV vaccination both in the European Union/European Economic Area and elsewhere. Safety data published on bivalent and quadrivalent HPV vaccines, both in pre-licensure and post-licensure phase, are reviewed. Based on the latest scientific evidence, both HPV vaccines seem to be safe. Nevertheless, public concern and rumors about adverse events (AE) represent an important barrier to overcome in order to increase vaccine coverage. Passive surveillance of AEs is an important tool for detecting safety signals, but it should be complemented by activities aimed at assessing the real cause of all suspect AEs. Improved vaccine safety surveillance is the first step for effective communication based on scientific evidence.

IAEA-led Operational Safety Team Reviews Dukovany Nuclear Power Plant, Czech Republic

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has commended the Dukovany Nuclear Power Plant (NPP) in the Czech Republic for its safety practices and has also made a series of recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of the Czech Republic to conduct an Operational Safety Review (OSART) of Dukovany NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review of the plant from 6 to 23 June 2011. The team was made up of experts from Armenia, Germany, Hungary, Romania, Slovenia, Sweden, the UK and the USA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at Dukovany conducted an in-depth review of the aspects essential to the safe operation of the NPP, which is largely under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; and Emergency Planning and Preparedness. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: The plant uses an integrated approach to recruit, select, psychologically assess and train new employees. This approach has resulted in consistently high success rates for licensed operator examinations and the identification of potential candidates for various plant departments; The performance

Involving patients in patient safety programmes: A scoping review and consensus procedure by the LINNEAUS collaboration on patient safety in primary care.

Science.gov (United States)

Trier, Hans; Valderas, Jose M; Wensing, Michel; Martin, Helle Max; Egebart, Jonas

2015-09-01

Patient involvement has only recently received attention as a potentially useful approach to patient safety in primary care. To summarize work conducted on a scoping review of interventions focussing on patient involvement for patient safety; to develop consensus-based recommendations in this area. Scoping review of the literature 2006-2011 about methods and effects of involving patients in patient safety in primary care identified evidence for previous experiences of patient involvement in patient safety. This information was fed back to an expert panel for the development of recommendations for healthcare professionals and policy makers. The scoping review identified only weak evidence in support of the effectiveness of patient involvement. Identified barriers included a number of patient factors but also the healthcare workers' attitudes, abilities and lack of training. The expert panel recommended the integration of patient safety in the educational curricula for healthcare professionals, and expected a commitment from professionals to act as first movers by inviting and encouraging the patients to take an active role. The panel proposed a checklist to be used by primary care clinicians at the point of care for promoting patient involvement. There is only weak evidence on the effectiveness of patient involvement in patient safety. The recommendations of the panel can inform future policy and practice on patient involvement in safety in primary care.

End of mission report on seismic safety review mission for Belene NPP site

International Nuclear Information System (INIS)

Gurpinar, A.; Mohammadioun, B.; Schneider, H.; Serva, L.

1995-01-01

Upon the invitation of the Bulgarian government through the Committee for the Peaceful Uses of Atomic Energy and within the framework of the implementation of the Technical Cooperation project BUL/9/012 related to site and seismic of NPPs, a mission visited Sofia 3 - 7 July 1995. The mission constituted a follow-up of the interim review of subjects related to tectonic stability and seismic hazard characterization of the site which was performed in September 1993. The main objective of the mission was the final review of the subjects already reviewed in September 1993 as well as issues related to geotechnical engineering and foundation safety. The main terms of reference of the present mission was to verify the implementation of the recommendations of the Site Safety Review Mission of June 1990. This document gives findings on geology-tectonics, seismology and foundation safety. In the end conclusions and recommendations of the mission are presented

Development of a draft of human factors safety review procedures for the Korean next generation reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Moon, B. S.; Park, J. C.; Lee, Y. H.; Oh, I. S.; Lee, H. C. [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-02-01

In this study, a draft of human factors engineering (HFE) safety review procedures (SRP) was developed for the safety review of KNGR based on HFE Safety and Regulatory Requirements and Guidelines (SRRG). This draft includes acceptance criteria, review procedure, and evaluation findings for the areas of review including HFE Program Management, Human Factors Analyses, Human Factors Design, and HFE Verification and Validation, based on Section 15.1 'Human Factors Engineering Design Process' and 15.2 'Control Room Human Factors Engineering' of KNGR Specific Safety Requirements and Chapter 15 'Human Factors Engineering' of KNGR Safety Regulatory Guides. For the effective review, human factors concerns or issues related to advanced HSI design that have been reported so far should be extensively examined. In this study, a total of 384 human factors issues related to the advanced HSI design were collected through our review of a total of 145 documents. A summary of each issue was described and the issues were identified by specific features of HSI design. These results were implemented into a database system. 8 refs., 2 figs. (Author)

Passenger safety, health, and comfort: a review.

Science.gov (United States)

Rayman, R B

1997-05-01

Since the birth of aviation medicine approximately 80 yrs ago, practitioners and scientists have given their attention primarily to flight deck crew, cabin crew, and ground support personnel. However, in more recent years we have broadened our horizons to include the safety, health, and comfort of passengers flying commercial aircraft. This will be even more compelling as more passengers take to the air in larger aircraft and flying longer hours to more distant destinations. Further, we can expect to see more older passengers because people in many countries are living longer, healthier lives. The author first discusses the stresses imposed by ordinary commercial flight upon travelers such as airport tumult, barometric pressure changes, immobility, jet lag, noise/ vibration, and radiation. Medical considerations are next addressed describing inflight illness and medical care capability aboard U.S. air carriers. Passenger safety, cabin air quality, and the preventive medicine aspects of air travel are next reviewed in the context of passenger safety, health, and comfort. Recommendations are addressed to regulator agencies, airlines aircraft manufacturers, and the aerospace medicine community.

A Systematic Review of the Safety of Lisdexamfetamine Dimesylate

OpenAIRE

Coghill, David R.; Caballero, Beatriz; Sorooshian, Shaw; Civil, Richard

2014-01-01

Background Here we review the safety and tolerability profile of lisdexamfetamine dimesylate (LDX), the first long-acting prodrug stimulant for the treatment of attention-deficit/hyperactivity disorder (ADHD). Methods A PubMed search was conducted for English-language articles published up to 16 September 2013 using the following search terms: (lisdexamfetamine OR lisdexamphetamine OR SPD489 OR Vyvanse OR Venvanse OR NRP104 NOT review [publication type]). Results In short-term, parallel-group...

Food Safety Evaluation Based on Near Infrared Spectroscopy and Imaging: A Review.

Science.gov (United States)

Fu, Xiaping; Ying, Yibin

2016-08-17

In recent years, due to the increasing consciousness of food safety and human health, much progress has been made in developing rapid and nondestructive techniques for the evaluation of food hazards, food authentication, and traceability. Near infrared (NIR) spectroscopy and imaging techniques have gained wide acceptance in many fields because of their advantages over other analytical techniques. Following a brief introduction of NIR spectroscopy and imaging basics, this review mainly focuses on recent NIR spectroscopy and imaging applications for food safety evaluation, including (1) chemical hazards detection; (2) microbiological hazards detection; (3) physical hazards detection; (4) new technology-induced food safety concerns; and (5) food traceability. The review shows NIR spectroscopy and imaging to be effective tools that will play indispensable roles for food safety evaluation. In addition, on-line/real-time applications of these techniques promise to be a huge growth field in the near future.

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

These Guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 of the Convention and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views. [fr

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

These Guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 of the Convention and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views.

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

These Guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 of the Convention and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views. [es

A review of the probabilistic safety assessment application to the TR-2 research reactor

International Nuclear Information System (INIS)

Goektepe, G.; Adalioglu, U.; Anac, H.; Sevdik, B.; Menteseoglu, S.

2001-01-01

A review of the Probabilistic Safety Assessment (PSA) to the TR-2 Research Reactor is presented. The level 1 PSA application involved: selection of accident initiators, mitigating functions and system definitions, event tree constructions and quantification, fault tree constructions and quantification, human reliability, component failure data base development, dependent failure analysis. Each of the steps of the analysis given above is reviewed briefly with highlights from the selected results. PSA application is found to be a practical tool for research reactor safety due to intense involvement of human interactions in an experimental facility. Insights gained from the application of PSA methodology to the TR-2 research reactor led to a significant safety review of the system

Nuclear Safety Review for the Year 2006

International Nuclear Information System (INIS)

2007-07-01

the various stakeholders effectively and efficiently. Related to this is the need for operators, users and regulatory bodies to communicate with the public effectively and in an open and transparent manner. The global nature of safety is reflected in the relevant international instruments, including conventions and codes of conduct, currently in place. All the international conventions related to safety welcomed additional contracting parties in 2006. During the year, the second review meeting took place for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The newly established Integrated Regulatory Review Service (IRRS) is contributing to the enhancement of Member States' legislative and regulatory infrastructure and the harmonization of regulatory approaches in nuclear, radiation, radioactive waste and transport safety. It is also one of the most effective feedback tools on the application of Agency standards that will be used for the further improvement of existing standards and guidance. In addition, the approach evaluates not only the policies and strategies, but also how efficient and effective they are regarding protection against all types of exposure. Therefore it is also a tool for information sharing and mutual learning on good policies and practices that can be used to reach harmonization step by step. Overall, the safety performance of the nuclear industry is good. However, there continue to be recurring events and there is a need to maintain vigilance. There is also a need for lessons learned to be transferred across the various sectors of the nuclear industry. Strong safety management and safety culture are vitally important for the continuation of this good performance. Leaders must ensure that personnel are properly trained and that adequate resources are available. The nuclear power industry around the world remains a safe and sound one with no worker or member of the public receiving a

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.

Research oil guidelines for safety review of category 2 waste disposal

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Safety confirmation items and monitoring items for engineered barriers were compiled, considering the current technical status and monitoring plan for the simulated subsurface disposal and its test facilities. In order to develop the guidelines of the safety review for the disposal of LLW generated from RI facilities and research facilities, technical issues relating toxic substances were surveyed. (author)

Industrial safety: its structuring and content

International Nuclear Information System (INIS)

Munoz, A.; Rodriguez, J.; Martinez-Val, J.M.

1999-01-01

Industrial development has led to an on-going increase in productivity, but the concept of safety has also become highly relevant. In this article, the authors address the structuring and content of industrial safety which involves laying down essential safety requirements, both in manufacturing and processes and in products. (Author)

Russian MINATOM nuclear safety research strategic plan. An international review

International Nuclear Information System (INIS)

1999-03-01

The 'Safety Research Strategic Plan for Russian Nuclear Power Plants' was published in draft form at the Russian International Nuclear Safety Centre (RINSC) by a working group of fifteen senior Russian experts. The Plan consists of 12 chapters, each addressing a specific technical area and containing a number of proposed research programmes and projects to advance the state-of-knowledge in that area. In part because a strong Recommendation to undertake such a Plan was made by the 1998 OECD/NEA study, the OECD Nuclear Energy Agency was asked by the Director of RINSC and the Director of USINSC to organize an international review of the Plan when the English-language version became available in October, 1998. This report represents the results of that review. (R.P.)

A Systematic Review of the Use of Social Media for Food Safety Risk Communication.

Science.gov (United States)

Overbey, Katie N; Jaykus, Lee-Ann; Chapman, Benjamin J

2017-09-01

This article covers the current published literature related to the use of social media in food safety and infectious disease communication. The aim was to analyze literature recommendations and draw conclusions about how best to utilize social media for food safety risk communication going forward. A systematic literature review was conducted, and 24 articles were included for analysis. The inclusion criteria were (i) original peer-reviewed articles and (ii) primary focus on communication through social media about food safety and/or infectious diseases. Studies were coded for themes about social media applications, benefits, limitations, and best practices. Trust and personal beliefs were important drivers of social media use. The wide reach, immediacy, and information gathering capacities of social media were frequently cited benefits. Suggestions for social media best practices were inconsistent among studies, and study designs were highly variable. More evidence-based suggestions are needed to better establish guidelines for social media use in food safety and infectious disease risk communication. The information gleaned from this review can be used to create effective messages for shaping food safety behaviors.

Safety evaluation for instrumentation and control system upgrading project of Malaysian TRIGA MARK II PUSPATI Research reactor

International Nuclear Information System (INIS)

Ridha Roslan; Nik Mohd Faiz Khairuddin

2013-01-01

Full-text: Malaysian TRIGA MARK II research reactor has been in safe operation since its first criticality in 1982. The reactor is licensed to be operated by Malaysian Nuclear Agency to perform training and research development related activities. Due to its extensive operation since last three decades, the option of modifications for safety and safety-related item and component become a necessary to replace the outdated equipment to a stat-of-art, reliable technologies. This paper will present the current regulatory activities performed by Atomic Energy Licensing Board (AELB) to ensure the upgrading of analogue to digital instrumentation and control system is implemented in safe manner. The review activity includes documentation review, manufacturer quality audit and on-site inspection for commissioning. The review performed by AELB is based on The International Atomic Energy Agency (IAEA) Safety Requirements NS-R-4, entitled Safety of Research Reactors. During this endeavour, AELB seeks technical cooperation from Korea Institute of Nuclear Safety (KINS), the nuclear experts organization of the country of origin of the instrumentation and control technology. The regulatory activity is still on-going and is expected to be completed by issuance of Authorization for Restart on December 2013. (author)

Standard Review Plan for the review of a license application for a low-level radioactive waste disposal facility: Safety analysis report

International Nuclear Information System (INIS)

1988-01-01

The Standard Review Plan (SRP) (NUREG-1200) provides guidance to staff reviewers in the Office of Nuclear Material Safety and Safeguards who perform safety reviews of applications to construct and operate low-level radioactive waste disposal facilities. The SRP ensures the quality and uniformity of the staff reviews and presents a well-defined base from which to evaluate proposed changes in the scope and requirements of the staff reviews. The SRP makes information about the regulatory licensing process widely available and serves to improve the understanding of the staff's review process by interested members of the public and the industry. Each individual SRP addresses the responsibilities of persons performing the review, the matters that are reviewed, the Commission's regulations and acceptance criteria necessary for the review, how the review is accomplished, the conclusions that are appropriate, and the implementation requirements

Standard review plan for the review of a license application for a low-level radioactive waste disposal facility: Safety analysis report

International Nuclear Information System (INIS)

1987-01-01

The Standard Review Plan (SRP) (NUREG-1200) provides guidance to staff reviewers in the Office of Nuclear Material Safety and Safeguards who perform safety reviews of applications to construct and operate low-level radioactive waste disposal facilities. The SRP ensures the quality and uniformity of the staff reviews and presents a well-defined base from which to evaluate proposed changes in the scope and requirements of the staff reviews. The SRP makes information about the regulatory licensing process widely available and serves to improve the understanding of the staff's review process by interested members of the public and the nuclear power industry. Each individual SRP addresses the responsibilities of persons performing the review, the matters that are reviewed, the Commission's regulations and acceptance criteria necessary for the review, how the review is accomplished, the conclusions that are appropriate, and the implementation requirements

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

International Nuclear Information System (INIS)

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

2004-01-01

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

New graduate registered nurses' knowledge of patient safety and practice: A literature review.

Science.gov (United States)

Murray, Melanie; Sundin, Deborah; Cope, Vicki

2018-01-01

To critically appraise available literature and summarise evidence pertaining to the patient safety knowledge and practices of new graduate registered nurses. Responsibility for patient safety should not be limited to the practice of the bedside nurses, rather the responsibility of all in the healthcare system. Previous research identified lapses in safety across the health care, more specifically with new practitioners. Understanding these gaps and what may be employed to counteract them is vital to ensuring patient safety. A focused review of research literature. The review used key terms and Boolean operators across a 5-year time frame in CINAHL, Medline, psycINFO and Google Scholar for research articles pertaining to the area of enquiry. Eighty-four articles met the inclusion criteria, 39 discarded due to irrelevant material and 45 articles were included in the literature review. This review acknowledges that nursing has different stages of knowledge and practice capabilities. A theory-practice gap for new graduate registered nurses exists, and transition to practice is a key learning period setting new nurses on the path to becoming expert practitioners. Within the literature, there was little to no acknowledgement of patient safety knowledge of the newly registered nurse. Issues raised in the 1970s remain a concern for today's new graduate registered nurses. Research has recognised several factors affecting transition from nursing student to new graduate registered nurse. These factors are leaving new practitioners open to potential errors and risking patient safety. Understanding the knowledge of a new graduate registered nurse upon entering clinical practice may assist in organisations providing appropriate clinical and theoretical support to these nurses during their transition. © 2017 John Wiley & Sons Ltd.

The safety of bone allografts used in dentistry: a review.

Science.gov (United States)

Holtzclaw, Dan; Toscano, Nicholas; Eisenlohr, Lisa; Callan, Don

2008-09-01

Recent media reports concerning "stolen body parts" have shaken the public's trust in the safety of and the use of ethical practices involving human allografts. The authors provide a comprehensive review of the safety aspects of human bone allografts. The authors reviewed U.S. government regulations, industry standards, independent industry association guidelines, company guidelines and scientific articles related to the use of human bone allografts in the practice of dentistry published in the English language. The use of human bone allografts in the practice of dentistry involves the steps of procurement, processing, use and tracking. Rigorous donor screening and aseptic proprietary processing programs have rendered the use of human bone allografts safe and effective as a treatment option. When purchasing human bone allografts for the practice of dentistry, one should choose products accredited by the American Association of Tissue Banks for meeting uniformly high safety and quality control measures. Knowledge of human bone allograft procurement, processing, use and tracking procedures may allow dental clinicians to better educate their patients and address concerns about this valuable treatment option.

Effectiveness of public health interventions in food safety: a systematic review.

Science.gov (United States)

Campbell, M E; Gardner, C E; Dwyer, J J; Isaacs, S M; Krueger, P D; Ying, J Y

1998-01-01

To summarize evidence on the effectiveness of public health interventions regarding food safety at restaurants, institutions, homes and other community-based settings. This systematic review of published and unpublished studies involved a comprehensive literature search, screening for relevance, quality assessment of relevant studies, data extraction and synthesis. The interventions identified in 15 studies included in this review were grouped into three categories: inspections, food handler training, and community-based education. The evidence suggests that: routine inspection (at least once per year) of food service premises is effective in reducing the risk of foodborne illness; food handler training can improve the knowledge and practices of food handlers; and selected community-based education programs can increase public knowledge of food safety. There is some evidence for the effectiveness of multiple public health interventions on food safety. Future research needs include evaluation of HACCP and community-based education programs.

Idaho National Laboratory Integrated Safety Management System 2010 Effectiveness Review and Declaration Report

Energy Technology Data Exchange (ETDEWEB)

Thomas J. Haney

2010-12-01

Idaho National Laboratory completes an annual Integrated Safety Management System effectiveness review per 48 CFR 970.5223-1 “Integration of Environment, Safety and Health into Work Planning and Execution.” The annual review assesses ISMS effectiveness, provides feedback to maintain system integrity, and helps identify target areas for focused improvements and assessments for the following year. Using one of the three Department of Energy (DOE) descriptors in DOE M 450.4-1 regarding the state of ISMS effectiveness during Fiscal Year (FY) 2010, the information presented in this review shows that INL achieved “Effective Performance.”

The value of peer reviews to nuclear plant safety

International Nuclear Information System (INIS)

Subalusky, W.T. Jr.

1994-01-01

On a global basis, the nuclear utility industry has clearly demonstrated the value of peer reviews for improving nuclear safety and overall plant performance. Peer reviews are conducted by small teams of technical experts who review various aspects of plant operation, recognize strengths and recommend improvements, thereby stimulating a positive response to the recommendations. U.S. nuclear utilities initiated the operator-to-operator peer review process first through the Institute of Nuclear Power Operations (INPO). Now, voluntary peer reviews are an important activity of the World Association of Nuclear Operators (WANO). Formed just five years ago. WANO has made significant progress in its key activities of the operator-to-operator exchanges, operating experience exchange, monitoring of plant performance indicators and sharing of good practices worldwide. A fifth activity, peer review on a strictly voluntary basis, is pertinent to this paper

Nuclear safety review requirements for launch approval

International Nuclear Information System (INIS)

Sholtis, J.A. Jr.; Winchester, R.O.

1992-01-01

Use of nuclear power systems in space requires approval which is preceded by extensive safety analysis and review. This careful study allows an informed risk-benefit decision at the highest level of our government. This paper describes the process as it has historically been applied to U.S. isotopic power systems. The Ulysses mission, launched in October 1990, is used to illustrate the process. Expected variations to deal with reactor-power systems are explained

Review of light water reactor safety through the Three Mile Island accident

International Nuclear Information System (INIS)

Phung, D.L.

1984-05-01

This review of light water reactor safety through the Three Mile Island accident has the purpose of establishing the baseline over which safety achievement post-TMI is assessed, and the need for new reactor designs and business direction is judged. Five major areas of reactor safety pre-TMI are examined: (1) safety philosophy and institutions, (2) reactor design criteria, (3) operational problems, (4) the Rasmussen reactor safety study, and (5) the TMI accident and repercussions. Although nuclear power has made spectacular achievements over the period pre-TMI and although TMI is technically a minor accident, this review concludes that there were basic flaws in the technology and in the manner safety philosophy was conceived and carried out. These flaws included (1) a reactor design that has high core power density, low heat capacity, and low system tolerance to upsets, (2) reactor deployment that had been expedited without extensive operational experience, (3) rules and regulations that had to play catch-up with commercial reactor development, (4) an industry that was fragmented, short-sighted, and tended to rely on the Nuclear Regulatory Commission for safety guidance, (5) information that was not effectively shared, and (6) attention that was inadequate to the human aspects of reactor operation and to public reaction to the specter of a reactor accident, major or minor

The Environmental Agency's Assessment of the Post-Closure Safety Case for the BNFL DRIGG Low Level Radioactive Waste Disposal Facility

International Nuclear Information System (INIS)

Streatfield, I. J.; Duerden, S. L.; Yearsley, R. A.

2002-01-01

The Environment Agency is responsible, in England and Wales, for authorization of radioactive waste disposal under the Radioactive Substances Act 1993. British Nuclear Fuels plc (BNFL) is currently authorized by the Environment Agency to dispose of solid low level radioactive waste at its site at Drigg, near Sellafield, NW England. As part of a planned review of this authorization, the Environment Agency is currently undertaking an assessment of BNFL's Post-Closure Safety Case Development Programme for the Drigg disposal facility. This paper presents an outline of the review methodology developed and implemented by the Environment Agency specifically for the planned review of BNFL's Post-Closure Safety Case. The paper also provides an overview of the Environment Agency's progress in its on-going assessment programme

Nuclear Safety Review for the Year 2005

International Nuclear Information System (INIS)

2006-01-01

In 2005, the Agency and its Director General were awarded the Nobel Peace Prize. The Nobel Committee statement recognizes the Agency's 'efforts to prevent nuclear energy from being used for military purposes and to ensure that nuclear energy for peaceful purposes is used in the safest possible way.' The global nature of safety is reflected in the relevant international legal instruments, both binding conventions and the non-binding codes of conduct currently in place. During the year, the third review meeting of the Contracting Parties to the Convention on Nuclear Safety as well as the third meeting of the representatives of the competent authorities under the Convention on Early Notification of a Nuclear Accident and Convention on Assistance in the Case of a Nuclear Accident or a Radiological Emergency took place. Improvements have been made in national legislation and regulatory infrastructure in many Member States in 2005. However, inadequate safety management and regulatory supervision of nuclear installations and use of ionizing radiation is a continuing issue in many Member States. A continuing challenge is to collect, analyse and disseminate safety experience and knowledge. Nuclear power plant (NPP) operational safety performance remained high throughout the world in 2005. Radiation doses to workers and members of the public due to NPP operation are well below regulatory limits. Personal injury accidents and incidents are among the lowest in industry. There were no accidents that resulted in the release of radiation that could adversely impact the environment. NPPs in many parts of the world have successfully coped with severe natural disaster conditions such as earthquakes, tsunamis, widespread river flooding and hurricanes. However, operational safety performance has been on a plateau for several years and concern has been expressed in many forums regarding the need to guard against complacency in the industry. Research reactors also maintained a good

Safety review for seismic qualification on nuclear power plant equipment

International Nuclear Information System (INIS)

Fang Qingxian

1995-01-01

The standards and requirements for seismic qualification of nuclear power plant's component have been fully addressed, including the scope of seismic qualification, the approach and the method of common seismic qualification, the procedure of the seismic tests, and the criteria for the seismic qualification review. The problems discovered in the safety review and the solution for these problems and some other issues are also discussed

Modern diaper performance: construction, materials, and safety review.

Science.gov (United States)

Dey, Swatee; Kenneally, Dianna; Odio, Mauricio; Hatzopoulos, Ioannis

2016-07-01

A review of the literature on diapers and diaper rash reveals that many clinicians are unfamiliar with modern diaper construction and materials as well as diaper safety testing methods. Typical modern diapers do not contain ingredients of concern such as latex and disperse dyes, but use ingredients such as spandex and pigments with a favorable safety profile. Today's disposable diaper is a high performance product whose carefully designed layers and liners provide optimal urine and feces absorption and an ever more clothing-like and comfortable fit. This is possible due to a variety of specialized polymer materials that provide optimal absorption of urine and feces, thereby minimizing skin exposure. © 2016 The International Society of Dermatology.

Idaho National Laboratory Integrated Safety Management System 2011 Effectiveness Review and Declaration Report

Energy Technology Data Exchange (ETDEWEB)

Farren Hunt

2011-12-01

Idaho National Laboratory (INL) performed an annual Integrated Safety Management System (ISMS) effectiveness review per 48 Code of Federal Regulations (CFR) 970.5223-1, 'Integration of Environment, Safety and Health into Work Planning and Execution.' The annual review assessed Integrated Safety Management (ISM) effectiveness, provided feedback to maintain system integrity, and helped identify target areas for focused improvements and assessments for fiscal year (FY) 2012. The information presented in this review of FY 2011 shows that the INL has performed many corrective actions and improvement activities, which are starting to show some of the desired results. These corrective actions and improvement activities will continue to help change culture that will lead to better implementation of defined programs, resulting in moving the Laboratory's performance from the categorization of 'Needs Improvement' to the desired results of 'Effective Performance.'

Extended reviewing or the role of potential siting cantons in the ongoing Swiss site selection procedure ('Sectoral Plan')

International Nuclear Information System (INIS)

Flueeler, Thomas

2014-01-01

The disposition of nuclear waste in Switzerland has a long-standing and sinuous history reflecting its complex socio-technical nature (Flueeler, 2006). Upon the twofold failure to site a repository for low- and intermediate-level radioactive waste at Wellenberg during the 1990's and 2000's, it was recognised that the respective site selections had not been fully transparent. The Swiss government, the Federal Council, accepted the lesson and, after an extensive nationwide consultation at that, established a new site selection process 'from scratch': a systematic, stepwise, traceable, fair and binding procedure with a safety-first approach, yet extensively participatory. The so-called Sectoral Plan for Deep Geological Repositories guarantees the inclusion of the affected and concerned cantons and communities, as well as the relevant authorities in neighbouring countries from an early stage (Swiss Nuclear Energy Act, 2003; BFE, 2008). This contribution shares experience and insights in the ongoing procedure from a cantonal point of view that is an intermediate position between national needs and regional concerns, and with technical regulatory expertise between highly specialised experts and involved publics. (authors)

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)

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.

Dam safety review using non-destructive methods for reinforced concrete structure

Energy Technology Data Exchange (ETDEWEB)

Philibert, Alain; Saint-Pierre, Francois; Turcotte, Bernard [Le Groupe S.M. International Inc., Sherbrooke, (Canada)

2010-07-01

Dams built at the beginning of the twentieth century include concrete structures that were put in under rehabilitation works. In some cases, the details of the structures are not well documented. In other cases, concrete damage can be hidden under new layers of undamaged material. This requires that the dam safety review in a real investigation gather the information necessary for carrying out the hydraulic and stability studies required by the Dam Safety Act. This paper presented the process of dam safety review using non-destructive methods for reinforced concrete structures. Two reinforced concrete dams built in the 1900's, the Eustic dam on the Coaticook River and the Frontenac dam on the Magog River near Sherbrooke, were evaluated by S.M. International using non-destructive methods such as sonic and ground penetrating radar methods. The studies allowed mapping of concrete damage and provided geometric information on some non visible structure elements that were part of previous reinforcement operations.

Determinants of safety outcomes and performance: A systematic literature review of research in four high-risk industries.

Science.gov (United States)

Cornelissen, Pieter A; Van Hoof, Joris J; De Jong, Menno D T

2017-09-01

In spite of increasing governmental and organizational efforts, organizations still struggle to improve the safety of their employees as evidenced by the yearly 2.3 million work-related deaths worldwide. Occupational safety research is scattered and inaccessible, especially for practitioners. Through systematically reviewing the safety literature, this study aims to provide a comprehensive overview of behavioral and circumstantial factors that endanger or support employee safety. A broad search on occupational safety literature using four online bibliographical databases yielded 27.527 articles. Through a systematic reviewing process 176 online articles were identified that met the inclusion criteria (e.g., original peer-reviewed research; conducted in selected high-risk industries; published between 1980-2016). Variables and the nature of their interrelationships (i.e., positive, negative, or nonsignificant) were extracted, and then grouped and classified through a process of bottom-up coding. The results indicate that safety outcomes and performance prevail as dependent research areas, dependent on variables related to management & colleagues, work(place) characteristics & circumstances, employee demographics, climate & culture, and external factors. Consensus was found for five variables related to safety outcomes and seven variables related to performance, while there is debate about 31 other relationships. Last, 21 variables related to safety outcomes and performance appear understudied. The majority of safety research has focused on addressing negative safety outcomes and performance through variables related to others within the organization, the work(place) itself, employee demographics, and-to a lesser extent-climate & culture and external factors. This systematic literature review provides both scientists and safety practitioners an overview of the (under)studied behavioral and circumstantial factors related to occupational safety behavior. Scientists

Review of current status of LWR safety research in Japan

International Nuclear Information System (INIS)

Yamada, Tasaburo; Mishima, Yoshitsugu; Ando, Yoshio; Miyazono, Shohachiro; Takashima, Yoichi.

1977-01-01

The Japan Atomic Energy Commission has exerted efforts on the research of the safety of nuclear plants in Japan, and ''Nuclear plant safety research committees'' was established in August 1974, which is composed of the government and the people. The philosophy of safety research, research and development plan, the forwarding procedure of the plan, international cooperation, for example LOFT program, and the effective feed back of the experimental results concerning nuclear safety are reviewed in this paper at first. As for the safety of nuclear reactors the basic philosophy that radio active fission products are contained in fuel or reactors with multiple barriers, (defence in depth) and almost no fission product is released outside reactor plants even at the time of hypothetical accident, is kept, and the research and development history and the future plan are described in this paper with the related technical problems. The structural safety is also explained, for example, on the philosophy ''leak before break'', pipe rupture, pipe restraint and stress analysis. The release of radioactive gas and liquid is decreased as the philosophy ''ALAP''. And probability safety evaluation method, LOCA, reactivity, accident and aseismatic design in nuclear plants in Japan are described. (Nakai, Y.)

Safety analysis and review system: a Department of Energy safety assurance tool

International Nuclear Information System (INIS)

Rosenthal, H.B.

1981-01-01

The concept of the Safety Analysis and Review System is not new. It has been used within the Department and its predecessor agencies, Atomic Energy Commission (AEC) and Energy Research and Development Administration (ERDA), for over 20 years. To minimize the risks from nuclear reactor and power plants, the AEC developed a process to support management authorization of each operation through identification and analysis of potential hazards and the measures taken to control them. As the agency evolved from AEC through ERDA to the Department of Energy, its responsibilities were broadened to cover a diversity of technologies, including those associated with the development of fossil, solar, and geothermal energy. Because the safety analysis process had proved effective in a technology of high potential hazard, the Department investigated the applicability of the process to the other technologies. This paper describes the system and discusses how it is implemented within the Department

An integrative review of patient safety in studies on the care and safety of patients with communication disabilities in hospital.

Science.gov (United States)

Hemsley, Bronwyn; Georgiou, Andrew; Hill, Sophie; Rollo, Megan; Steel, Joanne; Balandin, Susan

2016-04-01

To review the research literature on the experiences of patients with communication disabilities in hospital according to the Generic Model of patient safety. In 2014 and 2015, we searched four scientific databases for studies with an aim or result relevant to safety of hospital patients with communication disabilities. The review included 27 studies. A range of adverse event types were outlined in qualitative research. Little detail was provided about contributing or protective factors for safety incidents in hospital for these patients or the impact of the incidents on the patient or organisations involved. Further research addressing the safety of patients with communication disabilities is needed. Sufficient detail is required to identify the nature, timing, and detection of incidents; factors that contribute to or prevent adverse events; and detail the impact of the adverse events. In order to provide safe and effective care to people with communication disabilities in hospital, a priority for health and disability services must be the design and evaluation of ecologically appropriate and evidence-based interventions to improve patient care, communication, and reduce the risk of costly and harmful patient safety incidents. Copyright © 2015 Elsevier Ireland Ltd. All rights reserved.

Regulatory review and confidence building in post-closure safety assessments and safety cases for near surface disposal facilities-IAEA ASAM coordinated research programme

International Nuclear Information System (INIS)

Gonzales, A.; Simeonov, G.; Bennett, D.G.; Nys, V.; Ben Belfadhel, M.

2005-01-01

Some years ago, the IAEA successfully concluded a Coordinated Research Program (CRP) called Islam, which focussed on the development of an Improved Safety Assessment Methodology for near-surface radioactive waste disposal facilities. In November 2002, and as an extension of ISAM, the IAEA launched a new CRP called ASAM, designed to test the Application of the Safety Assessment Methodology by considering a range of near-surface disposal facilities. The ASAM work programme is being implemented by three application working groups and two cross-cutting working groups. The application working groups are testing the applicability of the ISAM methodology by assessing an existing disposal facility in Hungary, a copper mine in South Africa, and a hypothetical facility containing heterogenous wastes, such as disused sealed sources. The first cross-cutting working group is addressing a number of technical issues that are common to all near-surface disposal facilities, while the second group, the Regulatory Review Working Group (RRWG) is developing guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides a brief overview of the work being conducted by the Regulatory Review Working Group. (author)

Review of probabilistic safety assessments: insights and recommendations regarding further developments

International Nuclear Information System (INIS)

Spitzer, C.

1996-01-01

Probabilistic Safety Assessments (PSAs) performed by utilities in the framework of Periodic Safety Reviews for German nuclear power plants are reviewed by TUeV Suedwest. Insights gained and recommendations concerning the necessity and focus of further developments and applications according to practical requests for the performance and assessment of PSAs within regulatory procedures are presented in this paper. Further on, recommendations are made in order to ensure the validity of the results of PSAs necessary in order to achieve the goals thereof. Beside some general points of view the emphasis of the paper is on methodological aspects with respect to evaluation methods and assessment of common cause failures as well as human reliability assessment

Panel Resource Management (PRM) Implementation and Effects within Safety Review Panel Settings and Dynamics

Science.gov (United States)

Taylor, Robert W.; Nash, Sally K.

2007-01-01

While technical training and advanced degree's assure proficiency at specific tasks within engineering disciplines, they fail to address the potential for communication breakdown and decision making errors familiar to multicultural environments where language barriers, intimidating personalities and interdisciplinary misconceptions exist. In an effort to minimize these pitfalls to effective panel review, NASA's lead safety engineers to the ISS Safety Review Panel (SRP), and Payload Safety Review Panel (PSRP) initiated training with their engineers, in conjunction with the panel chairs, and began a Panel Resource Management (PRM) program. The intent of this program focuses on the ability to reduce the barriers inhibiting effective participation from all panel attendees by bolstering participants confidence levels through increased communication skills, situational awareness, debriefing, and a better technical understanding of requirements and systems.

Immunization Safety Review: Thimerosal - Containing Vaccines and Neurodevelopmental Disorders

National Research Council Canada - National Science Library

Stratton, Kathleen; Gable, Alicia; McCormick, Marie C

2001-01-01

..., and Marie C.McCormick, Editors Immunization Safety Review Committee Board on Health Promotion and Disease Prevention INSTITUTE OF MEDICINE NATIONAL ACADEMY PRESS Washington, D.C. Copyrightoriginal retained, the be not from cannot book, paper original however, for version formatting, authoritative the typesetting-specific created from the as publ...

Air Travel Safety in Postoperative Breast Cancer Patients: A Systematic Review.

Science.gov (United States)

Co, Michael; Ng, Judy; Kwong, Ava

2018-05-17

Air travel has long been a dilemma in post-breast cancer surgery patients. Anecdotal reports have described adverse outcomes on surgical wound, implants, and lymphedema during air travel. This review aims to evaluate the best evidence from the literature concerning the air travel safety in breast cancer patients. A comprehensive review was performed of the Medline, Embase, CINAHL, and Cochrane databases using a predefined strategy. Retrieved studies were independently screened and rated for relevance. Data were extracted by 2 researchers. We reviewed the best evidence on air travel safety in postoperative breast cancer patients. Evidence was limited in the current literature to suggest adverse effects on postoperative mastectomy wounds and drains by high-altitude travel. Similarly, adverse effects on breast implants were limited to case reports and ex vivo experiments. A systematic review of 12 studies concluded that air travel is not associated with upper limb lymphedema after breast cancer surgery. Deep-vein thrombosis (DVT) is a known complication after air travel; in addition, malignancy itself is a known risk factor for DVT. Evidence of safety to continue tamoxifen during the period of air travel is lacking in the literature. Evidence to support the use of systemic DVT prophylaxis in general postoperative breast cancer patients is also limited. Best evidence from a large retrospective study suggested that mechanical antiembolism devices and early mobilization are the only measures required. Air travel is generally safe in patients after breast cancer surgery. Copyright © 2018. Published by Elsevier Inc.

Pharmacist medication reviews to improve safety monitoring in primary care patients.

Science.gov (United States)

Gallimore, Casey E; Sokhal, Dimmy; Zeidler Schreiter, Elizabeth; Margolis, Amanda R

2016-06-01

Patients prescribed psychotropic medications within primary care are at risk of suboptimal monitoring. It is unknown whether pharmacists can improve medication safety through targeted monitoring of at risk populations. Access Community Health Centers implemented a quality improvement pilot project that included pharmacists on an integrated care team to provide medication reviews for patients. Aims were to determine whether inclusion of a pharmacist performing medication reviews within a primary care behavioral health (PCBH) practice is feasible and facilitates safe medication use. Pharmacists performed medication reviews of the electronic health record for patients referred for psychiatry consultation. Reviews were performed 1-3 months following consultation and focused on medications with known suboptimal monitoring rates. Reviews were documented within the EHR and routed to the primary care provider. Primary outcome measures were change in percentage up-to-date on monitoring and AIMS assessment, and at risk of experiencing drug interaction(s) between baseline and 3 months postreview. Secondary outcome was provider opinion of medication reviews collected via electronic survey. Reviews were performed for 144 patients. Three months postreview, percentage up-to-date on recommended monitoring increased 18% (p = .0001), at risk for drug interaction decreased 20% (p improved safety monitoring of psychotropic medications. Results identify key areas for improvement that other clinics considering integration of similar pharmacy services should consider. (PsycINFO Database Record (c) 2016 APA, all rights reserved).

SKI - ASAR - O3. As operated Safety Analysis Report. Recurring safety review 1996 Oskarshamn 3

International Nuclear Information System (INIS)

1997-12-01

According to Swedish law, the reactor owner is responsible for performing a safety review and writing a ''ASAR''-report. The Nuclear Power Inspectorate (SKI) examines this report, and reports the findings to the government (the ''SKI-ASAR'' report). Each Swedish reactor should pass through three full ASAR reviews during its life-time, similar to the licensing inspection before start-up of the reactor. The first series ASAR was delivered by OKG to SKI in December 1996, and forms the basis for the SKI analysis in the present report

SKI - ASAR - F3. As operated Safety Analysis Report. Recurring safety review 1996 Forsmark 3

International Nuclear Information System (INIS)

1997-12-01

According to Swedish law, the reactor owner is responsible for performing a safety review and writing a ''ASAR''-report. The Nuclear Power Inspectorate (SKI) examines this report, and reports the findings to the government (the ''SKI-ASAR'' report). Each Swedish reactor should pass through three full ASAR reviews during its life-time, similar to the licensing inspection before start-up of the reactor. The first series ASAR was delivered by FKA to SKI in December 1996, and forms the basis for the SKI analysis in the present report

SKI - ASAR - R1. As operated Safety Analysis Report. Recurring safety review 1995 Ringhals 1

International Nuclear Information System (INIS)

2000-01-01

According to Swedish law, the reactor owner is responsible for performing a safety review and writing a so called ASAR-report. The Nuclear Power Inspectorate (SKI) examines this report, and reports the findings to the government (the so called SKI-ASAR-report). Each Swedish reactor should pass through three full ASAR reviews during its lifetime, similar to the licensing inspection before start-up of the reactor. The second series ASAR was delivered by the Ringhals utility to SKI in September 1995, and forms the basis for the SKI analysis in the present report

Do genetically modified crops affect animal reproduction? A review of the ongoing debate.

Science.gov (United States)

Zhang, W; Shi, F

2011-05-01

In the past few years, genetically modified (GM) crops aimed at producing food/feed that became part of the regular agriculture in many areas of the world. However, we are uncertain whether GM food and feed can exert potential adverse effects on humans or animals. Of importance, the reproductive toxicology of GM crops has been studied using a number of methods, and by feeding GM crops to a number species of animals to ensure the safety assessment of GM food and feed. It appears that there are no adverse effects of GM crops on many species of animals in acute and short-term feeding studies, but serious debates of effects of long-term and multigenerational feeding studies remain. The aims of this review are to focus on the latest (last 3 to 4 years) findings and debates on reproduction of male and female animals after feeding daily diets containing the GM crops, and to present the possible mechanism(s) to explain their influences.

A tool to diagnose context riskiness in view of food safety activities and microbiological safety output

NARCIS (Netherlands)

Luning, P.A.; Marcelis, W.J.; Boekel, van M.A.J.S.; Rovira, J.; Uyttendaele, M.; Jacxsens, L.

2011-01-01

Stakeholders entail increasing demands on food safety management systems (FSMS) stimulating ongoing efforts of companies to progress to more advanced systems. However, the actual microbiological food safety (FS) output is not only a result of the performance of an FSMS, but it also depends on the

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.

IRIS guidelines. 2014 ed. Integrated Review of Infrastructure for Safety (IRIS) for self-assessment when establishing the safety infrastructure for a nuclear power programme

International Nuclear Information System (INIS)

2014-01-01

The IAEA safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment, and therefore represent what all Member States should achieve, whilst recognizing the ultimate responsibility of each State to ensure safety when implementing a nuclear power programme. IAEA Safety Standards Series No. SSG-16, entitled Establishing the Safety Infrastructure for a Nuclear Power Programme was published in order to provide recommendations, presented in the form of sequential actions, on meeting safety requirements progressively during the initial three phases of the development of safety, as described in INSAG-22, Nuclear Safety Infrastructure for a National Nuclear Power Programme Supported by the IAEA Fundamental Safety Principles. To that end, the 200 safety related actions, which are proposed by SSG-16, constitute a roadmap to establish a foundation for promoting a high level of safety over the entire lifetime of the nuclear power plant. These actions reflect international consensus on good practice in order to achieve full implementation of IAEA safety standards. The IAEA has developed a methodology and tool, the Integrated Review of Infrastructure for Safety (IRIS), to assist States in undertaking self-assessment with respect to SSG-16 recommendations when establishing the safety infrastructure for a nuclear power programme, and to develop an action plan for improvement. The IRIS methodology and the associated tool are fully compatible with the IAEA safety standards and are also used, when appropriate, in the preparation of review missions, such as the Integrated Regulatory Review Service and advisory missions. The present guidelines describe the IRIS methodology for self-assessment against SSG-16 recommendations. Through IRIS implementation, every organization concerned with nuclear safety may gain proper awareness and engage in a continuous progressive process to develop the effective national

IAEA Expert Team Completes Mission to Review Japan's Nuclear Power Plant Safety Assessment Process, 31 January 2012, Tokyo, Japan

International Nuclear Information System (INIS)

2012-01-01

Full text: A team of international nuclear safety experts today completed a review of Japan's two-stage process for assessing nuclear safety at the nation's nuclear power plants. The team began its work on 23 January and delivered a Preliminary Summary Report to Japanese officials today and plans to finish the final report by the end of February. National safety assessments and their peer review by the IAEA are a key component of the IAEA's Action Plan on Nuclear Safety, which was approved by the Agency's 152 Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. At the request of the Government of Japan, the International Atomic Energy Agency (IAEA) organized a 10-person team to review the Japanese Nuclear and Industrial Safety Agency's (NISA) approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. The IAEA safety review mission consisted of five IAEA and three international nuclear safety experts. To help its review, the team held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety (JNES) Organization, and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. 'We concluded that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, director of the IAEA's Nuclear Installation Safety Division. In its Preliminary Summary Report delivered today, the team highlighted a number of good practices and identified some improvements that would enhance the overall effectiveness of the Comprehensive Safety Assessment process. Good practices identified by the mission team include: Based on NISA instructions and commitments of the

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.

An international review of patient safety measures in radiotherapy practice

International Nuclear Information System (INIS)

Shafiq, Jesmin; Barton, Michael; Noble, Douglas; Lemer, Claire; Donaldson, Liam J.

2009-01-01

Errors from radiotherapy machine or software malfunction usually are well documented as they affect hundreds of patients, whereas random errors affecting individual patients are more difficult to be discovered and prevented. Although major clinical radiotherapy incidents have been reported, many more have remained unrecognised or have not been reported. The literature in this field is limited as it is mostly published as a result of investigation of major errors. We present a review of radiotherapy incidents internationally with the aim of identifying the domains where most errors occur through extensive review and synthesis of published reports, unpublished 'Grey literature' and departmental incident data. Our review of radiotherapy-related events in the last three decades (1976-2007) identified more than seven thousand (N = 7741) incidents and near misses. Three thousand one hundred and twenty-five incidents reported patient harm of variable intensity ranging from underdose increasing the risk of recurrence, to overdose causing toxicity, and even death for 1% (N = 38); 4616 events were near misses with no recognisable patient harm. Based on our review, a radiotherapy risk profile has been published by the WHO World Alliance for Patient Safety that highlights the role of communication, training and strict adherence to guidelines/protocols in improving the safety of radiotherapy process.

International review on safety requirements for the prototype fast breeder reactor “Monju” (Translated document)

International Nuclear Information System (INIS)

2016-02-01

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

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

International Nuclear Information System (INIS)

McGevna, V.; Peterson, L.R.

1981-01-01

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

International nuclear safety experts conclude IAEA peer review of China's regulatory system

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of senior experts on nuclear safety regulation today completed a two-week International Atomic Energy Agency (IAEA) review of the governmental and regulatory framework for nuclear safety in the People's Republic of China. The team identified good practices within the system and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of the People's Republic of China. The final report will be submitted to China by Autumn 2010. At the request of Chinese authorities, the IAEA assembled a team of 22 experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This mission is a peer review based on the IAEA Safety Standards . It is not an inspection, nor an audit. The experts came from 15 different countries: Australia, Canada, the Czech Republic, Finland, France, Hungary, Japan, Pakistan, the Republic of Korea, Slovenia, South Africa, Sweden, the United Kingdom, Ukraine and the United States. Mike Weightman, the United Kingdom's Head of Nuclear Directorate, HSE and HM Chief Inspector of Nuclear Installations said: ''I was honoured and pleased to lead such a team of senior regulatory experts from around the world, and I was impressed by their commitment, experience and hard work to provide their best advice possible. We had very constructive interactions with the Chinese authority to maximize the beneficial impact of the mission.'' The scope of the mission included the regulation of nuclear and radiation safety of the facilities and activities regulated by the Ministry of Environmental Protection (MEP) National Nuclear Safety Administration (NNSA). The mission was conducted from 18 to 30 July, mainly in Beijing. To observe Chinese regulatory activities, the IRRS team visited several nuclear facilities, including a nuclear power plant, a manufacturer of safety components for nuclear power plants, a research reactor, a fuel cycle facility, a waste management facility

The basis for confidence in the long-term safety of nuclear waste disposal

International Nuclear Information System (INIS)

Allen, C.J.; Whitaker, S.H.

1993-07-01

Confidence in the acceptability and the long-term safety of deep geological disposal draws strength from a number of sources: the technical approach, i.e., the use of multiple barriers for redundancy and defence in depth; the adoption of the observational approach to site characterization and to disposal vault design, construction, operation and, eventually, closure; the overall approach, which is based on ongoing review and incremental decision making; and, active and effective involvement of the public in this process

Safety cases for radioactive waste disposal facilities: guidance on confidence building and regulatory review IAEA-ASAM co-ordinated research project

International Nuclear Information System (INIS)

Ben Belfadhel, M.; Bennett, D.G.; Metcalf, P.; Nys, V.; Goldammer, W.

2008-01-01

The IAEA has been conducting two co-ordinated research programmes (CRPs) projects to develop and apply improved safety assessment methodologies for near-surface radioactive waste disposal facilities. The more recent of these projects, ASAM (application of safety assessment methodologies), included a Regulatory Review Working Group (RRWG) which has been working to develop guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides an overview of the ASAM project, focusing on the safety case and regulatory review. (authors)

International nuclear safety experts complete IAEA peer review of German regulatory system

International Nuclear Information System (INIS)

2008-01-01

Full text: An international expert team has today completed a two-week IAEA review of Germany's nuclear regulatory system. The team identified good practices within the system and gave advice on some areas for further improvement. The IAEA has conveyed the initial findings to German authorities but the final report will be submitted within two months. At the request of the Government of the Federal Republic of Germany, the International Atomic Energy Agency (IAEA) assembled a team of 14 experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This is a peer review based on IAEA Standards. It is not an inspection, nor an audit. The scope of the mission was limited to the safety regulation of nuclear power plants. Experts from Canada, the Czech Republic, Finland, France, Japan, the Netherlands, Republic of Korea, Spain, Switzerland, the UK, the US and from the IAEA took part in the mission, which was conducted from 7 to 19 September in Bonn, Stuttgart and Berlin. The main basis for the review was a well-prepared self-assessment made by the Federal Ministry of Environment, Nature Conservation and Nuclear Safety (BMU) and the Ministry of Environment of the federal state of Baden-Wuerttemberg (UM BW). 'The team members were impressed by the extensive preparation and dedication of the staff both at BMU and UM BW to excellence in nuclear safety,' said Mike Weightman, IRRS Team Leader and Chief Inspector of the UK nuclear regulatory body, the Nuclear Directorate of the Health and Safety Executive. 'We hope the IRRS mission will facilitate further improvements in the safety regulation of nuclear power in Germany and throughout the world.' 'Germany's invitation to undergo such a detailed review is a clear demonstration of its openness and commitment to continuously improve nuclear safety regulation,' said Philippe Jamet, Director of the IAEA's Nuclear Installation Safety Division. Among the particular strengths of BMU and UM BW associated with their

[Road safety measures and their effects on traffic injuries: a systematic review].

Science.gov (United States)

Aguilera, Sandra Lúcia Vieira Ulinski; Moysés, Simone Tetú; Moysés, Samuel Jorge

2014-10-01

To identify and summarize the findings of studies describing interventions aimed at reducing road traffic injuries. An integrative systematic review without meta-analysis was performed. The Preferred Reporting Items for Systematic Reviews and Meta-Analyses (PRISMA) were used to synthesize the findings of the articles reviewed. The keywords "traffic accidents", "review" and "public policy" were used in isolation or combined with boolean operator "And" to search PubMed, Web of Science, SciELO, and LILACS for the period between 2006 and 2011 RESULTS: Twenty-two studies were included in the systematic review. Of these, two described engineering strategies, two described other road safety policies, three described education strategies, and 15 described law enforcement policies. Law enforcement had the most effective immediate results. Engineering strategies proved important to promote a safe environment. Finally, education strategies had an informative role and served to support other strategies, but did not seem sufficient to promote cultural changes regarding road safety. Law enforcement seems to be the most effective strategy to change the behavior of drivers, especially regarding speed limits and drinking and driving.

Involving patients in patient safety programmes: A scoping review and consensus procedure by the LINNEAUS collaboration on patient safety in primary care

NARCIS (Netherlands)

Trier, H.; Valderas, J.M.; Wensing, M.; Martin, H.M.; Egebart, J.

2015-01-01

BACKGROUND: Patient involvement has only recently received attention as a potentially useful approach to patient safety in primary care. OBJECTIVE: To summarize work conducted on a scoping review of interventions focussing on patient involvement for patient safety; to develop consensus-based

Regulatory oversight of safety culture in nuclear installations - New IAEA developments

International Nuclear Information System (INIS)

Kerhoas, Anne; )

2012-01-01

Ms. Anne Kerhoas described the IAEA work on guidance for regulatory oversight of safety culture. She summarised the various IAEA, OECD/NEA and ANS meetings that have been held on the topic between 1995 and 2011. The IAEA has carried out two recent projects with the Bulgarian and Romanian regulatory bodies to develop a safety culture oversight program. The work was funded by the Norwegian government and has involved 30 experts from 17 different countries. Draft guidance for regulators on how to monitor licensee safety culture has also been produced (IAEA-TECDOC-DD1070). The document is intended to provide practical guidance on oversight strategies and is applicable to a wide range of nuclear installations, including nuclear power plants, fuel cycle facilities, research reactors and waste management facilities. A number of principles for regulatory oversight of safety culture were summarised. For example, the primary responsibility for safety remains with the licensee, safety culture oversight should be performed at all stages of the life cycle of the nuclear installation, and multiple data collection methods should be used. The overall approach to safety culture described in the draft IAEA Tech doc includes a range of approaches to build up a meaningful picture of the licensee's safety culture. These include interviews, observations, review of documents, review of events, discussions and surveys. The importance of ongoing discussion with the licensee throughout the process to develop a deeper shared understanding of issues was emphasised. The results of the Chester 2 workshop will be used as an input to finalization of the draft Tech Doc

Report of the review committee on evaluation of the R and D subjects in the field of nuclear safety research

International Nuclear Information System (INIS)

2000-09-01

On the basis of the JAERI's Basic Guidelines for the Research Evaluation Methods and the Practices Manuals of the Institution Evaluation Committee and Research Evaluation Committee, the Ad Hoc Review Committee on Nuclear Safety Research composed of twelve experts was set up under the Research Evaluation Committee of the JAERI in order to review the R and D subjects to be implemented for five years starting in FY2000 in the Nuclear Safety Research Center (Department of Reactor Safety Research, Department of Fuel Cycle Safety Research and Department of Safety Research Technical Support). The Ad Hoc Review Committee meeting was held on January 20, 2000. According to the review methods including review items, points of review and review criteria, determined by the Research Evaluation Committee, the review was conducted based on the research plan documents submitted in advance and presentations by the Department Directors. The review report was submitted to the Research Evaluation Committee for further review and discussions in its meeting held on August 31, 2000. The Research Evaluation Committee recognized the review results as appropriate. This report describes the review results. (author)

Improving patient safety in radiology: a work in progress

International Nuclear Information System (INIS)

Sze, Raymond W.

2008-01-01

The purpose of this paper is to share the experiences, including successes and failures, as well as the ongoing process of developing and implementing a safety program in a large pediatric radiology department. Building a multidisciplinary pediatric radiology safety team requires successful recruitment of team members, selection of a team leader, and proper and ongoing training and tools, and protected time. Challenges, including thorough examples, are presented on improving pediatric radiology safety intradepartmentally, interdepartmentally, and institutionally. Finally, some major challenges to improving safety in pediatric radiology, and healthcare in general, are presented along with strategies to overcome these challenges. Our safety program is a work in progress; this article is a personal account and the reader is asked for tolerance of its occasional subjective tone and contents. (orig.)

Safety and efficacy of Bolus administration of magnesium sulphate ...

African Journals Online (AJOL)

Safety and efficacy of Bolus administration of magnesium sulphate for preeclampsia. ... On-going research is addressing its administration in terms of dosage, duration and safety. Objective: We evaluated a ... Keywords: safety, efficacy, bolus magnesium sulphate, preeclampsia, University of Benin Teaching Hospital

Timing of Formal Phase Safety Reviews for Large-Scale Integrated Hazard Analysis

Science.gov (United States)

Massie, Michael J.; Morris, A. Terry

2010-01-01

Integrated hazard analysis (IHA) is a process used to identify and control unacceptable risk. As such, it does not occur in a vacuum. IHA approaches must be tailored to fit the system being analyzed. Physical, resource, organizational and temporal constraints on large-scale integrated systems impose additional direct or derived requirements on the IHA. The timing and interaction between engineering and safety organizations can provide either benefits or hindrances to the overall end product. The traditional approach for formal phase safety review timing and content, which generally works well for small- to moderate-scale systems, does not work well for very large-scale integrated systems. This paper proposes a modified approach to timing and content of formal phase safety reviews for IHA. Details of the tailoring process for IHA will describe how to avoid temporary disconnects in major milestone reviews and how to maintain a cohesive end-to-end integration story particularly for systems where the integrator inherently has little to no insight into lower level systems. The proposal has the advantage of allowing the hazard analysis development process to occur as technical data normally matures.

A review on food safety and food hygiene studies in Ghana

OpenAIRE

Ababio, P. F.; Lovatt, P.

2015-01-01

Food safety and hygiene in Ghana was studied using desk top literature review. Food research was highly concentrated in the capital city of the country and most research focus were on commercial food operations specifically street foods and microbiological safety with limited information from institutional catering and other forms of food hazards. The media currently serves as the main source for reporting of food borne diseases. Food establishments and other sources contributing to food born...

Human Factors and Safety Culture in Maritime Safety (revised

Directory of Open Access Journals (Sweden)

Heinz Peter Berg

2013-09-01

Full Text Available As in every industry at risk, the human and organizational factors constitute the main stakes for maritime safety. Furthermore, several events at sea have been used to develop appropriate risk models. The investigation on maritime accidents is, nowadays, a very important tool to identify the problems related to human factor and can support accident prevention and the improvement of maritime safety. Part of this investigation should in future also be near misses. Operation of ships is full of regulations, instructions and guidelines also addressing human factors and safety culture to enhance safety. However, even though the roots of a safety culture have been established, there are still serious barriers to the breakthrough of the safety management. One of the most common deficiencies in the case of maritime transport is the respective monitoring and documentation usually lacking of adequacy and excellence. Nonetheless, the maritime area can be exemplified from other industries where activities are ongoing to foster and enhance safety culture.

ITER final design report, cost review and safety analysis (FDR) and relevant documents

International Nuclear Information System (INIS)

1999-01-01

This volume contains the fourth major milestone report and documents associated with its acceptance, review and approval. This ITER Final Design Report, Cost Review and Safety Analysis was presented to the ITER Council at its 13th meeting in February 1998 and was approved at its extraordinary meeting on 25 June 1998. The contents include an outline of the ITER objectives, the ITER parameters and design overview as well as operating scenarios and plasma performance. Furthermore, design features, safety and environmental characteristics and schedule and cost estimates are given

Proceedings of the Second NASA Aviation Safety Program Weather Accident Prevention Review

Science.gov (United States)

Martzaklis, K. Gus (Compiler)

2003-01-01

The Second NASA Aviation Safety Program (AvSP) Weather Accident Prevention (WxAP) Annual Project Review held June 5-7, 2001, in Cleveland, Ohio, presented the NASA technical plans and accomplishments to the aviation community. NASA-developed technologies presented included an Aviation Weather Information System with associated digital communications links, electronic atmospheric reporting technologies, forward-looking turbulence warning systems, and turbulence mitigation procedures. The meeting provided feedback and insight from the aviation community of diverse backgrounds and assisted NASA in steering its plans in the direction needed to meet the national safety goal of 80-percent reduction of aircraft accidents by 2007. The proceedings of the review are enclosed.

Critical Review of Commercial Secondary Lithium-Ion Battery Safety Standards

Science.gov (United States)

Jones, Harry P.; Chapin, Thomas, J.; Tabaddor, Mahmod

2010-09-01

The development of Li-ion cells with greater energy density has lead to safety concerns that must be carefully assessed as Li-ion cells power a wide range of products from consumer electronics to electric vehicles to space applications. Documented field failures and product recalls for Li-ion cells, mostly for consumer electronic products, highlight the risk of fire, smoke, and even explosion. These failures have been attributed to the occurrence of internal short circuits and the subsequent thermal runaway that can lead to fire and explosion. As packaging for some applications include a large number of cells, the risk of failure is likely to be magnified. To address concerns about the safety of battery powered products, safety standards have been developed. This paper provides a review of various international safety standards specific to lithium-ion cells. This paper shows that though the standards are harmonized on a host of abuse conditions, most lack a test simulating internal short circuits. This paper describes some efforts to introduce internal short circuit tests into safety standards.

Gas-cooled fast reactor safety

International Nuclear Information System (INIS)

Rickard, C.L.; Simon, R.H.; Buttemer, D.R.

1977-01-01

Initial conceptual design work on the GCFR began in the USA in the early 1960s and since the later 1960s has proceeded with considerable international cooperation. A 300 MWe GCFR demonstration plant employing three main cooling loops is currently being developed at General Atomic. A major preapplication licensing review of this demonstration plant was initiated in 1971 leading in 1974 to publication of a Safety Evaluation Report by the USAEC Directorate of Licensing. The preapplication review is continuing by addressing areas of concern identified in this report such that a major part of the work necessary to support the actual licensing of a GCFR demonstration plant has been established. The safety performance of the GCFR demonstration plant is based upon its inherent safety characteristics among which are the single phase and chemically inert coolant which is not activated and has a low reactivity worth, the negative core power and temperature reactivity coefficients and the small and negative steam reactivity worth. Recent studies of larger core designs indicate that as the reactor size increases central fuel, clad and coolant reactivity worths decrease and the Doppler coefficient becomes more negative. These inherent safety characteristics are complemented by safety design features such as enclosing the entire primary coolant system within a prestressed concrete pressure vessel (PCRV), providing two independent and diverse shutdown systems and residual heat removal (RHR) systems, limiting the worth of control rods to less than $1, employing pressure-equalized fuel rods, a core supported rigidly at its upper end and otherwise unrestrained and coolant downflow within the core to enhance debris removal should local melting occur. The structurally redundant PCRV design allows the potential depressurization leak area to be controlled and, since the PCRV is located within a containment building, coolant is present even after a depressurization accident and each RHR

SRTC criticality safety technical review: Nuclear criticality safety evaluation 94-02, uranium solidification facility pencil tank module spacing

International Nuclear Information System (INIS)

Rathbun, R.

1994-01-01

Review of NMP-NCS-94-0087, ''Nuclear Criticality Safety Evaluation 94-02: Uranium Solidification Facility Pencil Tank Module Spacing (U), April 18, 1994,'' was requested of the SRTC Applied Physics Group. The NCSE is a criticality assessment to show that the USF process module spacing, as given in Non-Conformance Report SHM-0045, remains safe for operation. The NCSE under review concludes that the module spacing as given in Non-Conformance Report SHM-0045 remains in a critically safe configuration for all normal and single credible abnormal conditions. After a thorough review of the NCSE, this reviewer agrees with that conclusion

Preliminary results of an ongoing study of the Nicobar megapode Megapodius nicobariensis Blyth

NARCIS (Netherlands)

Sankaran, R.; Sivakumar, K.

1999-01-01

Data collected during an ongoing study on incubation mounds and the social organization of the Nicobar megapode Megapodius nicobariensis Blyth, 1846, are reviewed. Microbial decomposition of organic matter in mounds is likely to be the major source of heat production within incubation mounds of the

Reports and operational engineering: An independent safety assessment of Department of Energy nuclear reactor facilities

International Nuclear Information System (INIS)

Rochman, A.; Washburn, B.W.

1981-02-01

The Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee, established via an October 24, 1979 memorandum from the Department of Energy (DOE) Under Secretary, was instructed to review the ''Kemeny Commission'' recommendations and to identify possible implications for DOE's nuclear facilities. As a result of this review, the Committee recommended that DOE carry out assessments in seven categories. The assessments would address specific topics identified for each category as delineated in the NFPQT ''Guidelines for Assessing the Safe Operation of DOE-Owned Reactors,'' dated May 7, 1980. The Committee recognized that similar assessments had been ongoing in the DOE program and safety overview organizations since the Three Mile Island nuclear accident and it was the Committee's intent to use the results of those ongoing assessments as an input to their evaluations. This information would be supplemented by additional studies consisting of the subject-related documents used at each reactor facility studied, and an on-site review of these reactor facilities by professional personnel within the Department of Energy, its operating contractors and independent consultants. 1 tab

Preparation, review, and approval of implementation plans for nuclear safety requirements

International Nuclear Information System (INIS)

1994-10-01

This standard describes an acceptable method to prepare, review, and approve implementation plans for DOE Nuclear Safety requirements. DOE requirements are identified in DOE Rules, Orders, Notices, Immediate Action Directives, and Manuals

ENHANCING FOOD SAFETY AND STABILITY THROUGH IRRADIATION: A REVIEW

Directory of Open Access Journals (Sweden)

Manzoor Ahmad Shah

2014-04-01

Full Text Available Food irradiation is one of the non thermal food processing methods. It is the process of exposing food materials to the controlled amounts of ionizing radiations such as gamma rays, X-rays and accelerated electrons, to improve microbiological safety and stability. Irradiation disrupts the biological processes that lead to decay of food quality. It is an effective tool to reduce food-borne pathogens, spoilage microorganisms and parasites; to extend shelf-life and for insect disinfection. The safety and consumption of irradiated foods have been extensively studied at national levels and in international cooperations and have concluded that foods irradiated under appropriate technologies are both safe and nutritionally adequate. Specific applications of food irradiation have been approved by national legislations of more than 55 countries worldwide. This review aims to discuss the applications of irradiation in food processing with the emphasis on food safety and stability.

Comparison of Domestic Safety Review and European Union(EU) Stress Test After Nuclear Accident in Fukushima Daiichi NPPs

Energy Technology Data Exchange (ETDEWEB)

Kang, Hwa Sung; Kim, Jin Weon [Chosun University, Gwangju (Korea, Republic of)

2016-05-15

The European Union(EU) nuclear regulators group established stress test criteria and procedures, and utilities performed a self-review in accordance with those criteria and procedures. For Wolsung nuclear unit-1,the stress test was additionally conducted for deciding the continued operation of NPP, even though the safety review had been conducted after Fukushima NPP accident. Thus, this study is to compares the process, criteria, and results of the safety review performed in domestic NPPs and EU stress test performed in Cernavoda NPP. From the comparisons, the effectiveness and necessity of the stress test to decide the continued operation of NPPs is discussed. and the improvement items for safety enhancement are derived. The comparison showed that the process and review criteria of EU stress test was more systematic and specific than those used in domestic NPPs. But it was indicated that the improvement items resulted from the safety review performed in domestic NPPs are more comprehensive and powerful than EU stress tests (Cernavoda NPP) results. EU stress test for Cernavoda NPP evaluated in 3 fieldsand derived 13 design change items. The 50 improvement items derived from domestic safety review were including the contents of these 13 items.

Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report

International Nuclear Information System (INIS)

Herborn, D.I.

1993-11-01

Westinghouse Hanford Company (WHC) is the Integrating Contractor for the Hanford Waste Vitrification Plant (HWVP) Project, and as such is responsible for preparation of the HWVP Preliminary Safety Analysis Report (PSAR). The HWVP PSAR was prepared pursuant to the requirements for safety analyses contained in US Department of Energy (DOE) Orders 4700.1, Project Management System (DOE 1987); 5480.5, Safety of Nuclear Facilities (DOE 1986a); 5481.lB, Safety Analysis and Review System (DOE 1986b) which was superseded by DOE order 5480-23, Nuclear Safety Analysis Reports, for nuclear facilities effective April 30, 1992 (DOE 1992); and 6430.lA, General Design Criteria (DOE 1989). The WHC procedures that, in large part, implement these DOE requirements are contained in WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual. This manual describes the overall WHC safety analysis process in terms of requirements for safety analyses, responsibilities of the various contributing organizations, and required reviews and approvals

Integrated plant safety assessment, Systematic Evaluation Program: Dresden Nuclear Power Station, Unit 2 (Docket No. 50-237)

International Nuclear Information System (INIS)

1989-10-01

The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0823), under the scope of the Systematic Evaluation Program (SEP), for the Commonwealth Edison Company (CECo) Dresden Nuclear Power Station, Unit 2 located in Grundy County, Illinois. The NRC initiated the SEP to provide the framework for reviewing the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed by means of the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations subsequent to issuing the final IPSAR for Dresden Unit 2. The review was provided for (1) an assessment of the significance of differences between current technical positions on selected issues and those that existed when Dresden Unit 2 was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. The final IPSAR and this supplement forms part of the bases for considering the conversion of the existing provisional operating license to a full-term operating license. 83 refs., 9 tabs

Shielding modification and safety review on the nuclear ship 'Mutsu'

International Nuclear Information System (INIS)

Osanai, Masao

1978-01-01

The Japan Atomic Energy Commission (JAEC) called on the Japan Nuclear Ship Development Agency (JNSDA) for shielding modification and safety review on the nuclear ship ''Mutsu'', and JNSDA has conducted the research and development (R and D) to meet the request of JAEC for the above two items. Concerning the shield modification, the following matters are described: the study on the cause of radiation leakage which was concluded to the fast neutron streaming, the conceptual design for this modification, the mock up experiment for shielding utilizing JRR-4, the basic design following on the conceptual design, including the detailed drawings of the modified construction and the shielding analysis using RADHEAT-V3 code, and the relating experiments such as the heat transfer test of the primary shielding structure and the test of strength in stranding. As for the safety review, the survey of the troubles and the technical problems having been experienced in the light water reactor plants of land use, for example, fuel integrity, stress corrosion cracking and the leakage of steam generator tubes, the revision of the design so as to adapt to current safety standards and regulations, for example, in-service inspection, the setting of additional leak detectors in the primary cooling system, the modification of emergeney filters, etc., and the review of the design and construction corresponding to recent R and D works, such as re-evaluation of the core design, cooling capability of natural circulation, thermal stress analysis of main pipings, and the evaluation of ECCS performance are presented . (Nakai, Y.)

Obtaining Valid Safety Data for Software Safety Measurement and Process Improvement

Science.gov (United States)

Basili, Victor r.; Zelkowitz, Marvin V.; Layman, Lucas; Dangle, Kathleen; Diep, Madeline

2010-01-01

We report on a preliminary case study to examine software safety risk in the early design phase of the NASA Constellation spaceflight program. Our goal is to provide NASA quality assurance managers with information regarding the ongoing state of software safety across the program. We examined 154 hazard reports created during the preliminary design phase of three major flight hardware systems within the Constellation program. Our purpose was two-fold: 1) to quantify the relative importance of software with respect to system safety; and 2) to identify potential risks due to incorrect application of the safety process, deficiencies in the safety process, or the lack of a defined process. One early outcome of this work was to show that there are structural deficiencies in collecting valid safety data that make software safety different from hardware safety. In our conclusions we present some of these deficiencies.

International Expert Team Concludes IAEA Peer Review of Slovakia's Regulatory Framework for Nuclear Safety

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of senior nuclear safety and radiation protection experts today concluded an 11-day mission to review the regulatory framework for nuclear safety in Slovakia. At the request of the Slovak Government, the IAEA assembled a team of 12 senior regulatory experts from 12 nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Nuclear Regulatory Authority of the Slovak Republic (UJD SR). The international experts also met officials from the Public Health Authority of the Slovak Republic (UVZ SR) regarding the regulation of occupational radiation protection in nuclear facilities. The mission is a peer review based on the IAEA Safety Standards. Marta Ziakova, Chairperson of the Nuclear Regulatory Authority of Slovak Republic, declared that ''The IRRS mission has a great value for the future development and orientation of the UJD SR.'' ''Slovakia has established a regulatory framework for nuclear safety which is in line with international standards and practice,'' said Mission Team Leader Andrej Stritar, Director of the Slovenian Nuclear Safety Administration. The main observations of the IRRS Review team included: UJD SR operates with independence and transparency; UJD SR has developed and implemented a systematic training approach to meet its competence needs; and in response to the accident at TEPCO's Fukushima Daiichi Nuclear Power Station, UJD SR has reacted and communicated to interested parties, including the public. The good practices identified by the IRRS Review Team include: UJD SR has a comprehensive and well-formalized strategic approach to informing and consulting interested parties; UJD SR has developed and implemented a structured approach to training and developing its staff; and Detailed legal requirements provide a solid basis for on-site and off-site response in nuclear emergencies coordinated with local authorities. The IRRS Review team identified areas for further improvement and believes

Radiation safety

International Nuclear Information System (INIS)

Van Riessen, A.

2002-01-01

Full text: Experience has shown that modem, fully enclosed, XRF and XRD units are generally safe. This experience may lead to complacency and ultimately a lowering of standards which may lead to accidents. Maintaining awareness of radiation safety issues is thus an important role for all radiation safety officers. With the ongoing progress in technology, a greater number of radiation workers are more likely to use a range of instruments/techniques - eg portable XRF, neutron beam analysis, and synchrotron radiation analysis. The source for each of these types of analyses is different and necessitates an understanding of the associated dangers as well as use of specific radiation badges. The trend of 'suitcase science' is resulting in scientists receiving doses from a range of instruments and facilities with no coordinated approach to obtain an integrated dose reading for an individual. This aspect of radiation safety needs urgent attention. Within Australia a divide is springing up between those who work on Commonwealth property and those who work on State property. For example a university staff member may operate irradiating equipment on a University campus and then go to a CSIRO laboratory to operate similar equipment. While at the University State regulations apply and while at CSIRO Commonwealth regulations apply. Does this individual require two badges? Is there a need to obtain two licences? The application of two sets of regulations causes unnecessary confusion and increases the workload of radiation safety officers. Radiation safety officers need to introduce risk management strategies to ensure that both existing and new procedures result in risk minimisation. A component of this strategy includes ongoing education and revising of regulations. AXAA may choose to contribute to both of these activities as a service to its members as well as raising the level of radiation safety for all radiation workers. Copyright (2002) Australian X-ray Analytical

The safety and regulation of natural products used as foods and food ingredients.

Science.gov (United States)

Abdel-Rahman, Ali; Anyangwe, Njwen; Carlacci, Louis; Casper, Steve; Danam, Rebecca P; Enongene, Evaristus; Erives, Gladys; Fabricant, Daniel; Gudi, Ramadevi; Hilmas, Corey J; Hines, Fred; Howard, Paul; Levy, Dan; Lin, Ying; Moore, Robert J; Pfeiler, Erika; Thurmond, T Scott; Turujman, Saleh; Walker, Nigel J

2011-10-01

The use of botanicals and dietary supplements derived from natural substances as an adjunct to an improved quality of life or for their purported medical benefits has become increasingly common in the United States. This review addresses the safety assessment and regulation of food products containing these substances by the U.S. Food and Drug Administration (FDA). The issue of safety is particularly critical given how little information is available on the toxicity of some of these products. The first section uses case studies for stevia and green tea extracts as examples of how FDA evaluates the safety of botanical and herbal products submitted for consideration as Generally Recognized as Safe under the Federal Food, Drug, and Cosmetics Act. The 1994 Dietary Supplement Health Education Act (DSHEA) created a regulatory framework for dietary supplements. The article also discusses the regulation of this class of dietary supplements under DSHEA and addresses the FDA experience in analyzing the safety of natural ingredients described in pre-market safety submissions. Lastly, we discuss an ongoing interagency collaboration to conduct safety testing of nominated dietary supplements.

Perceived personal safety in relation to urban woodland vegetation – A review

OpenAIRE

Jansson, Märit; Fors, Hanna; Lindgren, Therese; Wiström, Björn

2013-01-01

Urban woodland vegetation provides people with many aesthetic, ecological and psychological benefits, but can also generate problems concerning people’s perception of safety. This paper reviews existing knowledge about perceived personal safety in relation to vegetation, particularly woodland vegetation, in urban green spaces such as parks and residential areas. Individual and social factors, but also vegetation character, maintenance and design, proved to be important for perceived personal ...

Safety of licensed vaccines in HIV-infected persons: a systematic review protocol

Science.gov (United States)

2014-01-01

Background Safety of vaccines remains a cornerstone of building public trust on the use of these cost-effective and life-saving public health interventions. In some settings, particularly Sub-Saharan Africa, there is a high prevalence of HIV infection and a high burden of vaccine-preventable diseases. There is evidence suggesting that the immunity induced by some commonly used vaccines is not durable in HIV-infected persons, and therefore, repeated vaccination may be considered to ensure optimal vaccine-induced immunity in this population. However, some vaccines, particularly the live vaccines, may be unsafe in HIV-infected persons. There is lack of evidence on the safety profile of commonly used vaccines among HIV-infected persons. We are therefore conducting a systematic review to assess the safety profile of routine vaccines administered to HIV-infected persons. Methods/Design We will select studies conducted in any setting where licensed and effective vaccines were administered to HIV-infected persons. We will search for eligible studies in PubMed, Web of Science, Cochrane Central Register of Controlled Trials (CENTRAL), Scopus, Africa-Wide, PDQ-Evidence and CINAHL as well as reference lists of relevant publications. We will screen search outputs, select studies and extract data in duplicate, resolving discrepancies by discussion and consensus. Discussion Globally, immunisation is a major public health strategy to mitigate morbidity and mortality caused by various infectious disease-causing agents. In general, there are efforts to increase vaccination coverage worldwide, and for these efforts to be successful, safety of the vaccines is paramount, even among people living with HIV, who in some situations may require repeated vaccination. Results from this systematic review will be discussed in the context of the safety of routine vaccines among HIV-infected persons. From the safety perspective, we will also discuss whether repeat vaccination strategies may be

ORSERG resource book. Operational reactor safety engineering and review group. Final report, March 1992

International Nuclear Information System (INIS)

1992-03-01

EPRI has prepared this resource book to help utilities with their Self-Assessment Programs at nuclear power plants. Self-assessments are reviews performed by nuclear power plant utilities to monitor plant performance status and adequacy, identify trends in operational activities important to safety, and assess the impact of these trends on plant safety. Activities performed as self-assessments include reviews and evaluations of plant performance and abnormal events, technical evaluations of plant activities to identify potential problem areas, and reviews of other sources of plant design and operating experience for applicability to safety. This resource book is based on information obtained from utilities and includes examples of activities and methods that have proven effective. The resource book includes a summary of NRC requirements, guidelines for self-assessment program planning, descriptions and examples of investigative techniques, and key references that can be consulted for additional information. It can serve as a training guide for plant staff members who are assigned to self-assessment activities. (author)

78 FR 4477 - Review of Safety Analysis Reports for Nuclear Power Plants, Introduction

Science.gov (United States)

2013-01-22

... Analysis Reports for Nuclear Power Plants: LWR Edition.'' The new subsection is the Standard Review Plan... Nuclear Power Plants: Integral Pressurized Water Reactor (iPWR) Edition.'' DATES: Comments must be filed... NUCLEAR REGULATORY COMMISSION [NRC-2012-0268] Review of Safety Analysis Reports for Nuclear Power...

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

Science.gov (United States)

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

2018-04-01

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

Fission, critical mass and safety-a historical review

International Nuclear Information System (INIS)

Meggitt, Geoff

2006-01-01

Since the discovery of fission, the notion of a chain reaction in a critical mass releasing massive amounts of energy has haunted physicists. The possibility of a bomb or a reactor prompted much of the early work on determining a critical mass, but the need to avoid an accidental critical excursion during processing or transport of fissile material drove much that took place subsequently. Because of the variety of possible situations that might arise, it took some time to develop adequate theoretical tools for criticality safety and the early assessments were based on direct experiment. Some extension of these experiments to closely similar situations proved possible, but it was not until the 1960s that theoretical methods (and computers to run them) developed enough for them to become reliable assessment tools. Validating such theoretical methods remained a concern, but by the end of the century they formed the backbone of criticality safety assessment. This paper traces the evolution of these methods, principally in the UK and USA, and summarises some related work concerned with the nature of criticality accidents and their radiological consequences. It also indicates how the results have been communicated and used in ensuring nuclear safety. (review)

International Nuclear Safety Experts Conclude IAEA Peer Review of Swiss Regulatory Framework

International Nuclear Information System (INIS)

2011-01-01

Full text: A team of international nuclear safety experts today completed a two-week International Atomic Energy Agency (IAEA) review of the regulatory framework for nuclear safety in Switzerland. The Integrated Regulatory Review Service (IRRS) mission noted good practices in the Swiss system and also made recommendations for the nation's nuclear regulatory authority, the Swiss Federal Nuclear Safety Inspectorate (ENSI). ''Our team developed a good impression of the independent Swiss regulator - ENSI - and the team considered that ENSI deserves particular credit for its actions to improve Swiss safety capability following this year's nuclear accident in Japan,'' said IRRS Team Leader Jean-Christophe Niel of France. The mission's scope covered the Swiss nuclear regulatory framework for all types of nuclear-related activities regulated by ENSI. The mission was conducted from 20 November to 2 December, mainly at ENSI headquarters in Brugg. The team held extensive discussions with ENSI staff and visited many Swiss nuclear facilities. IRRS missions are peer reviews, not inspections or audits, and are conducted at the request of host nations. For the Swiss review, the IAEA assembled a team of 19 international experts from 14 countries. The experts came from Belgium, Brazil, the Czech Republic, Finland, France, Germany, Italy, the Republic of Korea, Norway, Russia, Slovakia, Sweden, the United Kingdom, and the United States. ''The findings of the IRRS mission will help us to further improve our work. That is part of our safety culture,'' said ENSI Director General Hans Wanner. ''As Switzerland argued at international nuclear safety meetings this year for a strengthening of the international monitoring of nuclear power, we will take action to fulfil the recommendations.'' The IRRS team highlighted several good practices of the Swiss regulatory system, including the following: ENSI requires Swiss nuclear operators to back-fit their facilities by continuously upgrading

International Cooperation in the Field of International Space Station (ISS) Payload Safety

Science.gov (United States)

Grayson, C.; Sgobba, T.; Larsen, A.; Rose, S.; Heimann, T.; Ciancone, M.; Mulhern, V.

2005-12-01

In the frame of the International Space Station (ISS) Program cooperation, in 1998 the European Space Agency (ESA) approached the National Aeronautics and Space Administration (NASA) with the unique concept of a Payload Safety Review Panel (PSRP) "franchise" based at the European Space Technology Center (ESTEC), where the panel would be capable of autonomously reviewing flight hardware for safety. This paper will recount the course of an ambitious idea as it progressed into a fully functional reality. It will show how a panel initially conceived at NASA to serve a national programme has evolved into an international safety cooperation asset. The PSRP established at NASA began reviewing ISS payloads approximately in late 1994 or early 1995 as an expansion of the pre- existing Shuttle Program PSRP. This paper briefly describes the fundamental Shuttle safety process and the establishment of the safety requirements for payloads intending to use the Space Transportation System and ISS. The paper will also offer some historical statistics about the experiments that completed the payload safety process for Shuttle and ISS. The paper then presents the background of ISS agreements and international treaties that had to be considered when establishing the ESA PSRP. The paper will expound upon the detailed franchising model, followed by an outline of the cooperation charter approved by the NASA Associate Administrator, Office of Space Flight, and ESA Director of Manned Spaceflight and Microgravity. The paper will then address the resulting ESA PSRP implementation and its success statistics to date. Additionally, the paper presents ongoing developments with the Japan Aerospace Exploration Agency (JAXA). The discussion will conclude with ideas for future developments, such to achieve a fully integrated international system of payload safety panels for ISS.

International Cooperation in the Field of International Space Station (ISS) Payload Safety

Science.gov (United States)

Heimann, Timothy; Larsen, Axel M.; Rose, Summer; Sgobba, Tommaso

2005-01-01

In the frame of the International Space Station (ISS) Program cooperation, in 1998, the European Space Agency (ESA) approached the National Aeronautics and Space Administration (NASA) with the unique concept of a Payload Safety Review Panel (PSRP) "franchise" based at the European Space Technology Center (ESTEC), where the panel would be capable of autonomously reviewing flight hardware for safety. This paper will recount the course of an ambitious idea as it progressed into a fully functional reality. It will show how a panel initially conceived at NASA to serve a national programme has evolved into an international safety cooperation asset. The PSRP established at NASA began reviewing ISS payloads approximately in late 1994 or early 1995 as an expansion of the pre-existing Shuttle Program PSRP. This paper briefly describes the fundamental Shuttle safety process and the establishment of the safety requirements for payloads intending to use the Space Transportation System and International Space Station (ISS). The paper will also offer some historical statistics about the experiments that completed the payload safety process for Shuttle and ISS. The paper 1 then presents the background of ISS agreements and international treaties that had to be taken into account when establishing the ESA PSRP. The detailed franchising model will be expounded upon, followed by an outline of the cooperation charter approved by the NASA Associate Administrator, Office of Space Flight, and ESA Director of Manned Spaceflight and Microgravity. The resulting ESA PSRP implementation and its success statistics to date will then be addressed. Additionally the paper presents the ongoing developments with the Japan Aerospace Exploration Agency. The discussion will conclude with ideas for future developments, such to achieve a fully integrated international system of payload safety panels for ISS.

The Rare Cancer Network: ongoing studies and future strategy

Directory of Open Access Journals (Sweden)

Mahmut Ozsahin

2014-08-01

Full Text Available The Rare Cancer Network (RCN was formed in the early 1990’s to create a global network that could pool knowledge and resources in the studies of rare malignancies whose infrequency prevented both their study with prospective clinical trials. To date, the RCN has initiated 74 studies resulting in 46 peer reviewed publications. The First International Symposium of the Rare Cancer Network took place in Nice in March of 2014. Status updates and proposals for new studies were heard for fifteen topics. Ongoing studies continue for cardiac sarcomas, thyroid cancers, glomus tumors, and adult medulloblastomas. New proposals were presented at the symposium for primary hepatic lymphoma, solitary fibrous tumors, Rosai-Dorfman disease, tumors of the ampulla of Vater, salivary gland tumors, anorectal melanoma, midline nuclear protein in testes carcinoma, pulmonary lymphoepithelioma-like carcinoma, adenoid cystic carcinoma of the trachea, osteosarcomas of the mandible, and extra-cranial hemangiopericytoma. This manuscript presents the abstracts of those proposals and updates on ongoing studies, as well a brief summary of the vision and future of the RCN.

Status of the EU test blanket systems safety studies

International Nuclear Information System (INIS)

Panayotov, Dobromir; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

2015-01-01

Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

Status of the EU test blanket systems safety studies

Energy Technology Data Exchange (ETDEWEB)

Panayotov, Dobromir, E-mail: dobromir.panayotov@f4e.europa.eu; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

2015-10-15

Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

Review of the safety analysis of the Ignalina Nuclear Power Plant

International Nuclear Information System (INIS)

Weber, J.P.

1999-01-01

Description of the review of safety analysis report (SAR) of Ignalina NPP is presented. this review, called RSR, was conducted by independent group of international experts. SAR and RSR represented a unique international effort in a very short time. It was first attempt to provide Western-type SAR for any Soviet designed NPP. SAR was completed in December 1996, RSR was completed in March 1997. SAR has produced 85 reports, available on CR-ROM and RSR produced 86 reports also available on CD-ROM. SAR presented a large list of recommendations. RSR agreed with most of SAR recommendations and added further recommendations. SAR and RSR contributed significantly to better understanding of RBMK plant behaviour. Ignalina NPP has responded to the SAR/RSR recommendations by an ambitious Safety Improvement Programme SIP-2 which currently is under implementation

Can patients report patient safety incidents in a hospital setting? A systematic review.

Science.gov (United States)

Ward, Jane K; Armitage, Gerry

2012-08-01

Patients are increasingly being thought of as central to patient safety. A small but growing body of work suggests that patients may have a role in reporting patient safety problems within a hospital setting. This review considers this disparate body of work, aiming to establish a collective view on hospital-based patient reporting. This review asks: (a) What can patients report? (b) In what settings can they report? (c) At what times have patients been asked to report? (d) How have patients been asked to report? 5 databases (MEDLINE, EMBASE, CINAHL, (Kings Fund) HMIC and PsycINFO) were searched for published literature on patient reporting of patient safety 'problems' (a number of search terms were utilised) within a hospital setting. In addition, reference lists of all included papers were checked for relevant literature. 13 papers were included within this review. All included papers were quality assessed using a framework for comparing both qualitative and quantitative designs, and reviewed in line with the study objectives. Patients are clearly in a position to report on patient safety, but included papers varied considerably in focus, design and analysis, with all papers lacking a theoretical underpinning. In all papers, reports were actively solicited from patients, with no evidence currently supporting spontaneous reporting. The impact of timing upon accuracy of information has yet to be established, and many vulnerable patients are not currently being included in patient reporting studies, potentially introducing bias and underestimating the scale of patient reporting. The future of patient reporting may well be as part of an 'error detection jigsaw' used alongside other methods as part of a quality improvement toolkit.

[Patient safety in home care - A review of international recommendations].

Science.gov (United States)

Czakert, Judith; Lehmann, Yvonne; Ewers, Michael

2018-06-08

In recent years there has been a growing trend towards nursing care at home in general as well as towards intensive home care being provided by specialized home care services in Germany. However, resulting challenges for patient safety have rarely been considered. Against this background we aimed to explore whether international recommendations for patient safety in home care in general and in intensive home care in particular already exist and how they can stimulate further practice development in Germany. A review of online English documents containing recommendations for patient safety in intensive home care was conducted. Available documents were analyzed and compared in terms of their form and content. Overall, a small number of relevant documents could be identified. None of these documents exclusively refer to the intensive home care sector. Despite their differences, however, the analysis of four selected documents showed similarities, e. g., regarding specific topics of patient safety (communication, involvement of patients and their relatives, risk assessment, medication management, qualification). Furthermore, strengths and weaknesses of the documents became apparent: e. g., an explicit understanding of patient safety, a literature-based introduction to safety topics or an adaptation of the recommendations to the specific features of home care were occasionally lacking. This document analysis provides interesting input to the formal and content-related development of specific recommendations and to practice development in Germany to improve patient safety in home care. Copyright © 2018. Published by Elsevier GmbH.

Safety and clinical efficacy of golimumab in the treatment of arthritides

Directory of Open Access Journals (Sweden)

Ismail Simsek

2010-09-01

Full Text Available Ismail Simsek, Yusuf YaziciNew York University School of Medicine, NYU Hospital for Joint Diseases, New York, USAAbstract: Golimumab is a human anti-tumor necrosis factor (TNF-alpha monoclonal antibody that was recently approved for the treatment of patients with rheumatoid arthritis, psoriatic arthritis, and ankylosing spondylitis. This review covers the published clinical trial data on the use of golimumab for the approved indications mentioned above with respect to efficacy and safety. The various ongoing trials for golimumab have yielded promising results in terms of efficacy and safety in methotrexate-naive and -resistant patients with rheumatoid arthritis, as well as in patients who were previously treated with other anti-TNF agents. In addition, the efficacy of golimumab in psoriatic arthritis and ankylosing spondylitis has also been demonstrated. The real safety information will be available only once the drug has been used in many more patients, who frequently have comorbid conditions.Keywords: arthritis, rheumatoid, psoriatic arthritis, ankylosing spondylitis

Safety Experts Complete IAEA Nuclear Regulatory Review of the United States

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of senior nuclear safety experts today completed a two-week International Atomic Energy Agency (IAEA) review of the governmental and regulatory framework for nuclear safety in the United States. The team identified good practices within the U.S. system and offered suggestions for ways the U.S. Nuclear Regulatory Commission (NRC) could improve. The IAEA has conveyed the team's main conclusions to the NRC, and a final report will be submitted to the NRC in about two months. At the request of the United States, the IAEA assembled a team of 19 international experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This mission was a peer review based on the IAEA Safety Standards. It was not an inspection, nor an audit. The experts came from 14 different countries: Canada, China, the Czech Republic, Finland, France, Italy, Japan, Mexico, the Republic of Korea, Slovenia, Spain, Sweden, Switzerland, and the United Kingdom. Team leader Jukka Laaksonen of Finland said: ''We found a comprehensive, consistent, and mature regulatory system run by the NRC, which has a strong drive for continuous improvement.' The scope of the mission included the U.S. regulatory framework and the regulation of the nuclear plant operation. The mission was conducted from 18 to 29 October, mainly at NRC headquarters outside of Washington, D.C. To study U.S. regulatory activities, the mission conducted a series of interviews and discussions with NRC staff and other organizations to help assess the effectiveness of the regulatory system. In addition, the team observed regulatory activities at two operating nuclear power reactors and an emergency preparedness exercise. The IAEA's IRRS coordinator Gustavo Caruso said, ''This mission represents a milestone for the IRRS program because the U.S. regulatory system is the largest in the world and many nations look to it. The IRRS is a useful tool that allows host nations to gain guidance from experienced

Regulatory review of probabilistic safety assessment (PSA) level 1

International Nuclear Information System (INIS)

2000-02-01

Probabilistic safety assessment (PSA) is increasingly being used as part of the decision making process to assess the level of safety of nuclear power plants. The methodologies in use are maturing and the insights gained from the PSAs are being used along with those from the deterministic analysis. Many regulatory authorities consider that the current state of the art in PSA (especially Level 1 PSA) is sufficiently well developed that it can be used centrally in the regulatory decision making process - referred to as 'risk informed regulation'. For these applications to be successful, it will be necessary for regulatory authorities to have a high degree of confidence in PSA. However, at the IAEA Technical Committee Meeting on Use of PSA in the Regulatory Process in 1994 and at the OECD Nuclear Energy Agency Committee for Nuclear Regulatory Activities (CNRA) 'Special Issues' Meeting in 1997 on Review Procedures and Criteria for Different Regulatory Applications of PSA, it was recognized that formal regulatory review guidance for PSA did not exist. The senior regulators noted that there was a need to produce some international guidance for reviewing PSAs to establish an agreed basis for assessing whether important technological and methodological issues in PSAs are treated adequately and to verify that conclusions reached are appropriate. In 1997 the IAEA and OECD Nuclear Energy Agency agreed to produce in co-operation a technical document on the regulatory review of PSA. This publication is intended to provide guidance to regulatory authorities on how to review the PSA for a nuclear power plant to gain confidence that it has been carried out to an acceptable standard so that it can be used as the basis for taking risk informed decisions within a regulatory decision making process. The document gives guidance on how to set about reviewing a PSA and on the technical issues that need to be addressed. This publication gives guidance for the review of Level 1 PSA for

Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants

International Nuclear Information System (INIS)

O'Hara, J.M.; Higgins, J.; Fleger, Stephen

2011-01-01

The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

AGI Safety Literature Review

OpenAIRE

Everitt, Tom; Lea, Gary; Hutter, Marcus

2018-01-01

The development of Artificial General Intelligence (AGI) promises to be a major event. Along with its many potential benefits, it also raises serious safety concerns (Bostrom, 2014). The intention of this paper is to provide an easily accessible and up-to-date collection of references for the emerging field of AGI safety. A significant number of safety problems for AGI have been identified. We list these, and survey recent research on solving them. We also cover works on how best to think of ...

Nuclear Safety Review for the Year 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-15

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

An updated status of Department of Energy safety reviews of packages for transporting radioactive material

International Nuclear Information System (INIS)

Kapoor, A.

1995-01-01

The Department of Energy conducts conformance reviews and issues Certificates of Compliance for Type B packaging for radioactive materials. Several offices within DOE perform these reviews which are required by the Department of Transportation to be to the regulations promulgated by the Nuclear Regulatory Commission or their safety equivalent. This paper focuses on one of these offices, the Office of Facility Safety Analysis, EH-32, which is responsible for reviewing and certifying packages other than those used for weapons and weapons component, for Naval Reactors, and for Civilian Radioactive Waste Management. This paper gives the background and organizational history of EH-32, discusses the version of regulations to which the packaging is reviewed, updates the status of these reviews, describes the effectiveness of the reviews, updates the training courses sponsored by EH-32, and mentions the new Quality Assurance Evaluations being started by EH-32

The safety of Ontario's nuclear power reactors. A scientific and technical review. A submission to the Ontario Nuclear Safety Review by Atomic Energy Canada Limited

International Nuclear Information System (INIS)

1987-01-01

This submission comments on the evolution of the Canadian nuclear program, the management of safety, and the reactor design, analysis, operation and research programs that contribute to the safety of the CANDU reactor and provide assurance of safety to the regulatory agency and to the public. The CANDU reactor system has been designed and developed with close cooperation between Atomic Energy of Canada Ltd. (AECL), utilities, manufacturers, and the Atomic Energy Control Board (AECB). The AECB has the responsibility, on behalf of the public, for establishing acceptable standards with respect to public risk and for establishing through independent review that these standards are satisfied. The plant designer has responsibility for defining how those standards will be met. The plant operator has responsibility for operating within the framework of those standards. The Canadian approach to safety design is based on the philosophy of defence in depth. Defence in depth is achieved through a high level of equipment quality, system redundancy and fail-safe design; regulating and process systems designed to maintain all process systems within acceptable operating parameters; and, independent safety systems to shut down the reactor, provide long-term cooling, and contain potential release of radioactivity in the event of an accident. The resulting design meets regulatory requirements not only in Canada but also in other countries. Probabilistic safety and risk evaluations show that the CANDU design offers a level of safety and least as good as other commercially available reactor designs