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Sample records for safety guidelines volume

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

    Science.gov (United States)

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

    2015-01-01

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

  2. Electrical safety guidelines

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    The Electrical Safety Guidelines prescribes the DOE safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety standards and guidance for DOE installations in order to affect a reduction or elimination of risks associated with the use of electrical energy. The objectives of these guidelines are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  3. Public safety around dams guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, T [Canadian Dam Association, Edmonton, AB (Canada)

    2010-07-01

    This presentation discussed Canadian and international initiatives for improving dam safety and described some of the drivers for the development of new Canadian Dam Association (CDA) public safety guidelines for dams. The CDA guidelines were divided into the following 3 principal sections: (1) managed system elements, (2) risk assessment and management, and (3) technical bulletins. Public and media responses to the drownings have called for improved safety guidelines. While the public remains unaware of the hazards of dams, public interaction with dams is increasing as a result of interest in extreme sports and perceived rights of access. Guidelines are needed for dam owners in order to provide due diligence. Various organizations in Canada are preparing technical and public safety dam guidelines. CDA guidelines have also been prepared for signage, booms and buoys, and audible and visual alerts bulletins. Working groups are also discussing recommended practices for spill procedures, spillways and the role of professional engineers in ensuring public safety. Methods of assessing risk were also reviewed. Managed system elements for risk assessment and public interactions were also discussed, and stepped control measures were presented. tabs., figs.

  4. Best-practices guidelines for L2PSA development and applications. Volume 1 - General

    International Nuclear Information System (INIS)

    Raimond, E.; Pichereau, F.; Durin, T.; Rahni, N.; Loeffler, H.; Roesch, O.; Lajtha, G.; Santamaria, C.S.; Dienstbier, J.; Rydl, A.; Holmberg, J.E.; Lindholm, I.; Maennistoe, I.; Pauli, E.M.; Dirksen, G.; Grindon, L.; Peers, K.; Bassi, C.; Hulqvist, G.; Parozzi, F.; Polidoro, F.; Cazzoli, E.; Vitazkova, J.; Burgazzi, L.; Brinkman, H.; Seidel, A.; Schubert, B.; Wohlstein, R.; Guentay, S.; Oury, L.; Ngatchou, C.; Siltanen, S.; Niemela, I.; Routamo, T.; Vincon, L.; Helstroem, P.

    2010-01-01

    The objective of this coordinated action was to develop best practice guidelines for the performance and application of Level 2 PSA with a view to achieve harmonisation at EU level and to allow a meaningful and practical uncertainty evaluation in a Level 2 PSA. Specific relationships with communities in charge of nuclear reactor safety (utilities, safety authorities, vendors, and research or services companies) have been established in order to define the current needs in terms of guidelines for Level 2 PSA development and application. An international workshop was organised in Hamburg, with the support of VATTENFALL, in November 2008. The Level 2 PSA experts from ASAMPSA2 project partners have proposed some guidelines for the development and application of L2PSA based on their experience, open literature, and on information available from international cooperation (EC Severe Accident network of Excellence - SARNET, IAEA standards, OECD-NEA publications and workshop). There are a large number of technical issues addressed in the guideline which are not all covered with the same level of detail in the first version of the guideline. This version was submitted for external review in November 2010 by severe accident and PSA experts (especially from SARNET and OECD-NEA members). The feedback of the external review will be dis cussed during an international open works hop planned for March 2011 and all outcomes will be taken into consideration in the final version of this guideline (June 2011). The guideline includes 3 volumes: - Volume 1 - General considerations on L2PSA. - Volume 2 - Technical recommendations for Gen II and III reactors. - Volume 3 - Specific considerations for future reactors (Gen IV). The recommendations formulated in the guideline should not be considered as 'mandatory' but should help Level 2 PSA developers to achieve high quality studies with limited time and resources. It may also help Level 2 PSA reviewers by positioning one specific study in

  5. Guidelines for nuclear reactor equipments safety-analysis

    International Nuclear Information System (INIS)

    1978-01-01

    The safety analysis in approving the applications for nuclear reactor constructions (or alterations) is performed by the Committee on Examination of Reactor Safety in accordance with various guidelines prescribed by the Atomic Energy Commission. In addition, the above Committee set forth its own regulations for the safety analysis on common problems among various types of nuclear reactors. This book has collected and edited those guidelines and regulations. It has two parts: Part I includes the guidelines issued to date by the Atomic Energy Commission: and Part II - regulations of the Committee. Part I has collected 8 categories of guidelines which relate to following matters: nuclear reactor sites analysis guidelines and standards for their applications; standard exposure dose of plutonium; nuclear ship operation guidelines; safety design analysis guidelines for light-water type, electricity generating nuclear reactor equipments; safety evaluation guidelines for emergency reactor core cooling system of light-water type power reactors; guidelines for exposure dose target values around light-water type electricity generating nuclear reactor equipments, and guidelines for evaluation of above target values; and meteorological guidelines for the safety analysis of electricity generating nuclear reactor equipments. Part II includes regulations of the Committee concerning - the fuel assembly used in boiling-water type and in pressurized-water type reactors; techniques of reactor core heat designs, etc. in boiling-water reactors; and others

  6. Space station pressurized laboratory safety guidelines

    Science.gov (United States)

    Mcgonigal, Les

    1990-01-01

    Before technical safety guidelines and requirements are established, a common understanding of their origin and importance must be shared between Space Station Program Management, the User Community, and the Safety organizations involved. Safety guidelines and requirements are driven by the nature of the experiments, and the degree of crew interaction. Hazard identification; development of technical safety requirements; operating procedures and constraints; provision of training and education; conduct of reviews and evaluations; and emergency preplanning are briefly discussed.

  7. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Executive summary: Volume 1

    International Nuclear Information System (INIS)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer software used in the safety systems of nuclear power plants. The framework for the work consisted of the following software development and assurance activities: requirements specification; design; coding; verification and validation, including static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire range of software life-cycle activities; the assessment of the technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary, includes an overview of the framework and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; Volume 2 is the main report

  8. Human-system interface design review guideline -- Process and guidelines: Final report. Revision 1, Volume 1

    International Nuclear Information System (INIS)

    1996-06-01

    NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant's HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant's or licensee's HSI design

  9. A Handbook for Public Playground Safety. Volume II: Technical Guidelines for Equipment and Surfacing.

    Science.gov (United States)

    Consumer Product Safety Commission, Washington, DC.

    This handbook suggests safety guidelines for public playground equipment and describes various surfaces used under the equipment and possible injuries resulting from falls. The handbook is intended for use mainly by manufacturers, installers, school and park officials, and others interested in technical criteria for public playground equipment.…

  10. Cryogenic Safety Rules and Guidelines at CERN

    CERN Multimedia

    CERN. Geneva

    2016-01-01

    CERN defines and implements a Safety Policy that sets out the general principles governing safety at CERN. As an intergovernmental organisation, CERN further establishes its own Safety Rules as necessary for its proper functioning. In this process, it takes into account the laws and regulation of the Host States (France and Switzerland), EU regulations and directives, as well as international regulations, standards and directives. For the safety of cryogenic equipment, this is primarily covered by the Safety Regulation for Mechanical Equipment and the General Safety Instruction for Cryogenic Equipment. In addition, CERN has also developed Safety Guidelines to support the implementation of these safety rules, covering cryogenic equipment and oxygen deficiency hazard assessment and mitigation. An overview of the cryogenic safety rules and these safety guidelines will be presented.

  11. Human-system interface design review guideline -- Process and guidelines: Final report. Revision 1, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1996-06-01

    NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant`s or licensee`s HSI design.

  12. Efforts to update firefighter safety zone guidelines

    Science.gov (United States)

    Bret Butler

    2009-01-01

    One of the most critical decisions made on wildland fires is the identification of suitable safety zones for firefighters during daily fire management operations. To be effective (timely, repeatable, and accurate), these decisions rely on good training and judgment, but also on clear, concise guidelines. This article is a summary of safety zone guidelines and the...

  13. Highway Safety Program Manual: Volume 3: Motorcycle Safety.

    Science.gov (United States)

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

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

  14. NSPWG-recommended safety requirements and guidelines for SEI nuclear propulsion

    International Nuclear Information System (INIS)

    Marshall, A.C.; Lee, J.H.; McCulloch, W.H.; Sawyer, J.C. Jr.; Bari, R.A.; Brown, N.W.; Cullingford, H.S.; Hardy, A.C.; Remp, K.; Sholtis, J.A.

    1992-01-01

    An Interagency Nuclear Safety Policy Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program to facilitate the implementation of mission planning and conceptual design studies. The NSPWG developed a top- level policy to provide the guiding principles for the development and implementation of the nuclear propulsion safety program and the development of Safety Functional Requirements. In addition the NSPWG reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. Safety requirements were developed for reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, and safeguards. Guidelines were recommended for risk/reliability, operational safety, flight trajectory and mission abort, space debris and meteoroids, and ground test safety. In this paper the specific requirements and guidelines will be discussed

  15. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

    International Nuclear Information System (INIS)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report

  16. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B. [Mitre Corp., McLean, VA (United States)

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.

  17. Safety in Academic Chemistry Laboratories: Volume 2. Accident Prevention for Faculty and Administrators, 7th Edition.

    Science.gov (United States)

    American Chemical Society, Washington, DC.

    This book contains volume 2 of 2 and describes safety guidelines for academic chemistry laboratories to prevent accidents for college and university students. Contents include: (1) "Organizing for Accident Prevention"; (2) "Personal Protective Equipment"; (3) "Labeling"; (4) "Material Safety Data Sheets (MSDSs)"; (5) "Preparing for Medical…

  18. Human-system interface design review guideline -- Reviewer`s checklist: Final report. Revision 1, Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 2 is a complete set of the guidelines contained in Volume 1, Part 2, but in a checklist format that can be used by reviewers to assemble sets of individual guidelines for use in specific design reviews. The checklist provides space for reviewers to enter guidelines evaluations and comments.

  19. Safety in Academic Chemistry Laboratories: Volume 1. Accident Prevention for College and University Students, 7th Edition.

    Science.gov (United States)

    American Chemical Society, Washington, DC.

    This book contains volume 1 of 2 and describes safety guidelines for academic chemistry laboratories to prevent accidents for college and university students. Contents include: (1) "Your Responsibility for Accident Prevention"; (2) "Guide to Chemical Hazards"; (3) "Recommended Laboratory Techniques"; and (4) "Safety Equipment and Emergency…

  20. Guidelines for Self-assessment of Research Reactor Safety

    International Nuclear Information System (INIS)

    2018-01-01

    Self-assessment is an organization’s internal process to review its current status, processes and performance against predefined criteria and thereby to provide key elements for the organization’s continual development and improvement. Self-assessment helps the organization to think through what it is expected to do, how it is performing in relation to these expectations, and what it needs to do to improve performance, fulfil the expectations and achieve better compliance with the predefined criteria. This publication provides guidelines for a research reactor operating organization to perform a self-assessment of the safety management and the safety of the facility and to identify gaps between the current situation and the IAEA safety requirements for research reactors. These guidelines also provide a methodology for Member States, regulatory bodies and operating organizations to perform a self-assessment of their application of the provisions of the Code of Conduct on the Safety of Research Reactors. This publication also addresses planning, implementation and follow-up of actions to enhance safety and strengthen application of the Code. The guidelines are applicable to all types of research reactor and critical and subcritical assemblies, at all stages in their lifetimes, and to States, regulatory bodies and operating organizations throughout all phases of research reactor programmes. Research reactor operating organizations can use these guidelines at any time to support self-assessments conducted in accordance with the organization’s integrated management system. These guidelines also serve as a tool for an organization to prepare to receive an IAEA Integrated Safety Assessment of Research Reactors (INSARR) mission. An important result of this is the opportunity for an operating organization to identify focus areas and make safety improvements in advance of an INSARR mission, thereby increasing the effectiveness of the mission and efficiency of the

  1. Engineering design guidelines for nuclear criticality safety

    International Nuclear Information System (INIS)

    Waltz, W.R.

    1988-08-01

    This document provides general engineering design guidelines specific to nuclear criticality safety for a facility where the potential for a criticality accident exists. The guide is applicable to the design of new SRP/SRL facilities and to major modifications Of existing facilities. The document is intended an: A guide for persons actively engaged in the design process. A resource document for persons charged with design review for adequacy relative to criticality safety. A resource document for facility operating personnel. The guide defines six basic criticality safety design objectives and provides information to assist in accomplishing each objective. The guide in intended to supplement the design requirements relating to criticality safety contained in applicable Department of Energy (DOE) documents. The scope of the guide is limited to engineering design guidelines associated with criticality safety and does not include other areas of the design process, such as: criticality safety analytical methods and modeling, nor requirements for control of the design process

  2. Guidelines for upgrading of low volume roads

    CSIR Research Space (South Africa)

    Division of Roads

    1993-03-01

    Full Text Available The purpose of this manual is to provide guidelines on the upgrading of gravel low volume roads to roads and maintenance personnel of road authorities of all sizes. Low volume is, for the purpose of this document, defined to be less than 500...

  3. Sandia Software Guidelines, Volume 2. Documentation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This volume is one in a series of Sandia Software Guidelines intended for use in producing quality software within Sandia National Laboratories. In consonance with the IEEE Standards for software documentation, this volume provides guidance in the selection of an adequate document set for a software project and example formats for many types of software documentation. A tutorial on life cycle documentation is also provided. Extended document thematic outlines and working examples of software documents are available on electronic media as an extension of this volume.

  4. Sandia software guidelines, Volume 4: Configuration management

    Energy Technology Data Exchange (ETDEWEB)

    1992-06-01

    This volume is one in a series of Sandia Software Guidelines for use in producing quality software within Sandia National Laboratories. This volume is based on the IEEE standard and guide for software configuration management. The basic concepts and detailed guidance on implementation of these concepts are discussed for several software project types. Example planning documents for both projects and organizations are included.

  5. Contrast media. Safety issues and ESUR guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Thomsen, H.S. (ed.) [Copenhagen Univ. Hospital, Herlev (Denmark). Dept. of Diagnostic Radiology 54E2

    2006-07-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of the contrast media used in radiology departments. Since then, the committee has questioned members, reviewed the literature, proposed guidelines, and discussed these proposals with participants at the annual symposia on urogenital radiology. This book represents the end result of this hard work. It contains all of the agreed guidelines, updated when necessary, and thereby comprehensively covers the many different safety issues relating to the diverse contrast media: barium contrast media, iodinated contrast media, MR contrast media (both gadolinium-based extracellular and organ-specific) and ultrasound contrast media. The prevention and treatment of both acute and delayed non-renal adverse reactions as well as the renal adverse reactions are covered in detail. The inclusion of all the ESUR guidelines within one book will offer an invaluable, unique and unparalleled resource. (orig.)

  6. Contrast media. Safety issues and ESUR guidelines

    International Nuclear Information System (INIS)

    Thomsen, H.S.

    2006-01-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of the contrast media used in radiology departments. Since then, the committee has questioned members, reviewed the literature, proposed guidelines, and discussed these proposals with participants at the annual symposia on urogenital radiology. This book represents the end result of this hard work. It contains all of the agreed guidelines, updated when necessary, and thereby comprehensively covers the many different safety issues relating to the diverse contrast media: barium contrast media, iodinated contrast media, MR contrast media (both gadolinium-based extracellular and organ-specific) and ultrasound contrast media. The prevention and treatment of both acute and delayed non-renal adverse reactions as well as the renal adverse reactions are covered in detail. The inclusion of all the ESUR guidelines within one book will offer an invaluable, unique and unparalleled resource. (orig.)

  7. Safety culture enhancement through the implementation of IAEA guidelines

    International Nuclear Information System (INIS)

    Mengolini, A.; Debarberis, L.

    2007-01-01

    This paper presents the methodology applied and the results achieved in adapting and implementing the IAEA guidelines on safety culture to a research reactor as a step towards supporting its Life Management Program. The background is presented together with the effort undertaken to develop awareness on safety culture and the enhancement programme hereafter developed. The present study shows how issues of safety culture, management awareness and commitment deserve attention and can be of fundamental relevance also for research reactors. The study presents how guidelines developed specifically for nuclear power installations (NPPs) can be adapted to meet the needs and peculiarities of other nuclear installations. Moreover, the difficulties met during the implementation of the guidelines are discussed and important information and lessons can be learnt for the nuclear industry in general

  8. Nuclear criticality safety training: guidelines for DOE contractors

    International Nuclear Information System (INIS)

    Crowell, M.R.

    1983-09-01

    The DOE Order 5480.1A, Chapter V, Safety of Nuclear Facilities, establishes safety procedures and requirements for DOE nuclear facilities. This guide has been developed as an aid to implementing the Chapter V requirements pertaining to nuclear criticality safety training. The guide outlines relevant conceptual knowledge and demonstrated good practices in job performance. It addresses training program operations requirements in the areas of employee evaluations, employee training records, training program evaluations, and training program records. It also suggests appropriate feedback mechanisms for criticality safety training program improvement. The emphasis is on academic rather than hands-on training. This allows a decoupling of these guidelines from specific facilities. It would be unrealistic to dictate a universal program of training because of the wide variation of operations, levels of experience, and work environments among DOE contractors and facilities. Hence, these guidelines do not address the actual implementation of a nuclear criticality safety training program, but rather they outline the general characteristics that should be included

  9. Advanced human-system interface design review guideline. General evaluation model, technical development, and guideline description

    International Nuclear Information System (INIS)

    O'Hara, J.M.

    1994-07-01

    Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator's overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use

  10. Advanced human-system interface design review guideline. General evaluation model, technical development, and guideline description

    Energy Technology Data Exchange (ETDEWEB)

    O`Hara, J.M.

    1994-07-01

    Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.

  11. Highway Safety Program Manual: Volume 8: Alcohol in Relation to Highway Safety.

    Science.gov (United States)

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

    Volume 8 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on alcohol in relation to highway safety. The purpose and objectives of the alcohol program are outlined. Federal authority in the area of highway safety and general policies regarding…

  12. Advanced human-system interface design review guideline. Evaluation procedures and guidelines for human factors engineering reviews

    Energy Technology Data Exchange (ETDEWEB)

    O`Hara, J.M.; Brown, W.S. [Brookhaven National Lab., Upton, NY (United States); Baker, C.C.; Welch, D.L.; Granda, T.M.; Vingelis, P.J. [Carlow International Inc., Falls Church, VA (United States)

    1994-07-01

    Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.

  13. Advanced human-system interface design review guideline. Evaluation procedures and guidelines for human factors engineering reviews

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Brown, W.S.; Baker, C.C.; Welch, D.L.; Granda, T.M.; Vingelis, P.J.

    1994-07-01

    Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator's overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use

  14. Development of safety evaluation guidelines for base-isolated buildings in Japan

    International Nuclear Information System (INIS)

    Aoyama, Hiroyuki

    1989-01-01

    This paper describes the safety evaluation guidelines and the review process for non-nuclear base-isolated buildings proposed for construction in Japan. The paper discusses the guidelines application for two types of soil: hard soil and intermediate soil (soft soil was excluded.); safety evaluation items included in the level C design review; and safety margin of base isolation. Lessons learned through these design review efforts have potential applicability to design of seismic base isolation for nuclear power plants

  15. OSART Independent Safety Culture Assessment (ISCA) Guidelines

    International Nuclear Information System (INIS)

    2016-01-01

    Safety culture is understood as an important part of nuclear safety performance. This has been demonstrated by the analysis of significant events such as Chernobyl, Davis Besse, Vandellos II, Asco, Paks, Mihamma and Forsmark, among others. In order to enhance safety culture, one essential activity is to perform assessments. IAEA Safety Standard Series No. GS-R-3, The Management System for Facilitites and Activities, states requirements for continuous improvement of safety culture, of which self, peer and independent safety culture assessments constitute an essential part. In line with this requirement, the Independent Safety Culture Assessment (ISCA) module is offered as an add-on module to the IAEA Operational Safety Review Team (OSART) programme. The OSART programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. By including the ISCA module in an OSART mission, the receiving organization benefits from the synergy between the technical and the safety culture aspects of the safety review. The joint operational safety and safety culture assessment provides the organization with the opportunity to better understand the interactions between technical, human, organizational and cultural aspects, helping the organization to take a systemic approach to safety through identifying actions that fully address the root causes of any identified issue. Safety culture assessments provide insight into the fundamental drivers that shape organizational patterns of behaviour, safety consciousness and safety performance. The complex nature of safety culture means that the analysis of the results of such assessments is not as straightforward as for other types of assessment. The benefits of the results of nuclear safety culture assessments are maximized only if appropriate tools and guidance for these assessments is used; hence, this comprehensive guideline has been developed. The methodology explained

  16. EM Health and Safety Plan Guidelines

    Energy Technology Data Exchange (ETDEWEB)

    1994-12-01

    This document contains information about the Health and Safety Plan Guidelines. Topics discussed include: Regulatory framework; key personnel; hazard assessment; training requirements; personal protective equipment; extreme temperature disorders or conditions; medical surveillance; exposure monitoring/air sampling; site control; decontamination; emergency response/contingency plan; emergency action plan; confined space entry; and spill containment.

  17. [Definition of nodal volumes in breast cancer treatment and segmentation guidelines].

    Science.gov (United States)

    Kirova, Y M; Castro Pena, P; Dendale, R; Campana, F; Bollet, M A; Fournier-Bidoz, N; Fourquet, A

    2009-06-01

    To assist in the determination of breast and nodal volumes in the setting of radiotherapy for breast cancer and establish segmentation guidelines. Materials and methods. Contrast metarial enhanced CT examinations were obtained in the treatment position in 25 patients to clearly define the target volumes. The clinical target volume (CTV) including the breast, internal mammary nodes, supraclavicular and subclavicular regions and axxilary region were segmented along with the brachial plexus and interpectoral nodes. The following critical organs were also segmented: heart, lungs, contralateral breast, thyroid, esophagus and humeral head. A correlation between clinical and imaging findings and meeting between radiation oncologists and breast specialists resulted in a better definition of irradiation volumes for breast and nodes with establishement of segmentation guidelines and creation of an anatomical atlas. A practical approach, based on anatomical criteria, is proposed to assist in the segmentation of breast and node volumes in the setting of breast cancer treatment along with a definition of irradiation volumes.

  18. Sandia software guidelines: Volume 5, Tools, techniques, and methodologies

    Energy Technology Data Exchange (ETDEWEB)

    1989-07-01

    This volume is one in a series of Sandia Software Guidelines intended for use in producing quality software within Sandia National Laboratories. This volume describes software tools and methodologies available to Sandia personnel for the development of software, and outlines techniques that have proven useful within the Laboratories and elsewhere. References and evaluations by Sandia personnel are included. 6 figs.

  19. Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 4, In-vehicle safety

    Energy Technology Data Exchange (ETDEWEB)

    Mark, J.

    1992-11-01

    This report is the last of four volumes that identify and assess the environmental, health, and safety issues that may affect the commercial-scale use of sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles. The reports are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD&D) program for Na/S battery technology. The reports review the status of Na/S battery RD&D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers the in-vehicle safety issues of electric vehicles powered by Na/S batteries. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, and private industry. It has three major goals: (1) to identify the unique hazards associated with electric vehicle (EV) use; (2) to describe the existing standards, regulations, and guidelines that are or could be applicable to these hazards; and (3) to discuss the adequacy of the existing requirements in addressing the safety concerns of EVs.

  20. Development of Manitoba Hydro's public water safety around dams management guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, Dave; McPhail, Gord; Murphy, Shayla; Schellenberg, Gord [KGS Acres, Winnipeg, (Canada); Read, Nick [Manitoba Hydro, Winnipeg, (Canada)

    2010-07-01

    Several drowning fatalities and safety incidents have occurred around dams in Ontario, Manitoba and other jurisdictions in Canada. Following these incidents, Manitoba Hydro implemented several measures to improve public safety around its dams with the development of a warning signs manual. Manitoba Hydro found that a standard centralized approach to the process of improving public safety is better for ensuring compliance and consistency, even though they have safety measures in place. This paper described the process that Manitoba Hydro has followed in developing a formal set of public water safety around dams (PWSD) guidelines and a program for implementing these guidelines. This program was developed with the intent of providing a high standard of public protection and continuous improvement and monitoring on par with the effect spent on similar dam safety type programs. This paper focused on the development of the pilot PWSD management plan for Pine Falls generating station in order to test the effectiveness and usability of the guidelines.

  1. 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

  2. Safety investigation of 'Mutsu', the first nuclear ship in Japan (the correspondence to the guideline of safety design examination, etc.)

    International Nuclear Information System (INIS)

    1981-01-01

    Japan Nuclear Ship Development Agency had made previously application for the permission of the alteration of the reactor installation in the nuclear ship Mutsu (the first of this kind in Japan), based on the overall safety investigation of the ship made by JNDA. Taking the opportunity of the governmental safety examination concerning the permission, the correspondence of the safety aspects of the n.s. Mutsu to the existing guidelines for the safety of nuclear reactor facilities was examined. These results to further enhance the safety of the n.s. Mutsu are described concerning the following matters: the safety design examination guideline for power-generating LWR facilities (58 items); the safety evaluation guideline for power-generating LWR facilities (the analysis of abnormal transients during operation and accidents); the safety countermeasures to be adopted in the reactor plant of the n.s. Mutsu from the situation of the TMI nuclear accident in U.S. (7 in design and 10 in operation management); the analysis simulating the TMI accident. (J.P.N.)

  3. 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

  4. Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

    International Nuclear Information System (INIS)

    1993-11-01

    This document contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE non-reactor nuclear facilities. Adherence to these guidelines will provide consistency and uniformity in criticality safety evaluations (CSEs) across the complex and will document compliance with the requirements of DOE Order 5480.24

  5. Best-practices guidelines for L2PSA development and applications. Volume 2 - Best practices for the Gen II PWR, Gen II BWR L2PSAs. Extension to Gen III reactors

    International Nuclear Information System (INIS)

    Raimond, E.; Durin, T.; Rahni, N.; Meignen, R.; Cranga, M.; Pichereau, F.; Bentaib, A.; Guigueno, Y.; Loeffler, H.; Mildenberger, O.; Lajtha, G.; Santamaria, C.S.; Dienstbier, J.; Rydl, A.; Holmberg, J.E.; Lindholm, I.; Maennistoe, I.; Pauli, E.M.; Dirksen, G.; Grindon, L.; Peers, K.; Hulqvist, G.; Parozzi, F.; Polidoro, F.; Cazzoli, E.; Vitazkova, J.; Burgazzi, L.; Oury, L.; Ngatchou, C.; Siltanen, S.; Niemela, I.; Routamo, T.; Helstroem, P.; Bassi, C.; Brinkman, H.; Seidel, A.; Schubert, B.; Wohlstein, R.; Guentay, S.; Vincon, L.

    2010-01-01

    The objective of this coordinated action was to develop best practice guidelines for the performance of Level 2 PSA methodologies with a view of harmonisation at EU level and to allow meaningful and practical uncertainty evaluations in a Level 2 PSA. Specific relationships with community in charge of nuclear reactor safety (utilities, safety authorities, vendors, and research or services companies) have been established in order to define the current needs in terms of guidelines for level 2 PSA development and applications. An international workshop was organised in Hamburg, with the support of VATTENFALL, in November 2008. The level 2 PSA experts from the ASAMPSA2 project partners have proposed some guidelines for the development and application of L2PSA based on their experience and on information available from international cooperation (EC Severe Accident network of Excellence - SARNET, IAEA standards, OECD-NEA publications and workshop) or open literature. The number of technical issues addressed in the guideline is very large and all are not covered with the same relevancy in the first version of the guideline. This version is submitted for external review in November 2010 by severe accident experts and PSA, especially, from SARNET and OECD-NEA members. The feedback of the external review will be dis cussed during an international open works hop planned in March 2011 and all outcomes will be taken into consideration in the final version of this guideline (June 2011). The guideline includes 3 volumes: - Volume 1 - General considerations on L2PSA. - Volume 2 - Technical recommendations for Gen II and III reactors. - Volume 3 - Specific considerations for future reactor (Gen IV). The recommendations formulated in the guideline should not be considered as 'mandatory' but should help the L2PSA developers to achieve high quality studies with limited time and resources. It may also help the L2PSA reviewers by positioning one specific study in comparison with some

  6. Guidelines for selecting codes for ground-water transport modeling of low-level waste burial sites. Volume 1. Guideline approach

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, C.S.; Cole, C.R.

    1985-05-01

    This document was written for the National Low-Level Waste Management Program to provide guidance for managers and site operators who need to select ground-water transport codes for assessing shallow-land burial site performance. The guidance given in this report also serves the needs of applications-oriented users who work under the direction of a manager or site operator. The guidelines are published in two volumes designed to support the needs of users having different technical backgrounds. An executive summary, published separately, gives managers and site operators an overview of the main guideline report. This volume includes specific recommendations for decision-making managers and site operators on how to use these guidelines. The more detailed discussions about the code selection approach are provided. 242 refs., 6 figs.

  7. Guidelines for selecting codes for ground-water transport modeling of low-level waste burial sites. Volume 1. Guideline approach

    International Nuclear Information System (INIS)

    Simmons, C.S.; Cole, C.R.

    1985-05-01

    This document was written for the National Low-Level Waste Management Program to provide guidance for managers and site operators who need to select ground-water transport codes for assessing shallow-land burial site performance. The guidance given in this report also serves the needs of applications-oriented users who work under the direction of a manager or site operator. The guidelines are published in two volumes designed to support the needs of users having different technical backgrounds. An executive summary, published separately, gives managers and site operators an overview of the main guideline report. This volume includes specific recommendations for decision-making managers and site operators on how to use these guidelines. The more detailed discussions about the code selection approach are provided. 242 refs., 6 figs

  8. The Fukushima Daiichi Accident. Technical Volume 2/5. Safety Assessment

    International Nuclear Information System (INIS)

    2015-08-01

    Technical Volume 1 of this report has described what happened during the accident at the Fukushima Daiichi nuclear power plant (NPP). This volume begins (Section 2.1) with a review of how the design basis of the site for external events was assessed initially and then reassessed over the life of the NPP. The section also describes the physical changes that were made to the units as a result. The remainder of the volume describes the treatment of beyond design basis events in the safety assessment of the site, the accident management provisions, the effectiveness of regulatory programmes, human and organizational factors and the safety culture, and the role of operating experience. Further background information is contained in three annexes included on the CD-ROM of this Technical Volume which describe analytical investigations of the accident along with information on topics such as system performance, defence in depth and severe accident phenomena. Section 2.2 provides an assessment of the systems that failed, resulting in a failure to maintain the fundamental safety functions in Units 1–3, which were in operation at the time of the tsunami and in which the reactor pressure vessels (RPV) and containment vessels failed. The section also describes Units 4-6, which were shut down at the time of the tsunami, and the site’s central spent fuel storage facility. Section 2.3 discusses the probabilistic and deterministic safety assessments of beyond design basis accidents (BDBAs) that had been performed for the plant and the insights from these assessments that had led to changes in the plant’s design. The section pays particular attention to the assessment of extreme natural hazards, such as the one which led to the total loss of AC power supply on the site. The additional loss of DC power supply in Units 1 and 2 played a key role in the progression of the accident because it impeded the diagnosis of plant conditions and made the operators unaware of the status of

  9. Measure Guideline: Combustion Safety for Natural Draft Appliances Using Indoor Air

    Energy Technology Data Exchange (ETDEWEB)

    Brand, L.

    2014-04-01

    This measure guideline covers how to assess and carry out the combustion safety procedures for appliances and heating equipment that uses indoor air for combustion in low-rise residential buildings. Only appliances installed in the living space, or in an area freely communicating with the living space, vented alone or in tandem with another appliance are considered here. A separate measure guideline addresses combustion appliances located either within the living space in enclosed closets or side rooms or outside the living space in an adjacent area like an attic or garage that use outdoor air for combustion. This document is for inspectors, auditors, and technicians working in homes where energy upgrades are being conducted whether or not air infiltration control is included in the package of measures being applied. In the indoor combustion air case, guidelines summarized here are based on language provided in several of the codes to establish minimum requirements for the space using simplified prescriptive measures. In addition, building performance testing procedures are provided by testing agencies. The codes in combination with the test procedures offer comprehensive combustion safety coverage to address safety concerns, allowing inexperienced residential energy retrofit inspectors to effectively address combustion safety issues and allow energy retrofits to proceed.

  10. Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This Department of Energy (DOE) is approved for use by all components of DOE. It contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE Non-Reactor Nuclear Facilities. Adherence with these guidelines will provide consistency and uniformity in Criticality Safety Evaluations (CSEs) across the complex and will document compliance with DOE Order 5480.24 requirements as they pertain to CSEs.

  11. Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

    International Nuclear Information System (INIS)

    1998-09-01

    This Department of Energy (DOE) is approved for use by all components of DOE. It contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE Non-Reactor Nuclear Facilities. Adherence with these guidelines will provide consistency and uniformity in Criticality Safety Evaluations (CSEs) across the complex and will document compliance with DOE Order 5480.24 requirements as they pertain to CSEs

  12. Guidelines for implementation of RCM on safety systems

    International Nuclear Information System (INIS)

    Kim, Tae Woon; Brijendra Singh.

    1996-04-01

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

  13. NASA Aerospace Flight Battery Program: Generic Safety, Handling and Qualification Guidelines for Lithium-Ion (Li-Ion) Batteries; Availability of Source Materials for Lithium-Ion (Li-Ion) Batteries; Maintaining Technical Communications Related to Aerospace Batteries (NASA Aerospace Battery Workshop). Volume 1, Part 1

    Science.gov (United States)

    Manzo, Michelle A.; Brewer, Jeffrey C.; Bugga, Ratnakumar V.; Darcy, Eric C.; Jeevarajan, Judith A.; McKissock, Barbara I.; Schmitz, Paul C.

    2010-01-01

    This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 1 - Volume I: Generic Safety, Handling and Qualification Guidelines for Lithium-Ion (Li-Ion) Batteries, Availability of Source Materials for Lithium-Ion (Li-Ion) Batteries, and Maintaining Technical Communications Related to Aerospace Batteries (NASA Aerospace Battery Workshop).

  14. Review guidelines on software languages for use in nuclear power plant safety systems. Final report

    International Nuclear Information System (INIS)

    Hecht, H.; Hecht, M.; Graff, S.; Green, W.; Lin, D.; Koch, S.; Tai, A.; Wendelboe, D.

    1996-06-01

    Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada, C/C++, Programmable Logic Controller (PLC) Ladder Logic, International Electrotechnical Commission (IEC) Standard 1131-3 Sequential Function Charts, Pascal, and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages.s

  15. Human-system interface design review guideline -- Review software and user's guide: Final report. Revision 1, Volume 3

    International Nuclear Information System (INIS)

    1996-06-01

    NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant's HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 3 contains an interactive software application of the NUREG-0700, Revision 1 guidance and a user's guide for this software. The software supports reviewers during review preparation, evaluation design using the human factors engineering guidelines, and in report preparation. The user's guide provides system requirements and installation instructions, detailed explanations of the software's functions and features, and a tutorial on using the software

  16. An overview of review guidelines for HDL programmable devices in nuclear safety systems

    International Nuclear Information System (INIS)

    Komanduri, Raghavan; Srivani, L.; Thirugnana Murthy, D.

    2013-01-01

    HDL programmable devices viz. CPLDs and FPGAs are increasingly being used to implement digital designs in the I and C systems performing safety functions of nuclear power plants. Synthesizable RTL descriptions manually written in HDLs are the first step in developing industry standard large scale digital designs. The reliability of the implementation is determined by the methodologies followed by the designer during development. Very few guidelines on HPD design practices, specific to nuclear industry are available. This paper presents an overview of the existing guidelines such as IEC 62566 and U.S. NRC's 'Review guidelines for FPGAs in nuclear power plant safety systems'. (author)

  17. Monitoring and evaluation of Blyth Offshore wind farm: Health and Safety guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Pepper, L

    2002-07-01

    Experiences during the construction, operation and maintenance of the wind farm off the coast of Blyth in Northumberland are used to assess the practicality of implementing existing draft British Wind Energy Association (BWEA) guidelines. These best practice guidelines, which were drawn up in consultation with the Health and Safety Executive (HSE) offer advice on health and safety issues specific to the wind industry in the UK. The guidelines are intended to cover both onshore and offshore sites; common advice is followed by advice specific to offshore sites. The Blyth Offshore project, the first offshore wind farm in the UK, features two 2 MW turbines installed on a submerged rocky outcrop about 1 km from the coast in a depth of about 6 m at low tide and a tidal range of about 5 m. The report concluded that, from the experience at Blyth, the draft guidelines will provide a useful tool for those involved in all stages of a wind farm project.

  18. ASCOT guidelines revised 1996 edition. Guidelines for organizational self-assessment of safety culture and for reviews by the assessment of safety culture in organizations team

    International Nuclear Information System (INIS)

    1996-01-01

    In order to properly assess safety culture, it is necessary to consider the contribution of all organizations which have an impact on it. Therefore, while assessing the safety culture in an operating organization it is necessary to address at least its interfaces with the local regulatory agency, utility corporate headquarters and supporting organizations. These guidelines are primarily intended for use by any organization wishing to conduct a self-assessment of safety culture. They should also serve as a basis for conducting an international peer review of the organization's self-assessment carried out by an ASCOT (Assessment of Safety Culture in Organizations Team) mission

  19. Guideline for examination concerning the evaluation of safety in light water power reactor installations

    International Nuclear Information System (INIS)

    1978-01-01

    This guideline was drawn up as the guide for examination when the safety evaluation of nuclear reactors is carried out at the time of approving the installation of light water power reactors. Accordingly in case of the examination of safety, it must be confirmed that the contents of application are in conformity with this guideline. If they are in conformity, it is judged that the safety evaluation of the policy in the basic design of a reactor facility is adequate, and also that the evaluation concerning the separation from the public in surroundings is adequate as the condition of location of the reactor facility. This guideline is concerned with light water power reactors now in use, but the basic concept may be the reference for the examination of the other types of reactors. If such a case occurs that the safety evaluation does not conform to this guideline, it is not excluded when the appropriate reason is clarified. The purpose of safety evaluation, the scope to be evaluated, the selection of the events to be evaluated, the criteria for judgement, the matters taken into consideration at the time of analysis, the concrete events of abnormal transient change and accident in operation, and the concrete events of serious accident and hypothetic accident are stipulated. The explanation and two appendices are attached. (Kako, I.)

  20. Contrast media. Safety issues and ESUR guidelines. 2. rev. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Thomsen, Henrik S. [Copenhagen University Hospital, Herlev (Denmark). Dept. of Diagnostic Radiology; Copenhagen Univ., Herlev (Denmark). Dept. of Diagnostic Sciences; Webb, Judith A.W. (eds.) [St. Bartholomew' s Hospital London Univ. (United Kingdom). Dept. of Radiology

    2009-07-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned members, reviewed the literature, proposed guidelines and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006. This second edition not only updates the previous edition, but also contains some completely new chapters, for example on gadolinium-based contrast agents, meta-analyses in contrast media research and various regulatory issues. Comprehensive consideration is given to the many different safety issues relating to iodinated, MR, ultrasound and barium contrast media. The text includes chapters on both acute and delayed non-renal adverse reactions and on renal adverse reactions. All those questions frequently raised in radiological practice are addressed, and the well-known ESUR guidelines on contrast media are included. This book, presented in a handy, easy to use format, provides an invaluable, unique and unparalleled source of information on the safety issues relating to contrast media. (orig.)

  1. Contrast media. Safety issues and ESUR guidelines. 2. rev. ed.

    International Nuclear Information System (INIS)

    Thomsen, Henrik S.; Copenhagen Univ., Herlev; Webb, Judith A.W.

    2009-01-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned members, reviewed the literature, proposed guidelines and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006. This second edition not only updates the previous edition, but also contains some completely new chapters, for example on gadolinium-based contrast agents, meta-analyses in contrast media research and various regulatory issues. Comprehensive consideration is given to the many different safety issues relating to iodinated, MR, ultrasound and barium contrast media. The text includes chapters on both acute and delayed non-renal adverse reactions and on renal adverse reactions. All those questions frequently raised in radiological practice are addressed, and the well-known ESUR guidelines on contrast media are included. This book, presented in a handy, easy to use format, provides an invaluable, unique and unparalleled source of information on the safety issues relating to contrast media. (orig.)

  2. 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)

  3. Safety Specialist Manpower, Manpower Resources. Volumes II and III.

    Science.gov (United States)

    Booz Allen and Hamilton, Inc., Washington, DC.

    These second and third volumes of a four-volume study of manpower in state highway safety programs over the next decade estimate manpower resources by state and in national aggregate and describe present and planned training programs for safety specialists. For each educational level, both total manpower and manpower actually available for…

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

    International Nuclear Information System (INIS)

    1990-01-01

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

  5. KAERI software verification and validation guideline for developing safety-critical software in digital I and C system of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jang Yeol; Lee, Jang Soo; Eom, Heung Seop

    1997-07-01

    This technical report is to present V and V guideline development methodology for safety-critical software in NPP safety system. Therefore it is to present V and V guideline of planning phase for the NPP safety system in addition to critical safety items, for example, independence philosophy, software safety analysis concept, commercial off the shelf (COTS) software evaluation criteria, inter-relationships between other safety assurance organizations, including the concepts of existing industrial standard, IEEE Std-1012, IEEE Std-1059. This technical report includes scope of V and V guideline, guideline framework as part of acceptance criteria, V and V activities and task entrance as part of V and V activity and exit criteria, review and audit, testing and QA records of V and V material and configuration management, software verification and validation plan production etc., and safety-critical software V and V methodology. (author). 11 refs.

  6. KAERI software verification and validation guideline for developing safety-critical software in digital I and C system of NPP

    International Nuclear Information System (INIS)

    Kim, Jang Yeol; Lee, Jang Soo; Eom, Heung Seop.

    1997-07-01

    This technical report is to present V and V guideline development methodology for safety-critical software in NPP safety system. Therefore it is to present V and V guideline of planning phase for the NPP safety system in addition to critical safety items, for example, independence philosophy, software safety analysis concept, commercial off the shelf (COTS) software evaluation criteria, inter-relationships between other safety assurance organizations, including the concepts of existing industrial standard, IEEE Std-1012, IEEE Std-1059. This technical report includes scope of V and V guideline, guideline framework as part of acceptance criteria, V and V activities and task entrance as part of V and V activity and exit criteria, review and audit, testing and QA records of V and V material and configuration management, software verification and validation plan production etc., and safety-critical software V and V methodology. (author). 11 refs

  7. Discussions about safety criteria and guidelines for radioactive waste management.

    Science.gov (United States)

    Yamamoto, Masafumi

    2011-07-01

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

  8. 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

  9. The Italian National Guidelines for the fire safety of facades

    Directory of Open Access Journals (Sweden)

    Lamberto Mazziotti

    2013-11-01

    Full Text Available Traditionally, the facades' design buildings where once only focused on architectural or aesthetic purposes (in addition, of course, of whether protective issues. Nowadays, thanks to the technological development of the construction works and the use of new types of materials, the facades' design should also address fire safety related aspects. In Europe and especially in Italy – where the types of building façades are built with windows of small surface and natural stone coverings – the green building/sustainability movement has resulted in the development of new concepts in facade or curtain wall design that intended to enhance the energy efficiency of building façades. These new building surfaces are covered by extensive panelling fitted with insulating materials or by wide glass surfaces, capable of carry out the most diverse purposes including, just to name a few: energy reduction, climate comfort, recovery of electricity through photovoltaic panels that convert sunlight into electricity, large space for advertising purpose. One of the main fire safety goal for a building design is to restrict the vertical fire spread so that the smoke and flames are limited to the fire origin floor. The new building façade and curtain wall topologies could overwhelms concerns for fire safety, therefore the Italian National fire service has released a Fire Code Guideline in order to address the fire safety design for an high rise building façade. This paper aims to show the guideline contents and the related fire safety façades concerns.

  10. A guideline for comprehensive evaluation of a licensee's effort to cultivate safety culture

    International Nuclear Information System (INIS)

    Makino, Maomi; Ishii, Yoichi

    2009-01-01

    The nuclear industry in Japan had held excellent performance in safety in the world during 90's. However recent events stem from organizational factors and defects of safety culture are pointed out in their contexts. In order to reduce accidents caused by organizational factors, the Japanese Regulatory body NISA (Nuclear and Industrial Safety Agency) decided to evaluate a licensee's effort for the cultivation of safety culture, and to order all licensses to add the provision of cultivating safety culture to their safety preservation rules. The inspection for the new safety preservation rules started in December, 2007. For a measure of evaluation by resident inspectors, NISA and the Japan Nuclear Energy Safety Organization (JNES) prepared a guideline for the prevention of degradation of safety culture and organizational climate. In this guideline, 14 items were defined as the components of the safety culture or as the viewpoints to evaluate the effort made to prevent any degradation of safety culture and organizational climate in the daily safety preservation activities. The 14 items are also used to establish the method to comprehensively evaluate the effort to prevent degradation of safety culture and organizational climate. This method consists of 10 steps: two steps to taken prior to start of the evaluation, two steps to be taken during the evaluation period, 5 steps to be taken during a comprehensive evaluation period and a final step to be taken for comprehensive findings for safety culture. This paper mainly describes the viewpoints to evaluate comprehensively a licensee's effort for cultivation of safety culture. (author)

  11. Guidelines for pressure vessel safety assessment

    Science.gov (United States)

    Yukawa, S.

    1990-04-01

    A technical overview and information on metallic pressure containment vessels and tanks is given. The intent is to provide Occupational Safety and Health Administration (OSHA) personnel and other persons with information to assist in the evaluation of the safety of operating pressure vessels and low pressure storage tanks. The scope is limited to general industrial application vessels and tanks constructed of carbon or low alloy steels and used at temperatures between -75 and 315 C (-100 and 600 F). Information on design codes, materials, fabrication processes, inspection and testing applicable to the vessels and tanks are presented. The majority of the vessels and tanks are made to the rules and requirements of ASME Code Section VIII or API Standard 620. The causes of deterioration and damage in operation are described and methods and capabilities of detecting serious damage and cracking are discussed. Guidelines and recommendations formulated by various groups to inspect for the damages being found and to mitigate the causes and effects of the problems are presented.

  12. Technical guidelines for the seismic safety re-evaluation at Eastern European NPPs

    International Nuclear Information System (INIS)

    Godoy, A.R.; Guerpinar, A.

    2001-01-01

    The paper describes one of the outcomes of the Engineering Safety Review Services (ESRS) that the IAEA provides as an element of the Agency's national, regional and interregional technical assistance and co-operation programmes and other extrabudgetary programmes to assess the safety of nuclear facilities. This refers to the establishment of detailed guidelines for conducting the seismic safety re-evaluation of existing nuclear power plants in Eastern European countries in line with updated criteria and current international practice. (author)

  13. Review guidelines for software languages for use in nuclear power plant safety systems: Final report. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Hecht, M.; Decker, D.; Graff, S.; Green, W.; Lin, D.; Dinsmore, G.; Koch, S. [SoHaR, Inc., Beverly Hills, CA (United States)

    1997-10-01

    Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada83 and Ada95; C and C++; International Electrochemical Commission (IEC) Standard 1131-3 Ladder Logic, Sequential Function Charts, Structured Text, and Function Block Diagrams; Pascal; and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages.

  14. Review guidelines for software languages for use in nuclear power plant safety systems: Final report. Revision 1

    International Nuclear Information System (INIS)

    Hecht, M.; Decker, D.; Graff, S.; Green, W.; Lin, D.; Dinsmore, G.; Koch, S.

    1997-10-01

    Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada83 and Ada95; C and C++; International Electrochemical Commission (IEC) Standard 1131-3 Ladder Logic, Sequential Function Charts, Structured Text, and Function Block Diagrams; Pascal; and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages

  15. 75 FR 15485 - Pipeline Safety: Workshop on Guidelines for Integrity Assessment of Cased Pipe

    Science.gov (United States)

    2010-03-29

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID...: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice of workshop. SUMMARY... ``Guidelines for Integrity Assessment of Cased Pipe in Gas Transmission Pipelines'' and related Frequently...

  16. Radiologic measurement of extraocular muscle volumes in patients with Graves' orbitopathy: a review and guideline

    NARCIS (Netherlands)

    Bijlsma, Ward R.; Mourits, Maarten Ph

    2006-01-01

    OBJECTIVE: To evaluate and compare techniques for extraocular muscle (EOM) volume measurement and to provide guidelines for future measurements. DESIGN: Systematic review. RESULTS: Existing techniques used to measure extraocular muscle volumes on radiologic scans can be divided into manual

  17. Guidelines for the Layout and Contents of Safety Reports for Stationary Nuclear Power Plants

    International Nuclear Information System (INIS)

    1970-01-01

    The purpose of the present document is to suggest guidelines for the organization and contents of the Safety Reports which support the request for authorization to construct and operate a nuclear power plant incorporating one or more reactors. Safety Reports represent the principal communication between the applicant and the Regulatory Body, as outlined in the Code of Practice for the Safe Operation of Nuclear Power Plants. It should be understood that these Safety Reports will be a valuable document for the applicant. They should contain, therefore, precise information on the plant and its operating conditions. The writing of Safety Reports should be considered an opportunity to enhance the safety of the plant and its operating conditions. Their main purpose is to provide information to permit the assessment of the nuclear safety implications which may arise from the establishment of the plant at the chosen site with due consideration to the health and safety of the general public and the operating personnel. Safety Reports should include information such as design bases, site and plant characteristics, limits and conditions, conduct of operation and safety analyses, in such way that the Regulatory Body may be able to evaluate the safety of the plant. The applicant should consider the present guidelines as a series of recommendations to be interpreted according to each specific case.

  18. International Spine Radiosurgery Consortium Consensus Guidelines for Target Volume Definition in Spinal Stereotactic Radiosurgery

    International Nuclear Information System (INIS)

    Cox, Brett W.; Spratt, Daniel E.; Lovelock, Michael; Bilsky, Mark H.; Lis, Eric; Ryu, Samuel; Sheehan, Jason; Gerszten, Peter C.; Chang, Eric; Gibbs, Iris; Soltys, Scott; Sahgal, Arjun; Deasy, Joe; Flickinger, John; Quader, Mubina; Mindea, Stefan

    2012-01-01

    Purpose: Spinal stereotactic radiosurgery (SRS) is increasingly used to manage spinal metastases. However, target volume definition varies considerably and no consensus target volume guidelines exist. This study proposes consensus target volume definitions using common scenarios in metastatic spine radiosurgery. Methods and Materials: Seven radiation oncologists and 3 neurological surgeons with spinal radiosurgery expertise independently contoured target and critical normal structures for 10 cases representing common scenarios in metastatic spine radiosurgery. Each set of volumes was imported into the Computational Environment for Radiotherapy Research. Quantitative analysis was performed using an expectation maximization algorithm for Simultaneous Truth and Performance Level Estimation (STAPLE) with kappa statistics calculating agreement between physicians. Optimized confidence level consensus contours were identified using histogram agreement analysis and characterized to create target volume definition guidelines. Results: Mean STAPLE agreement sensitivity and specificity was 0.76 (range, 0.67-0.84) and 0.97 (range, 0.94-0.99), respectively, for gross tumor volume (GTV) and 0.79 (range, 0.66-0.91) and 0.96 (range, 0.92-0.98), respectively, for clinical target volume (CTV). Mean kappa agreement was 0.65 (range, 0.54-0.79) for GTV and 0.64 (range, 0.54-0.82) for CTV (P<.01 for GTV and CTV in all cases). STAPLE histogram agreement analysis identified optimal consensus contours (80% confidence limit). Consensus recommendations include that the CTV should include abnormal marrow signal suspicious for microscopic invasion and an adjacent normal bony expansion to account for subclinical tumor spread in the marrow space. No epidural CTV expansion is recommended without epidural disease, and circumferential CTVs encircling the cord should be used only when the vertebral body, bilateral pedicles/lamina, and spinous process are all involved or there is extensive metastatic

  19. Activities of ARCAL XX for the development of guidelines for the safety of radiation sources

    International Nuclear Information System (INIS)

    Velasques de Oliveira, S.M.; Betancourt, L.A.

    2001-01-01

    This report presents the contribution of the ARCAL XX project 'Guidelines for the Control of Radiation Sources' for the development and harmonization of the safety of radiation sources in Latin America. The project began in 1997 with the participation of nine countries. The methodology adopted has enabled all experts from the nine countries involved in the project to participate in discussions on the development of guidelines based on regional experience. Three common documents for all practices and six safety guides for the main practices have been revised for publication. For the next two years, the project co-ordinators are proposing regional and national workshops for the application of the safety guides approved by the ARCAL programme. (author)

  20. Methodology for calculating guideline concentrations for safety shot sites

    International Nuclear Information System (INIS)

    1997-06-01

    Residual plutonium (Pu), with trace quantities of depleted uranium (DU) or weapons grade uranium (WU), exists in surficial soils at the Nevada Test Site (NTS), Nellis Air Force Range (NAFR), and the Tonopah Test Range (TTR) as the result of the above-ground testing of nuclear weapons and special experiments involving the detonation of plutonium-bearing devices. The special experiments (referred to as safety shots) involving plutonium-bearing devices were conducted to study the behavior of Pu as it was being explosively compressed; ensure that the accidental detonation of the chemical explosive in a production weapon would not result in criticality; evaluate the ability of personnel to manage large-scale Pu dispersal accidents; and develop criteria for transportation and storage of nuclear weapons. These sites do not pose a health threat to either workers or the general public because they are under active institutional control. The DOE is committed to remediating the safety shot sites so that radiation exposure to the public, both now and in the future, will be maintained within the established limits and be as low as reasonably achievable. Remediation requires calculation of a guideline concentration for the Pu, U, and their decay products that are present in the surface soil. This document presents the methodology for calculating guideline concentrations of weapons grade plutonium, weapons grade uranium, and depleted uranium in surface soils at the safety shot sites. Emphasis is placed on obtaining site-specific data for use in calculating dose to potential residents from the residual soil contamination

  1. Methodology for calculating guideline concentrations for safety shot sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    Residual plutonium (Pu), with trace quantities of depleted uranium (DU) or weapons grade uranium (WU), exists in surficial soils at the Nevada Test Site (NTS), Nellis Air Force Range (NAFR), and the Tonopah Test Range (TTR) as the result of the above-ground testing of nuclear weapons and special experiments involving the detonation of plutonium-bearing devices. The special experiments (referred to as safety shots) involving plutonium-bearing devices were conducted to study the behavior of Pu as it was being explosively compressed; ensure that the accidental detonation of the chemical explosive in a production weapon would not result in criticality; evaluate the ability of personnel to manage large-scale Pu dispersal accidents; and develop criteria for transportation and storage of nuclear weapons. These sites do not pose a health threat to either workers or the general public because they are under active institutional control. The DOE is committed to remediating the safety shot sites so that radiation exposure to the public, both now and in the future, will be maintained within the established limits and be as low as reasonably achievable. Remediation requires calculation of a guideline concentration for the Pu, U, and their decay products that are present in the surface soil. This document presents the methodology for calculating guideline concentrations of weapons grade plutonium, weapons grade uranium, and depleted uranium in surface soils at the safety shot sites. Emphasis is placed on obtaining site-specific data for use in calculating dose to potential residents from the residual soil contamination.

  2. Radiation Safety Management Guidelines for PET-CT: Focus on Behavior and Environment

    International Nuclear Information System (INIS)

    Jung, Jin Wook; Han, Eun Ok

    2011-01-01

    Our purpose is to specify behavior and environmental factors aimed at reducing the exposed dosage caused by PET-CT and to develop radiation safety management guidelines adequate for domestic circumstances. We have used a multistep-multimethod as the methodological approach to design and to carry out the research both in quality and quantity, including an analysis on previous studies, professional consultations and a survey. The survey includes responses from 139 practitioners in charged of 109 PET-CTs installed throughout Korea(reported by the Korean Society of Nuclear Medicine, 2010). The research use 156 questions using Cronbach's α (alpha) coefficients which were: 0.818 for 'the necessity of setting and installing the radiation protective environment'; 0.916 for 'the necessity of radiation protection', 'setting and installing the radiation protective environment'; and 0.885 for 'radiation protection'. The check list, derived from the radiation safety management guidelines focused on behavior and environment, was composed of 20 items for the radiation protective environment: including 5 items for the patient; 4 items for the guardian; 3 items for the radiologist; and 8 items applied to everyone involved; for a total of 26 items for the radiation protective behavior including: 12 items for the patient; 1 item for the guardian, 7 items for the radiologist; and 6 items applied to everyone involved. The specific check list is shown in (Table 5-6). Since our country has no safety management guidelines of its own to reduce the exposed dosage caused by PET-CTs, we believe the guidelines developed through this study means great deal to the field as it is not only appropriate for domestic circumstances, but also contains specific check lists for each target who may be exposed to radiation in regards to behavior and environment.

  3. Blanket comparison and selection study. Volume II

    International Nuclear Information System (INIS)

    1983-10-01

    This volume contains extensive data for the following chapters: (1) solid breeder tritium recovery, (2) solid breeder blanket designs, (3) alternate blanket concept screening, and (4) safety analysis. The following appendices are also included: (1) blanket design guidelines, (2) power conversion systems, (3) helium-cooled, vanadium alloy structure blanket design, (4) high wall loading study, and (5) molten salt safety studies

  4. Guidelines for the verification and validation of expert system software and conventional software: Bibliography. Volume 8

    International Nuclear Information System (INIS)

    Miller, L.A.; Hayes, J.E.; Mirsky, S.M.

    1995-03-01

    This volume contains all of the technical references found in Volumes 1-7 concerning the development of guidelines for the verification and validation of expert systems, knowledge-based systems, other AI systems, object-oriented systems, and conventional systems

  5. Guidelines for the verification and validation of expert system software and conventional software: Bibliography. Volume 8

    Energy Technology Data Exchange (ETDEWEB)

    Miller, L.A.; Hayes, J.E.; Mirsky, S.M. [Science Applications International Corp., McLean, VA (United States)

    1995-03-01

    This volume contains all of the technical references found in Volumes 1-7 concerning the development of guidelines for the verification and validation of expert systems, knowledge-based systems, other AI systems, object-oriented systems, and conventional systems.

  6. New guidelines for dam safety classification

    International Nuclear Information System (INIS)

    Dascal, O.

    1999-01-01

    Elements are outlined of recommended new guidelines for safety classification of dams. Arguments are provided for the view that dam classification systems should require more than one system as follows: (a) classification for selection of design criteria, operation procedures and emergency measures plans, based on potential consequences of a dam failure - the hazard classification of water retaining structures; (b) classification for establishment of surveillance activities and for safety evaluation of dams, based on the probability and consequences of failure - the risk classification of water retaining structures; and (c) classification for establishment of water management plans, for safety evaluation of the entire project, for preparation of emergency measures plans, for definition of the frequency and extent of maintenance operations, and for evaluation of changes and modifications required - the hazard classification of the project. The hazard classification of the dam considers, as consequence, mainly the loss of lives or persons in jeopardy and the property damages to third parties. Difficulties in determining the risk classification of the dam lie in the fact that no tool exists to evaluate the probability of the dam's failure. To overcome this, the probability of failure can be substituted for by a set of dam characteristics that express the failure potential of the dam and its foundation. The hazard classification of the entire project is based on the probable consequences of dam failure influencing: loss of life, persons in jeopardy, property and environmental damage. The classification scheme is illustrated for dam threatening events such as earthquakes and floods. 17 refs., 5 tabs

  7. Measure Guideline: Combustion Safety for Natural Draft Appliances Through Appliance Zone Isolation

    Energy Technology Data Exchange (ETDEWEB)

    Fitzgerald, J. [Center for Energy and Environment, Minneapolis, MN (United States); Bohac, D. [Center for Energy and Environment, Minneapolis, MN (United States)

    2014-04-01

    This measure guideline covers how to assess and carry out the isolation of natural draft combustion appliances from the conditioned space of low-rise residential buildings. It deals with combustion appliances located either within the living space in enclosed closets or side rooms or outside the living space in an adjacent area like an attic or garage. This subset of houses does not require comprehensive combustion safety tests and simplified prescriptive procedures can be used to address safety concerns. This allows residential energy retrofit contractors inexperienced in advanced combustion safety testing to effectively address combustion safety issues and allow energy retrofits including tightening and changes to distribution and ventilation systems to proceed.

  8. Guideline on evaluation and acceptance of commercial grade digital equipment for nuclear safety applications

    International Nuclear Information System (INIS)

    1996-10-01

    Nuclear power plants are increasingly upgrading their instrumentation and control (I ampersand C) systems with commercial digital equipment, which allows them to continue meeting safety and reliability requirements while controlling operating costs. However, the use of commercial software-based devices for safety related applications has raised new issues that impact design, procurement, and licensing activities. This guideline describes a consistent, comprehensive approach for the evaluation and acceptance of commercial digital equipment for nuclear safety systems

  9. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    International Nuclear Information System (INIS)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index

  10. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

  11. A treatment planning comparison of four target volume contouring guidelines for locally advanced pancreatic cancer radiotherapy

    International Nuclear Information System (INIS)

    Fokas, Emmanouil; Eccles, Cynthia; Patel, Neel; Chu, Kwun-Ye; Warren, Samantha; McKenna, W. Gillies; Brunner, Thomas B.

    2013-01-01

    Background and purpose: Contouring of target volumes varies significantly in radiotherapy of pancreatic ductal adenocarcinoma (PDAC). There is a lack of consensus as to whether elective lymph nodes (eLN’s) should be included or not in the planning target volume (PTV). In the present study we analyzed the dosimetric coverage of the eLN’s and organs at risk (OAR) by comparing four different contouring guidelines. Methods and materials: PTVs were delineated with (Oxford and RTOG guidelines) or without (Michigan and SCALOP guidelines) including the eLNs in eleven patients with PDAC. eLNs included the peripancreatic, paraaortic, paracaval, celiac trunk, superior mesenteric and portal vein clinical target volumes (CTVs). A 3D-CRT plan (50.40 Gy in 28 fractions) was performed to analyze and compare the dosimetric coverage of all eLNs and OAR between the 4 contouring guidelines. Results: The size of Oxford and RTOG PTVs was comparable and significantly larger than the SCALOP and Michigan PTVs. Interestingly the eLNs received a significant amount of incidental dose irradiation by PTV-based plans that only aimed to treat the tumor without the eLNs. The dosimetric coverage of eLN presented a large variability according to the respective contouring methods. The difference in the size of the 4 PTVs was reflected to the dose distribution at the OAR. Conclusions: Our study provides important information regarding the impact of different contouring guidelines on the dose distribution to the eLNs and the OAR in patients with locally advanced PDAC treated with radiotherapy

  12. Safety of transcranial magnetic stimulation: review of international guidelines and new findings

    Directory of Open Access Journals (Sweden)

    N. A. Suponeva

    2017-01-01

    Full Text Available Transcranial magnetic stimulation (TMS is a rapidly developing method of neuromodulation. The use of TMS has increased significantly in both research and clinical practice. This allows not only to better understand this method, but also assess possible risks and consequences for both healthy individuals and patients. In 1998 and 2009 safety, ethical considerations, and application guidelines for the use of TMS in clinical practice and research were published. These recommendations are now the basis for safe application of the method in clinical practice and research. Safety of brain stimulation includes several aspects: the prevention and treatment of adverse effects, the strategy of patient and stimulation protocols selection, as well as safety and monitoring procedures. The most common adverse effects of TMS include headache and neck pain, syncope, transient hearing impairment. The risk of epileptic seizureis extremely low and can be minimized by careful selection of patients and the use of safe stimulation protocols. Careful selection of patients is important, taking into account a large number of factors that influence the risk of adverse effects. These factors are considered in the questionnaires to identify limitations and absolute or relative contraindications to TMS. Another important part of TMS safety is the choice of the stimulation protocol and parameters such as intensity, frequency, duration of one train of stimuli, and the interstimulus interval. Currently, the recommended limits of stimulation parameters are covered in the safety guidelines. It is also necessary to follow the procedure, including the monitoring the patient's condition during TMS and the providing qualified assistance in case of adverse effects.

  13. Contrast media. Safety issues and ESUR guidelines. 3. ed.

    International Nuclear Information System (INIS)

    Thomsen, Henrik S.; Webb, Judith A.W.

    2014-01-01

    Fully updates the previous edition and includes new chapters on various complex topics. Represents a unique and unparalleled source of information on the many safety issues relating to different contrast media. Includes chapters on acute and delayed non-renal adverse reactions and on renal adverse reactions. Presented in a handy, easy-to-use format. In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned ESUR members, reviewed the literature, proposed guidelines, and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006, which was followed by an equally successful second edition in 2009. This third edition not only fully updates the previous edition, but also includes new chapters on complex topics such as use of contrast media in children and practical aspects of off-label contrast media use. The authorship includes members, past members, and non-members of the Contrast Media Safety Committee.

  14. Issues in the management of acute agitation: how much current guidelines consider safety?

    Directory of Open Access Journals (Sweden)

    Bruno ePacciardi

    2013-05-01

    Full Text Available Agitated behavior constitutes up to 10% of emergency psychiatric interventions. Pharmacological tranquilization is often used as a valid treatment for agitation but a strong evidence base does not underpin it. Available literature shows different recommendations, supported by research data, theoretical considerations or clinical experience. Rapid tranquilization is mainly based on parenteral drug treatment and the few existing guidelines on this topic, when suggesting the use of first generation antipsychotics and benzodiazepines, include drugs with questionable tolerability profile such as chlorpromazine, haloperidol, midazolam and lorazepam. In order to systematically evaluate safety concerns related to the adoption of such guidelines, we reviewed them independently from principal diagnosis while examining tolerability data for suggested treatments. There is a growing evidence about safety profile of second generation antipsychotics for rapid tranquilization but further controlled studies providing definitive data in this area are urgently needed.

  15. Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W B; Passiakos, M

    1980-06-01

    This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

  16. Seismic PSA implementation standards by AESJ and the utilization of the advanced safety examination guideline for seismic design for nuclear power plant

    International Nuclear Information System (INIS)

    Ebisawa, Katsumi; Hibino, Kenta

    2008-01-01

    The Advanced Safety Examination Guideline for Seismic Design for Nuclear Power Plant (the advanced safety examination guideline) was worked out on September 19, 2006. In this paper, a summary of the method of probability theory in the advanced safety examination guideline and the Seismic PSA Implementation Standards is stated. On utilization of the probability theory for the advanced safety examination guideline, the uncertainty resulting from the process of the decision of the basic design earthquake ground motion (Ss) is stated to be considered using the proper method. The references of the extra probability for evaluation of earthquake hazard and combination of the working load and the earthquake load are stated. Definition, evaluation method and effort to lower the 'residual risks', and relation between the residual risks and the extra probability of Ss are described. A summary of the earthquake-resistant design for nuclear power facilities is explained by the old guideline. (S.Y.)

  17. OSART guidelines

    International Nuclear Information System (INIS)

    1988-02-01

    The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the operational safety of nuclear power plants. These OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Specific guidelines are provided as guide for the systematic review in the following areas important to operational safety: management, organization and administration, training and qualification, operations, maintenance, technical support, radiation protection, chemistry, emergency planning and preparedness

  18. Guidelines for selecting codes for ground-water transport modeling of low-level waste burial sites. Volume 2. Special test cases

    International Nuclear Information System (INIS)

    Simmons, C.S.; Cole, C.R.

    1985-08-01

    This document was written for the National Low-Level Waste Management Program to provide guidance for managers and site operators who need to select ground-water transport codes for assessing shallow-land burial site performance. The guidance given in this report also serves the needs of applications-oriented users who work under the direction of a manager or site operator. The guidelines are published in two volumes designed to support the needs of users having different technical backgrounds. An executive summary, published separately, gives managers and site operators an overview of the main guideline report. Volume 1, titled ''Guideline Approach,'' consists of Chapters 1 through 5 and a glossary. Chapters 2 through 5 provide the more detailed discussions about the code selection approach. This volume, Volume 2, consists of four appendices reporting on the technical evaluation test cases designed to help verify the accuracy of ground-water transport codes. 20 refs

  19. System Guidelines for EMC Safety-Critical Circuits: Design, Selection, and Margin Demonstration

    Science.gov (United States)

    Lawton, R. M.

    1996-01-01

    Demonstration of safety margins for critical points (circuits) has traditionally been required since it first became a part of systems-level Electromagnetic Compatibility (EMC) requirements of MIL-E-6051C. The goal of this document is to present cost-effective guidelines for ensuring adequate Electromagnetic Effects (EME) safety margins on spacecraft critical circuits. It is for the use of NASA and other government agencies and their contractors to prevent loss of life, loss of spacecraft, or unacceptable degradation. This document provides practical definition and treatment guidance to contain costs within affordable limits.

  20. Guidelines for confirmatory inplant tests of safety-relief valve discharges for BWR plants

    International Nuclear Information System (INIS)

    Su, T.M.

    1981-05-01

    Inplant tests of safety/relief valve (SRV) discharges may be required to confirm generically established specifications for SRV loads and the maximum suppression pool temperature, and to evaluate possible effects of plant-unique parameters. These tests are required in those plants which have features that differ substantially from those previously tested. Guidelines for formulating appropriate test matrices, establishing test procedures, selecting necessary instrumentation, and reporting the test results are provided in this report. Guidelines to determine if inplant tests are required on the basis of the plant unique parameters are also included in the report

  1. 19th JANNAF Safety and Environmental Protection Subcommittee Meeting. Volume 1

    Science.gov (United States)

    Cocchiaro, J. E. (Editor); Becker, D. L. (Editor)

    2002-01-01

    This volume, the first of two volumes, is a compilation of 22 unclassified/unlimited technical papers presented at the 19th Joint Army-Navy-NASA-Air Force (JANNAF) Safety & Environmental Protection Subcommittee Meeting. The meeting was held 18-21 March 2002 at the Sheraton Colorado Springs Hotel, Colorado Springs, Colorado. Topics covered include green energetic materials and life cycle pollution prevention; space launch range safety; propellant/munitions demilitarization, recycling, and reuse: and environmental and occupational health aspects of propellants and energetic materials.

  2. 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

  3. 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.

  4. A consensus-based guideline defining clinical target volume for primary disease in external beam radiotherapy for intact uterine cervical cancer

    International Nuclear Information System (INIS)

    Toita, Takafumi; Ohno, Tatsuya; Kaneyasu, Yuko

    2011-01-01

    The objective of this study was to develop a consensus-based guideline to define clinical target volume for primary disease (clinical target volume primary) in external beam radiotherapy for intact uterine cervical cancer. The working subgroup of the Japan Clinical Oncology Group (JCOG) Radiation Therapy Study Group began developing a guideline for primary clinical target volume in November 2009. The group consisted of 10 radiation oncologists and 2 gynecologic oncologists. The process started with comparing the contouring on computed tomographic images of actual cervical cancer cases among the members. This was followed by a comprehensive literature review that included primary research articles and textbooks as well as information on surgical procedures. Extensive discussion occurred in face-to-face meetings (three occasions) and frequent e-mail communications until a consensus was reached. The working subgroup reached a consensus on the definition for the clinical target volume primary. The clinical target volume primary consists of the gross tumor volume, uterine cervix, uterine corpus, parametrium, vagina and ovaries. Definitions for these component structures were determined. Anatomical boundaries in all directions were defined for the parametrium. Examples delineating these boundaries were prepared for the posterior border of the parametrium for various clinical situations (id est (i.e.) central tumor bulk, degree of parametrial involvement). A consensus-based guideline defining the clinical target volume primary was developed for external beam radiotherapy for intact uterine cervical cancer. This guideline will serve as a template for radiotherapy protocols in future clinical trials. It may also be used in actual clinical practice in the setting of highly precise external beam radiotherapy, including intensity-modulated radiotherapy. (author)

  5. Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations

    International Nuclear Information System (INIS)

    Lacour, J.

    1964-01-01

    In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [fr

  6. Thirteenth water reactor safety research information meeting: proceedings Volume 1

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1986-02-01

    This six-volume report contains 151 papers out of the 178 that were presented at the Thirteenth Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 22-25, 1985. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included thirty-one different papers presented by researchers from Japan, Canada and eight European countries. The title of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume presents information on: risk analysis PRA application; severe accident sequence analysis; risk analysis/dependent failure analysis; and industry safety research

  7. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2

    International Nuclear Information System (INIS)

    Osborn, R.N.; Olson, J.; Sommers, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators

  8. Guidelines regarding National Reports 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 on Nuclear Safety (hereinafter called 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 regarding material that it may be useful to include in the National Reports required under Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention [es

  9. Guidelines regarding National Reports 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 on Nuclear Safety (hereinafter called 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 regarding material that may be useful to include in the National Reports required under Article 5 of the Convention and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention.

  10. Guidelines regarding National Reports 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 on Nuclear Safety (hereinafter called 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 regarding material that it may be useful to include in the National Reports required under Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention

  11. IAEA/NEA incident reporting system (IRS). Reporting guidelines. Feedback from safety related operating experience for nuclear power plants

    International Nuclear Information System (INIS)

    1998-01-01

    The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants. These guidelines have been jointly developed and approved by the NEA/IAEA

  12. Sensitivity and uncertainty analyses applied to criticality safety validation. Volume 2

    International Nuclear Information System (INIS)

    Broadhead, B.L.; Hopper, C.M.; Parks, C.V.

    1999-01-01

    This report presents the application of sensitivity and uncertainty (S/U) analysis methodologies developed in Volume 1 to the code/data validation tasks of a criticality safety computational study. Sensitivity and uncertainty analysis methods were first developed for application to fast reactor studies in the 1970s. This work has revitalized and updated the existing S/U computational capabilities such that they can be used as prototypic modules of the SCALE code system, which contains criticality analysis tools currently in use by criticality safety practitioners. After complete development, simplified tools are expected to be released for general use. The methods for application of S/U and generalized linear-least-square methodology (GLLSM) tools to the criticality safety validation procedures were described in Volume 1 of this report. Volume 2 of this report presents the application of these procedures to the validation of criticality safety analyses supporting uranium operations where enrichments are greater than 5 wt %. Specifically, the traditional k eff trending analyses are compared with newly developed k eff trending procedures, utilizing the D and c k coefficients described in Volume 1. These newly developed procedures are applied to a family of postulated systems involving U(11)O 2 fuel, with H/X values ranging from 0--1,000. These analyses produced a series of guidance and recommendations for the general usage of these various techniques. Recommendations for future work are also detailed

  13. Dam safety operating guidelines

    International Nuclear Information System (INIS)

    Elsayed, E.; Leung, T.; Kirkham, A.; Lum, D.

    1990-01-01

    As part of Ontario Hydro's dam structure assessment program, the hydraulic design review of several river systems has revealed that many existing dam sites, under current operating procedures, would not have sufficient discharge capacity to pass the Inflow Design Flood (IDF) without compromising the integrity of the associated structures. Typical mitigative measures usually considered in dealing with these dam sites include structural alterations, emergency action plans and/or special operating procedures designed for extreme floods. A pilot study was carried out for the Madawaska River system in eastern Ontario, which has seven Ontario Hydro dam sites in series, to develop and evaluate the effectiveness of the Dam Safety Operating Guidelines (DSOG). The DSOG consist of two components: the flood routing schedules and the minimum discharge schedules, the former of which would apply in the case of severe spring flood conditions when the maximum observed snowpack water content and the forecast rainfall depth exceed threshold values. The flood routing schedules would identify to the operator the optimal timing and/or extent of utilizing the discharge facilities at each dam site to minimize the potential for dam failures cased by overtopping anywhere in the system. It was found that the DSOG reduced the number of structures overtopped during probable maximum flood from thirteen to four, while the number of structures that could fail would be reduced from seven to two. 8 refs., 4 figs., 3 tabs

  14. Canadian Association of Gastroenterology Consensus Guidelines on Safety and Quality Indicators in Endoscopy

    Directory of Open Access Journals (Sweden)

    David Armstrong

    2012-01-01

    Full Text Available Several organizations worldwide have developed procedure-based guidelines and/or position statements regarding various aspects of quality and safety indicators, and credentialing for endoscopy. Although important, they do not specifically address patient needs or provide a framework for their adoption in the context of endoscopy services. The consensus guidelines reported in this article, however, aimed to identify processes and indicators relevant to the provision of high-quality endoscopy services that will support ongoing quality improvement across many jurisdictions, specifically in the areas of ethics, facility standards and policies, quality assurance, training and education, reporting standards and patient perceptions.

  15. Biological effects of electromagnetic fields and recently updated safety guidelines for strong static magnetic fields

    International Nuclear Information System (INIS)

    Yamaguchi-Sekino, Sachiko; Sekino, Masaki; Ueno, Shoogo

    2011-01-01

    Humans are exposed daily to artificial and naturally occurring magnetic fields that originate from many different sources. We review recent studies that examine the biological effects of and medical applications involving electromagnetic fields, review the properties of static and pulsed electromagnetic fields that affect biological systems, describe the use of a pulsed electromagnetic field in combination with an anticancer agent as an example of a medical application that incorporates an electromagnetic field, and discuss the recently updated safety guidelines for static electromagnetic fields. The most notable modifications to the 2009 International Commission on Non-Ionizing Radiation Protection guidelines are the increased exposure limits, especially for those who work with or near electromagnetic fields (occupational exposure limits). The recommended increases in exposure were determined using recent scientific evidence obtained from animal and human studies. Several studies since the 1994 publication of the guidelines have examined the effects on humans after exposure to high static electromagnetic fields (up to 9.4 tesla), but additional research is needed to ascertain further the safety of strong electromagnetic fields. (author)

  16. Radiological risk comparison guidelines

    International Nuclear Information System (INIS)

    Hallinan, E.J.; Muhlestein, L.D.; Brown, L.F.; Yoder, R.E.

    1992-01-01

    An important aspect of DOE safety analyses is estimating potential accident risk. The estimates are used to: determine if additional controls are needed, identify Safety Class Items, and demonstrate adequate risk reduction. Thus, guidelines are needed to measure comparative risks. The Westinghouse M ampersand O Nuclear Facility Safety Committee and the Safety Envelope Working Group have developed radiological risk guidelines for comparing the risks from individual accident analyses. These guidelines were prepared under contract with the US Department of Energy. These guidelines are based on historical DOE guidelines and current requirements, and satisfy DOE and technical community proposals. for goals that demonstrate acceptable risk. The guidelines consist of a frequency versus consequence curve for credible accidents. Offsite and onsite guidelines are presented. The offsite risk acceptance guidelines are presented in Figure 1. The guidelines are nearly isorisk for anticipated events where impacts are chronic, and provide additional reduction for unlikely events where impacts may be acute and risk uncertainties may be significant. The guidelines are applied to individual release accident scenarios where a discrete frequency and consequence has been estimated. The guideline curves are not to be used for total risk assessments. Common cause events are taken into consideration only for an individual facility. Frequencies outside the guideline range are considered to be local site option (analyst judgement) as far as assessments of risk acceptance are concerned. If the curve is exceeded, then options include either a more detailed analysis or imposing additional preventive or mitigative features. Another presentation discusses implementation in detail. Additional work is needed to provide risk comparison guidelines for releases from multiple facilities and for toxic releases

  17. 2009 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

    International Nuclear Information System (INIS)

    2009-01-01

    After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety (safety organisation, general measures, measures related to various risks, inspections, control of emergency situations, audits and second level control, measures in basic nuclear installations) and radioprotection (organisation, significant facts, dosimeter results). It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of measurements of releases and of their impact on the environment (chemical and radiological assessment). Then after a description of measures to limit the volume of stored radioactive wastes and their impact on health and on the environment, tables indicate the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation) for which a significant event occurred on the 6 October 2009. For these installations, release measurements concern gaseous and liquid releases

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

    International Nuclear Information System (INIS)

    1992-01-01

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

  19. Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces.

  20. Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

    International Nuclear Information System (INIS)

    1984-01-01

    This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

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

    International Nuclear Information System (INIS)

    2005-01-01

    when exchanging ideas, at the working level, for enhancing safety. The OSART programme is based on the IAEA's Nuclear Safety Standard Series (Fundamentals, Requirements and Safety Guides) for nuclear power plants and the Basic Safety Standards for Radiation Protection. The Nuclear Safety Standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Advisory Group, identifying important current nuclear safety issues also serve as references during an OSART review. The OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Additional guidance and reference material prepared by the IAEA and the expertise of the OSART members contribute to the bases of the review. OSART reviews are performance oriented in that they accept different approaches to commissioning and operational safety that represent good practices and may contribute to ensuring a good safety record on the part of the operating organization. Recommendations are made on items of direct relevance to safety, whereas suggestions made might enhance plant safety indirectly but would certainly improve performance. Commendable good practices identified at plants are communicated to other plants where relevant in order to effect improvements. This revision of the OSART guidelines supersedes the 1994 Edition (IAEA-TECDOC-744)

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

    International Nuclear Information System (INIS)

    2007-01-01

    when exchanging ideas, at the working level, for enhancing safety. The OSART programme is based on the IAEA's Nuclear Safety Standard Series (Fundamentals, Requirements and Safety Guides) for nuclear power plants and the Basic Safety Standards for Radiation Protection. The Nuclear Safety Standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Advisory Group, identifying important current nuclear safety issues also serve as references during an OSART review. The OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Additional guidance and reference material prepared by the IAEA and the expertise of the OSART members contribute to the bases of the review. OSART reviews are performance oriented in that they accept different approaches to commissioning and operational safety that represent good practices and may contribute to ensuring a good safety record on the part of the operating organization. Recommendations are made on items of direct relevance to safety, whereas suggestions made might enhance plant safety indirectly but would certainly improve performance. Commendable good practices identified at plants are communicated to other plants where relevant in order to effect improvements. This revision of the OSART guidelines supersedes the 1994 Edition (IAEA-TECDOC-744)

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

    International Nuclear Information System (INIS)

    2008-01-01

    when exchanging ideas, at the working level, for enhancing safety. The OSART programme is based on the IAEA's Nuclear Safety Standard Series (Fundamentals, Requirements and Safety Guides) for nuclear power plants and the Basic Safety Standards for Radiation Protection. The Nuclear Safety Standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Advisory Group, identifying important current nuclear safety issues also serve as references during an OSART review. The OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Additional guidance and reference material prepared by the IAEA and the expertise of the OSART members contribute to the bases of the review. OSART reviews are performance oriented in that they accept different approaches to commissioning and operational safety that represent good practices and may contribute to ensuring a good safety record on the part of the operating organization. Recommendations are made on items of direct relevance to safety, whereas suggestions made might enhance plant safety indirectly but would certainly improve performance. Commendable good practices identified at plants are communicated to other plants where relevant in order to effect improvements. This revision of the OSART guidelines supersedes the 1994 Edition (IAEA-TECDOC-744)

  10. Canadian Association of Gastroenterology consensus guidelines on safety and quality indicators in endoscopy.

    Science.gov (United States)

    Armstrong, David; Barkun, Alan; Bridges, Ron; Carter, Rose; de Gara, Chris; Dube, Catherine; Enns, Robert; Hollingworth, Roger; Macintosh, Donald; Borgaonkar, Mark; Forget, Sylviane; Leontiadis, Grigorios; Meddings, Jonathan; Cotton, Peter; Kuipers, Ernst J

    2012-01-01

    Increasing use of gastrointestinal endoscopy, particularly for colorectal cancer screening, and increasing emphasis on health care quality, highlight the need for clearly defined, evidence-based processes to support quality improvement in endoscopy. To identify processes and indicators of quality and safety relevant to high-quality endoscopy service delivery. A multidisciplinary group of 35 voting participants developed recommendation statements and performance indicators. Systematic literature searches generated 50 initial statements that were revised iteratively following a modified Delphi approach using a web-based evaluation and voting tool. Statement development and evidence evaluation followed the AGREE (Appraisal of Guidelines, REsearch and Evaluation) and GRADE (Grading of Recommendations, Assessment, Development and Evaluation) guidelines. At the consensus conference, participants voted anonymously on all statements using a 6-point scale. Subsequent web-based voting evaluated recommendations for specific, individual quality indicators, safety indicators and mandatory endoscopy reporting fields. Consensus was defined a priori as agreement by 80% of participants. Consensus was reached on 23 recommendation statements addressing the following: ethics (statement 1: agreement 100%), facility standards and policies (statements 2 to 9: 90% to 100%), quality assurance (statements 10 to 13: 94% to 100%), training, education, competency and privileges (statements 14 to 19: 97% to 100%), endoscopy reporting standards (statements 20 and 21: 97% to 100%) and patient perceptions (statements 22 and 23: 100%). Additionally, 18 quality indicators (agreement 83% to 100%), 20 safety indicators (agreement 77% to 100%) and 23 recommended endoscopy-reporting elements (agreement 91% to 100%) were identified. The consensus process identified a clear need for high-quality clinical and outcomes research to support quality improvement in the delivery of endoscopy services. The

  11. Guidelines for Safety Evaluation of a Potential for PWR Steam Generator Tube Failure due to Fluid elastic Instability

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Jong Chull; Do, Kyu Sik; Sheen, Cheol [Nuclear System Evaluation Dept., Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-05-15

    It was found that both SG tube rupture events occurred at North Anna Unit 1 in 1987 and at Mihama Unit 2 in 1991 were caused by a high cycle fatigue due to fluid elastic instability. Therefore, with regard to nuclear safety it is important to design the SG properly in a conservative manner so that the potential for SG U-tube failures due to fluid elastic instability can be minimized. This article provides guidelines for assessing the potential for SG U-tube damage due to fluid elastic instability. This article described guidelines for safety evaluation of a potential for PWR steam generator tube failure due to fluid elastic instability. The guidelines address the requirements for realistically performing the SG thermal-hydraulic analysis and the modal analysis of tubes as well as the criteria for conservatively determining the added mass, the damping ratio and the fluid elastic instability coefficient. The guidelines can be used to predict the potential SG tubes which are susceptible to failure due to fluid elastic instability at operating nuclear power plants and also to evaluate the safety and structural integrity of new SG designs at the licensing review stage. Failure of a pressurized water reactor (PWR) steam generator (SG) tube leads to a leakage of contaminated primary coolant to the secondary system, which has serious safety implications such as the potential for direct release of radioactive fission products to the environment and the loss of coolant. Excessive tube vibration excited by dynamic forces of internal or external fluid flow is called flow-induced vibration (FIV). Among the FIV mechanisms, the so-called fluid elastic instability of SG tubes in cross flow is the most important safety issue in the design of SGs because it may cause severe tube failure in a very short time.

  12. Proceedings of the international topical meeting on advanced reactors safety: Volume 2

    International Nuclear Information System (INIS)

    1997-01-01

    In this volume, 89 papers are grouped under the following headings: advances in research/test reactor safety; advanced reactor accident management and emergency actions; advanced reactors instrumentation/controls/human factors; probabilistic risk/safety and reliability assessments; steam explosion research and issues; advanced reactor severe accident issues and research (analysis and assessments); advanced reactor thermal hydraulics; accelerator-driven source safety; liquid-metal reactor safety; structural assessments and issues; late papers

  13. State of the art of probabilistic safety analysis (PSA) in the FRG, and principles of a PSA-guideline

    International Nuclear Information System (INIS)

    Balfanz, H.P.

    1987-01-01

    Contents of the articles: Survey of PSA performed during licensing procedures of an NPP; German Nuclear Standards' requirements on the reliability of safety systems; PSA-guideline for NPP: Principles and suggestions; Motivation and tasks of PSA; Aspects of the methodology of safety analyses; Structure of event tree and fault tree analyses; Extent of safety analyses; Performance and limits of PSA. (orig./HSCH)

  14. Workplace health and safety during pandemic influenza : CAGC guideline

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-11-15

    Pandemic influenza is a possible biological hazard that employers must take into account during hazard assessment and emergency planning. This report presented a guideline to all workplaces in Alberta and provided information on legislated requirements, best practices, guidelines and strategies in workplace health and safety and employment standards in the event of a pandemic influenza. The report explained the difference between a pandemic and a pandemic influenza, and why scientists expect another pandemic influenza. Pandemic influenza was described as being different from seasonal influenza. This document also explained how pandemic influenza relates to the worker and the workplace, and how the workplace can prepare for and respond to pandemic influenza. Pandemic influenza hazard categories were also listed along with steps in the hazard assessment and control of pandemic influenza. The steps involve listing the types of work and work-related activities; identifying the hazard; assessing the hazards; implementing controls; communicating the information to workers and providing training; and evaluating the effectiveness of controls. The guide also addressed emergency response plan development for pandemic influenza; first aid; and employment standards during pandemic influenza. refs., tabs.

  15. Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 1, Cell and battery safety

    Energy Technology Data Exchange (ETDEWEB)

    Ohi, J M

    1992-09-01

    This report is the first of four volumes that identify and assess the environmental, health, and safety issues involved in using sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles that may affect the commercialization of Na/S batteries. This and the other reports on recycling, shipping, and vehicle safety are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD&D) program for Na/S battery technology. The reports review the status of Na/S battery RD&D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers cell design and engineering as the basis of safety for Na/S batteries and describes and assesses the potential chemical, electrical, and thermal hazards and risks of Na/S cells and batteries as well as the RD&D performed, under way, or to address these hazards and risks. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, universities, and private industry. Subsequent volumes will address environmental, health, and safety issues involved in shipping cells and batteries, using batteries to propel electric vehicles, and recycling and disposing of spent batteries. The remainder of this volume is divided into two major sections on safety at the cell and battery levels. The section on Na/S cells describes major component and potential failure modes, design, life testing and failure testing, thermal cycling, and the safety status of Na/S cells. The section on batteries describes battery design, testing, and safety status. Additional EH&S information on Na/S batteries is provided in the appendices.

  16. 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

  17. 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.

  18. 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

  19. A study on the establishment of safety assessment guidelines of commercial grade item dedication in digitalized safety systems

    International Nuclear Information System (INIS)

    Hwang, H. S.; Kim, B. R.; Oh, S. H.

    1999-01-01

    Because of obsolescing the components used in safety related systems of nuclear power plants, decreasing the number of suppliers qualified for the nuclear QA program and increasing maintenance costs of them, utilities have been considering to use commercial grade digital computers as an alternative for resolving such issues. However, commercial digital computers use the embedded pre-existing software, including operating system software, which are not developed by using nuclear grade QA program. Thus, it is necessary for utilities to establish processes for dedicating digital commercial grade items. A regulatory body also needs guidance to evaluate the digital commercial products properly. This paper surveyed the regulations and their regulatory guides, which establish the requirements for commercial grade items dedication, industry standards and guidances applicable to safety related systems. This paper provides some guidelines to be applied in evaluating the safety of digital upgrades and new digital plant protection systems in Korea

  20. Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1

    International Nuclear Information System (INIS)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety

  1. SU-E-P-43: A Knowledge Based Approach to Guidelines for Software Safety

    International Nuclear Information System (INIS)

    Salomons, G; Kelly, D

    2015-01-01

    Purpose: In the fall of 2012, a survey was distributed to medical physicists across Canada. The survey asked the respondents to comment on various aspects of software development and use in their clinic. The survey revealed that most centers employ locally produced (in-house) software of some kind. The respondents also indicated an interest in having software guidelines, but cautioned that the realities of cancer clinics include variations, that preclude a simple solution. Traditional guidelines typically involve periodically repeating a set of prescribed tests with defined tolerance limits. However, applying a similar formula to software is problematic since it assumes that the users have a perfect knowledge of how and when to apply the software and that if the software operates correctly under one set of conditions it will operate correctly under all conditions Methods: In the approach presented here the personnel involved with the software are included as an integral part of the system. Activities performed to improve the safety of the software are done with both software and people in mind. A learning oriented approach is taken, following the premise that the best approach to safety is increasing the understanding of those associated with the use or development of the software. Results: The software guidance document is organized by areas of knowledge related to use and development of software. The categories include: knowledge of the underlying algorithm and its limitations; knowledge of the operation of the software, such as input values, parameters, error messages, and interpretation of output; and knowledge of the environment for the software including both data and users. Conclusion: We propose a new approach to developing guidelines which is based on acquiring knowledge-rather than performing tests. The ultimate goal is to provide robust software guidelines which will be practical and effective

  2. SU-E-P-43: A Knowledge Based Approach to Guidelines for Software Safety

    Energy Technology Data Exchange (ETDEWEB)

    Salomons, G [Cancer Center of Southeastern Ontario & Queen’s University, Kingston, ON (Canada); Kelly, D [Royal Military College of Canada, Kingston, ON, CA (Canada)

    2015-06-15

    Purpose: In the fall of 2012, a survey was distributed to medical physicists across Canada. The survey asked the respondents to comment on various aspects of software development and use in their clinic. The survey revealed that most centers employ locally produced (in-house) software of some kind. The respondents also indicated an interest in having software guidelines, but cautioned that the realities of cancer clinics include variations, that preclude a simple solution. Traditional guidelines typically involve periodically repeating a set of prescribed tests with defined tolerance limits. However, applying a similar formula to software is problematic since it assumes that the users have a perfect knowledge of how and when to apply the software and that if the software operates correctly under one set of conditions it will operate correctly under all conditions Methods: In the approach presented here the personnel involved with the software are included as an integral part of the system. Activities performed to improve the safety of the software are done with both software and people in mind. A learning oriented approach is taken, following the premise that the best approach to safety is increasing the understanding of those associated with the use or development of the software. Results: The software guidance document is organized by areas of knowledge related to use and development of software. The categories include: knowledge of the underlying algorithm and its limitations; knowledge of the operation of the software, such as input values, parameters, error messages, and interpretation of output; and knowledge of the environment for the software including both data and users. Conclusion: We propose a new approach to developing guidelines which is based on acquiring knowledge-rather than performing tests. The ultimate goal is to provide robust software guidelines which will be practical and effective.

  3. UPSAT guidelines. 1996 edition. Reference document for IAEA Uranium Productions Safety Assessment Teams (UPSATs)

    International Nuclear Information System (INIS)

    1996-05-01

    The IAEA Uranium Production Safety Assessment Team (UPSAT) programme provides advice and assistance to Member States to enhance the safety and environmental performance of uranium production facilities during construction, commissioning and operation. Sound design and construction are prerequisite for the safe and environmentally responsible operation of uranium mines and mills. However, the safety of the facility depends ultimately on sound policies, procedures and practices; on the capability and reliability of the construction, 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. The UPSAT guidelines have been developed in the following areas: (1) management, organization and administration; (2) training and qualification; (3) operation (4) maintenance; (5) safety, fire protection, emergency planning, and preparedness; (6) radiation protection; (7) environmental monitoring programme; (8) construction management; (9) commissioning and decommissioning

  4. Guidelines for the verification and validation of expert system software and conventional software: Rationale and description of V ampersand V guideline packages and procedures. Volume 5

    International Nuclear Information System (INIS)

    Mirsky, S.M.; Hayes, J.E.; Miller, L.A.

    1995-03-01

    This report is the fifth volume in a series of reports describing the results of the Expert System Verification C, and Validation (V ampersand V) project which is jointly funded by the U.S. Nuclear Regulatory Commission and the Electric Power Research Institute toward the objective of formulating Guidelines for the V ampersand V of expert systems for use in nuclear power applications. This report provides the rationale for and description of those guidelines. The actual guidelines themselves are presented in Volume 7, open-quotes User's Manual.close quotes Three factors determine what V ampersand V is needed: (1) the stage of the development life cycle (requirements, design, or implementation); (2) whether the overall system or a specialized component needs to be tested (knowledge base component, inference engine or other highly reusable element, or a component involving conventional software); and (3) the stringency of V ampersand V that is needed (as judged from an assessment of the system's complexity and the requirement for its integrity to form three Classes). A V ampersand V Guideline package is provided for each of the combinations of these three variables. The package specifies the V ampersand V methods recommended and the order in which they should be administered, the assurances each method provides, the qualifications needed by the V ampersand V team to employ each particular method, the degree to which the methods should be applied, the performance measures that should be taken, and the decision criteria for accepting, conditionally accepting, or rejecting an evaluated system. In addition to the Guideline packages, highly detailed step-by-step procedures are provided for 11 of the more important methods, to ensure that they can be implemented correctly. The Guidelines can apply to conventional procedural software systems as well as all kinds of Al systems

  5. Overview of IAEA guidelines for fire safety inspection and operation in nuclear power plants

    International Nuclear Information System (INIS)

    Mowrer, D.S.

    1998-01-01

    In 1992, the International Atomic Energy Agency began an ambitious project on fire safety in nuclear power plants. The purpose of this ongoing project is to provide specific guidance on compliance with the requirements set forth through the IAEA Nuclear Safety Standards program established in 1974. The scope of the Fire Safety project encompasses several tasks, including the development of new standards and guidelines to assist Member States in assessing the level of fire safety in existing plants. Five new Safety Practices, one new Safety Guide and a Technical Document have been developed for use by the fire safety community. The primary intent of these new documents is to provide detailed guidance and a consistent format for the assessment of the overall level of fire safety being provided in existing nuclear power plants around the world and especially in developing countries. Sufficient detail is provided in the Safety Guide and Safety Practices to allow technically knowledgeable plant personnel, outside consultants or other technical experts to assess the adequacy of fire safety within the plant facilities. This paper describes topics addressed by each of the IAEA Fire Safety documents and discussed the relationship of each document to others in the series. (author)

  6. Safety of magnetic fusion facilities: Volume 2, Guidance

    International Nuclear Information System (INIS)

    1995-01-01

    This document provides guidance for the implementation of the requirements identified in Vol. 1 of this Standard. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While Vol. 1 is generally applicable in that requirements there apply to a wide range of fusion facilities, this volume is concerned mainly with large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This volume is oriented toward regulation in the Department of Energy (DOE) environment

  7. RSK-guidelines for PWR reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The RSK guidelines for PWA reactors of April 24, 1974, have been revised and amended in this edition. The RSK presents a summary of safety requirements to be observed in the design, construction, and operation of PWR reactors in the form of guidelines. From January 1979 onwards these guidelines will be the basis of siting and safety considerations for new PWR reactors, and newly built nuclear power plants will have to form these guidelines. They are not binding for existing nuclear power plants under construction or in operation. It will be a matter of individual discussion whether or not the guidelines will be applied in these plants. The main purpose of the guidelines is to facilitate discussion among RSK members and to give early information on necessary safety requirements. If the guidelines are observed by producers and operators, the RSK will make statements on individual projects at short notice. (orig./HP) [de

  8. PETRO-SAFE '94 conference papers: Book 2. Volume 5: Emergency response ampersand spill control; Volume 6: Remediation; Volume 7: Health ampersand safety issues

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    The Fifth Annual Environmental, Safety and Health Conference and Exhibition for the oil, gas and petrochemical industries was held January 25--27, 1994 in Houston, Texas. The objective of this conference was to provide a multidisciplinary forum dealing with state-of-the-art environmental and safety issues. This volume focuses on the following: emergency response and spill control; remediation; and health and safety issues. Individual papers have been processed separately for inclusion in the appropriate data bases

  9. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

  10. 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

  11. Development of safety and regulatory requirements for Korean next generation reactor - Development of human factors design review guidelines (II)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Lee, Hyun Chul; Cheon, Se Woo [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-02-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25. Human Factors Engineering Program Review Model' and '26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and the characteristics of the KNGR design, and reviewing the reference documents of NURGE-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides at KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system design review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we updated the guidelines by reviewing the literature related to alarm design that published after 1994. 12 refs., 11 figs., 2 tabs. (Author)

  12. Development of safety and regulatory requirements for Korean next generation reactor - Development of human factors design review guidelines (II)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Lee, Hyun Chul; Cheon, Se Woo [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-02-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25. Human Factors Engineering Program Review Model' and '26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and the characteristics of the KNGR design, and reviewing the reference documents of NURGE-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides at KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system design review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we updated the guidelines by reviewing the literature related to alarm design that published after 1994. 12 refs., 11 figs., 2 tabs. (Author)

  13. Inventory of Federal energy-related environment and safety research for FY 1978. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    1979-12-01

    The FY 1978 Federal Inventory is a compilation of 3225 federally funded energy-related environmental and safety reserch projects. It consists of three volumes: an executive summary providing an overview of the data (Volume I), a catalog listing each Inventory project followed by series of indexes (Volume II), and an interactive terminal guide giving instructions for on-line data retrieval (Volume III). Volume I reviews the inventory data as a whole and also within each of three major categories: biomedical and environmental research, environmental control technology research, and operational safety research

  14. Verification and validation guidelines for high integrity systems. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Hecht, H.; Hecht, M.; Dinsmore, G.; Hecht, S.; Tang, D. [SoHaR, Inc., Beverly Hills, CA (United States)

    1995-03-01

    High integrity systems include all protective (safety and mitigation) systems for nuclear power plants, and also systems for which comparable reliability requirements exist in other fields, such as in the process industries, in air traffic control, and in patient monitoring and other medical systems. Verification aims at determining that each stage in the software development completely and correctly implements requirements that were established in a preceding phase, while validation determines that the overall performance of a computer system completely and correctly meets system requirements. Volume I of the report reviews existing classifications for high integrity systems and for the types of errors that may be encountered, and makes recommendations for verification and validation procedures, based on assumptions about the environment in which these procedures will be conducted. The final chapter of Volume I deals with a framework for standards in this field. Volume II contains appendices dealing with specific methodologies for system classification, for dependability evaluation, and for two software tools that can automate otherwise very labor intensive verification and validation activities.

  15. Verification and validation guidelines for high integrity systems. Volume 1

    International Nuclear Information System (INIS)

    Hecht, H.; Hecht, M.; Dinsmore, G.; Hecht, S.; Tang, D.

    1995-03-01

    High integrity systems include all protective (safety and mitigation) systems for nuclear power plants, and also systems for which comparable reliability requirements exist in other fields, such as in the process industries, in air traffic control, and in patient monitoring and other medical systems. Verification aims at determining that each stage in the software development completely and correctly implements requirements that were established in a preceding phase, while validation determines that the overall performance of a computer system completely and correctly meets system requirements. Volume I of the report reviews existing classifications for high integrity systems and for the types of errors that may be encountered, and makes recommendations for verification and validation procedures, based on assumptions about the environment in which these procedures will be conducted. The final chapter of Volume I deals with a framework for standards in this field. Volume II contains appendices dealing with specific methodologies for system classification, for dependability evaluation, and for two software tools that can automate otherwise very labor intensive verification and validation activities

  16. Usability and Safety in Electronic Medical Records Interface Design: A Review of Recent Literature and Guideline Formulation.

    Science.gov (United States)

    Zahabi, Maryam; Kaber, David B; Swangnetr, Manida

    2015-08-01

    The objectives of this study were to (a) review electronic medical record (EMR) and related electronic health record (EHR) interface usability issues, (b) review how EMRs have been evaluated with safety analysis techniques along with any hazard recognition, and (c) formulate design guidelines and a concept for enhanced EMR interfaces with a focus on diagnosis and documentation processes. A major impact of information technology in health care has been the introduction of EMRs. Although numerous studies indicate use of EMRs to increase health care quality, there remain concerns with usability issues and safety. A literature search was conducted using Compendex, PubMed, CINAHL, and Web of Science databases to find EMR research published since 2000. Inclusion criteria included relevant English-language papers with subsets of keywords and any studies (manually) identified with a focus on EMR usability. Fifty studies met the inclusion criteria. Results revealed EMR and EHR usability problems to include violations of natural dialog, control consistency, effective use of language, effective information presentation, and customization principles as well as a lack of error prevention, minimization of cognitive load, and feedback. Studies focusing on EMR system safety made no objective assessments and applied only inductive reasoning methods for hazard recognition. On the basis of the identified usability problems and structure of safety analysis techniques, we provide EMR design guidelines and a design concept focused on the diagnosis process and documentation. The design guidelines and new interface concept can be used for prototyping and testing enhanced EMRs. © 2015, Human Factors and Ergonomics Society.

  17. IAEA guidance on ageing management for nuclear power plants. Guidance on effective management of the physical ageing of systems, structures and components important to safety for nuclear power plants. Overview. Programmatic guidelines. Component specific guidelines. Review guidelines. Version 1, 2002

    International Nuclear Information System (INIS)

    2002-01-01

    Operational experience shows that excellent plant safety and excellent performance go hand in hand, and that they are achieved by effective leadership and management that includes a unified approach to safety and production. This is also applicable to ageing management. Effective ageing management leads to both enhanced plant safety and enhanced performance and is a prerequisite for long service life. The IAEA project on Safety Aspects of NPP Ageing has produced since 1990 a comprehensive set of programmatic and component specific guidelines on managing ageing, while providing an interactive environment for information exchange and co-operation among practitioners, and has assisted Member States in the application of the guidelines through the provision of training and advice. The objective of the CD-ROM is to preserve the IAEA's guidance on ageing management and to facilitate its retrieval, updating, extension and dissemination in order to help increase the effectiveness of ageing management at nuclear power plants

  18. Nuclear criticality safety experiments, calculations, and analyses: 1958 to 1982. Volume 1. Lookup tables

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1982-01-01

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains - in chronological order - the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

  19. Fast reactor safety: proceedings of the international topical meeting. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences.

  20. Fast reactor safety: proceedings of the international topical meeting. Volume 1

    International Nuclear Information System (INIS)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences

  1. Implementation guidelines for seismic PSA

    International Nuclear Information System (INIS)

    Coman, Ovidiu; Samaddar, Sujit; Hibino, Kenta; )

    2014-01-01

    The presentation was devoted to development of guidelines for implementation of a seismic PSA. If successful, these guidelines can close an important gap. ASME/ANS PRA standards and the related IAEA Safety Guide (IAEA NS-G-2.13) describe capability requirements for seismic PSA in order to support risk-informed applications. However, practical guidance on how to meet these requirements is limited. Such guidelines could significantly contribute to improving risk-informed safety demonstration, safety management and decision making. Extensions of this effort to further PSA areas, particularly to PSA for other external hazards, can enhance risk-informed applications

  2. Radiologic measurement of extraocular muscle volumes in patients with Graves' orbitopathy: a review and guideline.

    Science.gov (United States)

    Bijlsma, Ward R; Mourits, Maarten Ph

    2006-06-01

    To evaluate and compare techniques for extraocular muscle (EOM) volume measurement and to provide guidelines for future measurements. Systematic review. Existing techniques used to measure extraocular muscle volumes on radiologic scans can be divided into manual outlining, computer assisted and automated segmentation. Both computed tomography (CT) and magnetic resonance (MR) image datasets can be used. On CT scans, one best measures muscle volume using region grow segmentation, accepting an overestimation of true volume by inevitable inclusion of non-muscular tissue. On high resolution MRI scans, single muscles can be outlined manually, but measurements include only part of the muscle due to poor tissue contrast at the orbital apex. Measurement errors can be reduced 3.5% by exact horizontal repositioning. A measured volume change of at least 6-17% is required to demonstrate a significant difference. Currently the best choice for EOM volume measurements on CT images is computer assisted grey value segmentation and on MRI images is manual outlining of individual muscles. Because of the time required and the complexity of the measurements, present EOM volume measurement is as yet only suitable for research purposes.

  3. 2007 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

    International Nuclear Information System (INIS)

    2007-01-01

    After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety: safety organisation, general measures, measures related to various risks, control of emergency situations, inspections, audits and second level control, measures in basic nuclear installations. It describes the measures concerning the radioprotection on this site: organisation, significant facts, and dose measurement results. It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of release measurements and of radiological and chemical assessments of the impact these releases on the environment. The report then describes measures implemented to limit the volume of stored radioactive wastes and also their impact on health and on the environment. It provides a series of tables indicating the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. It reports the recommendations expressed by the CHSCT (committee on hygiene, security and working conditions) after the 2006 report. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation), for which the significant events occurred on the 13. of March and on the 25. of May 2007. For these installations, release measurements concern gaseous and liquid releases

  4. OSART guidelines. 1992 edition

    International Nuclear Information System (INIS)

    1992-01-01

    The IAEA Operational Safety Review Team (OSART) Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Specific guidelines are provided as a guide for the systematic review in the following areas important to operational safety: management, organization and administration, training and qualification, operations, maintenance, technical support, radiation protection, chemistry, emergency planning and preparedness. Additional guidance and reference material has been prepared by the IAEA to complement the expertise of the OSART members

  5. A consensus-based guideline defining the clinical target volume for pelvic lymph nodes in external beam radiotherapy for uterine cervical cancer

    International Nuclear Information System (INIS)

    Toita, Takafumi; Ohno, Tatsuya; Kaneyasu, Yuko

    2010-01-01

    The objective of this study was to develop a consensus-based guideline as well as an atlas defining pelvic nodal clinical target volumes in external beam radiotherapy for uterine cervical cancer. A working subgroup to establish the consensus-based guideline on clinical target volumes for uterine cervical cancer was formulated by the Radiation Therapy Study Group of the Japan Clinical Oncology Group in July 2008. The working subgroup consisted of seven radiation oncologists. The process resulting in the consensus included a comparison of contouring on CT images among the members, reviewing of published textbooks and the relevant literature and a distribution analysis of metastatic nodes on computed tomography/magnetic resonance imaging of actual patients. The working subgroup defined the pelvic nodal clinical target volumes for cervical cancer and developed an associated atlas. As a basic criterion, the lymph node clinical target volume was defined as the area encompassed by a 7 mm margin around the applicable pelvic vessels. Modifications were made in each nodal area to cover adjacent adipose tissues at risk of microscopic nodal metastases. Although the bones and muscles were excluded, the bowel was not routinely excluded in the definition. Each of the following pelvic node regions was defined: common iliac, external iliac, internal iliac, obturator and presacral. Anatomical structures bordering each lymph node region were defined for six directions; anterior, posterior, lateral, medial, cranial and caudal. Drafts of the definition and the atlas were reviewed by members of the JCOG Gynecologic Cancer Study Group (GCSG). We developed a consensus-based guideline defining the pelvic node clinical target volumes that included an atlas. The guideline will be continuously updated to reflect the ongoing changes in the field. (author)

  6. A framework for the development of patient safety education and training guidelines.

    Science.gov (United States)

    Zikos, Dimitrios; Diomidous, Marianna; Mantas, John

    2010-01-01

    Patient Safety (PS) is a major concern that involves a wide range of roles in healthcare, including those who are directly and indirectly involved, and patients as well. In order to succeed into developing a safety culture among healthcare providers, carers and patients, there should be given great attention into building appropriate education and training tools, especially addressing those who plan patient safety activities. The framework described in this policy paper is based on the results of the European Network for Patient Safety (EUNetPaS) project and analyses the principles and elements of the guidance that should be provided to those who design and implement Patient Safety Education and training activities. The main principles that it should be based on and the core teaching objectives-expected outcomes are addressed. Once the main context and considerations are properly set, the guidance should define the general schema of the content that should be included in the Education and Training activities, as well as how these activities would be delivered. It is also important that the different roles of the recipients are clearly distinguished and linked to their role-specific methods, proper delivery platforms and success stories. Setting these principles into practice when planning and implementing interventions, primarily aims to enlighten and support those who are enrolled to design and implement Patient Safety education and training teaching activities. This is achieved by providing them with a framework to build upon, succeeding to build a collaborative, safety conscious and competent environment, in terms of PS. A guidelines web platform has been developed to support this process.

  7. Guidelines for the verification and validation of expert system software and conventional software: Volume 5, Rationale and description of verification and validation guideline packages and procedures. Final report

    International Nuclear Information System (INIS)

    Miller, L.A.; Hayes, J.E.; Mirsky, S.M.

    1995-05-01

    This report is the fifth volume in a series of reports describing the results of the Expert System Verification and Validation (V ampersand V) project which is jointly funded by US NRC and EPRI toward formulating guidelines for V ampersand V of expert systems for use in nuclear power applications. This report provides the rationale for and description of those guidelines. The actual guidelines themselves (and the accompanying 11 step by step Procedures) are presented in Volume 7, User's Manual. Three factors determine what V ampersand V is needed: (1) the stage, of the development life cycle (requirements, design, or implementation), (2) whether the overall system or a specialized component needs be tested (knowledge base component, inference engine or other highly reusable element, or a component involving conventional software), and (3) the stringency of V ampersand V that is needed (as judged from an assessment of the system's complexity and the requirement for its integrity to form three Classes). A V ampersand V guideline package is provided for each of the combinations of these three variables. The package specifies the V ampersand V methods recommended and the order in which they should be administered, the assurances each method provides, the qualifications needed by the V ampersand V team to employ each Particular method, the degree to which the methods should be applied, the performance measures that should be taken, and the decision criteria for accepting, conditionally accepting, or rejecting an evaluated system. In addition to the guideline packages, highly detailed step-by-step procedures are provided for 11 of the more important methods, to ensure that they Can be implemented correctly. The guidelines can apply to conventional procedural software systems as well as all kinds of AI systems

  8. Safety assessment methodologies for near surface disposal facilities. Results of a co-ordinated research project (ISAM). Volume 1: Review and enhancement of safety assessment approaches and tools. Volume 2: Test cases

    International Nuclear Information System (INIS)

    2004-07-01

    the Safety Guide on 'Safety Assessment for Near Surface Disposal of Radioactive Waste' (Safety Standards Series No. WS-G- 1.1). The report of this CRP is presented in two volumes; Volume 1 contains a summary and a complete description of the ISAM project methodology and Volume 2 presents the application of the methodology to three hypothetical test cases

  9. Guideline for radiotherapy of liver cancer

    International Nuclear Information System (INIS)

    Kishi, Kazushi; Shirai, Shintaro; Satou, Morio; Ueda, Hiroki; Wigg, D.R

    2007-01-01

    This paper describes bases of radiotherapy (RT) of liver cancer for its application, efficacy, clinical target volume (CTV) and characteristics, dose fractionation and its theory, 2D/3D irradiation, evaluation, and safety. The description here is leading to execute the Guideline 200X to be issued in a near future by the Japanese College of Radiology, and is supplementary to the Guideline in nature. The Guideline is to incorporate the recent progresses of the therapy to complement the previous Guideline 2004. Thus here are described the application of RT to unresectable hepatoma in relation to intervention; characteristics of RT including dose-effect relationships, morphological characteristics of intravascular tumor thrombi (ITT) and CTV, dose fractionation and a/b ratio (liver 2.5 vs hepatoma 7.4), focal lesion in parenchyma, ITT and RT, lymph metastasis, arteriovenous shunt and dissemination, and desensitization in bone and adrenal metastases; prediction of radiation liver damage; and adverse effect by radiation and its control. The evidenced bases of RT are still poor in this field, but the fact that hepatoma, highly sensitive to radiation, exhibits clear dose-response ensures its efficacy if the problems of low tolerance and of breathing movement at irradiation can be solved. (R.T.)

  10. General safety guidelines for looking for a low mass activity-long life waste storage site

    International Nuclear Information System (INIS)

    2008-01-01

    The objective of this document is to define general guidelines which must be followed during the stages of search for a site and stages of design of a storage facility for low activity-long life radioactive wastes, in order to ensure its safety after closure. After having specified the considered wastes, geological shapes, and situations, this document defines the fundamental objective and the associated criteria (protection against chemical risk, radioprotection). It presents the design aspects related to safety (safety principles and functions, waste packages, public works engineering, geological environment, storage concepts). The last part deals with the safety demonstration after site closure which includes the control of some components, the assessment of disturbances in the storage facility or due to its presence, the taking of uncertainty and sensitivity studies into account, the influence of natural events

  11. Impact of target volume coverage with Radiation Therapy Oncology Group (RTOG) 98-05 guidelines for transrectal ultrasound guided permanent Iodine-125 prostate implants

    International Nuclear Information System (INIS)

    Horwitz, Eric M.; Mitra, Raj K.; Uzzo, Robert G.; Das, Indra J.; Pinover, Wayne H.; Hanlon, Alexandra L.; McNeeley, Shawn W.; Hanks, Gerald E.

    2003-01-01

    Purpose: Despite the wide use of permanent prostate implants for the treatment of early stage prostate cancer, there is no consensus for optimal pre-implant planning guidelines that results in maximal post-implant target coverage. The purpose of this study was to compare post-implant target volume coverage and dosimetry between patients treated before and after Radiation Therapy Oncology Group (RTOG) 98-05 guidelines were adopted using several dosimetric endpoints. Materials and methods: Ten consecutively treated patients before the adoption of the RTOG 98-05 planning guidelines were compared with ten consecutively treated patients after implementation of the guidelines. Pre-implant planning for patients treated pre-RTOG was based on the clinical target volume (CTV) defined by the pre-implant TRUS definition of the prostate. The CTV was expanded in each dimension according to RTOG 98-05 and defined as the planning target volume. The evaluation target volume was defined as the post-implant computed tomography definition of the prostate based on RTOG 98-05 protocol recommendations. Implant quality indicators included V 100 , V 90 , V 100 , and Coverage Index (CI). Results: The pre-RTOG median V 100 , V 90 , D 90 , and CI values were 82.8, 88.9%, 126.5 Gy, and 17.1, respectively. The median post-RTOG V 100 , V 90 , D 90 , and CI values were 96.0, 97.8%, 169.2 Gy, and 4.0, respectively. These differences were all statistically significant. Conclusions: Implementation of the RTOG 98-05 implant planning guidelines has increased coverage of the prostate by the prescription isodose lines compared with our previous technique, as indicated by post-implant dosimetry indices such as V 100 , V 90 , D 90 . The CI was also improved significantly with the protocol guidelines. Our data confirms the validity of the RTOG 98-05 implant guidelines for pre-implant planning as it relates to enlargement of the CTV to ensure adequate margin between the CTV and the prescription isodose

  12. Guideline for collection, analysis and presentation of safety data in clinical trials of vaccines in pregnant women

    Science.gov (United States)

    Jones, Christine E.; Munoz, Flor M.; Spiegel, Hans M.L.; Heininger, Ulrich; Zuber, Patrick L.F.; Edwards, Kathryn M.; Lambach, Philipp; Neels, Pieter; Kohl, Katrin S.; Gidudu, Jane; Hirschfeld, Steven; Oleske, James M.; Khuri-Bulos, Najwa; Bauwens, Jorgen; Eckert, Linda O.; Kochhar, Sonali; Bonhoeffer, Jan; Heath, Paul T.

    2017-01-01

    Vaccination during pregnancy is increasingly being used as an effective approach for protecting both young infants and their mothers from serious infections. Drawing conclusions from published studies in this area can be difficult because of the inability to compare vaccine trial results across different studies and settings due to the heterogeneity in the definitions of terms used to assess the safety of vaccines in pregnancy and the data collected in such studies. The guidelines proposed in this document have been developed to harmonize safety data collection in all phases of clinical trials of vaccines in pregnant women and apply to data from the mother, fetus and infant. Guidelines on the prioritization of the data to be collected is also provided to allow applicability in various geographic, cultural and resource settings, including high, middle and low-income countries. PMID:27481360

  13. Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety.

  14. Factors controlling volume errors through 2D gully erosion assessment: guidelines for optimal survey design

    Science.gov (United States)

    Castillo, Carlos; Pérez, Rafael

    2017-04-01

    The assessment of gully erosion volumes is essential for the quantification of soil losses derived from this relevant degradation process. Traditionally, 2D and 3D approaches has been applied for this purpose (Casalí et al., 2006). Although innovative 3D approaches have recently been proposed for gully volume quantification, a renewed interest can be found in literature regarding the useful information that cross-section analysis still provides in gully erosion research. Moreover, the application of methods based on 2D approaches can be the most cost-effective approach in many situations such as preliminary studies with low accuracy requirements or surveys under time or budget constraints. The main aim of this work is to examine the key factors controlling volume error variability in 2D gully assessment by means of a stochastic experiment involving a Monte Carlo analysis over synthetic gully profiles in order to 1) contribute to a better understanding of the drivers and magnitude of gully erosion 2D-surveys uncertainty and 2) provide guidelines for optimal survey designs. Owing to the stochastic properties of error generation in 2D volume assessment, a statistical approach was followed to generate a large and significant set of gully reach configurations to evaluate quantitatively the influence of the main factors controlling the uncertainty of the volume assessment. For this purpose, a simulation algorithm in Matlab® code was written, involving the following stages: - Generation of synthetic gully area profiles with different degrees of complexity (characterized by the cross-section variability) - Simulation of field measurements characterised by a survey intensity and the precision of the measurement method - Quantification of the volume error uncertainty as a function of the key factors In this communication we will present the relationships between volume error and the studied factors and propose guidelines for 2D field surveys based on the minimal survey

  15. Nuclear space power safety and facility guidelines study

    International Nuclear Information System (INIS)

    Mehlman, W.F.

    1995-01-01

    This report addresses safety guidelines for space nuclear reactor power missions and was prepared by The Johns Hopkins University Applied Physics Laboratory (JHU/APL) under a Department of Energy grant, DE-FG01-94NE32180 dated 27 September 1994. This grant was based on a proposal submitted by the JHU/APL in response to an open-quotes Invitation for Proposals Designed to Support Federal Agencies and Commercial Interests in Meeting Special Power and Propulsion Needs for Future Space Missionsclose quotes. The United States has not launched a nuclear reactor since SNAP 10A in April 1965 although many Radioisotope Thermoelectric Generators (RTGs) have been launched. An RTG powered system is planned for launch as part of the Cassini mission to Saturn in 1997. Recently the Ballistic Missile Defense Office (BMDO) sponsored the Nuclear Electric Propulsion Space Test Program (NEPSTP) which was to demonstrate and evaluate the Russian-built TOPAZ II nuclear reactor as a power source in space. As of late 1993 the flight portion of this program was canceled but work to investigate the attributes of the reactor were continued but at a reduced level. While the future of space nuclear power systems is uncertain there are potential space missions which would require space nuclear power systems. The differences between space nuclear power systems and RTG devices are sufficient that safety and facility requirements warrant a review in the context of the unique features of a space nuclear reactor power system

  16. RELAP/MOD3 code manual: User's guidelines. Volume 5, Revision 1

    International Nuclear Information System (INIS)

    Fletcher, C.D.; Schultz, R.R.

    1995-08-01

    The RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and operational transients, such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. Volume V contains guidelines that have solved over the past several years through the use of the RELAP5 code

  17. Guidelines for safety related telecommunications systems on normally unattended fixed offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    Guidance is given on the design of telecommunications systems required for safety purposes on normally unattended offshore installations associated with oil and gas production on the United Kingdom continental shelf. The guidelines are mainly concerned with ensuring that: while the installation is unattended, its operation can be remotely monitored and controlled effectively to prevent the escalation of any abnormal situation; the installation can be safely approached when it is necessary to transfer personnel on board; persons on board, for example for inspection or maintenance activities, are safe. (UK)

  18. Fast reactor safety: proceedings of the international topical meeting. Volume 2

    International Nuclear Information System (INIS)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments

  19. Chemical Safety Vulnerability Working Group report. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 3 consists of eleven appendices containing the following: Field verification reports for Idaho National Engineering Lab., Rocky Flats Plant, Brookhaven National Lab., Los Alamos National Lab., and Sandia National Laboratories (NM); Mini-visits to small DOE sites; Working Group meeting, June 7--8, 1994; Commendable practices; Related chemical safety initiatives at DOE; Regulatory framework and industry initiatives related to chemical safety; and Chemical inventory data from field self-evaluation reports.

  20. Chemical Safety Vulnerability Working Group report. Volume 3

    International Nuclear Information System (INIS)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 3 consists of eleven appendices containing the following: Field verification reports for Idaho National Engineering Lab., Rocky Flats Plant, Brookhaven National Lab., Los Alamos National Lab., and Sandia National Laboratories (NM); Mini-visits to small DOE sites; Working Group meeting, June 7--8, 1994; Commendable practices; Related chemical safety initiatives at DOE; Regulatory framework and industry initiatives related to chemical safety; and Chemical inventory data from field self-evaluation reports

  1. [Optimal intravascular brachytherapy: safety and radiation protection, reliability and precision guaranteed by guidelines, recommendations and regulatory requirements].

    Science.gov (United States)

    Quast, Ulrich; Kaulich, Theodor W; Lorenz, Joachim

    2002-02-01

    The success of intravascular brachytherapy relies entirely on the interdisciplinary approach. Interventional cardiologists, radiation oncologists and medical physicists must form a team from day 1. All members of the team need special knowledge and regular training in the field of vascular radiation therapy. Optimization of intravascular brachytherapy requires the use of standardized methods of dose specification, recording and reporting. This also implies using standardized methods of source calibration in terms of absorbed dose to water and having methods for simple internal control of the dosimetric quantities of new or replaced sources. Guidance is offered by international recommendations (AAPM TG 60, DGMP Report 16, NCS and EVA GEC-ESTRO). LEGAL REQUIREMENTS FOR RADIATION PROTECTION--WHAT'S NEW?: In Europe, new legal requirements on radiation protection issues have to be fulfilled. For Germany, the revised "Strahlenschutzverordnung" has been released recently. Nearly all organizational and medical processes are affected. For intravascular brachytherapy, several changes of requirements have to be considered. However, to follow these requirements does not cause serious problems. DGMP REPORT 16: GUIDELINES FOR MEDICAL PHYSICAL ASPECTS OF INTRAVASCULAR BRACHYTHERAPY: Evaluation of clinical results by comparison of intravascular brachytherapy treatment parameters is possible only if the prescribed dose and the applied dose distribution are reported clearly, completely and uniformly. The DGMP guidelines thus recommend to prescribe the dose to water at the system related reference point PRef at 2 mm radial distance for intracoronary application (and at 5 mm for peripheral vessels). The mean dose at 1 mm tissue depth (respectively at 2 mm) should be reported in addition. To safely define the planning target volume from the injured length, safety margins of at least 5 mm (10 mm) have to be taken into account on both ends. Safety margins have also to be considered for

  2. Safety of Sodium-Glucose Co-Transporter 2 Inhibitors during Ramadan Fasting: Evidence, Perceptions and Guidelines

    Directory of Open Access Journals (Sweden)

    Salem A. Beshyah

    2016-06-01

    Full Text Available Sodium-glucose co-transporter 2 (SGLT2 inhibitors are a new glucose-lowering therapy for T2DM with documented benefits on blood glucose, hypertension, weight reduction and long term cardiovascular benefit. They have an inherent osmotic diuretic effect and lead to some volume loss and possible dehydration. There is some concern about the safety of using SGLT2 inhibitors in Muslim type 2 diabetes mellitus (T2DM patients during the fast during Ramadan. Currently, there is a dearth of research data to help guide physicians and reassure patients.  One study confirmed good glycemic control with less risk of hypoglycemia and no marked volume depletion. Data in the elderly and in combination with diuretics are reassuring of their safe to use in Ramadan in general. SGLT2 inhibitor-related diabetic ketoacidosis has not been reported during Ramadan and is unlikely to be relevant. Survey of physicians revealed that the majority felt that SGLT2 inhibitors are generally safe in T2DM patients during Ramadan fasting but should be discontinued in certain high risk patients. Some professional groups with interest in diabetes and Ramadan fasting included SGLT2 inhibitors in their guidelines on management of diabetes during Ramadan. They acknowledged the lack of trial data, recommended caution in high risk groups, advised regular monitoring and emphasized pre-Ramadan patients’ education. In conclusion, currently, knowledge, data and experience with SGLT2 inhibitors in Ramadan are limited. Nonetheless, stable patients with normal kidney function and low risk of dehydration may safely use the SGLT2 inhibitors therapy. Higher risk patients should be observed carefully and managed on individual basis.

  3. Fatal Exertional Heat Stroke and American Football Players: The Need for Regional Heat-Safety Guidelines.

    Science.gov (United States)

    Grundstein, Andrew J; Hosokawa, Yuri; Casa, Douglas J

    2018-01-01

      Weather-based activity modification in athletics is an important way to minimize heat illnesses. However, many commonly used heat-safety guidelines include a uniform set of heat-stress thresholds that do not account for geographic differences in acclimatization.   To determine if heat-related fatalities among American football players occurred on days with unusually stressful weather conditions based on the local climate and to assess the need for regional heat-safety guidelines.   Cross-sectional study.   Data from incidents of fatal exertional heat stroke (EHS) in American football players were obtained from the National Center for Catastrophic Sport Injury Research and the Korey Stringer Institute.   Sixty-one American football players at all levels of competition with fatal EHSs from 1980 to 2014.   We used the wet bulb globe temperature (WBGT) and a z-score WBGT standardized to local climate conditions from 1991 to 2010 to assess the absolute and relative magnitudes of heat stress, respectively.   We observed a poleward decrease in exposure WBGTs during fatal EHSs. In milder climates, 80% of cases occurred at above-average WBGTs, and 50% occurred at WBGTs greater than 1 standard deviation from the long-term mean; however, in hotter climates, half of the cases occurred at near average or below average WBGTs.   The combination of lower exposure WBGTs and frequent extreme climatic values in milder climates during fatal EHSs indicates the need for regional activity-modification guidelines with lower, climatically appropriate weather-based thresholds. Established activity-modification guidelines, such as those from the American College of Sports Medicine, work well in the hotter climates, such as the southern United States, where hot and humid weather conditions are common.

  4. On-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation

    International Nuclear Information System (INIS)

    Davis, E.; Rasmussen, B.

    2004-01-01

    This report is a guide for a technical specification change submittal and subsequent implementation of on-line monitoring for safety-related applications. This report is the third in a three-volume set. Volume 1, ''Guidelines for Model Development and Implementation'', presents the various tasks that must be completed to prepare models for and to implement an on-line monitoring system

  5. From Clinical Practice Guidelines to Computer-interpretable Guidelines. A Literature Overview

    NARCIS (Netherlands)

    Latoszek-Berendsen, A.; Tange, H.; van den Herik, H. J.; Hasman, A.

    2010-01-01

    Background: Guidelines are among us for over 30 years. Initially they were used as algorithmic protocols by nurses and other ancillary personnel. Many physicians regarded the use of guidelines as cookbook medicine. However, quality and patient safety issues have changed the attitude towards

  6. SU-F-BRA-14: Optimization of Dosimetric Guidelines for Accelerated Partial Breast Irradiation (APBI) Using the Strut-Adjusted Volume Implant (SAVI)

    International Nuclear Information System (INIS)

    Mooney, K; Altman, M; Garcia-Ramirez, J; Thomas, M; Zoberi, I; Mullen, D; DeWees, T; Esthappan, J

    2015-01-01

    Purpose: Treatment planning guidelines for accelerated partial breast irradiation (ABPI) using the strut-adjusted volume implant (SAVI) are inconsistent between the manufacturer and NSABP B-39/RTOG 0413 protocol. Furthermore neither set of guidelines accounts for different applicator sizes. The purpose of this work is to establish guidelines specific to the SAVI that are based on clinically achievable dose distributions. Methods: Sixty-two consecutive patients were implanted with a SAVI and prescribed to receive 34 Gy in 10 fractions twice daily using high dose-rate (HDR) Ir-192 brachytherapy. The target (PTV-EVAL) was defined per NSABP. The treatments were planned and evaluated using a combination of dosimetric planning goals provided by the NSABP, the manufacturer, and our prior clinical experience. Parameters evaluated included maximum doses to skin and ribs, and volumes of PTV-EVAL receiving 90%, 95%, 100%, 150%, and 200% of the prescription (V90, etc). All target parameters were evaluated for correlation with device size using the Pearson correlation coefficient. Revised dosimetric guidelines for target coverage and heterogeneity were determined from this population. Results: Revised guidelines for minimum target coverage (ideal in parentheses): V90≥95%(97%), V95≥90%(95%), V100≥88%(91%). The only dosimetric parameters that were significantly correlated (p<0.05) with device size were V150 and V200. Heterogeneity criteria were revised for the 6–1 Mini/6-1 applicators to V150≤30cc and V200≤15cc, and unchanged for the other sizes. Re-evaluation of patient plans showed 90% (56/62) met the revised minimum guidelines and 76% (47/62) met the ideal guidelines. All and 56/62 patients met our institutional guidelines for maximum skin and rib dose, respectively. Conclusions: We have optimized dosimetric guidelines for the SAVI applicators, and found that implementation of these revised guidelines for SAVI treatment planning yielded target coverage exceeding

  7. Safety work organization in nuclear power plant. A9. Volume 2

    International Nuclear Information System (INIS)

    1985-01-01

    The second volume provides the laws, directives, major standards, principles, lists of selected workplaces where woman work is prohibited, instructions for new personnel, general principles of workplace safety, reports and provisions by commissions for reporting accidents and injuries, recourses, etc. (J.P.)

  8. Best Practice Guidelines for the use of CFD in Nuclear Reactor Safety Applications

    International Nuclear Information System (INIS)

    Mahaffy, J.; Chung, B.; Song, C.; Dubois, F.; Graffard, E.; Ducros, F.; Heitsch, M.; Scheuerer, M.; Henriksson, M.; Komen, E.; Moretti, F.; Morii, T.; Muehlbauer, P.; Rohde, U.; Smith, B. L.; Watanabe, T.; Zigh, G.

    2007-01-01

    In May 2002, an 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems' was held at Aix-en-Provence, France. One of three recommended actions was the formation of this writing group to report on the need for guidelines for use of CFD in single phase Nuclear Reactor Safety (NRS) applications. CSNI approved this writing group at the end of 2002, and work began in March 2003. A final report was submitted to GAMA in September 2004, summarizing existing Best Practice Guidelines (BPG) for CFD, and recommending creation of a BPG document for Nuclear Reactor Safety (NRS) applications. The present document is intended to provide an internally complete set of guidelines for a range of single phase applications of CFD to NRS problems. However, it is not meant to be comprehensive; it is recognized that for any specific application a higher level of specificity is possible on questions of nodalization, model selection, and validation. This document should provide direct guidance on the key considerations in known single phase applications, and general directions for resolving remaining details. The intent is that it will serve as a template for further application specific (e.g. PTS, induced break) BPG documents that will provide much more detailed information and examples. The document begins with a summary of NRS related CFD analysis in countries represented by the authors. Chapter 3 deals with definition of the problem and its solution approach. This includes isolation of the portion of the NRS problem most in need of CFD, and use of a classic thermal hydraulic (TH) safety code to provide boundary conditions for the CFD based upon less detailed simulation of the balance of plant. Chapter 4 provides guidance in choosing between various options, and also discusses use of a transient calculation with tightly coupled CFD and TH codes. Chapter 5 discusses selection of physical

  9. Safety of treatments for inflammatory bowel disease: Clinical practice guidelines of the Italian Group for the Study of Inflammatory Bowel Disease (IG-IBD).

    Science.gov (United States)

    Biancone, Livia; Annese, Vito; Ardizzone, Sandro; Armuzzi, Alessandro; Calabrese, Emma; Caprioli, Flavio; Castiglione, Fabiana; Comberlato, Michele; Cottone, Mario; Danese, Silvio; Daperno, Marco; D'Incà, Renata; Frieri, Giuseppe; Fries, Walter; Gionchetti, Paolo; Kohn, Anna; Latella, Giovanni; Milla, Monica; Orlando, Ambrogio; Papi, Claudio; Petruzziello, Carmelina; Riegler, Gabriele; Rizzello, Fernando; Saibeni, Simone; Scribano, Maria Lia; Vecchi, Maurizio; Vernia, Piero; Meucci, Gianmichele

    2017-04-01

    Inflammatory bowel diseases are chronic conditions of unknown etiology, showing a growing incidence and prevalence in several countries, including Italy. Although the etiology of Crohn's disease and ulcerative colitis is unknown, due to the current knowledge regarding their pathogenesis, effective treatment strategies have been developed. Several guidelines are available regarding the efficacy and safety of available drug treatments for inflammatory bowel diseases. Nevertheless, national guidelines provide additional information adapted to local feasibility, costs and legal issues related to the use of the same drugs. These observations prompted the Italian Group for the Study of Inflammatory Bowel Disease (IG-IBD) to establish Italian guidelines on the safety of currently available treatments for Crohn's disease and ulcerative colitis. These guidelines discuss the use of aminosalicylates, systemic and low bioavailability corticosteroids, antibiotics (metronidazole, ciprofloxacin, rifaximin), thiopurines, methotrexate, cyclosporine A, TNFα antagonists, vedolizumab, and combination therapies. These guidelines are based on current knowledge derived from evidence-based medicine coupled with clinical experience of a national working group. Copyright © 2017 Editrice Gastroenterologica Italiana S.r.l. Published by Elsevier Ltd. All rights reserved.

  10. Main-coolant-pump shaft-seal guidelines. Volume 2. Operational guidelines. Final report

    International Nuclear Information System (INIS)

    Fair, C.E.; Greer, A.O.

    1983-03-01

    This report presents a set of guidelines and criteria for improving main coolant pump shaft seal operational reliability. The noted guidelines are developed from EPRI sponsored nuclear power plant seal operating experience studies. Usage procedures/practices and operational environment influence on seal life and reliability from the most recent such survey are summarized. The shaft seal and its auxiliary supporting systems are discussed both from technical and operational related viewpoints

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

    International Nuclear Information System (INIS)

    2008-01-01

    on the SCART Guidelines, which provide overall guidance to ensure the consistency and comprehensiveness of the safety culture review. At the same time, SCART missions are designed to be able to respond to more specific or detailed requirements in accordance with national or regional culture. SCART missions are conducted with the aim to develop recommendations and suggestions in areas of direct relevance to the safety culture of the reviewed nuclear organizations. Commendable good safety culture practices are identified and communicated to other nuclear organizations in order to effect improvements worldwide. SCART is available to all Member States, and to all kinds of organizations, using or regulating the use of nuclear materials (e.g. nuclear facilities, regulatory bodies, nuclear design organizations)

  12. ON-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    E Davis, B Rasmussen

    2004-12-31

    This report is a guide for a technical specification change submittal and subsequent implementation of on-line monitoring for safety-related applications. This report is the third in a three-volume set. Volume 1, ''Guidelines for Model Development and Implementation'', presents the various tasks that must be completed to prepare models for and to implement an on-line monitoring system.

  13. Radionuclide administration to nursing mothers: mathematically derived guidelines

    International Nuclear Information System (INIS)

    Romney, B.M.; Nickoloff, E.L.; Esser, P.D.; Alderson, P.O.

    1986-01-01

    We determined a formula to establish objective guidelines for the administration of radionuclides to nursing mothers. The formula is based on the maximum permissible dose to the infant's critical organ, serial measurements of breast milk activity, milk volume, and dose to the critical organ per microcurie in milk. Using worst-case assumptions, we believe that cessation of nursing for 24 hours after administration of technetium labeled radiopharmaceuticals is sufficient for safety. Longer-lived agents require greater delays. Iodine-123 radiopharmaceuticals are preferable to iodine-131 agents and should always be used when studying the unblocked thyroid

  14. Main-coolant-pump shaft-seal guidelines. Volume 3. Specification guidelines. Final report

    International Nuclear Information System (INIS)

    Fair, C.E.; Greer, A.O.

    1983-03-01

    This report presents a set of guidelines and criteria to aid in the generation of procurement specifications for Main Coolant Pump Shaft Seals. The noted guidelines are developed from EPRI sponsored nuclear power plant seal operating experience studies, a review of pump and shaft seal literature and discussions with pump and seal designers. This report is preliminary in nature and could be expanded and finalized subsequent to completion of further design, test and evaluation efforts

  15. Fast reactor safety: proceedings of the international topical meeting. Volume 2. [R

    Energy Technology Data Exchange (ETDEWEB)

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments.

  16. ESTRO ACROP guidelines for target volume definition in the treatment of locally advanced non-small cell lung cancer.

    Science.gov (United States)

    Nestle, Ursula; De Ruysscher, Dirk; Ricardi, Umberto; Geets, Xavier; Belderbos, Jose; Pöttgen, Christoph; Dziadiuszko, Rafal; Peeters, Stephanie; Lievens, Yolande; Hurkmans, Coen; Slotman, Ben; Ramella, Sara; Faivre-Finn, Corinne; McDonald, Fiona; Manapov, Farkhad; Putora, Paul Martin; LePéchoux, Cécile; Van Houtte, Paul

    2018-04-01

    Radiotherapy (RT) plays a major role in the curative treatment of locally advanced non-small cell lung cancer (NSCLC). Therefore, the ACROP committee was asked by the ESTRO to provide recommendations on target volume delineation for standard clinical scenarios in definitive (chemo)radiotherapy (RT) and adjuvant RT for locally advanced NSCLC. The guidelines given here are a result of the evaluation of a structured questionnaire followed by a consensus discussion, voting and writing procedure within the committee. Hence, we provide advice for methods and time-points of diagnostics and imaging before the start of treatment planning and for the mandatory and optional imaging to be used for planning itself. Concerning target volumes, recommendations are given for GTV delineation of primary tumour and lymph nodes followed by issues related to the delineation of CTVs for definitive and adjuvant radiotherapy. In the context of PTV delineation, recommendations about the management of geometric uncertainties and target motion are given. We further provide our opinions on normal tissue delineation and organisational and responsibility questions in the process of target volume delineation. This guideline intends to contribute to the standardisation and optimisation of the process of RT treatment planning for clinical practice and prospective studies. Copyright © 2018 Elsevier B.V. All rights reserved.

  17. Guidelines for radiation safety in interventional cardiology (JCS 2006)

    International Nuclear Information System (INIS)

    Nagai, Ryozo; Awai, Kazuo; Iesaka, Yoshihito

    2006-01-01

    The guidelines are made for physicians in cardiovascular field who may be unfamiliar to radiation safety, to understand and know it easily. The introductory chapter describes the basic knowledge for management of radiation exposure and clinical feature of radiation-induced dermal damages like classification, clinical progress and case presentation. Following chapter is itemized, explained in a style of Q and A, and contains sections of; the fundamental knowledge's of radiation exposure management and of radiation skin damage, informed consent and measures for excessive exposure and skin damage crisis, factors influencing the exposure dose, contrivances to reduce the dose in patients, additional factors affecting the crisis of skin damage, contrivances to reduce the dose in medical personnel exposure, management of imaging instruments, methods to measure the exposure dose in patients, intervention in vessels other than the coronary artery, electro-physiological examinations and treatments, nuclear medical diagnoses, CT examinations, diagnosis and treatment of pregnant women, and present states in other countries. (T.I.)

  18. 23 CFR 650.211 - Guidelines.

    Science.gov (United States)

    2010-04-01

    ... 23 Highways 1 2010-04-01 2010-04-01 false Guidelines. 650.211 Section 650.211 Highways FEDERAL..., STRUCTURES, AND HYDRAULICS Erosion and Sediment Control on Highway Construction Projects § 650.211 Guidelines. (a) The FHWA adopts the AASHTO Highway Drainage Guidelines, Volume III, “Erosion and Sediment Control...

  19. RELAP/MOD3 code manual: User`s guidelines. Volume 5, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Fletcher, C.D.; Schultz, R.R. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1995-08-01

    The RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and operational transients, such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. Volume V contains guidelines that have solved over the past several years through the use of the RELAP5 code.

  20. Consensus Guidelines for Delineation of Clinical Target Volume for Intensity-Modulated Pelvic Radiotherapy for the Definitive Treatment of Cervix Cancer

    International Nuclear Information System (INIS)

    Lim, Karen; Small, William; Portelance, Lorraine; Creutzberg, Carien; Juergenliemk-Schulz, Ina M.; Mundt, Arno; Mell, Loren K.; Mayr, Nina; Viswanathan, Akila; Jhingran, Anuja; Erickson, Beth; De Los Santos, Jennifer; Gaffney, David; Yashar, Catheryn; Beriwal, Sushil; Wolfson, Aaron

    2011-01-01

    Purpose: Accurate target definition is vitally important for definitive treatment of cervix cancer with intensity-modulated radiotherapy (IMRT), yet a definition of clinical target volume (CTV) remains variable within the literature. The aim of this study was to develop a consensus CTV definition in preparation for a Phase 2 clinical trial being planned by the Radiation Therapy Oncology Group. Methods and Materials: A guidelines consensus working group meeting was convened in June 2008 for the purposes of developing target definition guidelines for IMRT for the intact cervix. A draft document of recommendations for CTV definition was created and used to aid in contouring a clinical case. The clinical case was then analyzed for consistency and clarity of target delineation using an expectation maximization algorithm for simultaneous truth and performance level estimation (STAPLE), with kappa statistics as a measure of agreement between participants. Results: Nineteen experts in gynecological radiation oncology generated contours on axial magnetic resonance images of the pelvis. Substantial STAPLE agreement sensitivity and specificity values were seen for gross tumor volume (GTV) delineation (0.84 and 0.96, respectively) with a kappa statistic of 0.68 (p < 0.0001). Agreement for delineation of cervix, uterus, vagina, and parametria was moderate. Conclusions: This report provides guidelines for CTV definition in the definitive cervix cancer setting for the purposes of IMRT, building on previously published guidelines for IMRT in the postoperative setting.

  1. Chemical Safety Vulnerability Working Group report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains the Executive summary; Introduction; Summary of vulnerabilities; Management systems weaknesses; Commendable practices; Summary of management response plan; Conclusions; and a Glossary of chemical terms.

  2. Chemical Safety Vulnerability Working Group report. Volume 1

    International Nuclear Information System (INIS)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains the Executive summary; Introduction; Summary of vulnerabilities; Management systems weaknesses; Commendable practices; Summary of management response plan; Conclusions; and a Glossary of chemical terms

  3. Proposal of a post-prostatectomy clinical target volume based on pre-operative MRI: volumetric and dosimetric comparison to the RTOG guidelines

    International Nuclear Information System (INIS)

    Croke, Jennifer; Maclean, Jillian; Nyiri, Balazs; Li, Yan; Malone, Kyle; Avruch, Leonard; Kayser, Cathleen; Malone, Shawn

    2014-01-01

    Recurrence rates following radiotherapy for prostate cancer in the post-operative adjuvant or salvage setting remain substantial. Previous work from our institution demonstrated that published prostate bed CTV guidelines frequently do not cover the pre-operative MRI defined prostate. Inadequate target delineation may contribute to the high recurrence rates, but increasing target volumes may increase dose to organs at risk. We propose guidelines for delineating post-prostatectomy target volumes based upon an individual’s co-registered pre-operative MRI. MRI-based CTVs and PTVs were compared to those created using the RTOG guidelines in 30 patients. Contours were analysed in terms of absolute volume, intersection volume (Jaccard Index) and the ability to meet the RADICALS and QUANTEC rectal and bladder constraints (tomotherapy IMRT plans with PTV coverage of V98% ≥98%). CTV MRI was a mean of 18.6% larger than CTV RTOG: CTV MRI mean 138 cc (range 72.3 - 222.2 cc), CTV RTOG mean 116.3 cc (range 62.1 - 176.6 cc), (p < 0.0001). The difference in mean PTV was only 4.6%: PTV MRI mean 386.9 cc (range 254.4 – 551.2), PTV RTOG mean 370 cc (range 232.3 - 501.6) (p = 0.05). The mean Jaccard Index representing intersection volume between CTVs was 0.72 and 0.84 for PTVs. Both criteria had a similar ability to meet rectal and bladder constraints. Rectal DVH: 77% of CTV RTOG cases passed all RADICALS criteria and 37% all QUANTEC criteria; versus 73% and 40% for CTV MRI (p = 1.0 for both). Bladder DVH; 47% of CTV RTOG cases passed all RADICALS criteria and 67% all QUANTEC criteria, versus 57% and 60% for CTV MRI (p = 0.61for RADICALS, p = 0.79 for QUANTEC). CTV MRI spares more of the lower anterior bladder wall than CTV RTOG but increases coverage of the superior lateral bladder walls. CTV contours based upon the patient’s co-registered pre-operative MRI in the post-prostatectomy setting may improve coverage of the individual’s prostate bed without substantially increasing

  4. 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

  5. Site locality identification study: Hanford Site. Volume I. Methodology, guidelines, and screening

    International Nuclear Information System (INIS)

    1980-07-01

    Presented in this report are the results of the site locality identification study for the Hanford Site using a screening process. To enable evaluation of the entire Hanford Site, the screening process was applied to a somewhat larger area; i.e., the Pasco Basin. The study consisted of a series of screening steps that progressively focused on smaller areas which are within the Hanford Site and which had a higher potential for containing suitable repository sites for nuclear waste than the areas not included for further study. Five site localities, designated H-1, H-2, H-3, H-4, H-5 (Figure A), varying in size from approximately 10 to 50 square miles, were identified on the Hanford Site. It is anticipated that each site locality may contain one or more candidate sites suitable for a nuclear waste repository. The site locality identification study began with definition of objectives and the development of guidelines for screening. Three objectives were defined: (1) maximize public health and safety; (2) minimize adverse environmental and socioeconomic impacts; and (3) minimize system costs. The screening guidelines have numerical values that provided the basis for the successive reduction of the area under study and to focus on smaller areas that had a higher likelihood of containing suitable sites

  6. Main-coolant-pump shaft-seal guidelines. Volume 1. Maintenance-manual guidelines. Final report

    International Nuclear Information System (INIS)

    Fair, C.E.; Greer, A.O.

    1983-03-01

    This report presents a set of guidelines and a listing of information and data which should be included in maintenance manuals and procedures for Main Coolant Pump Shaft Seals. The noted guidelines and data listing are developed from EPRI sponsored nuclear plant seal operating experience studies. The maintenance oriented results of the most recent such study is summarized. The shaft seal and its auxiliary supporting systems are discussed from both technical and maintenance related viewpoints

  7. Improving the implementation of perioperative safety guidelines using a multifaceted intervention approach: protocol of the IMPROVE study, a stepped wedge cluster randomized trial.

    Science.gov (United States)

    Emond, Yvette E J J M; Calsbeek, Hiske; Teerenstra, Steven; Bloo, Gerrit J A; Westert, Gert P; Damen, Johan; Wolff, André P; Wollersheim, Hub C

    2015-01-08

    This study is initiated to evaluate the effects, costs, and feasibility at the hospital and patient level of an evidence-based strategy to improve the use of Dutch perioperative safety guidelines. Based on current knowledge, expert opinions and expertise of the project team, a multifaceted implementation strategy has been developed. This is a stepped wedge cluster randomized trial including nine representative hospitals across The Netherlands. Hospitals are stratified into three groups according to hospital type and geographical location and randomized in terms of the period for receipt of the intervention. All adult surgical patients meeting the inclusion criteria are assessed for patient outcomes. The implementation strategy includes education, audit and feedback, organizational interventions (e.g., local embedding of the guidelines), team-directed interventions (e.g., multi-professional team training), reminders, as well as patient-mediated interventions (e.g., patient safety cards). To tailor the implementation activities, we developed a questionnaire to identify barriers for effective guideline adherence, based on (a) a theoretical framework for classifying barriers and facilitators, (b) an instrument for measuring determinants of innovations, and (c) 19 semi-structured interviews with perioperative key professionals. Primary outcome is guideline adherence measured at the hospital (i.e., cluster) and patient levels by a set of perioperative Patient Safety Indicators (PSIs), which was developed parallel to the perioperative guidelines. Secondary outcomes at the patient level are in-hospital complications, postoperative wound infections and mortality, length of hospital stay, and unscheduled transfer to the intensive care unit, non-elective readmission to the hospital and unplanned reoperation, all within 30 days after the initial surgery. Also, patient safety culture and team climate will be studied as potential determinants. Finally, a process evaluation is

  8. Chemical Safety Vulnerability Working Group report. Volume 2

    International Nuclear Information System (INIS)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 2 consists of seven appendices containing the following: Tasking memorandums; Project plan for the CSV Review; Field verification guide for the CSV Review; Field verification report, Lawrence Livermore National Lab.; Field verification report, Oak Ridge Reservation; Field verification report, Savannah River Site; and the Field verification report, Hanford Site

  9. Chemical Safety Vulnerability Working Group report. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 2 consists of seven appendices containing the following: Tasking memorandums; Project plan for the CSV Review; Field verification guide for the CSV Review; Field verification report, Lawrence Livermore National Lab.; Field verification report, Oak Ridge Reservation; Field verification report, Savannah River Site; and the Field verification report, Hanford Site.

  10. ASCOT guidelines

    International Nuclear Information System (INIS)

    1994-05-01

    These guidelines describe an approach used in conducting an Assessment of Safety Culture in Organizations Team (ASCOT) review. They are intended to assist the team members in conducting their reviews and at the same time provide guidance to hosts preparing to receive an ASCOT review. They may also be used by any organization wishing to conduct their own self-assessment of safety culture, independent of an ASCOT review

  11. The role of post-earthquake structural safety in pre-earthquake retrof in decision: guidelines and applications

    International Nuclear Information System (INIS)

    Bazzurro, P.; Telleen, K.; Maffei, J.; Yin, J.; Cornell, C.A.

    2009-01-01

    Critical structures such as hospitals, police stations, local administrative office buildings, and critical lifeline facilities, are expected to be operational immediately after earthquakes. Any rational decision about whether these structures are strong enough to meet this goal or whether pre-empitive retrofitting is needed cannot be made without an explicit consideration of post-earthquake safety and functionality with respect to aftershocks. Advanced Seismic Assessment Guidelines offer improvement over previous methods for seismic evaluation of buildings where post-earthquake safety and usability is a concern. This new method allows engineers to evaluate the like hood that a structure may have restricted access or no access after an earthquake. The building performance is measured in terms of the post-earthquake occupancy classifications Green Tag, Yellow Tag, and Red Tag, defining these performance levels quantitatively, based on the structure's remaining capacity to withstand aftershocks. These color-coded placards that constitute an established practice in US could be replaced by the standard results of inspections (A to E) performed by the Italian Dept. of Civil Protection after an event. The article also shows some applications of these Guidelines to buildings of the largest utility company in California, Pacific Gas and Electric Company (PGE). [it

  12. Probabilistic safety analysis procedures guide, Sections 8-12. Volume 2, Rev. 1

    International Nuclear Information System (INIS)

    McCann, M.; Reed, J.; Ruger, C.; Shiu, K.; Teichmann, T.; Unione, A.; Youngblood, R.

    1985-08-01

    A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. The first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. This second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

  13. Guidelines on the safety of light-based home-use hair removal devices from the European Society for Laser Dermatology

    DEFF Research Database (Denmark)

    Town, Graham; Ash, C; Dierickx, C

    2012-01-01

    . These guidelines provide a definition of light-based home-use technology, to inform healthcare professionals about home-use light-based technology and encourage manufacturers wishing to sell in Europe to adopt 'best practice'. The review presents the current status on standards and regulation issues and considers...... home-use safety issues, encompassing human, device and electrical safety, given risks to the eyes and skin from optical radiation both to the consumer and persons in the vicinity. Proposed technical measurement methodology is considered with focus on recognized critical parameters for the safe use...... of light-based hair removal technology including recording the technical performance and safety claims of a range of home-use hair removal devices. The literature review emphasizes potential adverse incidents and safety aspects of treating cosmetic conditions, such as unwanted hair growth. Although some...

  14. Safety guidelines for magnetic resonance diagnostic facilities (1991)

    International Nuclear Information System (INIS)

    1992-01-01

    These guidelines provide information on levels and health effects of exposure to magnetic and radiofrequency electromagnetic fields associated with magnetic resonance (MR) devices, and on precautions to minimize effects on patients, staff, and the general public. The guidelines are for use by regulatory authorities, MR users and health professionals. 22 refs., 1 tab

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

    Science.gov (United States)

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

    1993-01-01

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

  16. Swiss guideline: Protection objectives for the disposal of radioactive waste

    International Nuclear Information System (INIS)

    Zurkinden, A.

    1994-01-01

    The Swiss guideline R-21 establishing the protection objectives for the disposal of radioactive waste has been reviewed and amended in order to adapt it to improvements made in the field of radioactive waste disposal. In an introductory part, the new guideline states the overall objective of radioactive waste disposal and the associated principles which have to be observed. The guideline then establishes the safety requirements applied to a geological disposal facility. These safety requirements are formulated as protection goals for the whole disposal system and not as specific criteria applying to the system components. The guideline gives finally a series of explanatory comments and indications concerning the conduct of the safety assessment for a disposal facility

  17. The System 80+ Standard Plant design control document. Volume 23

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains part 16 References and Appendix 19 A Design Alternatives for section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Also covered is section 20 Unresolved Safety Issues of the ADM Design and Analysis. Finally sections 1--6 of the ADM Emergency Operations Guidelines are contained in this volume. Information covered in these sections include: standard post-trip actions; diagnostic actions; reactor trip recovery guideline; LOCA recovery; SG tube rupture recovery

  18. Comparison of evaluation guidelines for life-safety seismic hazards

    International Nuclear Information System (INIS)

    Wyllie, L.A.; Love, R.J.

    1989-01-01

    The guidelines presented in Design Evaluation guidelines for Department of Energy Facilities Subjected to natural Phenomena Hazards (UCRL 15910 Draft; May 1989) include evaluation criteria for existing Department of Energy buildings subjected to earthquakes. These criteria were developed at the Lawrence Livermore National Laboratory for use in both the seismic design of new structures and the evaluation of existing structures. ATC-14: Evaluating The Seismic Resistance of Existing Buildings developed by the Applied Technology Council, consists of guidelines and criteria for identifying the buildings or building components that present unacceptable risk to human lives. This paper compares and contrasts the two evaluation guidelines for existing buildings using a prototype building as an example. The prototype building is a seven story, concrete shear wall building assuming a General Use Occupancy

  19. Efficacy and safety testing of mycotoxin-detoxifying agents in broilers following the European Food Safety Authority guidelines.

    Science.gov (United States)

    Osselaere, A; Devreese, M; Watteyn, A; Vandenbroucke, V; Goossens, J; Hautekiet, V; Eeckhout, M; De Saeger, S; De Baere, S; De Backer, P; Croubels, S

    2012-08-01

    Contamination of feeds with mycotoxins is a worldwide problem and mycotoxin-detoxifying agents are used to decrease their negative effect. The European Food Safety Authority recently stated guidelines and end-points for the efficacy testing of detoxifiers. Our study revealed that plasma concentrations of deoxynivalenol and deepoxy-deoxynivalenol were too low to assess efficacy of 2 commercially available mycotoxin-detoxifying agents against deoxynivalenol after 3 wk of continuous feeding of this mycotoxin at concentrations of 2.44±0.70 mg/kg of feed and 7.54±2.20 mg/kg of feed in broilers. This correlates with the poor absorption of deoxynivalenol in poultry. A safety study with 2 commercially available detoxifying agents and veterinary drugs showed innovative results with regard to the pharmacokinetics of 2 antibiotics after oral dosing in the drinking water. The plasma and kidney tissue concentrations of oxytetracycline were significantly higher in broilers receiving a biotransforming agent in the feed compared with control birds. For amoxicillin, the plasma concentrations were significantly higher for broilers receiving an adsorbing agent in comparison to birds receiving the biotransforming agent, but not to the control group. Mycotoxin-detoxifying agents can thus interact with the oral bioavailability of antibiotics depending on the antibiotic and detoxifying agent, with possible adverse effects on the health of animals and humans.

  20. Interaction of national and foreign safety guidelines

    International Nuclear Information System (INIS)

    Domaratzki, Z.

    1991-01-01

    A commercial contract for a nuclear power plant includes an agreement on the appropriate safety requirements with which the plant must conform. This may involve adopting the safety requirements of the exporting country, the importing country or a combination of the two sets of safety requirements. To ensure that a high level of safety is achieved it is appropriate that the regulatory authorities in the two countries should establish a co-operative arrangement which will extend for the life of the plant. The regulatory authority in the importing country will need to develop a good understanding of the design, safety analysis and operating history of the reactor type which is being purchased. The regulator in the exporting country can be of great assistance in this regard. The co-operative arrangement should extend into the commissioning and operating stage at which point there will be a two way flow of information. During the operating stage information exchange should include significant operating events, operating problems, new safety related research information, necessary design changes and the results of periodic updating of the safety analysis. In some cases the co-operation should extend to training of regulatory staff. The choice of national versus foreign safety requirements may be important. However, if the two regulatory authorities are to discharge their legal and moral safety responsibilities it is at least equally important to maintain a co-operative arrangement for the life of the plant. (author)

  1. Methodological guidelines for developing accident modification functions

    DEFF Research Database (Denmark)

    Elvik, Rune

    2015-01-01

    This paper proposes methodological guidelines for developing accident modification functions. An accident modification function is a mathematical function describing systematic variation in the effects of road safety measures. The paper describes ten guidelines. An example is given of how to use...... limitations in developing accident modification functions are the small number of good evaluation studies and the often huge variation in estimates of effect. It is therefore still not possible to develop accident modification functions for very many road safety measures. © 2015 Elsevier Ltd. All rights...... the guidelines. The importance of exploratory analysis and an iterative approach in developing accident modification functions is stressed. The example shows that strict compliance with all the guidelines may be difficult, but represents a level of stringency that should be strived for. Currently the main...

  2. Inventory of Federal energy-related environment and safety research for FY 1977. Volume II. Project listings

    Energy Technology Data Exchange (ETDEWEB)

    1978-07-01

    This volume contains Biomedical and Environmental Research, Environmental Control Technology Research, and Operational and Environmental Safety Research project listings. The projects are ordered numerically by log number.

  3. Site Environmental Report for 2006. Volume I, Environment, Health, and Safety Division

    Energy Technology Data Exchange (ETDEWEB)

    None

    2007-09-30

    Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2006 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2006. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I is organized into an executive summary followed by six chapters that contain an overview of the Laboratory, a discussion of the Laboratory’s environmental management system, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from surveillance and monitoring activities.

  4. Mexican Asthma Guidelines: GUIMA 2017

    Directory of Open Access Journals (Sweden)

    Désirée Larenas-Linnemann

    2017-04-01

    Full Text Available Background: The need for a national guideline, with a broad basis among specialists and primary care physicians was felt in Mexico, to try unifying asthma management. As several high-quality asthma guidelines exist worldwide, it was decided to select the best three for transculturation. Methods: Following the internationally recommended methodology for guideline transculturation, ADAPTE, a literature search for asthma guidelines, published 1-1-2007 through 31-12-2015 was conducted. AGREE-II evaluations yielded 3/40 most suitable for transculturation. Their compound evidence was fused with local reality, patient preference, cost and safety considerations to draft the guideline document. Subsequently, this was adjusted by physicians from 12 national medical societies in several rounds of a Delphi process and 3 face-to-face meetings to reach the final version. Results: Evidence was fused from British Thoracic Society Asthma Guideline 2014, Global Initiative on Asthma 2015, and Guía Española del Manejo del Asma 2015 (2016 updates included. After 3 Delphi-rounds we developed an evidence-based document taking into account patient characteristics, including age, treatment costs and safety and best locally available medication. Conclusion: In cooperation pulmonologists, allergists, ENT physicians, paediatricians and GPs were able to develop an evidence-based document for the prevention, diagnosis and treatment of asthma and its exacerbations in Mexico.

  5. SARIS Guidelines. 2014 Ed

    International Nuclear Information System (INIS)

    2014-01-01

    The IAEA fundamental safety principles provide the basis for IAEA safety standards and IAEA related programmes. 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 regulators should achieve. These standards, in particular IAEA Safety Standards Series No. GSR Part 1, Governmental, Legal and Regulatory Framework for Safety, provide the basics for establishing, maintaining and continuously improving the governmental, legal and regulatory framework for safety. Additional IAEA requirements and guidance, such as the IAEA Safety Standards Series No. GSR Part 3 (Interim), Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, and IAEA Safety Standards Series No. GS-R-3, The Management System for Facilities and Activities, are also used to establish and develop the national infrastructure for safety and for establishing and implementing a management system. Assessment of the regulatory framework for safety with respect to the IAEA safety standards can be made either through an external review or through internal self-assessment. Self-assessment offers a mechanism by which an organization can assess its performance against established standards and models and thereby identify areas for improvement. The IAEA has developed a methodology and tool for Self-assessment of the Regulatory Infrastructure for Safety (SARIS), to assist States in undertaking self-assessment of their national safety framework in accordance with the requirements and recommendations of the IAEA safety standards, and to develop an action plan for improvement. The IAEA self-assessment methodology and the associated tools are fully compatible with the IAEA safety standards and are also used in the preparation for regulatory review missions, such as the Integrated Regulatory Review Service and advisory missions. These guidelines have been developed to

  6. Guidelines on Building Regulations 2008

    DEFF Research Database (Denmark)

    Thse guidelines clarify and intepret the provisions of the Building Regulations of 2008 (BR08). The Guidelines, which match BR08 in terms of organisation into Parts, are accompanied by the full text of the regulations and the explanatory notes issued by the Danish Enterprise and Construction...... Authority. The Guidelines refer the reader to sources such as relevant standards, instructions and other background material which provides more detailed information. The Guidelines cover the same ground as BR08, including building control regulations, layout, fitting out, structures, fire safety, indoor...... climate, energy consumotion and services. The Guidelines are aimed at all professionals involved in building projects, particularly building design consultants, contractors and municipal application officers....

  7. 7 CFR 1724.55 - Dam safety.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 11 2010-01-01 2010-01-01 false Dam safety. 1724.55 Section 1724.55 Agriculture... § 1724.55 Dam safety. (a) The provisions of this section apply only to RUS financed electric system... for Dam Safety,”(Guidelines), as applicable. A dam, as more fully defined in the Guidelines, is...

  8. 49 CFR 350.339 - What are tolerance guidelines?

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 5 2010-10-01 2010-10-01 false What are tolerance guidelines? 350.339 Section 350... MOTOR CARRIER SAFETY ASSISTANCE PROGRAM Funding § 350.339 What are tolerance guidelines? Tolerance guidelines set forth the limited deviations from the FMCSRs allowed in your State's laws and regulations...

  9. Between demarcation and discretion: The medical-administrative boundary as a locus of safety in high-volume organisational routines.

    Science.gov (United States)

    Grant, Suzanne; Guthrie, Bruce

    2018-04-01

    Patient safety is an increasing concern for health systems internationally. The majority of administrative work in UK general practice takes place in the context of organisational routines such as repeat prescribing and test results handling, where high workloads and increased clinician dependency on administrative staff have been identified as an emerging safety issue. Despite this trend, most research to date has focused on the redistribution of the clinical workload between doctors, nurses and allied health professionals within individual care settings. Drawing on Strauss's negotiated order perspective, we examine ethnographically the achievement of safety across the medical-administrative boundary in key high-volume routines in UK general practice. We focus on two main issues. First, GPs engaged in strategies of demarcation by defining receptionist work as routine, unspecialised and dependent upon GP clinical knowledge and oversight as the safety net to deal with complexity and risk. Receptionists consented to this 'social closure' when describing their role, thus reinforcing the underlying inter-occupational relationship of medical domination. Second, in everyday practice, GPs and receptionists engaged in informal boundary-blurring to safely accommodate the complexity of everyday high-volume routine work. This comprised additional informal discretionary spaces for receptionist decision-making and action that went beyond the routine safety work formally assigned to them. New restratified intra-occupational hierarchies were also being created between receptionists based on the complexity of the safety work that they were authorised to do at practice level, with specialised roles constituting a new form of administrative 'professional project'. The article advances negotiated order theory by providing an in-depth examination of the ways in which medical-administrative boundary-making and boundary-blurring constitute distinct modes of safety in high-volume

  10. Car Seat Safety

    Science.gov (United States)

    ... Staying Safe Videos for Educators Search English Español Car Seat Safety KidsHealth / For Parents / Car Seat Safety ... certified child passenger safety technician.) Guidelines for Choosing Car Seats Choose a seat with a label that ...

  11. Guidelines and workbook for assessment of organization and administration of utilities seeking operating license for a nuclear power plant. Guidelines for utility organization and administration plan. Volume 1, Revision 1

    International Nuclear Information System (INIS)

    Thurber, J.A.; Olson, J.; Osborn, R.N.; Sommers, P.; Widrig, R.D.

    1986-09-01

    Volumes 1 and 2 of this report are a partial response to the requirements of Item I.B.1.1 of the ''NRC Action Plan Developed as a Result of the TMI-2 Accident,'' NUREG-0660, and are designed to serve as a basis for replacing the earlier NUREG-0731, ''Guidelines for Utility Management Structure and Technical Resources.'' These Guidelines are intended to provide guidance to the user in preparing a written plan for a proposed nuclear organization and administration. The purpose of the Workbook (Vol. 2) is to guide the NRC reviewer through a systematic review and assessment of a proposed organization and administration. It is the NRC's intention to incorporate these Guidelines and Workbook into a future revision of the Standard Review Plan (SRP), NUREG-0800. However, at this time the report is being published so that the material may be used on a voluntary basis by industry to systematically prepare or evaluate their organization or administration plans. Use of the report by the NRC would not occur until after it has been incorpoarted in the SRP

  12. Bathroom safety - children

    Science.gov (United States)

    Well child - bathroom safety ... be put in charge of a younger child's safety. There should be an adult in the bathroom ... sure grandparents, friends, and other caretakers follow bathroom safety guidelines. Make sure your child's daycare also follows ...

  13. Integrated Safety in ''SARAF'

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  14. It’s all about safety signs!

    CERN Multimedia

    2013-01-01

    Their first occurrence may date back to the Egyptian hieroglyphs, but today they can be found everywhere: on our clothes labels as care labels, in train stations and airports to guide us, during the Olympics to identify various sports, on our dashboards, etc.   Safety wise, they are used to indicate a danger, a prohibition, an obligation, a safety exit, firefighting equipment, etc. The HSE Unit has decided to update the 150 safety signs used on the CERN site and, to correspond with this, recently published a Safety Guideline GS-1-0-1, available on the Safety Unit website. The Guideline contains more than 150 safety signs as well as diverse information regarding the meaning of the signs, their location and how to use them. The Guideline will shortly be completed with a new Safety Rule that will replace the former Security Code A3, “Safety colours and safety signs”. Please be informed that you also have the option to create new safety signs, provided that you first g...

  15. Development of human factors design review guidelines

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

    1997-10-01

    The Objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, Human factors engineering program review model' and '26, Review criteria for human actors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides be ing performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we well update the guidelines by reviewing the literature related to alarm design published after 1994

  16. Development of human factors design review guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea)

    1997-10-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: 25. Human Factors Engineering Program Review Model and 26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation, which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994. (author). 12 refs., 5 figs., 2 tabs.

  17. Joint IAEA/NEA IRS guidelines

    International Nuclear Information System (INIS)

    1997-01-01

    The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants

  18. Probabilistic safety analysis procedures guide. Sections 1-7 and appendices. Volume 1, Revision 1

    International Nuclear Information System (INIS)

    Bari, R.A.; Buslik, A.J.; Cho, N.Z.

    1985-08-01

    A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. This first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. The second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

  19. Safety research on fusion DEMO in Japan: Toward development of safety strategy of a water-cooled DEMO

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, Makoto, E-mail: nakamura.makoto@jaea.go.jp [Japan Atomic Energy Agency, Rokkasho 039-3212, Aomori (Japan); Tobita, Kenji; Someya, Youji; Utoh, Hiroyasu; Sakamoto, Yoshiteru [Japan Atomic Energy Agency, Rokkasho 039-3212, Aomori (Japan); Gulden, Werner [Fusion for Energy, Garching D-85748 (Germany)

    2016-11-01

    Highlights: • This paper reports the current status of a safety research on water-cooled fusion DEMO in Japan. • We report analyses of two transients: (i) complete loss of decay heat removal and (ii) major ex-VV LOCA. • The MELCOR analysis has clarified the temperature histories of the DEMO components in complete loss of decay heat removal. • A strategy to reduce the pressure load to the final barrier confining radioactive materials is proposed against the major ex-VV LOCA. - Abstract: This paper reports the current status of a safety research on water-cooled fusion DEMO in Japan. A basic strategy of development of the safety guidelines is described for DEMO based on a water-cooled solid pebble bed blanket. Clarification of safety features of the DEMO in accident situations is a key issue to develop the guidelines. Recent achievements in understanding of the safety features of the water-cooled DEMO are reported. The MELCOR analysis has clarified the temperature histories of the DEMO components in a complete loss of decay heat removal event. The transient behavior of the first wall temperature is found to be essentially different from that of ITER. The pressure load to the tokamak cooling water system vault (TCWSV) is analyzed based on a simple model equation of the energy conservation. If the amount of the primary coolant is the same as that of Slim-CS, the previous small Japanese DEMO, the discharged water does not damage the TCWSV with the volume and pressure-tightness similar to those of pressurized light water reactors. It is shown that implementation of a pressure suppression system to the small TCWSV is effective to suppress the pressure load to the second confinement barrier.

  20. Safety system status monitoring

    International Nuclear Information System (INIS)

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide

  1. Safety system status monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

  2. ASSET guidelines

    International Nuclear Information System (INIS)

    1990-11-01

    The IAEA Assessment of Safety Significant Events Team (ASSET) Service provides advice and assistance to Member States to enhance the overall level of plant safety while dealing with the policy of prevention of incidents at nuclear power plants. The ASSET programme, initiated in 1986, is not restricted to any particular group of Member States, whether developing or industrialized, but is available to all countries with nuclear power plants in operation or approaching commercial operation. The IAEA Safety Series publications form common basis for the ASSET reviews, including the Nuclear Safety Standards (NUSS) and the Basic Safety Principles (Recommendations of Safety Series No. 75-INSAG-3). The ASSET Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of their review of incident investigations. Additional guidance and reference material is provided by the IAEA to complement the expertise of the ASSET members. ASSET reviews accept different approaches that contribute to ensuring an effective prevention of incidents at plants. Suggestions are offered to enhance plant safety performance. Commendable good practices are identified and generic lessons are communicated to other plants, where relevant, for long term improvement

  3. Technical Issues and Proposes on the Legislation of Probabilistic Safety Assessment in Periodic Safety Review

    International Nuclear Information System (INIS)

    Hwang, Seok-Won; Jeon, Ho-Jun; Na, Jang-Hwan

    2015-01-01

    Korean Nuclear Power Plants have performed a comprehensive safety assessment reflecting design and procedure changes and using the latest technology every 10 years. In Korea, safety factors of PSR are revised to 14 by revision of IAEA Safety Guidelines in 2003. In the revised safety guidelines, safety analysis field was subdivided into deterministic safety analysis, PSA (Probabilistic safety analysis), and hazard analysis. The purpose to examine PSA as a safety factor on PSR is to make sure that PSA results and assumptions reflect the latest state of NPPs, validate the level of computer codes and analytical models, and evaluate the adequacy of PSA instructions. In addition, its purpose is to derive the plant design change, operating experience of other plants and safety enhancement items as well. In Korea, PSA is introduced as a new factor. Thus, the overall guideline development and long-term implementation strategy are needed. Today in Korea, full-power PSA model revision and low-power and shutdown (LPSD) PSA model development is being performed as a part of the post Fukushima action items for operating plants. The scope of the full-power PSA is internal/external level 1, 2 PSA. But in case of fire PSA, the scope is level 1 PSA using new method, NUREG/CR-6850. In case of LPSD PSA, level 1 PSA for all operating plants, and level 2 PSA for 2 demonstration plants are under development. The result of the LPSD PSA will be used as major input data for plant specific SAMG (Severe Accident Management Guideline). The scope of PSA currently being developed in Korea cannot fulfill 'All Mode, All Scope' requirements recommended in the IAEA Safety Guidelines. Besides the legislation of PSA, step-by-step development strategy for non-performed scopes such as level 3 PSA and new fire PSA is one of the urgent issues in Korea. This paper suggests technical issues and development strategies for each PSA technical elements.

  4. Inspector qualification guidelines

    International Nuclear Information System (INIS)

    Batty, A.C.; Van Binnebeek, J.J.; Ericsson, P.O.; Fisher, J.C.; Geiger, P.; Grandame, M.; Grimes, B.K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

    1994-07-01

    The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied

  5. Inspector qualification guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Batty, A. C.; Van Binnebeek, J. J.; Ericsson, P. O.; Fisher, J. C.; Geiger, P.; Grandame, M.; Grimes, B. K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

    1994-07-15

    The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied.

  6. [Guidelines for management of epilepsy--commentary on Scottish ("SIGN") guidelines].

    Science.gov (United States)

    Planjar-Prvan, Miljenka; Granić, Davorka

    2005-01-01

    The choice of AED (antiepileptic drug), worldwide and in Croatia, is been still based on the physician's subjective decision, personal experience, knowledge and marketing pressure made by big pharmaceutical industries. Therefore, according to some opinions, there is a need of treatment guidelines for epilepsy that would provide relevant information based on scientific evidence on the efficacy, tolerability and safety of AEDs. The guidelines, published by a competent source, should be designed as to allow for easy access to the information on the best practice in specific cases. An extensive background literature review was made to identify such a type of guidelines for the management of epilepsy. The literature review revealed a number of references with the recommendations for treating epilepsy in different groups of patients and from various, specific aspects of epilepsy treatment. However, only one comprehensive set of guidelines for the diagnosis and treatment of epilepsy treatment was found, i.e. the evidence-based guidelines published by the Scottish Intercollegiate Guidelines Network (SIGN). The development of this set of guidelines is quite extensively described in order to illustrate how rigorous and long-lasting the process was, including a great number of health professionals at the national level. Such a type of well designed guidelines facilitates access to highest educational standards for all professionals involved in the primary and secondary care of people with epilepsy. However, it is clear that guidelines can fully replace the standards of clinical practice based on critical evaluation and integration of all clinical data of each individual patient. No guidelines can replace the physician's obligation to keep informed of the novel achievements in the epileptology either.

  7. Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

    International Nuclear Information System (INIS)

    Lucas, D.E.; Ikenberry, T.A.

    1993-09-01

    Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91. The DOE nuclear safety policy states that the general public shall be protected such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL, and are not intended for evaluation of routine exposures. A safety analyst uses the,frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy. The radiological risk evaluation guidelines are an effective tool for assisting in the management of risk at DOE nonreactor nuclear facilities. These guidelines (1) meet the nuclear safety policy of DOE, (2) establish a tool for managing risk at a consistent level within the defined constraints, and (3) set risk at an appropriate level, as compared with other risks encountered by the public and worker. Table S.1 summarizes the guidelines developed in this report

  8. Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately.

  9. Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

    International Nuclear Information System (INIS)

    Monteleone, S.

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately

  10. Training Requirements in OSHA Standards and Training Guidelines. Revised.

    Science.gov (United States)

    Occupational Safety and Health Administration, Washington, DC.

    This guide provides an overview of Occupational Safety and Health Act (OSHA) standards and training guidelines for various industries. The first section introduces the concept of voluntary training guidelines, explaining that the guidelines are designed to help employers determine whether a worksite problem can be solved by training, what training…

  11. Metrics design for safety assessment

    NARCIS (Netherlands)

    Luo, Yaping; van den Brand, M.G.J.

    2016-01-01

    Context:In the safety domain, safety assessment is used to show that safety-critical systems meet the required safety objectives. This process is also referred to as safety assurance and certification. During this procedure, safety standards are used as development guidelines to keep the risk at an

  12. TIBER II/ETR final design report: Volume 3, 5.0 Radiation safety and environment; 6.0 Physics and technology R and D needs

    International Nuclear Information System (INIS)

    Lee, J.D.

    1987-09-01

    This paper discusses the design of the TIBER II Tokamak. This particular volume discusses: safety and environmental requirements and design targets; accident analyses; personnel safety and maintenance exposure; effluent control; waste management and decommissioning; safety considerations in building design; and safety and environmental conclusions and recommendations

  13. Community Documentation Centre on Industrial Risk. Volume 3 (consolidated volume containing also content of vol. 1 and 2)

    International Nuclear Information System (INIS)

    1990-09-01

    The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

  14. Guidelines for safely changing to S.I. radiological units

    International Nuclear Information System (INIS)

    Canada is adopting the International System of Units (SI) in all sectors of the economy. The basic radiological units formerly in use, the curie, rad, rem, and roentgen are being replaced by the becquerel, gray, sievert, and coulomb per kilogram. During the transition period for conversion to SI units some problems may arise concerning received or administered radiation doses. These guidelines exaiine the occupational safety ramifications of of the change to SI by identifying the major safety concerns and providing guidelines for applying a model method within individual organizations for analyzing safety implicatikns during the changeover period

  15. Inventory of Federal energy-related environment and safety research for FY 1979. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    1980-12-01

    The FY 1979 Federal Inventory contains information on 3506 federally funded energy-related environmental and safety research projects. The Inventory is published in two volumes: Volume I, an executive summary and overview of the data and Volume II, project listings, summaries, and indexes. Research and development (R and D) categories were reorganized into three main areas; environmental and safety control technology, technology impacts overview and assessments, and biological and environmental R and D and assessments. Federal offices submitting project data were: Council on Environmental Quality; Department of Agriculture; Department of Commerce; Department of Defense; Department of Energy; Department of Health, Education, and Welfare; Department of Housing and Urban Development; Department of the Interior; Department of Transportation; Environmental Protection Agency; National Aeronautics and Space Administration; Nuclear Regulatory Commission; National Science Foundation; Office of Technology Assessment; and Tennessee Valley Authority. The inventory also breaks out research sponsored by various federal agencies and the amount of funding provided by each in various research categories. The format and index system allows efficient access to information compiled. Users are able to identify projects by log agency, performing organization, principal investigator and subject

  16. Development of human factors design review guidelines(II)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea)

    1998-06-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: 25. Human Factors Engineering Program Review Model and 26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation, which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994. (author). 11 refs., 2 figs., 2 tabs.

  17. Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 2. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Jenkins, C. E.; Murphy, E. S.; Schneider, K. J.

    1979-01-01

    Volume 2 contains appendixes on small MOX fuel fabrication facility description, site description, residual radionuclide inventory estimates, decommissioning, financing, radiation dose methodology, general considerations, packaging and shipping of radioactive materials, cost assessment, and safety (JRD)

  18. Reactor Safety Commission Code of Practice for Pressurized Water Reactors

    International Nuclear Information System (INIS)

    1990-01-01

    The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

  19. Evidence-based guidelines

    DEFF Research Database (Denmark)

    Wattjes, Mike P; Rovira, Àlex; Miller, David

    2015-01-01

    . This use of MRI can help predict treatment response and assess the efficacy and safety of new therapies. In the second part of the MAGNIMS (Magnetic Resonance Imaging in MS) network's guidelines on the use of MRI in MS, we focus on the implementation of this technique in prognostic and monitoring tasks. We...

  20. Space Biology and Medicine. Volume 4; Health, Performance, and Safety of Space Crews

    Science.gov (United States)

    Dietlein, Lawrence F. (Editor); Pestov, Igor D. (Editor)

    2004-01-01

    Volume IV is devoted to examining the medical and associated organizational measures used to maintain the health of space crews and to support their performance before, during, and after space flight. These measures, collectively known as the medical flight support system, are important contributors to the safety and success of space flight. The contributions of space hardware and the spacecraft environment to flight safety and mission success are covered in previous volumes of the Space Biology and Medicine series. In Volume IV, we address means of improving the reliability of people who are required to function in the unfamiliar environment of space flight as well as the importance of those who support the crew. Please note that the extensive collaboration between Russian and American teams for this volume of work resulted in a timeframe of publication longer than originally anticipated. Therefore, new research or insights may have emerged since the authors composed their chapters and references. This volume includes a list of authors' names and addresses should readers seek specifics on new information. At least three groups of factors act to perturb human physiological homeostasis during space flight. All have significant influence on health, psychological, and emotional status, tolerance, and work capacity. The first and most important of these factors is weightlessness, the most specific and radical change in the ambient environment; it causes a variety of functional and structural changes in human physiology. The second group of factors precludes the constraints associated with living in the sealed, confined environment of spacecraft. Although these factors are not unique to space flight, the limitations they entail in terms of an uncomfortable environment can diminish the well-being and performance of crewmembers in space. The third group of factors includes the occupational and social factors associated with the difficult, critical nature of the

  1. 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

  2. Guidelines for target volume definition in post-operative radiotherapy for prostate cancer, on behalf of the EORTC Radiation Oncology Group

    International Nuclear Information System (INIS)

    Poortmans, Philip; Bossi, Alberto; Vandeputte, Katia; Bosset, Mathieu; Miralbell, Raymond; Maingon, Philippe; Boehmer, Dirk; Budiharto, Tom; Symon, Zvi; Bergh, Alfons C.M. van den; Scrase, Christopher; Poppel, Hendrik van; Bolla, Michel

    2007-01-01

    The appropriate application of 3-D conformal radiotherapy, intensity modulated radiotherapy or image guided radiotherapy for patients undergoing post-operative radiotherapy for prostate cancer requires a standardisation of the target volume definition and delineation as well as standardisation of the clinical quality assurance procedures. Recommendations for this are presented on behalf of the European Organisation for Research and Treatment of Cancer (EORTC) Radiation Oncology Group and in addition to the already published guidelines for radiotherapy as the primary treatment

  3. International standardization of safety requirements for fast reactors

    International Nuclear Information System (INIS)

    2011-06-01

    Japan Atomic Energy Agency (JAEA) is conducting the FaCT (Fast Reactor Cycle Technology Development) project in cooperation with Japan Atomic Power Company (JAPC) and Mitsubishi FBR systems inc. (MFBR), where an advanced loop-type fast reactor named JSFR (Japan Sodium-cooled Fast Reactor) is being developed. It is important to develop software technologies (a safety guideline, safety design criteria, safety design standards etc.) of FBRs as well as hardware ones (a reactor plant itself) in order to address prospective worldwide utilization of FBR technology. Therefore, it is expected to establish a rational safety guideline applicable to the JSFR and harmonized with national nuclear-safety regulations as well, including Japan, the United States and the European Union. This report presents domestic and international status of safety guideline development for sodium-cooled fast reactors (SFRs), results of comparative study for safety requirements provided in existing documents and a proposal for safety requirements of future SFRs with a roadmap for their refinement and worldwide utilization. (author)

  4. Safety of MR liver specific contrast media

    Energy Technology Data Exchange (ETDEWEB)

    Bellin, Marie-France [Hopital Paul Brousse, Universite Paris 11, Villejuif Cedex (France); Webb, Judith A.W. [St. Bartholomew' s Hospital, Department of Diagnostic Imaging, London (United Kingdom); Molen, Aart J. van der [Leiden University Medical Centre, Department of Radiology, Leiden (Netherlands); Thomsen, Henrik S. [Copenhagen University Hospital at Herlev, Department of Diagnostic Radiology 54E2, Herlev (Denmark); Morcos, Sameh K. [Northern General Hospital, Sheffield Teaching Hospitals NHS Trust, Department of Diagnostic Imaging, Sheffield (United Kingdom)

    2005-08-01

    Over the past few years a number of magnetic resonance (MR) liver specific contrast agents have been introduced. In this report the safety issues of these agents are addressed. A literature search was carried out. Based on the available information, simple guidelines on the safety issue of liver specific contrast agents have been produced by the Contrast Media Safety Committee of the European Society of Urogenital Radiology. The report and guidelines were discussed at the 11th European Symposium on Urogenital Radiology in Santiago de Compostela. Liver specific contrast agents appear in general to be safe and well tolerated. However, the incidence of adverse reactions with iron oxides and the intravenous manganese based agent seems to be slightly higher than with gadolinium based agents. However, no safety information from comparative clinical trials has been published. Guidelines on the safety aspects are presented. (orig.)

  5. Safety of MR liver specific contrast media

    International Nuclear Information System (INIS)

    Bellin, Marie-France; Webb, Judith A.W.; Molen, Aart J. van der; Thomsen, Henrik S.; Morcos, Sameh K.

    2005-01-01

    Over the past few years a number of magnetic resonance (MR) liver specific contrast agents have been introduced. In this report the safety issues of these agents are addressed. A literature search was carried out. Based on the available information, simple guidelines on the safety issue of liver specific contrast agents have been produced by the Contrast Media Safety Committee of the European Society of Urogenital Radiology. The report and guidelines were discussed at the 11th European Symposium on Urogenital Radiology in Santiago de Compostela. Liver specific contrast agents appear in general to be safe and well tolerated. However, the incidence of adverse reactions with iron oxides and the intravenous manganese based agent seems to be slightly higher than with gadolinium based agents. However, no safety information from comparative clinical trials has been published. Guidelines on the safety aspects are presented. (orig.)

  6. Site Environmental Report for 2004. Volume 1, Environment, Health, and Safety Division

    Energy Technology Data Exchange (ETDEWEB)

    None

    2005-09-30

    Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2004 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2004. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I contains an overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from these activities. This year, the Site Environmental Report was distributed by releasing it on the Web from the Berkeley Lab Environmental Services Group (ESG) home page, which is located at http://www.lbl.gov/ehs/esg/. Many of the documents cited in this report also are accessible from the ESG Web page. CD and printed copies of this Site Environmental Report are available upon request.

  7. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1 of 2: Technical standard

    International Nuclear Information System (INIS)

    1998-05-01

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities

  8. Smaller self-inflating bags produce greater guideline consistent ventilation in simulated cardiopulmonary resuscitation.

    Science.gov (United States)

    Nehme, Ziad; Boyle, Malcolm J

    2009-02-20

    Suboptimal bag ventilation in cardiopulmonary resuscitation (CPR) has demonstrated detrimental physiological outcomes for cardiac arrest patients. In light of recent guideline changes for resuscitation, there is a need to identify the efficacy of bag ventilation by prehospital care providers. The objective of this study was to evaluate bag ventilation in relation to operator ability to achieve guideline consistent ventilation rate, tidal volume and minute volume when using two different capacity self-inflating bags in an undergraduate paramedic cohort. An experimental study using a mechanical lung model and a simulated adult cardiac arrest to assess the ventilation ability of third year Monash University undergraduate paramedic students. Participants were instructed to ventilate using 1600 ml and 1000 ml bags for a length of two minutes at the correct rate and tidal volume for a patient undergoing CPR with an advanced airway. Ventilation rate and tidal volume were recorded using an analogue scale with mean values calculated. Ethics approval was granted. Suboptimal ventilation with the use of conventional 1600 ml bag was common, with 77% and 97% of participants unable to achieve guideline consistent ventilation rates and tidal volumes respectively. Reduced levels of suboptimal ventilation arouse from the use of the smaller bag with a 27% reduction in suboptimal tidal volumes (p = 0.015) and 23% reduction in suboptimal minute volumes (p = 0.045). Smaller self-inflating bags reduce the incidence of suboptimal tidal volumes and minute volumes and produce greater guideline consistent results for cardiac arrest patients.

  9. ASSET guidelines. Revised 1991 Edition

    International Nuclear Information System (INIS)

    1991-12-01

    The present publication is an updated version of the IAEA Assessment of Safety Significant Events Team (ASSET) Guidelines, IAEA-TECDOC-573, published in 1990. Sections 5 and 6 include revised definitions and investigation guidelines for identification of both direct and root causes. These revisions were recommended by a Consultants Meeting held in Vienna on 3-7 December 1990. This guidance is not intended to infringe an expert's prerogative to investigate additional items. Its main purpose is to provide a basic structure and ensure consistency in the assessments. Use of the ASSET guidelines should also facilitate comparison between the observations made in different nuclear power plants and harmonize the reporting of generic ASSET results. The guidelines should always be used with a critical attitude and a view to possible improvements

  10. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

  11. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    International Nuclear Information System (INIS)

    1998-05-01

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist

  12. ECORA - Evaluation of Computational Methods for Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Scheuerer, Martina

    2002-01-01

    There were three motivations behind the ECORA Project: - the shortcomings of 0-D system codes in the simulation of 3-D, local flow and heat transfer phenomena, - increased interest in the application of 3-D CFD software as supplement to system codes, - high safety requirements in the nuclear industry required consistent standards for the use and assessment of CFD software. The purpose of ECORA was therefore: - to establish performance criteria for the assessment of CFD software, - to establish Best Practice Guidelines for application and use of CFD software, with the following objectives: - assessment of CFD applications in reactor safety: flows in containment (PANDA experiments) and flows in primary system (UPTF experiments) - Best Practice Guidelines for reactor safety: starting point (ERCOFTAC Best Practice Guidelines), adaptation to CFD application for nuclear safety, extension to assessment of experimental data - recommendations for improvements of CFD software, - network of European 'Centres of Competence for CFD Applications in Reactor Safety'. Currently, there were twelve partners in the ECORA Project, representing nine European countries. The Project was scheduled to last until September 2004. Ms Scheuerer then described the work programme and project structure, the Best Practice Guidelines for CFD simulations, the procedures for quantifying errors, applications of Best Practice Guidelines, Best Practice Guidelines for experimental data, applications to primary system, UPTF and PANDA data. Her conclusions were the following: - the Project had led to the improvement of the quality of CFD calculations in reactor safety, through: the ECORA Best Practice Guidelines, the assessment of shortcomings and the improvement of mathematical models. - It had also led to higher acceptance of CFD in reactor safety. - The next step was the establishment of European 'Centres of Competence for CFD Applications in reactor Safety'

  13. Practice guidelines for endoscopic ultrasound-guided celiac plexus neurolysis

    DEFF Research Database (Denmark)

    Wyse, Jonathan M; Battat, Robert; Sun, Siyu

    2017-01-01

    OBJECTIVES: The objective of guideline was to provide clear and relevant consensus statements to form a practical guideline for clinicians on the indications, optimal technique, safety and efficacy of endoscopic ultrasound guided celiac plexus neurolysis (EUS-CPN). METHODS: Six important clinical...

  14. Practice guidelines for endoscopic ultrasound-guided celiac plexus neurolysis

    NARCIS (Netherlands)

    Wyse, J.M. (Jonathan M.); Battat, R. (Robert); Sun, S. (Siyu); A. Saftoiu (Adrian); Siddiqui, A.A. (Ali A.); Leong, A.T. (Ang Tiing); Arias, B.L.A. (Brenda Lucia Arturo); Fabbri, C. (Carlo); Adler, D.G. (Douglas G.); Santo, E. (Erwin); Kalaitzakis, E. (Evangelos); Artifon, E. (Everson); Mishra, G. (Girish); Okasha, H.H. (Hussein Hassan); J.-W. Poley (Jan-Werner); Guo, J. (Jintao); Vila, J.J. (Juan J.); Lee, L.S. (Linda S.); Sharma, M. (Malay); Bhutani, M.S. (Manoop S.); M. Giovannini (Marcello); Kitano, M. (Masayuki); Eloubeidi, M.A. (Mohamad Ali); Khashab, M.A. (Mouen A.); Nguyen, N.Q. (Nam Q.); Saxena, P. (Payal); Vilmann, P. (Peter); Fusaroli, P. (Pietro); Garg, P.K. (Pramod Kumar); Ho, S. (Sammy); Mukai, S. (Shuntaro); Carrara, S. (Silvia); Sridhar, S. (Subbaramiah); S. Lakhtakia (S.); Rana, S.S. (Surinder S.); Dhir, V. (Vinay); Sahai, A.V. (Anand V.)

    2017-01-01

    textabstractObjectives: The objective of guideline was to provide clear and relevant consensus statements to form a practical guideline for clinicians on the indications, optimal technique, safety and efficacy of endoscopic ultrasound guided celiac plexus neurolysis (EUS-CPN). Methods: Six important

  15. Development of human factors design review guidelines(III)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1999-02-15

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994.

  16. Development of human factors design review guidelines(III)

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

    1999-02-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994

  17. Development of human factors design review guidelines(II)

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

    1998-06-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994

  18. Development of human factors design review guidelines(III)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1999-02-15

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994.

  19. Sandia software guidelines: Software quality planning

    Energy Technology Data Exchange (ETDEWEB)

    1987-08-01

    This volume is one in a series of Sandia Software Guidelines intended for use in producing quality software within Sandia National Laboratories. In consonance with the IEEE Standard for Software Quality Assurance Plans, this volume identifies procedures to follow in producing a Software Quality Assurance Plan for an organization or a project, and provides an example project SQA plan. 2 figs., 4 tabs.

  20. ESTRO consensus guideline on target volume delineation for elective radiation therapy of early stage breast cancer

    International Nuclear Information System (INIS)

    Offersen, Birgitte V.; Boersma, Liesbeth J.; Kirkove, Carine; Hol, Sandra; Aznar, Marianne C.; Biete Sola, Albert; Kirova, Youlia M.; Pignol, Jean-Philippe; Remouchamps, Vincent; Verhoeven, Karolien; Weltens, Caroline; Arenas, Meritxell; Gabrys, Dorota; Kopek, Neil; Krause, Mechthild; Lundstedt, Dan; Marinko, Tanja

    2015-01-01

    Background and purpose: Delineation of clinical target volumes (CTVs) is a weak link in radiation therapy (RT), and large inter-observer variation is seen in breast cancer patients. Several guidelines have been proposed, but most result in larger CTVs than based on conventional simulator-based RT. The aim was to develop a delineation guideline obtained by consensus between a broad European group of radiation oncologists. Material and methods: During ESTRO teaching courses on breast cancer, teachers sought consensus on delineation of CTV through dialogue based on cases. One teacher delineated CTV on CT scans of 2 patients, followed by discussion and adaptation of the delineation. The consensus established between teachers was sent to other teams working in the same field, both locally and on a national level, for their input. This was followed by developing a broad consensus based on discussions. Results: Borders of the CTV encompassing a 5 mm margin around the large veins, running through the regional lymph node levels were agreed, and for the breast/thoracic wall other vessels were pointed out to guide delineation, with comments on margins for patients with advanced breast cancer. Conclusion: The ESTRO consensus on CTV for elective RT of breast cancer, endorsed by a broad base of the radiation oncology community, is presented to improve consistency

  1. Guidelines for wireless technology in nuclear power plants

    International Nuclear Information System (INIS)

    Shankar, Ramesh

    2003-01-01

    As a result of technological breakthroughs, increased demand for the use of wireless technology is common in all industries today, and the electric power industry is no exception. Already, wireless technology has many applications in our industry, including - but not limited to - cellular phone systems, paging systems, two-way radio communication systems, dose management and tracking systems, and operator logs. EPRI has prepared a comprehensive guidelines document to support evaluation of wireless technologies in power plants for integrated (voice/data/video) communication, remote equipment and system monitoring, and to complement an electronic procedures support system (EPSS). The guidelines effort focuses on the development of a rules structure to support the deployment of wireless devices in a plant without compromising continuous, safe, and reliable operation. The guidelines document consists of two volumes. The first volume is introductory in nature and lays out the business case for applying wireless technologies. The intended audience is senior plant management personnel and utility industry executives. This volume contains background information, templates, worksheets, processes, and presentations that will allow internal sponsors to create business cases for piloting wireless projects. The second volume includes guidance on implementation and regulatory issues relevant to plant implementation. It covers the following application areas: implementation of integrated communication capability, equipment monitoring, work quality control, time and knowledge management, and business process automation. It details regulatory issues relevant to the adoption of wireless technology within nuclear power plants and offers guidance on preparing for and executing pilot and implementations of wireless technologies. The paper will cover important aspects on the guidelines. (author)

  2. Development application guidelines : Newfoundland offshore area

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    The Canada-Newfoundland Offshore Petroleum Board has created a set of guidelines which describe the information needed by the Board to process a development application by a proponent of an offshore hydrocarbon development project. The guidelines also describe the review process that will be followed in considering a proponent`s application. Proponents must also refer to the Canada-Newfoundland Atlantic Accord Implementation Act and the Canada-Newfoundland Atlantic Accord Implementation (Newfoundland) Act. These guidelines also describe the requirements for the Canada-Newfoundland benefits plan, the environmental impact statement, the socio-economic impact statement, the safety plan, and the environmental protection plan.

  3. Sector-specific issues and reporting methodologies supporting the General Guidelines for the voluntary reporting of greenhouse gases under Section 1605(b) of the Energy Policy Act of 1992. Volume 2: Part 4, Transportation sector; Part 5, Forestry sector; Part 6, Agricultural sector

    International Nuclear Information System (INIS)

    1994-10-01

    This volume, the second of two such volumes, contains sector-specific guidance in support of the General Guidelines for the voluntary reporting of greenhouse gas emissions and carbon sequestration. This voluntary reporting program was authorized by Congress in Section 1605(b) of the Energy Policy Act of 1992. The General Guidelines, bound separately from this volume, provide the overall rationale for the program, discuss in general how to analyze emissions and emission reduction/carbon sequestration projects, and address programmatic issues such as minimum reporting requirements, time parameters, international projects, confidentiality, and certification. Together, the General Guidelines and the guidance in these supporting documents will provide concepts and approaches needed to prepare the reporting forms. This second volume of sector-specific guidance covers the transportation sector, the forestry sector, and the agricultural sector

  4. Health protection guidelines for electromagnetic field exposures

    International Nuclear Information System (INIS)

    Taki, Masao

    1999-01-01

    In order to protect human health from excessive exposure to electromagnetic fields safety guidelines have been established by national and international organizations. The International Commission on Nonionization Radiation Protection is one of these organizations, whose guidelines are briefly regarded as typical. The activities on this issue in various countries are reviewed. Recent situations and the problems still unsolved are also discussed. (author)

  5. Smaller self-inflating bags produce greater guideline consistent ventilation in simulated cardiopulmonary resuscitation

    Directory of Open Access Journals (Sweden)

    Boyle Malcolm J

    2009-02-01

    Full Text Available Abstract Background Suboptimal bag ventilation in cardiopulmonary resuscitation (CPR has demonstrated detrimental physiological outcomes for cardiac arrest patients. In light of recent guideline changes for resuscitation, there is a need to identify the efficacy of bag ventilation by prehospital care providers. The objective of this study was to evaluate bag ventilation in relation to operator ability to achieve guideline consistent ventilation rate, tidal volume and minute volume when using two different capacity self-inflating bags in an undergraduate paramedic cohort. Methods An experimental study using a mechanical lung model and a simulated adult cardiac arrest to assess the ventilation ability of third year Monash University undergraduate paramedic students. Participants were instructed to ventilate using 1600 ml and 1000 ml bags for a length of two minutes at the correct rate and tidal volume for a patient undergoing CPR with an advanced airway. Ventilation rate and tidal volume were recorded using an analogue scale with mean values calculated. Ethics approval was granted. Results Suboptimal ventilation with the use of conventional 1600 ml bag was common, with 77% and 97% of participants unable to achieve guideline consistent ventilation rates and tidal volumes respectively. Reduced levels of suboptimal ventilation arouse from the use of the smaller bag with a 27% reduction in suboptimal tidal volumes (p = 0.015 and 23% reduction in suboptimal minute volumes (p = 0.045. Conclusion Smaller self-inflating bags reduce the incidence of suboptimal tidal volumes and minute volumes and produce greater guideline consistent results for cardiac arrest patients.

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

    International Nuclear Information System (INIS)

    1991-12-01

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

  7. Understanding standard drinks and drinking guidelines.

    Science.gov (United States)

    Kerr, William C; Stockwell, Tim

    2012-03-01

    For consumers to follow drinking guidelines and limit their risk of negative consequences they need to track their ethanol consumption. This paper reviews published research on the ability of consumers to utilise information about the alcohol content of beverages when expressed in different forms, for example in standard drinks or units versus percentage alcohol content. A review of the literature on standard drink definitions and consumer understanding of these, actual drink pouring, use of standard drinks in guidelines and consumer understanding and use of these. Standard drink definitions vary across countries and typically contain less alcohol than actual drinks. Drinkers have difficulty defining and pouring standard drinks with over-pouring being the norm such that intake volume is typically underestimated. Drinkers have difficulty using percentage alcohol by volume and pour size information in calculating intake but can effectively utilise standard drink labelling to track intake. Standard drink labelling is an effective but little used strategy for enabling drinkers to track their alcohol intake and potentially conform to safe or low-risk drinking guidelines. © 2011 Australasian Professional Society on Alcohol and other Drugs.

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

    International Nuclear Information System (INIS)

    1994-01-01

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

  9. Volumizing effects of a smooth, highly cohesive, viscous 20-mg/mL hyaluronic acid volumizing filler: prospective European study

    Directory of Open Access Journals (Sweden)

    Hoffmann Klaus

    2009-08-01

    Full Text Available Abstract Background Facial volume loss contributes significantly to facial aging. The 20-mg/mL hyaluronic acid (HA formulation used in this study is a smooth, highly cohesive, viscous, fully reversible, volumizing filler indicated to restore facial volume. This first prospective study evaluated use in current aesthetic clinical practice. Methods A pan-European evaluation conducted under guidelines of the World Association of Opinion and Marketing Research, the trial comprised a baseline visit (visit 1 and a follow-up (visit 2 at 14 ± 7 days posttreatment. Physicians photographed patients at each visit. Each patient was treated with the 20-mg/mL HA volumizing filler as supplied in standard packaging. Procedural details, aesthetic outcomes, safety, and physician and patient ratings of their experience were recorded. Results Fifteen physicians and 70 patients (91% female; mean age: 50 years participated. Mean volume loss at baseline was 3.7 (moderate on the Facial Volume Loss Scale. Local anesthesia was used in 64.3% of cases. Most injections (85% were administered with needles rather than cannulas. Of the 208 injections, 59% were in the malar region, primarily above the periosteum. Subcutaneous injections were most common for other sites. The mean total injection volume per patient was 4.6 mL. The mean volume loss score declined significantly (P Conclusion The 20-mg/mL smooth, highly cohesive, viscous, volumizing HA filler was effective, well tolerated, and easy to use in current clinical practice. Participants were very likely to recommend this product to colleagues and friends, and patients would be very or quite likely to request this product for future treatments.

  10. Report of the tunnel safety working group

    International Nuclear Information System (INIS)

    Gannon, J.

    1991-04-01

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

  11. Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

    International Nuclear Information System (INIS)

    Weiss, A.J.

    1988-02-01

    This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately

  12. Reinforced soil structures. Volume I, Design and construction guidelines

    Science.gov (United States)

    1990-11-01

    This report presents comprehensive guidelines for evaluating and using soil reinforcement techniques in the construction of retaining walls, embankment slopes, and natural or cut slopes. A variety of available systems for reinforced soil including in...

  13. Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1982-01-01

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

  14. Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

    Energy Technology Data Exchange (ETDEWEB)

    Koponen, B.L.; Hampel, V.E.

    1982-10-21

    This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41.

  15. Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

    International Nuclear Information System (INIS)

    Lucas, D.E.; Ikenberry, T.A.

    1994-03-01

    Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91 (DOE 1991). The DOE nuclear safety policy states that the general public be protected-such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL. A safety analyst uses the frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy

  16. 75 FR 73946 - Worker Safety and Health Program: Safety Conscious Work Environment

    Science.gov (United States)

    2010-11-30

    ... Environment AGENCY: Office of the General Counsel, Department of Energy (DOE). ACTION: Notice of denial of... Nuclear Regulatory Commission's ``Safety-Conscious Work Environment'' guidelines as a model. DOE published.... Second, not only would instituting a ``Safety-Conscious Work Environment'' by regulation be redundant...

  17. Guidelines for providing privileges and credentials to physicians for transvaginal placement of surgical mesh for pelvic organ prolapse.

    Science.gov (United States)

    2012-01-01

    The adoption of new technology or procedures into a clinician's surgical armamentarium is driven by multiple factors. Patient safety and anticipated long-term improvement in outcomes should be the primary objective that guides a surgeon's decision to deliver care involving new procedures. Surgically complex procedures require a balance of knowledge, surgical skill, and experience, with appropriate ongoing surgical volume and monitoring of outcomes and adverse events. Transvaginal placement of surgical mesh for pelvic organ prolapse has the potential to improve quality of life and anatomic outcomes (especially in the anterior compartment), but also has potential serious adverse events as outlined by the FDA's July 2011 Safety Communication. This document provides Guidelines for privileging and credentialing of physicians planning to implement or continue using this new technology in clinical practice.

  18. OPG waterways public safety program

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, T [Ontario Power Generation Inc., Niagara Falls, ON (Canada)

    2009-07-01

    Ontario Power Generation (OPG) has 64 hydroelectric generating stations, 241 dams, and 109 dams in Ontario's registry with the International Commission on Large Dams (ICOLD). In 1986, it launched a formal dam safety program. This presentation addressed the importance of public safety around dams. The safety measures are timely because of increasing public interaction around dams; the public's unawareness of hazards; public interest in extreme sports; easier access by recreational vehicles; the perceived right of public to access sites; and the remote operation of hydroelectric stations. The presentation outlined the OPG managed system approach, with particular reference to governance; principles; standards and procedures; and aspects of implementation. Specific guidelines and governing documents for public safety around dams were identified, including guidelines for public safety of waterways; booms and buoys; audible warning devices and lights; public safety signage; fencing and barricades; and risk assessment for public safety around waterways. The presentation concluded with a discussion of audits and management reviews to determine if safety objectives and targets have been met. figs.

  19. Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume I

    International Nuclear Information System (INIS)

    2000-12-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance, design or manufacturing error) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This publication is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canadian deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including the Soviet designed 'water moderated and water cooled energy reactors' (WWERs), are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed at technical experts and managers from NPPs and from regulatory, plant design, manufacturing

  20. Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume II

    International Nuclear Information System (INIS)

    2000-12-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance, design or manufacturing error) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This publication is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canadian deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including the Soviet designed 'water moderated and water cooled energy reactors' (WWERs), are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed at technical experts and managers from NPPs and from regulatory, plant design, manufacturing

  1. Heat exchanger performance monitoring guidelines

    International Nuclear Information System (INIS)

    Stambaugh, N.; Closser, W. Jr.; Mollerus, F.J.

    1991-12-01

    Fouling can occur in many heat exchanger applications in a way that impedes heat transfer and fluid flow and reduces the heat transfer or performance capability of the heat exchanger. Fouling may be significant for heat exchanger surfaces and flow paths in contact with plant service water. This report presents guidelines for performance monitoring of heat exchangers subject to fouling. Guidelines include selection of heat exchangers to monitor based on system function, safety function and system configuration. Five monitoring methods are discussed: the heat transfer, temperature monitoring, temperature effectiveness, delta P and periodic maintenance methods. Guidelines are included for selecting the appropriate monitoring methods and for implementing the selected methods. The report also includes a bibliography, example calculations, and technical notes applicable to the heat transfer method

  2. Management response plan for the Chemical Safety Vulnerability Working Group report. Volume 1

    International Nuclear Information System (INIS)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 146 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains a discussion of the chemical safety improvements planned or already underway at DOE sites to correct facility or site-specific vulnerabilities. The main part of the report is a discussion of each of the programmatic deficiencies; a description of the tasks to be accomplished; the specific actions to be taken; and the organizational responsibilities for implementation

  3. The healing arts radiation protection guidelines

    International Nuclear Information System (INIS)

    Yaffe, M.

    1987-06-01

    The objective of these guidelines is to help the health professional render the risks associated with diagnostic radiation as low as reasonably achievable. The guidelines contain advice and recommendations, but no mandatory requirements. They assist radiation protection officers in establishing and maintaining a Quality Assurance Program and in carrying out other duties required by the Healing Arts Radiation Protection Act; assist staff to comply with the X-ray Safety Code in a way that will raise the standards of x-ray diagnosis and patient safety; address the relationship between the radiation exposure of the patient and the quality of the image; address the problem of protecting the patient in x-ray examinations; summarize x-ray safety problems from the point of view of the operator and other staff; indicate what remedial measures can be taken; define the quality assurance needs of x-ray users; and encourage the users of x-rays for diagnostic purposes to go beyond the scope of the Act and comply with the ALARA principle

  4. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-01-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This first volume is divided into 3 sections: plenary session; high burnup fuel; and containment and structural aging. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  5. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1997-01-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This first volume is divided into 3 sections: plenary session; high burnup fuel; and containment and structural aging. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  6. Guidelines for authorities and operators from the EURATOM regulation according to nuclear safety

    International Nuclear Information System (INIS)

    Karpenstein, Ulrich

    2010-01-01

    At 22nd July, 2009 the guideline 2009/71/EURATOM on a community framework for the nuclear security of nuclear installations comes into effect. A lot of regulations of this guideline intervene very deeply in the competencies of the member states. In acknowledgment of the national responsibility for nuclear security, the guideline grants large free space to the member states. Thereby, the guideline aims at a general legal framework and a mutual learning process off.

  7. Impact of Minimum Driveway Spacing Policies on Safety Performance: An Integrated Traffic Micro-Simulation and Automated Conflict Analysis

    Directory of Open Access Journals (Sweden)

    Chu C. Minh

    2014-09-01

    Full Text Available A key strategy for successful access management is the adoption of driveway spacing guidelines that consider both safety and operations. The goal is to provide sufficient distance from one driveway to the next so that drivers can perceive and react to the conditions at each potential conflict point in succession. State DOTs across the country have adopted different driveway spacing standards that vary according to the access class and characteristics of the adjacent roadway, such as type of roadway, posted speed limit, and traffic volume. Utilizing the VISSIM microscopic traffic simulation tool and FHWA's Surrogate Safety Assessment Model (SSAM, this research examined safety implications of four different driveway spacing policies representing 13 states. The analysis involved calibrating the VISSIM model for an arterial roadway corridor in West Columbia, SC, and then using the calibrated model to simulate various operational changes to the corridor, including speed limits, traffic volumes, and the associated minimum driveway spacing criteria for the four different policies. SSAM was used to analyze vehicle trajectories derived from VISSIM to determine the number of conflict points. Experimental results indicate that posted speed limit and traffic volume are the primary impact factors for driveway safety, and thus, these parameters should be considered in establishing minimum driveway spacing. Findings from this study indicate that there are significant differences in safety impacts between the different driveway spacing policies adopted by various state DOTs.

  8. Space Guidelines for Libraries.

    Science.gov (United States)

    Wisconsin Coordinating Committee for Higher Education, Madison.

    The following guidelines are recommended: stack space--for each 10 volumes, one square foot of space; reading room--25 square feet per station x 20% of the total undergraduate population; carrel space--25% of the graduate enrollment x 45 square feet; office and auxilliary space--135 square feet x full time equivalent staff. (NI)

  9. Human Factors Engineering Guidelines for Overhead Cranes

    Science.gov (United States)

    Chandler, Faith; Delgado, H. (Technical Monitor)

    2001-01-01

    This guideline provides standards for overhead crane cabs that can be applied to the design and modification of crane cabs to reduce the potential for human error due to design. This guideline serves as an aid during the development of a specification for purchases of cranes or for an engineering support request for crane design modification. It aids human factors engineers in evaluating existing cranes during accident investigations or safety reviews.

  10. Public announcement of guidelines for the packing and safe stowing of cargo in freight containers and vehicles for ocean transport (Container Stowage Guidelines)

    International Nuclear Information System (INIS)

    1987-01-01

    The IMO and ILO guidelines are given, which help to meet the requirements of the Maritime Safety Ordinance and the Ordinance on Ocean Transport of Dangerous Goods. The guidelines explain the principles of safe packing and stowing of cargo in freight containers and vehicles for ocean transports. Further information and practical hints are given in international publications referred to in the annex. The guidelines are also meant for training purposes. (orig./HSCH) [de

  11. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

    International Nuclear Information System (INIS)

    1980-06-01

    This volume of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power - generating capability and one without

  12. Reliability Based Calibration of Fatigue Design Guidelines for Ship Structures

    DEFF Research Database (Denmark)

    Folsø, Rasmus; Otto, S.; Parmentier, G.

    2002-01-01

    A simple reliability based framework is applied to calibrate a new set of fatigue design guidelines. This new guideline considers two different approaches for the assessment of both loads, stresses and local stress raising effects, and partial safety factors must be given for any combination...

  13. Guidelines for the design and operation of makeup water treatment systems

    International Nuclear Information System (INIS)

    Lee, Y.H.; Planek, M.A.; Sopocy, D.M.; Tomaga, C.M.; Abrams, I.M.; Anderson, C.C.; Balazs, M.K.; Houskava, J.; Williams, R.

    1989-06-01

    These guidelines present the industry with a standardized program to ensure the optimum design and operation of their individual makeup water treatment systems. These guidelines present, in a non-technical and non-proprietary format, the makeup water treatment system design and operating topics that are discussed in detail in Volumes 1 and 2 of NP-6377-SL. The individual guidelines contained in Volumes 1 and 2 are presented as separate imperative statements, followed by a technical justification discussion, which provides further explanations. In addition and when applicable, the guidelines relate pertinent operational in regard to monitoring parameters for operation, alternative actions, troubleshooting, management responsibilities and shutdown practices. Design considerations are also addressed, when applicable, in regard to equipment cost and advantages and disadvantages for the design recommendations. Appendices provide background information for performance criteria, component description, economic evaluation procedures and definitions. 4 refs

  14. Sodium fast reactor safety and licensing research plan - Volume II

    International Nuclear Information System (INIS)

    Ludewig, H.; Powers, D.A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A.; Phillips, J.; Zeyen, R.; Clement, B.; Garner, Frank; Walters, Leon; Wright, Steve; Ott, Larry J.; Suo-Anttila, Ahti Jorma; Denning, Richard; Ohshima, Hiroyuki; Ohno, S.; Miyhara, S.; Yacout, Abdellatif; Farmer, M.; Wade, D.; Grandy, C.; Schmidt, R.; Cahalen, J.; Olivier, Tara Jean; Budnitz, R.; Tobita, Yoshiharu; Serre, Frederic; Natesan, Ken; Carbajo, Juan J.; Jeong, Hae-Yong; Wigeland, Roald; Corradini, Michael; Thomas, Justin; Wei, Tom; Sofu, Tanju; Flanagan, George F.; Bari, R.; Porter D.

    2012-01-01

    Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

  15. Sodium fast reactor safety and licensing research plan. Volume II.

    Energy Technology Data Exchange (ETDEWEB)

    Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

    2012-05-01

    Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

  16. The potential carcinogenic risk of tanning beds: clinical guidelines and patient safety advice

    International Nuclear Information System (INIS)

    Mogensen, Mette; Jemec, Gregor BE

    2010-01-01

    In 2009, the WHO listed ultraviolet (UV) radiation as a group 1 carcinogen. In spite of this, each year, millions of people tan indoor in Western countries. The aim of this review is to summarize evidence of tanning bed carcinogenesis and to present guidelines for use of tanning beds and patient safety advice. A narrative review of the literature was conducted based on both PubMed and Medline searches and on literature review of the retrieved papers. Use of indoor tanning beds represents a significant and avoidable risk factor for the development of both melanoma and nonmelanoma skin cancers. Frequent tanners are more often adolescent females. Tanning beds have additional potential adverse effects such as burns, solar skin damage, infection, and possibly also addictive behavior. The effort in preventing UV light-induced carcinogenesis should currently be aimed at developing new strategies for public health information. Tanning beds are one preventable source of UV radiation. In the majority of people solar UV radiation continues to be the major factor and therefore anti-tanning campaigns must always include sunbathers

  17. 40 CFR 243.201 - Safety.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Safety. 243.201 Section 243.201 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES GUIDELINES FOR THE STORAGE... Procedures § 243.201 Safety. ...

  18. Guidelines for testing sealed radiation sources

    International Nuclear Information System (INIS)

    1989-01-01

    These guidelines are based on article 16(1) of the Ordinance on the Implementation of Atomic Safety and Radiation Protection dated 11 October 1984 (VOAS), in connection with article 36 of the Executory Provision to the VOAS, of 11 October 1984. They apply to the testing of sealed sources to verify their intactness, tightness and non-contamination as well as observance of their fixed service time. The type, scope and intervals of testing as well as the evaluation of test results are determined. These guidelines also apply to the testing of radiation sources forming part of radiation equipment, unless otherwise provided for in the type license or permit. These guidelines enter into force on 1 January 1990

  19. Road safety audits: The way forward

    CSIR Research Space (South Africa)

    Labuschagne, FJJ

    2010-08-01

    Full Text Available The South African Road Safety Manual (SARSM) was published in 1999 and includes guidelines on road safety audits (RSA). The development of SARSM was a proactive process for improving the road environment with respect to road safety but was never...

  20. Commentary on guidelines for radiation measurement and treatment of substances including naturally occurring radioactive materials

    International Nuclear Information System (INIS)

    Sakurai, Naoyuki; Ishiguro, Hideharu

    2007-01-01

    Study group on safety regulation on research reactors in Ministry of Education, Culture, Sports, Science and Technology (MEXT) reported the guidelines of 'Guidelines on radiation measurement and treatment of naturally occurring radioactive materials (NORM)' on 6 February 2006. RANDEC made the website contents 'Study on use and safety of the substances including uranium or thorium', based on the contract with MEXT to make theirs contents. This paper describes the outline of the website in MEXT homepage, background and contents of NORM guidelines in order to understand easily and visually the NORM guidelines, adding in some flowcharts and figures. (author)

  1. [Clinical application evaluation of Guidelines for Diagnosis and Treatment of Internal Diseases in Traditional Chinese Medicine].

    Science.gov (United States)

    Han, Xue-Jie; Liu, Meng-Yu; Lian, Zhi-Hua; Wang, Li-Ying; Shi, Nan-Nan; Zhao, Jun

    2017-09-01

    To evaluate the applicability and clinical applications of Guidelines for Diagnosis and Treatment of Internal Diseases in Traditional Chinese Medicine, so as to provide the basis for the revision of the guidelines. This study was completed by the research and promotion base for traditional Chinese medicine(TCM) standard. The methods of applicability evaluation and application evaluation were used in the study. The questionnaires were filled out to evaluate applicability of the guideline, including doctor's familiarity with the guideline,the quality of the guideline, applicable conditions and clinical applications. The prospective case study analysis method was used to evaluate application of the guideline, including evaluation of clinical application compliance and application results(such as clinical effects, safety and economy). There were two parts in the guideline, which were TCM guideline and Western medicine guideline. The results of applicability evaluation showed that there were no obvious differences between TCM guideline and Western medicine guideline in doctor's familiarity with guideline(85.43%, 84.57%) and the use of the guideline(52.10%, 54.47%); the guidelines with good quality, and higher scores in the scope of application and the use of the term rationality(91.94%, 93.35%); the rationality scores of relevant contents in syndrome differentiation and treatment were more than 75%; the applicable conditions were better, and the safety score was the the highest. The comprehensive applicability evaluation showed that the proportion of the application of TCM guideline and Western medicine guideline were 77.73%, 75.46%, respectively. The results of application evaluation showed that there was high degree coincidence between the guideline with its clinical application; except for "other treatment" and "recuperation and prevention" in TCM, other items got high scores which were more than 90%; in the evaluation of application effects, safety of the guideline

  2. Radiation safety program in high dose rate brachytherapy facility at INHS Asvini

    Directory of Open Access Journals (Sweden)

    Kirti Tyagi

    2014-01-01

    Full Text Available Brachytherapy concerns primarily the use of radioactive sealed sources which are inserted into catheters or applicators and placed directly into tissue either inside or very close to the target volume. The use of radiation in treatment of patients involves both benefits and risks. It has been reported that early radiation workers had developed radiation induced cancers. These incidents lead to continuous work for the improvement of radiation safety of patients and personnel The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. The widespread adoption of high dose rate brachytherapy needs appropriate quality assurance measures to minimize the risks to both patients and medical staff. The radiation safety program covers five major aspects: quality control, quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. This paper will discuss the radiation safety program developedfor a high dose rate brachytherapy facility at our centre which may serve as a guideline for other centres intending to install a similar facility.

  3. Implementing a pediatric obesity care guideline in a freestanding children's hospital to improve child safety and hospital preparedness.

    Science.gov (United States)

    Porter, Renee M; Thrasher, Jodi; Krebs, Nancy F

    2012-12-01

    Medical and surgical care of children with severe obesity is complicated and requires recognition of the problem, appropriate equipment, and safe management. There is little literature describing patient, provider, and institutional needs for the severely obese pediatric patient. Nonetheless, the limited data suggest 3 broad categories of needs unique to this population: (a) airway management, (b) drug dosing and pharmacology, and (c) equipment and infrastructure. We describe an opportunity at the Children's Hospital Colorado to better prepare and optimize care for this patient population by creation of a Pediatric Obesity Care Guideline that focused on key areas of quality and safety. Copyright © 2012 Elsevier Inc. All rights reserved.

  4. Safety classification of items in Tianwan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sun Yongbin

    2005-01-01

    The principle of integrality, moderation and equilibrium should be considered in the safety classification of items in nuclear power plant. The basic ways for safety classification of items is to classify the safety function based on the effect of the outside enclosure damage of the items (parts) on the safety. Tianwan Nuclear Power Plant adopts Russian VVER-1000/428 type reactor, it safety classification mainly refers to Russian Guidelines and standards. The safety classification of the electric equipment refers to IEEE-308(80) standard, including 1E and Non 1E classification. The safety classification of the instrumentation and control equipment refers to GB/T 15474-1995 standard, including safety 1E, safety-related SR and NC non-safety classification. The safety classification of Tianwan Nuclear Power Plant has to be approved by NNSA and satisfy Chinese Nuclear Safety Guidelines. (authors)

  5. Nuclear safety management at the Wolsong NGS

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-01

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

  6. Nuclear safety management at the Wolsong NGS

    International Nuclear Information System (INIS)

    Han Bong-Seob

    1997-01-01

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

  7. Design data and safety features of commercial nuclear power plants including cumulative index for Volumes I--VI

    International Nuclear Information System (INIS)

    Heddleson, F.A.

    1977-01-01

    Design data, safety features, and site characteristics are summarized for 12 nuclear power units in 6 power stations in the United States. Six pages of data are presented for each station, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. In addition, an aerial perspective is presented for each plant. This volume covers plants with docket numbers 50-553 through 50-569 (Phipps Bend, Black Fox, Yellow Creek, and NEP) and two earlier plants not previously reported--Hope Creek (50-354, 50-355) and WPPSS 1 and 4 (50-460, 50-513). Indexes for this volume and the five earlier volumes are presented in three forms--by docket number, by plant name, and by participating utility

  8. Programming Guidelines for FBD Programs in Reactor Protection System Software

    International Nuclear Information System (INIS)

    Jung, Se Jin; Lee, Dong Ah; Kim, Eui Sub; Yoo, Jun Beom; Lee, Jang Su

    2014-01-01

    Properties of programming languages, such as reliability, traceability, etc., play important roles in software development to improve safety. Several researches are proposed guidelines about programming to increase the dependability of software which is developed for safety critical systems. Misra-c is a widely accepted programming guidelines for the C language especially in the sector of vehicle industry. NUREG/CR-6463 helps engineers in nuclear industry develop software in nuclear power plant systems more dependably. FBD (Function Block Diagram), which is one of programming languages defined in IEC 61131-3 standard, is often used for software development of PLC (programmable logic controllers) in nuclear power plants. Software development for critical systems using FBD needs strict guidelines, because FBD is a general language and has easily mistakable elements. There are researches about guidelines for IEC 61131-3 programming languages. They, however, do not specify details about how to use languages. This paper proposes new guidelines for the FBD based on NUREG/CR-6463. The paper introduces a CASE (Computer-Aided Software Engineering) tool to check FBD programs with the new guidelines and shows availability with a case study using a FBD program in a reactor protection system. The paper is organized as follows

  9. Programming Guidelines for FBD Programs in Reactor Protection System Software

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Se Jin; Lee, Dong Ah; Kim, Eui Sub; Yoo, Jun Beom [Division of Computer Science and Engineering College of Information and Communication, Konkuk University, Seoul (Korea, Republic of); Lee, Jang Su [Man-Machine Interface System team Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    Properties of programming languages, such as reliability, traceability, etc., play important roles in software development to improve safety. Several researches are proposed guidelines about programming to increase the dependability of software which is developed for safety critical systems. Misra-c is a widely accepted programming guidelines for the C language especially in the sector of vehicle industry. NUREG/CR-6463 helps engineers in nuclear industry develop software in nuclear power plant systems more dependably. FBD (Function Block Diagram), which is one of programming languages defined in IEC 61131-3 standard, is often used for software development of PLC (programmable logic controllers) in nuclear power plants. Software development for critical systems using FBD needs strict guidelines, because FBD is a general language and has easily mistakable elements. There are researches about guidelines for IEC 61131-3 programming languages. They, however, do not specify details about how to use languages. This paper proposes new guidelines for the FBD based on NUREG/CR-6463. The paper introduces a CASE (Computer-Aided Software Engineering) tool to check FBD programs with the new guidelines and shows availability with a case study using a FBD program in a reactor protection system. The paper is organized as follows.

  10. Sensitivity and uncertainty analyses applied to criticality safety validation, methods development. Volume 1

    International Nuclear Information System (INIS)

    Broadhead, B.L.; Hopper, C.M.; Childs, R.L.; Parks, C.V.

    1999-01-01

    This report presents the application of sensitivity and uncertainty (S/U) analysis methodologies to the code/data validation tasks of a criticality safety computational study. Sensitivity and uncertainty analysis methods were first developed for application to fast reactor studies in the 1970s. This work has revitalized and updated the available S/U computational capabilities such that they can be used as prototypic modules of the SCALE code system, which contains criticality analysis tools currently used by criticality safety practitioners. After complete development, simplified tools are expected to be released for general use. The S/U methods that are presented in this volume are designed to provide a formal means of establishing the range (or area) of applicability for criticality safety data validation studies. The development of parameters that are analogous to the standard trending parameters forms the key to the technique. These parameters are the D parameters, which represent the differences by group of sensitivity profiles, and the ck parameters, which are the correlation coefficients for the calculational uncertainties between systems; each set of parameters gives information relative to the similarity between pairs of selected systems, e.g., a critical experiment and a specific real-world system (the application)

  11. The effect of terrain slope on firefighter safety zone effectiveness

    Science.gov (United States)

    Bret Butler; J. Forthofer; K. Shannon; D. Jimenez; D. Frankman

    2010-01-01

    The current safety zone guidelines used in the US were developed based on the assumption that the fire and safety zone were located on flat terrain. The minimum safe distance for a firefighter to be from a flame was calculated as that corresponding to a radiant incident energy flux level of 7.0kW-m-2. Current firefighter safety guidelines are based on the assumption...

  12. Comparison of the diabetes guidelines from the ADA/EASD and the AACE/ACE.

    Science.gov (United States)

    Cornell, Susan

    To compare recent diabetes guideline updates from the American Diabetes Association-European Association for the Study of Diabetes (ADA/EASD) and the American Association of Clinical Endocrinologists-American College of Endocrinology (AACE/ACE). The ADA/EASD guideline continues to advocate a stepwise approach to glycemic control that initiates with metformin and intensifies treatment incrementally to dual and triple therapy at 3-month intervals until the patient is at their individualized goal. The AACE/ACE guideline provides a broader choice of first-line medications, with a suggested hierarchy of use, and it encourages initial dual and triple therapy if the glycated hemoglobin (A1C) level is high enough at diagnosis (7.5%-9.0% and >9.0%, respectively). Target A1C levels are higher in the ADA/EASD guideline (≤7.0%) compared with the AACE/ACE guideline (≤6.5%), although both statements indicate that targets should be adjusted to specific clinical scenarios based on safety. Both guidelines now include the new sodium-glucose cotransporter-2 inhibitors among their choices of acceptable glucose-lowering medications and endorse the overall cardiovascular and pancreatic safety of incretin therapies, and the safety of pioglitazone vis-a-vis bladder cancer. In practice, the ADA/EASD guidelines tend to be more user-friendly for general practitioners because of the simple stepwise intensification regimen, whereas the AACE/ACE guidelines are more commonly followed by specialists (endocrinologists) because of the more aggressive A1C targets. Copyright © 2017 American Pharmacists Association®. Published by Elsevier Inc. All rights reserved.

  13. JANNAF 28th Propellant Development and Characterization Subcommittee and 17th Safety and Environmental Protection Subcommittee Joint Meeting. Volume 1

    Science.gov (United States)

    Cocchiaro, James E. (Editor); Mulder, Edwin J. (Editor); Gomez-Knight, Sylvia J. (Editor)

    1999-01-01

    This volume contains 37 unclassified/unlimited-distribution technical papers that were presented at the JANNAF 28th Propellant Development & Characterization Subcommittee (PDCS) and 17th Safety & Environmental Protection Subcommittee (S&EPS) Joint Meeting, held 26-30 April 1999 at the Town & Country Hotel and the Naval Submarine Base, San Diego, California. Volume II contains 29 unclassified/limited-distribution papers that were presented at the 28th PDCS and 17th S&EPS Joint Meeting. Volume III contains a classified paper that was presented at the 28th PDCS Meeting on 27 April 1999. Topics covered in PDCS sessions include: solid propellant rheology; solid propellant surveillance and aging; propellant process engineering; new solid propellant ingredients and formulation development; reduced toxicity liquid propellants; characterization of hypergolic propellants; and solid propellant chemical analysis methods. Topics covered in S&EPS sessions include: space launch range safety; liquid propellant hazards; vapor detection methods for toxic propellant vapors and other hazardous gases; toxicity of propellants, ingredients, and propellant combustion products; personal protective equipment for toxic liquid propellants; and demilitarization/treatment of energetic material wastes.

  14. Prefabricated vertical drains, vol. I : engineering guidelines.

    Science.gov (United States)

    1986-09-01

    This volume presents procedures and guidelines applicable to the design and instal : tion of prefabricated vertical drains to accelerate consolidation of soils. The : contents represent the Consultant's interpretation of the state-of-the-art as of : ...

  15. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

    International Nuclear Information System (INIS)

    1979-12-01

    Volume 6 of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power-generating capability and one without. This volume also provides estimates of the time required for development of large-scale commercial reactor systems to reach the construction permit application stage and for fuel-cycle facilities to reach the operating license application stage, which is a measure of the relative technical status of alternative nuclear systems

  16. NASA Aerospace Flight Battery Program: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries. Volume 2, Part 3; Appendices

    Science.gov (United States)

    Jung, David S,; Lee, Leonine S.; Manzo, Michelle A.

    2010-01-01

    This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 3 - Volume II Appendices to Part 3 - Volume I.

  17. The System 80+ Standard Plant design control document. Volume 24

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains sections 7--11 of the ADM Emergency Operations Guidelines. Topics covered are: excess steam demand recovery; loss of all feedwater; loss of offsite power; station blackout recovery; and functional recovery guideline. Appendix A Severe Accident Management Guidelines and Appendix B Lower Mode Operational Guidelines are also included

  18. Critical safety function guidelines for experimental fusion facilities

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1989-01-01

    As fusion experiments proceed toward deuterium-tritium operation, more attention is being given to public safety. This paper presents the four classes of functions that fusion experiments must provide to assure safe, stable shutdown and retention of radionuclides. These functions are referred to as critical safety functions (CSFs). Selecting CSFs is an important step in probabilistic risk assessment (PRA). An example of CSF selection and usage for the Compact Ignition Tokamak (CIT) is also presented

  19. UMTRA Project environmental, health, and safety plan

    International Nuclear Information System (INIS)

    1989-02-01

    The basic health and safety requirements established in this plan are designed to provide guidelines to be applied at all Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Specific restrictions are given where necessary. However, an attempt has been made to provide guidelines which are generic in nature, and will allow for evaluation of site-specific conditions. Health and safety personnel are expected to exercise professional judgment when interpreting these guidelines to ensure the health and safety of project personnel and the general population. This UMTRA Project Environmental, Health, and Safety (EH ampersand S) Plan specifies the basic Federal health and safety standards and special DOE requirements applicable to this program. In addition, responsibilities in carrying out this plan are delineated. Some guidance on program requirements and radiation control and monitoring is also included. An Environmental, Health, and Safety Plan shall be developed as part of the remedial action plan for each mill site and associated disposal site. Special conditions at the site which may present potential health hazards will be described, and special areas that should should be addressed by the Remedial Action Contractor (RAC) will be indicated. Site-specific EH ampersand S concerns will be addressed by special contract conditions in RAC subcontracts. 2 tabs

  20. Guidelines for the verification and validation of expert system software and conventional software. Volume 7, User's manual: Final report

    International Nuclear Information System (INIS)

    Miller, L.A.; Hayes, J.E.; Mirsky, S.M.

    1995-05-01

    Reliable software is required for nuclear power industry applications. Verification and validation techniques applied during the software development process can help eliminate errors that could inhibit the proper operation of digital systems and cause availability and safety problems. Most of the techniques described in this report are valid for conventional software systems as well as for expert systems. The project resulted in a set of 16 V ampersand V guideline packages and 11 sets of procedures based on the class, development phase, and system component being tested. These guideline packages and procedures help a utility define the level of V ampersand V, which involves evaluating the complexity and type of software component along with the consequences of failure. In all, the project identified 153 V ampersand V techniques for conventional software systems and demonstrated their application to all aspects of expert systems except for the knowledge base, which requires specially developed tools. Each of these conventional techniques covers anywhere from 2-52 total types of conventional software defects, and each defect is covered by 21-50 V ampersand V techniques. The project also identified automated tools to Support V ampersand V activities

  1. ITS logical architecture : volume 3, data dictionary.

    Science.gov (United States)

    1981-01-01

    The objective of the research effort was to develop an empirically and experiencially based model pedestrian safety program which cities can use as guidelines for pedestrian safety program planning, implementation, and evaluation. The basis of these ...

  2. PROSPER guidelines: Guidelines for peer review and for plant self-assessment of operational experience feedback process

    International Nuclear Information System (INIS)

    2003-01-01

    Effective use of operational performance information is an important element in any plant operator's arrangements for enhancing the operational safety of a nuclear power plant (NPP). This has been recognized in the IAEA Safety Fundamental, The Safety of Nuclear Installations (Safety Series No. 110). Under the technical aspects of safety, one of the principles of operation and maintenance is that the operating organization and the regulatory body shall establish complementary programmes to analyse operating experience to ensure that lessons are learned and acted upon. Such experience shall be shared with relevant national and international bodies. The Convention on Nuclear Safety, which entered into force in July 1996, also recognized the importance of operational experience feedback as a tool of high importance for the safety of nuclear plant operation and its further enhancement. It follows that the arrangements and results achieved under the operation experience feedback process in Member States will be covered by the national report under the Convention and will be subject to periodical review. These principles are further expanded in the IAEA Safety Standards Safety of Nuclear Power Plants: Operation (Safety Standard Series No. NS-R-2, year 2000) under the Feedback of The IAEA-led Peer Review of the effectiveness of the Operational Safety Performance Experience Review process (PROSPER) and associated guidelines have been developed to provide advice and assistance to utilities or individual power plants to strengthen and enhance the effectiveness of operational experience programmes in achieving these fundamental objectives. The objectives of the former IAEA Assessment of Significant Safety Events Team (ASSET) service have been expanded to include an evaluation of the effective use of all operating performance information available to the plant (e.g. external operating experience, internal low-level and near miss event reports and other relevant operating

  3. [Guidelines for wise utilization of knee imaging].

    Science.gov (United States)

    Finestone, Aharon S; Eshed, Iris; Freedman, Yehuda; Beer, Yiftah; Bar-Sever, Zvi; Kots, Yavvgeni; Adar, Eliyahu; Mann, Gideon

    2012-02-01

    The knee is a complex structure afflicted with diverse pathologies. Correct management of knee complaints demands wise utilization of imaging modalities, considering their accuracy in the specific clinical situation, the patient's safety and availability and financial issues. Some of these considerations are universal, while others are local, depending on medical and insurance systems. There is controversy and unclearness regarding the best imaging modality in different clinical situations. To develop clinical guidelines for utilizing knee imaging. Leading physicians in specialties associated with knee disease and imaging were invited to participate in a panel on the guidelines. Controversies were settled in the main panel or in sub-panels. The panel agreed on the principles in choosing from the various modalities, primarily medical accuracy, followed by patient safety, availability and cost. There was agreement that the physician is responsible to choose the most appropriate diagnostic tool, consulting, when necessary, on the advantages, limitations and risks of the various imaging modalities. A comprehensive table was compiled with the importance of the different imaging modalities in various clinical situations. For the first time, Israeli guidelines on wise utilization of knee imaging are presented. They take into consideration the clinical situations and also availability and financial issues specific to Israel. These guidelines will serve physicians of several disciplines and medical insurers to improve patient management efficiently.

  4. System safety engineering analysis handbook

    Science.gov (United States)

    Ijams, T. E.

    1972-01-01

    The basic requirements and guidelines for the preparation of System Safety Engineering Analysis are presented. The philosophy of System Safety and the various analytic methods available to the engineering profession are discussed. A text-book description of each of the methods is included.

  5. 40 CFR 240.209 - Safety.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Safety. 240.209 Section 240.209 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES GUIDELINES FOR THE THERMAL PROCESSING OF SOLID WASTES Requirements and Recommended Procedures § 240.209 Safety. ...

  6. [Standards and guidelines of radiation protection and safety in dental X-ray examinations].

    Science.gov (United States)

    Guo, X L; Li, G; Cheng, Y; Yu, Q; Wang, H; Zhang, Z Y

    2017-12-09

    With the rapid development of imaging technology, the application of dental imaging in diagnosis, treatment planning, intraoperative surgical navigation, monitoring of treatment or lesion development and assessment of treatment outcomes is playing an essential role in oral healthcare. The increased total number of dental X-ray examinations is accompanied by a relatively significant increase in collective dose to patients as well as to dental healthcare workers, which is harmful to human bodies to a certain degree. Some radiation protection standards and guidelines in dental radiology have been published in European countries, US, Canada and Australia, etc. Adherence to these standards and guidelines helps to achieve images with diagnostic quality and avoid unnecessary and repeated exposures. However, no radiation protection standard or guideline with regard to dental X-ray examinations has been put in force so far in mainland China. Therefore, a literature review on available radiation protection standards and guidelines was conducted to provide reference to the development of radiation protection standards or guidelines in mainland China.

  7. Critical safety function guidelines for experimental fusion facilities

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1989-01-01

    As fusion experiments proceed toward deuterium-tritium operation, more attention is being given to public safety. This paper presents the four classes of functions that fusion experiments must provide to assure safe, stable shutdown and retention of radionuclides. These functions are referred to as critical safety functions (CSFs). Selecting CSFs is an important step in probabilistic risk assessment (PRA). An example of CSF selection and usage for the Compact Ignition Tokamak (CIT) is also presented. 10 refs., 6 figs

  8. Vehicle recovery and towing guideline

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-01-15

    This guideline was developed to provide light and medium duty vehicles operators in the oil and gas industry with a set of best practices for avoiding injury and damage during the recovery of stuck vehicles. The aim of the guideline was to increase awareness of safety issues and promote the safe usage of the vehicles by personnel throughout the petroleum industry and to establish minimum standards of practice for vehicle recovery. The guideline included a step-by-step guide for pulling out a vehicle with a recovery strap as well as vehicle-mounted winch procedures. Pre-job checklists for both procedures were provided. Issues related to the strength rating of vehicle tow hooks and hitch receivers were discussed, as well as some of the hazards associated with steep terrains and heavy mud. The guideline also included recommendations for a vehicle recovery kit with instructions on vehicle recovery, a recovery strap, a recovery hitch and shackle, a collapsible shovel, traffic cones and reflector flares, and a heavy blanket and gloves. 7 refs., 2 tabs., 13 figs.

  9. The emergency response guidelines for the Westinghouse pressurized water reactor

    International Nuclear Information System (INIS)

    Dekens, J.P.; Bastien, R.; Prokopovich, S.R.

    1985-01-01

    The Three Mile Island accident has demonstrated that the guidance provided for mitigating the consequences of design basis accidents could be inadequate when multiple incidents, failures or errors occur during or after the accident. Westinghouse and the Westinghouse Owners Group have developed new Emergency Response Guidelines (E.R.G.). The E.R.G. are composed of two independent sets of procedures and of a systematic tool to continuously evaluate the plant safety throughout the response to an accident. a) The Optimal Recovery Guidelines are entered each time the reactor is tripped or the Emergency Core Cooling System is actuated. An immediate verification of the automatic protective actuations is performed and the accident diagnosis process is initiated. When nature of the accident is identified, the operator is transferred to the applicable recovery procedure and subprocedures. A permanent rediagnosis is performed throughout the application of the optimal Recovery Guidelines and cross connections are provided to the adequate procedure if an error in diagnosis is identified. b) Early in the course of the accident, the operating staff initiates monitoring of the Critical Safety Functions. These are defined as the set of functions ensuring the integrity of the physical barriers against radioactivity release. The review of these functions is peformed continuously through a cyclic application of the status trees. c) The Function Restoration Guidelines are entered when the Critical Safety Function monitoring identifies a challenge to one of the functions. Depending on the severity of the challenge, the transfer to a Function Restoration Guideline can be immediate for a severe challenge or delayed for a minor challenge. Those guidelines are independent of the scenario of the accident, but only based on plant parameters and equipment availability

  10. Kilowatt isotope power system. Phase II plan. Volume V. Safety, quality assurance and reliability

    International Nuclear Information System (INIS)

    1978-01-01

    The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a 238 PuO 2 -fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Included in this volume are: launch and flight safety considerations; quality assurance techniques and procedures to be followed through system fabrication, assembly and inspection; and the reliability program made up of reliability prediction analysis, failure mode analysis and criticality analysis

  11. Guide to Radiation Safety regulations and guidelines (SSMFS 2012:3) on the management of contaminated ash

    International Nuclear Information System (INIS)

    Moere, Hans

    2012-06-01

    Energy producers burning peat or wood fuel can obtain ash that is contaminated with cesium-137 from Tjernobyl accident or naturally occurring uranium, thorium and potassium, from some peat bogs. Regulations (SSMFS 2012:3) have been developed which regulates how the contaminated ash should be handled. The regulations affect all who handle contaminated ash in incinerators, landfills, public works, ash recycling, transportation or recycling of ash in other ways. Radiation Safety regulations and guidelines (SSMFS 2012:3) on the management of contaminated ash will apply from 1 September 2012. At that time Regulations (SSMFS 2008:16) on the management of ash that is contaminated with cesium-137, ceases to apply. The contents have been incorporated into the new regulations. This report provides explanations and guidance to the Regulations in order to facilitate the practical application. This guidance is not legally binding

  12. Philosophy of safety evaluation on fast breeder reactor

    International Nuclear Information System (INIS)

    1981-01-01

    This is the report submitted from the special subcommittee on reactor safety standard to the Nuclear Safety Commission on October 14, 1980, and it was decided to temporarily apply this concept to the safety examination on fast breeder reactors. The examination and discussion of this report were performed by taking the prototype reactor ''Monju'' into consideration, which is to be the present target, referring to the philosophy of the safety evaluation on fast breeder reactors in foreign countries and based on the experiences in the fast experimental reactor ''Joyo''. The items applicable to the safety evaluation for liquid metal-cooled fast breeder reactors (LMFBR) as they are among the existing safety examination guidelines are applied. In addition to the existing guidelines, the report describes the matters to be considered specifically for core, fuel, sodium, sodium void, reactor shut-down system, reactor coolant boundary, cover gas boundary and others, intermediate cooling system, removal of decay heat, containment vessels, high temperature structures, and aseismatic property in the safety design of LMFBR's. For the safety evaluation for LMFBR's, the abnormal transient changes in operation and the phenomena to be evaluated as accidents are enumerated. In order to judge the propriety of the criteria of locating LMFBR facilities, the serious and hypothetical accidents are decided to be evaluated in accordance with the guideline for reactor location investigation. (Wakatsuki, Y.)

  13. Southern African guidelines on the safe use of pre-exposure ...

    African Journals Online (AJOL)

    With the flurry of data that has been generated in PrEP clinical research since the first guideline, it became evident that there was a need to revise and expand the PrEP guidelines with new evidence of safety and efficacy of PrEP in several populations, including MSM, transgender persons, heterosexual men and women, ...

  14. Bone mineral density across a range of physical activity volumes: NHANES 2007-2010.

    Science.gov (United States)

    Whitfield, Geoffrey P; Kohrt, Wendy M; Pettee Gabriel, Kelley K; Rahbar, Mohammad H; Kohl, Harold W

    2015-02-01

    The association between aerobic physical activity volume and bone mineral density (BMD) is not completely understood. The purpose of this study was to clarify the association between BMD and aerobic activity across a broad range of activity volumes, particularly volumes between those recommended in the 2008 Physical Activity Guidelines for Americans and those of trained endurance athletes. Data from the 2007-2010 National Health and Nutrition Examination Survey were used to quantify the association between reported physical activity and BMD at the lumbar spine and proximal femur across the entire range of activity volumes reported by US adults. Participants were categorized into multiples of the minimum guideline-recommended volume based on reported moderate- and vigorous-intensity leisure activity. Lumbar and proximal femur BMD were assessed with dual-energy x-ray absorptiometry. Among women, multivariable-adjusted linear regression analyses revealed no significant differences in lumbar BMD across activity categories, whereas proximal femur BMD was significantly higher among those who exceeded the guidelines by 2-4 times than those who reported no activity. Among men, multivariable-adjusted BMD at both sites neared its highest values among those who exceeded the guidelines by at least 4 times and was not progressively higher with additional activity. Logistic regression estimating the odds of low BMD generally echoed the linear regression results. The association between physical activity volume and BMD is complex. Among women, exceeding guidelines by 2-4 times may be important for maximizing BMD at the proximal femur, whereas among men, exceeding guidelines by ≥4 times may be beneficial for lumbar and proximal femur BMD.

  15. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

    International Nuclear Information System (INIS)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices

  16. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

  17. Efficacy and safety of tolvaptan in heart failure patients with sustained volume overload despite the use of conventional diuretics: a phase III open-label study.

    Science.gov (United States)

    Fukunami, Masatake; Matsuzaki, Masunori; Hori, Masatsugu; Izumi, Tohru

    2011-12-01

    Volume overload is a common complication associated with heart failure (HF) and is recommended to be treated with loop or thiazide diuretics. However, use of diuretics can cause serum electrolyte imbalances and diuretic resistance. Tolvaptan, a selective, oral, non-peptide vasopressin V2-receptor antagonist, offers a new option for treating volume overload in HF patients. The aim of this study was to investigate the efficacy and safety of tolvaptan in Japanese HF patients with volume overload. Fifty-one HF patients with volume overload, despite using conventional diuretics, were treated with 15 mg/day tolvaptan for 7 days. If the response was insufficient at Day 7, tolvaptan was continued for a further 7 days at either 15 mg/day or 30 mg/day. Outcomes included changes in body weight, symptoms and safety parameters. Thirty-six patients discontinued treatment within 7 days, therefore 15 patients entered the second phase of treatment. In two patients, tolvaptan was increased to 30 mg/day after 7 days. Body weight was reduced on Day 7 (-1.95 ± 1.98 kg; n = 41) and Day 14 (-2.35 ± 1.44 kg; n = 11, 15 mg/day). Symptoms of volume overload, including lower limb edema, pulmonary congestion, jugular venous distention and hepatomegaly, were improved by tolvaptan treatment for 7 or 14 days. Neither tolvaptan increased the incidence of severe or serious adverse events when administered for 7-14 days. This study confirms the efficacy and safety of 15 mg/day tolvaptan for 7-14 days in Japanese HF patients with volume overload despite conventional diuretics.

  18. Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations; Rapport de surete du reacteur pegase - tome 1 - Description des installations - tome 2 - Surete des installations

    Energy Technology Data Exchange (ETDEWEB)

    Lacour, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legoin, P. [S.E.M. Hispano-Suiza, 92 - Colombes (France)

    1964-07-01

    In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [French] Dans le volume 1: Ce rapport est une description du reacteur Pegase, afin d'examiner la surete des installations. Le site de CADARACHE ou elles sont situees, a ete sommairement decrit, en particulier, a cause des consequences sur les techniques mises en oeuvre pour la realisation de Pegase. Nous nous sommes egalement attache a decrire les aspects originaux du reacteur. Les boucles autonomes destinees a tester en vraie grandeur des elements combustibles de la filiere uranium naturel graphite-gaz, ainsi que leurs dispositifs de controle et d'exploitation, figurent egalement dans ce rapport. Dans le volume 2: Dans le present rapport, nous examinons des accidents pouvant endommager des installations du reacteur Pegase. Les origines d'accidents examines

  19. Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations; Rapport de surete du reacteur pegase - tome 1 - Description des installations - tome 2 - Surete des installations

    Energy Technology Data Exchange (ETDEWEB)

    Lacour, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legoin, P [S.E.M. Hispano-Suiza, 92 - Colombes (France)

    1964-07-01

    In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [French] Dans le volume 1: Ce rapport est une description du reacteur Pegase, afin d'examiner la surete des installations. Le site de CADARACHE ou elles sont situees, a ete sommairement decrit, en particulier, a cause des consequences sur les techniques mises en oeuvre pour la realisation de Pegase. Nous nous sommes egalement attache a decrire les aspects originaux du reacteur. Les boucles autonomes destinees a tester en vraie grandeur des elements combustibles de la filiere uranium naturel graphite-gaz, ainsi que leurs dispositifs de controle et d'exploitation, figurent egalement dans ce rapport. Dans le volume 2: Dans le present rapport, nous examinons des accidents pouvant endommager des installations du reacteur Pegase. Les origines d'accidents examines comprennent la seismicite

  20. Continuing Education, Guideline Implementation, and the Emerging Transdisciplinary Field of Knowledge Translation

    Science.gov (United States)

    Davis, Dave

    2006-01-01

    This article discusses continuing education and the implementation of clinical practice guidelines or best evidence, quality improvement, and patient safety. Continuing education focuses on the perspective of the adult learner and is guided by well-established educational principles. In contrast, guideline implementation and related concepts…

  1. IAEA/NEA Fuel Incident Notification and Analysis System (FINAS) guidelines

    International Nuclear Information System (INIS)

    2006-01-01

    The Fuel Incident Notification and Analysis System (FINAS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development (OECD/NEA). The fundamental objective of FINAS is to contribute to improving the safety of fuel cycle facilities, which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance, which occur at these facilities. The purpose of these guidelines, which supersede the previous NEA FINAS guidelines is to describe the system and to give users the necessary background and guidance to enable them to produce FINAS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating FCFs. These guidelines have been jointly developed and approved by the NEA/IAEA

  2. An improvement of the applicability of human factors guidelines for coping with human factors issues in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Y. H.; Lee, J. Y.

    2003-01-01

    Human factors have been well known as one of the key factors to the system effectiveness as well as the efficiency and safety of nuclear power plants(NPPs). Human factors engineering(HFE) are included in periodic safety review(PSR) on the existing NPPs and the formal safety assessment for the new ones. However, HFE for NPPs is still neither popular in practice nor concrete in methodology. Especially, the human factors guidelines, which are the most frequent form of human factors engineering in practice, reveal the limitations in their applications. We discuss the limitations and their casual factors found in human factors guidelines in order to lesson the workload of HFE practitioners and to improve the applicability of human factors guidelines. According to the purposes and the phases of HFE for NPPs, more selective items and specified criteria should be prepared carefully in the human factors guidelines for the each HFE applications in practice. These finding on the human factors guidelines can be transferred to the other HFE application field, such as military, aviation, telecommunication, HCI, and product safety

  3. The reality of life safety consequence classification

    International Nuclear Information System (INIS)

    Hartford, D.N.D.; Assaf, H.; Kerr, I.R.

    1999-01-01

    Because empirical methods of consequence estimation were not designed for application in risk analysis for dam safety, BC Hydro developed its own method for determining loss of life due to dam failures as part of the development of the risk analysis process. Because loss of life estimation for consequence classification entails the generation of essentially the same information, the method can also be used to determine the consequence category of the dam for life safety considerations, and the model can be extended to third party property damage. The methodology adopted for dealing with life safety differs considerably from the empirical approach by modelling the response of the downstream population to a dam failure flood. The algorithm simulates the response of various groups of populations to the warnings of dam failure and the physical process of fleeing from the areas of potential innundation. Assessing the life safety consequences of dam failure is a first step in estimating dam safety in terms of CDA Guidelines, and empirical methods in use are not suitable for determining loss of life due to dam failures. The process described herein is the only physically based method available for estimating loss of life due to dam failures required by the Dam Safety Guidelines. The model is transparent, logically sound, and has been peer reviewed. The method provides a rational basis for the first step in performing safety assessments of dams in terms of the Guidelines, particularly high consequence dams. 8 refs., 3 figs

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

    International Nuclear Information System (INIS)

    1993-12-01

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

  5. Ethical Guideline to Authors,Editors,and Reviewers

    Institute of Scientific and Technical Information of China (English)

    Editorial office of CHM

    2016-01-01

    Drug products are specific goods with safety and effectiveness in medical health case.All of researchers(authors),reviewers,and editors must abide by medical ethical obligation,and also must deter to the ethical obligation for publication.These guidelines are offered as ethical

  6. Determination of safety distance limits for a human near a cellular base station antenna, adopting the IEEE standard or ICNIRP guidelines.

    Science.gov (United States)

    Cooper, Justin; Marx, Bernd; Buhl, Johannes; Hombach, Volker

    2002-09-01

    This paper investigates the minimum distance for a human body in the near field of a cellular telephone base station antenna for which there is compliance with the IEEE or ICNIRP threshold values for radio frequency electromagnetic energy absorption in the human body. First, local maximum specific absorption rates (SARs), measured and averaged over volumes equivalent to 1 and to 10 g tissue within the trunk region of a physical, liquid filled shell phantom facing and irradiated by a typical GSM 900 base station antenna, were compared to corresponding calculated SAR values. The calculation used a homogeneous Visible Human body model in front of a simulated base station antenna of the same type. Both real and simulated base station antennas operated at 935 MHz. Antenna-body distances were between 1 and 65 cm. The agreement between measurements and calculations was excellent. This gave confidence in the subsequent calculated SAR values for the heterogeneous Visible Human model, for which each tissue was assigned the currently accepted values for permittivity and conductivity at 935 MHz. Calculated SAR values within the trunk of the body were found to be about double those for the homogeneous case. When the IEEE standard and the ICNIRP guidelines are both to be complied with, the local SAR averaged over 1 g tissue was found to be the determining parameter. Emitted power values from the antenna that produced the maximum SAR value over 1 g specified in the IEEE standard at the base station are less than those needed to reach the ICNIRP threshold specified for the local SAR averaged over 10 g. For the GSM base station antenna investigated here operating at 935 MHz with 40 W emitted power, the model indicates that the human body should not be closer to the antenna than 18 cm for controlled environment exposure, or about 95 cm for uncontrolled environment exposure. These safe distance limits are for SARs averaged over 1 g tissue. The corresponding safety distance limits

  7. K-Basins design guidelines

    International Nuclear Information System (INIS)

    Roe, N.R.; Mills, W.C.

    1995-06-01

    The purpose of the design guidelines is to enable SNF and K Basin personnel to complete fuel and sludge removal, and basin water mitigation by providing engineering guidance for equipment design for the fuel basin, facility modifications (upgrades), remote tools, and new processes. It is not intended to be a purchase order reference for vendors. The document identifies materials, methods, and components that work at K Basins; it also Provides design input and a technical review process to facilitate project interfaces with operations in K Basins. This document is intended to compliment other engineering documentation used at K Basins and throughout the Spent Nuclear Fuel Project. Significant provisions, which are incorporated, include portions of the following: General Design Criteria (DOE 1989), Standard Engineering Practices (WHC-CM-6-1), Engineering Practices Guidelines (WHC 1994b), Hanford Plant Standards (DOE-RL 1989), Safety Analysis Manual (WHC-CM-4-46), and Radiological Design Guide (WHC 1994f). Documents (requirements) essential to the engineering design projects at K Basins are referenced in the guidelines

  8. Functional safety measurement in the automotive domain : adaptation of PSM

    NARCIS (Netherlands)

    Luo, Y.; Stelma, J.; Brand, van den M.G.J.

    2015-01-01

    In the safety domain, safety standards are used as a development guideline to keep the risk at an acceptable level. Safety of the safety-critical systems can be assessed according to those safety standards. This assessment process is called safety assurance. Due to the manual work, the safety

  9. LFR safety approach and main ELFR safety analysis results

    International Nuclear Information System (INIS)

    Bubelis, E.; Schikorr, M.; Frogheri, M.; Mansani, L.; Bandini, G.; Burgazzi, L.; Mikityuk, K.; Zhang, Y.; Lo Frano, R.; Forgione, N.

    2013-01-01

    LFR safety approach: → A global safety approach for the LFR reference plant has been assessed and the safety analyses methodology has been developed. → LFR follows the general guidelines of the Generation IV safety concept recommendations. Thus, improved safety and higher reliability are recognized as an essential priority. → The fundamental safety objectives and the Defence-in-Depth (DiD) approach, as described by IAEA Safety Guides, have been preserved. → The recommendations of the Risk and Safety Working Group (RSWG) of GEN-IV IF has been taken into account: • safety is to be “built-in” in the fundamental design rather than “added on”; • full implementation of the Defence-in-Depth principles in a manner that is demonstrably exhaustive, progressive, tolerant, forgiving and well-balanced; • “risk-informed” approach - deterministic approach complemented with a probabilistic one; • adoption of an integrated methodology that can be used to evaluate and document the safety of Gen IV nuclear systems - ISAM. In particular the OPT tool is the fundamental methodology used throughout the design process

  10. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  11. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  12. School Safety Policies With Emphasis on Physical Education, Athletics and Recreation.

    Science.gov (United States)

    American Association for Health, Physical Education, and Recreation, Washington, DC.

    This booklet outlines principles of hazard control, school accident problems, and the need for guidelines and policies. Suggested general school safety policies, guidelines for courses in safety education and for the provision of facilities and supplies, policies for the administration of first aid and emergency care, and procedures for reporting…

  13. Laboratory Safety Manual for Alabama Schools. Bulletin 1975. No. 20.

    Science.gov (United States)

    Alabama State Dept. of Education, Montgomery.

    This document presents the Alabama State Department of Education guidelines for science laboratory safety, equipment, storage, chemical safety, rocket safety, electrical safety, safety with radioisotopes, and safety with biologicals. Also included is a brief bibliography, a teacher's checklist, a listing of laser facts and regulations, and a…

  14. Technical guideline technology according to the X-ray regulations

    International Nuclear Information System (INIS)

    2011-01-01

    The guideline covers the required technical knowledge concerning radiation protection and knowledge concerning for the operation of X-ray devices for technical purposes and stray radiation sources requiring licensing, and requirements for the qualification of officially authorized inspectors. The guidelines includes the following chapters: (1) introductory regulations; (2) Volume of the required technical knowledge; (3) Acquirement and certification of the technical knowledge; (4) Actualization of the technical knowledge; (5)Approval of courses and other training measures; (6) Combination of courses and training measures according to the guideline; (7) Requirements for qualification of officially authorized inspectors; (8) Interim regulations.

  15. Building Chronic Kidney Disease Clinical Practice Guidelines Using the openEHR Guideline Definition Language.

    Science.gov (United States)

    Lin, Ching-Heng; Lo, Ying-Chih; Hung, Pei-Yuan; Liou, Der-Ming

    2016-12-07

    As a result of the disease's high prevalence, chronic kidney disease (CKD) has become a global public health problem. A clinical decision support system that integrates with computer-interpretable guidelines (CIGs) should improve clinical outcomes and help to ensure patient safety. The openEHR guideline definition language (GDL) is a formal language used to represent CIGs. This study explores the feasibility of using a GDL approach for CKD; it also attempts to identify any potential gaps between the ideal concept and reality. Using the Kidney Disease Improving Global Outcomes (KDIGO) anemia guideline as material, we designed a development workflow in order to establish a series of GDL guidelines. Focus group discussions were conducted in order to identify important issues related to GDL implementation. Ten GDL guidelines and 37 archetypes were established using the KDIGO guideline document. For the focus group discussions, 16 clinicians and 22 IT experts were recruited and their perceptions, opinions and attitudes towards the GDL approach were explored. Both groups provided positive feedback regarding the GDL approach, but raised various concerns about GDL implementation. Based on the findings of this study, we identified some potential gaps that might exist during implementation between the GDL concept and reality. Three directions remain to be investigated in the future. Two of them are related to the openEHR GDL approach. Firstly, there is a need for the editing tool to be made more sophisticated. Secondly, there needs to be integration of the present approach into non openEHR-based hospital information systems. The last direction focuses on the applicability of guidelines and involves developing a method to resolve any conflicts that occur with insurance payment regulations.

  16. NASA System Safety Handbook. Volume 1; System Safety Framework and Concepts for Implementation

    Science.gov (United States)

    Dezfuli, Homayoon; Benjamin, Allan; Everett, Christopher; Smith, Curtis; Stamatelatos, Michael; Youngblood, Robert

    2011-01-01

    System safety assessment is defined in NPR 8715.3C, NASA General Safety Program Requirements as a disciplined, systematic approach to the analysis of risks resulting from hazards that can affect humans, the environment, and mission assets. Achievement of the highest practicable degree of system safety is one of NASA's highest priorities. Traditionally, system safety assessment at NASA and elsewhere has focused on the application of a set of safety analysis tools to identify safety risks and formulate effective controls.1 Familiar tools used for this purpose include various forms of hazard analyses, failure modes and effects analyses, and probabilistic safety assessment (commonly also referred to as probabilistic risk assessment (PRA)). In the past, it has been assumed that to show that a system is safe, it is sufficient to provide assurance that the process for identifying the hazards has been as comprehensive as possible and that each identified hazard has one or more associated controls. The NASA Aerospace Safety Advisory Panel (ASAP) has made several statements in its annual reports supporting a more holistic approach. In 2006, it recommended that "... a comprehensive risk assessment, communication and acceptance process be implemented to ensure that overall launch risk is considered in an integrated and consistent manner." In 2009, it advocated for "... a process for using a risk-informed design approach to produce a design that is optimally and sufficiently safe." As a rationale for the latter advocacy, it stated that "... the ASAP applauds switching to a performance-based approach because it emphasizes early risk identification to guide designs, thus enabling creative design approaches that might be more efficient, safer, or both." For purposes of this preface, it is worth mentioning three areas where the handbook emphasizes a more holistic type of thinking. First, the handbook takes the position that it is important to not just focus on risk on an individual

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

    Science.gov (United States)

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

    2017-04-27

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

  18. NPP Temelin safety analysis reports and PSA status

    International Nuclear Information System (INIS)

    Mlady, O.

    1999-01-01

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

  19. Efficacy and safety of tolvaptan in heart failure patients with volume overload despite the standard treatment with conventional diuretics: a phase III, randomized, double-blind, placebo-controlled study (QUEST study).

    Science.gov (United States)

    Matsuzaki, Masunori; Hori, Masatsugu; Izumi, Tohru; Fukunami, Masatake

    2011-12-01

    Diuretics are recommended to treat volume overload with heart failure (HF), however, they may cause serum electrolyte imbalance, limiting their use. Moreover, patients with advanced HF could poorly respond to these diuretics. In this study, we evaluated the efficacy and safety of Tolvaptan, a competitive vasopressin V2-receptor antagonist developed as a new drug to treat volume overload in HF patients. A phase III, multicenter, randomized, double-blind, placebo-controlled parallel study was performed to assess the efficacy and safety of tolvaptan in treating HF patients with volume overload despite the use of conventional diuretics. One hundred and ten patients were randomly assigned to receive either placebo or 15 mg/day tolvaptan for 7 consecutive days. Compared with placebo, tolvaptan administered for 7 days significantly reduced body weight and improved symptoms associated with volume overload. The safety profile of tolvaptan was considered acceptable for clinical use with minimal adverse effects. Tolvaptan reduced volume overload and improved congestive symptoms associated with HF by a potent water diuresis (aquaresis).

  20. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting; Volume 2, Severe accident research, Thermal hydraulics

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, A.J. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

  1. Software safety analysis techniques for developing safety critical software in the digital protection system of the LMR

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jang Soo; Cheon, Se Woo; Kim, Chang Hoi; Sim, Yun Sub

    2001-02-01

    This report has described the software safety analysis techniques and the engineering guidelines for developing safety critical software to identify the state of the art in this field and to give the software safety engineer a trail map between the code and standards layer and the design methodology and documents layer. We have surveyed the management aspects of software safety activities during the software lifecycle in order to improve the safety. After identifying the conventional safety analysis techniques for systems, we have surveyed in details the software safety analysis techniques, software FMEA(Failure Mode and Effects Analysis), software HAZOP(Hazard and Operability Analysis), and software FTA(Fault Tree Analysis). We have also surveyed the state of the art in the software reliability assessment techniques. The most important results from the reliability techniques are not the specific probability numbers generated, but the insights into the risk importance of software features. To defend against potential common-mode failures, high quality, defense-in-depth, and diversity are considered to be key elements in digital I and C system design. To minimize the possibility of CMFs and thus increase the plant reliability, we have provided D-in-D and D analysis guidelines.

  2. Software safety analysis techniques for developing safety critical software in the digital protection system of the LMR

    International Nuclear Information System (INIS)

    Lee, Jang Soo; Cheon, Se Woo; Kim, Chang Hoi; Sim, Yun Sub

    2001-02-01

    This report has described the software safety analysis techniques and the engineering guidelines for developing safety critical software to identify the state of the art in this field and to give the software safety engineer a trail map between the code and standards layer and the design methodology and documents layer. We have surveyed the management aspects of software safety activities during the software lifecycle in order to improve the safety. After identifying the conventional safety analysis techniques for systems, we have surveyed in details the software safety analysis techniques, software FMEA(Failure Mode and Effects Analysis), software HAZOP(Hazard and Operability Analysis), and software FTA(Fault Tree Analysis). We have also surveyed the state of the art in the software reliability assessment techniques. The most important results from the reliability techniques are not the specific probability numbers generated, but the insights into the risk importance of software features. To defend against potential common-mode failures, high quality, defense-in-depth, and diversity are considered to be key elements in digital I and C system design. To minimize the possibility of CMFs and thus increase the plant reliability, we have provided D-in-D and D analysis guidelines

  3. 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.

  4. Recent findings relating to firefighter safety zones

    Science.gov (United States)

    Bret Butler; Russ Parsons; William Mell

    2015-01-01

    Designation of safety zones is a primary duty of all wildland firefighters. Unfortunately, information regarding what constitutes an adequate safety zone is inadequately defined. Measurements of energy release from wildland fires have been used to develop an empirically based safety zone guideline. The basis for this work is described here.

  5. Tank farm health and safety plan. Revision 2

    International Nuclear Information System (INIS)

    Mickle, G.D.

    1995-01-01

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

  6. Tank farm health and safety plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Mickle, G.D.

    1995-03-29

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

  7. Emergency concepts for the safety level four; Notfallkonzepte der Sicherheitsebene Vier

    Energy Technology Data Exchange (ETDEWEB)

    Richner, Martin [Axpo Power AG, Doettingen (Switzerland). Kernkraftwerk Beznau

    2016-04-15

    According to the IAEA Guidelines and the Swiss Safety Guidelines the defence-in depth safety concept for a nuclear power plant consists of four safety levels. Emergency measures for the limitation of beyond design basis accidents are of safety level four. They are referred to as incident management. After the Chernobyl accident in 1986, in Switzerland the former regulatory body HSK (today ENSI) requested several retrofit measures in the field of accident management. The importance of accident management was visible again in Fukushima and demands for preventive measures grew.

  8. Factors influencing adherence to dietary guidelines: a qualitative ...

    African Journals Online (AJOL)

    2014-01-17

    Jan 17, 2014 ... Original Research: Factors influencing adherence to dietary guidelines. 76. 2014 Volume ..... eat, because they dik (tired) of giving you special food. Then they go .... patients in this study were satisfied with the advice received ...

  9. Content and quality of workplace guidelines developed to prevent mental health problems

    DEFF Research Database (Denmark)

    Nexø, Mette Andersen; Kristensen, Josefine Vejlby; Grønvad, Majbritt Thorhauge

    2018-01-01

    Objectives A wide range of guidelines have been developed to prevent work-related mental health problems (MHP), but little is known about the quality of such guidelines. We systematically reviewed the content and quality of workplace guidelines aiming to prevent, detect, and/or manage work......-related MHP. Methods We conducted systematic online and database searches (MEDLINE; Web of Science; PsychNET; occupational safety and health databases) to identify guidelines. Eligibility criteria included guidelines recommending primary, secondary, or tertiary preventive interventions to be implemented...... at the workplace by employers, employees or organizational staff. A minimum of minimum three independent reviewers assessed the quality of guidelines using the Guidelines for Research and Evaluation (AGREE II). Guidelines rated ≥65% with regards to domain I, II, and III were considered to be of good developmental...

  10. Medical Physics Practice Guideline 4.a: Development, implementation, use and maintenance of safety checklists.

    Science.gov (United States)

    Fong de Los Santos, Luis E; Evans, Suzanne; Ford, Eric C; Gaiser, James E; Hayden, Sandra E; Huffman, Kristina E; Johnson, Jennifer L; Mechalakos, James G; Stern, Robin L; Terezakis, Stephanie; Thomadsen, Bruce R; Pronovost, Peter J; Fairobent, Lynne A

    2015-05-08

    The American Association of Physicists in Medicine (AAPM) is a nonprofit professional society whose primary purposes are to advance the science, education and professional practice of medical physics. The AAPM has more than 8,000 members and is the principal organization of medical physicists in the United States.The AAPM will periodically define new practice guidelines for medical physics practice to help advance the science of medical physics and to improve the quality of service to patients throughout the United States. Existing medical physics practice guidelines will be reviewed for the purpose of revision or renewal, as appropriate, on their fifth anniversary or sooner.Each medical physics practice guideline represents a policy statement by the AAPM, has undergone a thorough consensus process in which it has been subjected to extensive review, and requires the approval of the Professional Council. The medical physics practice guidelines recognize that the safe and effective use of diagnostic and therapeutic radiology requires specific training, skills, and techniques, as described in each document. Reproduction or modification of the published practice guidelines and technical standards by those entities not providing these services is not authorized.The following terms are used in the AAPM practice guidelines:Must and Must Not: Used to indicate that adherence to the recommendation is considered necessary to conform to this practice guideline.Should and Should Not: Used to indicate a prudent practice to which exceptions may occasionally be made in appropriate circumstances.

  11. Addressing implementation challenges during guideline development - a case study of Swedish national guidelines for methods of preventing disease.

    Science.gov (United States)

    Richter-Sundberg, Linda; Kardakis, Therese; Weinehall, Lars; Garvare, Rickard; Nyström, Monica E

    2015-01-22

    Many of the world's life threatening diseases (e.g. cancer, heart disease, stroke) could be prevented by eliminating life-style habits such as tobacco use, unhealthy diet, physical inactivity and excessive alcohol use. Incorporating evidence-based research on methods to change unhealthy lifestyle habits in clinical practice would be equally valuable. However gaps between guideline development and implementation are well documented, with implications for health care quality, safety and effectiveness. The development phase of guidelines has been shown to be important both for the quality in guideline content and for the success of implementation. There are, however, indications that guidelines related to general disease prevention methods encounter specific barriers compared to guidelines that are diagnosis-specific. In 2011 the Swedish National board for Health and Welfare launched guidelines with a preventive scope. The aim of this study was to investigate how implementation challenges were addressed during the development process of these disease preventive guidelines. Seven semi-structured interviews were conducted with members of the guideline development management group. Archival data detailing the guideline development process were also collected and used in the analysis. Qualitative data were analysed using content analysis as the analytical framework. The study identified several strategies and approaches that were used to address implementation challenges during guideline development. Four themes emerged from the analysis: broad agreements and consensus about scope and purpose; a formalized and structured development procedure; systematic and active involvement of stakeholders; and openness and transparency in the specific guideline development procedure. Additional factors concerning the scope of prevention and the work environment of guideline developers were perceived to influence the possibilities to address implementation issues. This case study

  12. How GPs implement clinical guidelines in everyday clinical practice

    DEFF Research Database (Denmark)

    Videbæk Le, Jette; Hansen, Helle P; Riisgaard, Helle

    2015-01-01

    BACKGROUND: Clinical guidelines are considered to be essential for improving quality and safety of health care. However, interventions to promote implementation of guidelines have demonstrated only partial effectiveness and the reasons for this apparent failure are not yet fully understood....... OBJECTIVE: To investigate how GPs implement clinical guidelines in everyday clinical practice and how implementation approaches differ between practices. METHODS: Individual semi-structured open-ended interviews with seven GPs who were purposefully sampled with regard to gender, age and practice form....... Interviews were recorded, transcribed verbatim and then analysed using systematic text condensation. RESULTS: Analysis of the interviews revealed three different approaches to the implementation of guidelines in clinical practice. In some practices the GPs prioritized time and resources on collective...

  13. Nuclear safety legislation and supervision in China

    International Nuclear Information System (INIS)

    Zhang Shiguan

    1991-02-01

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

  14. Right-Turn Traffic Volume Adjustments in Traffic Signal Warrant Analysis

    Science.gov (United States)

    2015-01-01

    To accomplish this research, a comprehensive literature review of existing guidelines and findings based on national and local studies was conducted. Ultimately, guidelines for consistent application for adjusting right-turn traffic volumes were deve...

  15. Safety and reliability. V. 1. Proceedings

    International Nuclear Information System (INIS)

    Soares, C.G.

    1997-01-01

    Proceedings of a 1997 conference on industrial safety and reliability are reported. The first volume looks at risk management, probabilistic safety assessment and management styles in various industrial settings, including nuclear power plants. The second volume addresses safety and reliability in the offshore and transport industries, focusing on the role of staff training and appropriate maintenance routines to effectively reduce accidents and outages. (UK)

  16. Anatomic guidelines defined by reformatting images on MRI for volume measurement of amygdala and hippocampus

    International Nuclear Information System (INIS)

    Hoshida, Tohru; Sakaki, Toshisuke; Uematsu, Sumio.

    1995-01-01

    Twelve patients with intractable partial epilepsy underwent MR scans at the Epilepsy Center of the Johns Hopkins Hospital. There were five women and seven men, ranging in age from five to 51 years (mean age: 26 years). Coronal images were obtained using a 3-D SPGR. The coronal images were transferred to an Allegro 5.1 workstation, and reformatted along the cardinal axes (axial and sagittal) in multiple view points. The anterior end of the amygdala was measured at the level just posterior to the disappearance of the temporal stem. The semilunar gyrus of the amygdala was separated from the ambient gyrus by the semianular sulcus that forms the boundary between the amygdala and the entorhinal cortex. The delineation of the hippocampal formation included the subicular complex, hippocampal proper, dentate gyrus, alveus, and fimbria. The uncal cleft separated the uncus above from the parahippocampal gyrus below. The roof of this cleft was formed by the hippocampus and the dentate gyrus, and the floor, by the presubiculum and subiculum. Although using some guidelines, strictly separating the hippocampal head from the posterior part of the amygdala was not feasible as was previously reported, because of the isointensity on MRI between the cortex of the amygdala and the hippocampus. The most posterior portion of the hippocampus was measured at the level of the subsplenial gyri, just below the splenium of the corpus callosum, to measure the hippocampal volume in its near totality. Therefore, it is reliable, and clinically useful, to measure the combined total volume of the amygdala and the hippocampus when comparing results with those of other centers. (S.Y.)

  17. SALTO guidelines. Guidelines for peer review of long term operation and ageing management of nuclear power plants

    International Nuclear Information System (INIS)

    2008-01-01

    other and apply good practices in dealing with LTO of NPPs. The peer review service 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 services that indirectly address some aspects of LTO, including safety review services for design, engineering, operation and external hazards. OSART (Operational Safety Review Team) services include some review of ageing management programmes. In addition, several Member States have requested AMAT (Ageing Management Assessment Team) missions. Through these activities and considering the increasing average age of NPPs connected to the grid worldwide, it was recognized that a comprehensive engineering safety review service on LTO would be very useful to Member States. The Safe Long Term Operation (SALTO) peer review is a new comprehensive engineering safety review service directly addressing strategy and the key elements for safe LTO of NPPs, which includes AMAT objectives and complements OSART reviews. The SALTO peer review service is designed to assist NPP operators in adopting a proper approach to long term operation of their plants and in implementing complete and appropriate activities to ensure that plant safety will be maintained during the LTO period. The SALTO peer review service can be tailored to focus on AMPs and/or on other programmes related to LTO to support the Member State in enhancing the safety of its NPPs. The SALTO peer review service can also support regulators in establishing or improving regulatory and licensing strategies for LTO of NPPs. These guidelines are primarily intended for members of the SALTO review team and they provide a basic structure and common reference for peer reviews of LTO. However, the guidelines could provide useful information to operating organizations of NPPs (or technical support organizations) for carrying out their own self-assessments or comprehensive programme reviews. The

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

    International Nuclear Information System (INIS)

    1998-01-01

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

  19. Advanced human-system interface design review guidelines

    International Nuclear Information System (INIS)

    O'Hara, J.M.

    1990-01-01

    Advanced, computer-based, human-system interface designs are emerging in nuclear power plant (NPP) control rooms. These developments may have significant implications for plant safety in that they will greatly affect the ways in which operators interact with systems. At present, however, the only guidance available to the US Nuclear Regulatory Commission (NRC) for the review of control room-operator interfaces, NUREG-0700, was written prior to these technological changes and is thus not designed to address them. The objective of the project reported in this paper is to develop an Advanced Control Room Design Review Guideline for use in performing human factors reviews of advanced operator interfaces. This guideline will be implemented, in part, as a portable, computer-based, interactive document for field use. The paper describes the overall guideline development methodology, the present status of the document, and the plans for further guideline testing and development. 21 refs., 3 figs

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

    International Nuclear Information System (INIS)

    1994-12-01

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

  1. Case study: the Argentina Road Safety Project: lessons learned for the decade of action for road safety, 2011-2020.

    Science.gov (United States)

    Raffo, Veronica; Bliss, Tony; Shotten, Marc; Sleet, David; Blanchard, Claire

    2013-12-01

    This case study of the Argentina Road Safety Project demonstrates how the application of World Bank road safety project guidelines focused on institution building can accelerate knowledge transfer, scale up investment and improve the focus on results. The case study highlights road safety as a development priority and outlines World Bank initiatives addressing the implementation of the World Report on Road Traffic Injury's recommendations and the subsequent launch of the Decade of Action for Road Safety, from 2011-2020. The case study emphasizes the vital role played by the lead agency in ensuring sustainable road safety improvements and promoting the shift to a 'Safe System' approach, which necessitated the strengthening of all elements of the road safety management system. It summarizes road safety performance and institutional initiatives in Argentina leading up to the preparation and implementation of the project. We describe the project's development objectives, financing arrangements, specific components and investment staging. Finally, we discuss its innovative features and lessons learned, and present a set of supplementary guidelines, both to assist multilateral development banks and their clients with future road safety initiatives, and to encourage better linkages between the health and transportation sectors supporting them.

  2. The System 80+ Standard Plant design control document. Volume 11

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers parts 6 and 7 and appendix 7A for section 7 (Instrumentation and Control) of the ADM Design and Analysis. The topics covered by these are: other systems required for safety; control systems not required by safety; and CMF evaluation of limiting faults. Parts 1--3 of section 8 (Electric Power) of the ADM are also included in this volume. Topics covered by these parts are: introduction; offsite power system; and onsite power system

  3. BWR water chemistry guidelines and PWR primary water chemistry guidelines in Japan – Purpose and technical background

    Energy Technology Data Exchange (ETDEWEB)

    Kawamura, Hirotaka, E-mail: kawamuh@criepi.denken.or.jp [Central Research Institute of Electric Power Industry (Japan); Hirano, Hideo [Central Research Institute of Electric Power Industry (Japan); Katsumura, Yousuke [University of Tokyo (Japan); Uchida, Shunsuke [Tohoku University (Japan); Mizuno, Takayuki [Mie University (Japan); Kitajima, Hideaki; Tsuzuki, Yasuo [Japan Nuclear Safety Institute (Japan); Terachi, Takumi [Institute of Nuclear Safety System, Inc. (Japan); Nagase, Makoto; Usui, Naoshi [Hitachi-GE Nuclear Energy, Ltd. (Japan); Takagi, Junichi; Urata, Hidehiro [Toshiba Corporation (Japan); Shoda, Yasuhiko; Nishimura, Takao [Mitsubishi Heavy Industry, Ltd. (Japan)

    2016-12-01

    Highlights: • Framework of BWR/PWR water chemistry Guidelines in Japan are presented. • Guideline necessity, definitions, philosophy and technical background are mentioned. • Some guideline settings for control parameters and recommendations are explaines. • Chemistry strategy is also mentioned. - Abstract: After 40 years of light water reactor (LWR) operations in Japan, the sustainable development of water chemistry technologies has aimed to ensure the highest coolant system component integrity and fuel reliability performance for maintaining LWRs in the world; additionally, it aimed to achieve an excellent dose rate reduction. Although reasonable control and diagnostic parameters are utilized by each boiling water reactor (BWR) and pressurized water reactor (PWR) owner, it is recognized that specific values are not shared among everyone involved. To ensure the reliability of BWR and PWR operation and maintenance, relevant members of the Atomic Energy Society of Japan (AESJ) decided to establish guidelines for water chemistry. The Japanese BWR and PWR water chemistry guidelines provide strategies to improve material and fuel reliability performance as well as to reduce dosing rates. The guidelines also provide reasonable “control values”, “diagnostic values” and “action levels” for multiple parameters, and they stipulate responses when these levels are exceeded. Specifically, “conditioning parameters” are adopted in the Japanese PWR primary water chemistry guidelines. Good practices for operational conditions are also discussed with reference to long-term experience. This paper presents the purpose, technical background and framework of the preliminary water chemistry guidelines for Japanese BWRs and PWRs. It is expected that the guidelines will be helpful as an introduction to achieve safety and reliability during operations.

  4. General Guidelines for Remote Operation and Maintenance of Pyroprocess Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. H.; Park, B. S.; Park, H. S.; Lee, H. J.; Choi, C. W.; Lee, J. K

    2007-12-15

    As the pyroprocess handle the high radioactive materials, a high radioactive material handling facility required high safety, radioactive shielding, strict quality control, and the remote handling equipment of high technology. This report describes the guidelines of for pyroprocess based the design guides for radioactive material handling facility and equipment from American Nuclear Society(ANS), design guidelines for remotely maintained equipment from Oak Ridge National Laboratory(ORNL), and the experience of design for ACP equipment installed at the ACPF(Advanced Conditioning Process Facility). The General guidelines in this report are as follows. The General guidelines for remote operation and maintenance of pyroprocess equipment: Pyroprocess, Remote handling equipment for pyroprocess, General guide for remote operation and maintenance, general guidelines for the design of remotely operated and maintained equipment, Estimation and analysis for remote maintenance.

  5. SU-D-18C-06: Initial Experience with Implementing MRI Safety Guidelines for Patients with Pacemakers - Medical Physicist Perspective

    Energy Technology Data Exchange (ETDEWEB)

    James, J; Place, V; Panda, A [Mayo Clinic, Scottsdale, AZ (United States); Edmonson, H [Mayo Clinic College of Medicine, Rochester, MN (United States); Felmlee, J [Mayo Clinic, Rochester, MN (United States); Pooley, R [Mayo Clinic, Jacksonville, FL (United States)

    2014-06-01

    Purpose: Several institutions have developed MRI guidelines for patients with MR-unsafe or MR-conditional pacemakers. Here we highlight the role of a medical physicist in implementing these guidelines for non-pacemaker dependent patients. Guidelines: Implementing these guidelines requires involvement from several medical specialties and a strong collaboration with the site MRI supervisor to develop a structured workflow. A medical physicist is required to be present during the scan to supervise the MR scanning and to maintain a safety checklist that ensures: 1) uninterrupted patient communication with the technologist, 2) continuous patient physiologic monitoring (e.g. blood pressure and electrocardiography) by a trained nurse, 3) redundant patient vitals monitoring (e.g. pulse oximetry) due to the possibility of in vivo electrocardiography reading fluctuations during image acquisition. A radiologist is strongly recommended to be available to review the images before patients are discharged from the scanner. Pacemaker MRI should be restricted to 1.5T field strength. The MRI sequences should be optimized by the physicist with regards to: a) SAR: limited to <1.5 W/Kg for MR-unsafe pacemakers in normal operating mode, b) RF exposure time: <30 min, c) Coils: use T/R coils but not restricted to such, d) Artifacts: further optimization of sequences whenever image quality is compromised due to the pacemaker. In particular, cardiac, breast and left-shoulder MRIs are most susceptible to these artifacts. Possible strategies to lower the SAR include: a) BW reduction, 2) echo-train-length reduction, 3) increase TR, 4) decrease number of averages, 5) decrease flip angle, 6) reduce slices and/or a combination of all the options. Conclusion: A medical physicist in collaboration with the MR supervisor plays an important role in the supervision/implementation of safe MR scanning of pacemaker patients. Developing and establishing a workflow has enabled our institution to scan over

  6. SU-D-18C-06: Initial Experience with Implementing MRI Safety Guidelines for Patients with Pacemakers - Medical Physicist Perspective

    International Nuclear Information System (INIS)

    James, J; Place, V; Panda, A; Edmonson, H; Felmlee, J; Pooley, R

    2014-01-01

    Purpose: Several institutions have developed MRI guidelines for patients with MR-unsafe or MR-conditional pacemakers. Here we highlight the role of a medical physicist in implementing these guidelines for non-pacemaker dependent patients. Guidelines: Implementing these guidelines requires involvement from several medical specialties and a strong collaboration with the site MRI supervisor to develop a structured workflow. A medical physicist is required to be present during the scan to supervise the MR scanning and to maintain a safety checklist that ensures: 1) uninterrupted patient communication with the technologist, 2) continuous patient physiologic monitoring (e.g. blood pressure and electrocardiography) by a trained nurse, 3) redundant patient vitals monitoring (e.g. pulse oximetry) due to the possibility of in vivo electrocardiography reading fluctuations during image acquisition. A radiologist is strongly recommended to be available to review the images before patients are discharged from the scanner. Pacemaker MRI should be restricted to 1.5T field strength. The MRI sequences should be optimized by the physicist with regards to: a) SAR: limited to <1.5 W/Kg for MR-unsafe pacemakers in normal operating mode, b) RF exposure time: <30 min, c) Coils: use T/R coils but not restricted to such, d) Artifacts: further optimization of sequences whenever image quality is compromised due to the pacemaker. In particular, cardiac, breast and left-shoulder MRIs are most susceptible to these artifacts. Possible strategies to lower the SAR include: a) BW reduction, 2) echo-train-length reduction, 3) increase TR, 4) decrease number of averages, 5) decrease flip angle, 6) reduce slices and/or a combination of all the options. Conclusion: A medical physicist in collaboration with the MR supervisor plays an important role in the supervision/implementation of safe MR scanning of pacemaker patients. Developing and establishing a workflow has enabled our institution to scan over

  7. Los Alamos National Laboratory corregated metal pipe saw facility preliminary safety analysis report. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-09-19

    This Preliminary Safety Analysis Report addresses site assessment, facility design and construction, and design operation of the processing systems in the Corrugated Metal Pipe Saw Facility with respect to normal and abnormal conditions. Potential hazards are identified, credible accidents relative to the operation of the facility and the process systems are analyzed, and the consequences of postulated accidents are presented. The risk associated with normal operations, abnormal operations, and natural phenomena are analyzed. The accident analysis presented shows that the impact of the facility will be acceptable for all foreseeable normal and abnormal conditions of operation. Specifically, under normal conditions the facility will have impacts within the limits posted by applicable DOE guidelines, and in accident conditions the facility will similarly meet or exceed the requirements of all applicable standards. 16 figs., 6 tabs.

  8. Seismic and tsunami safety margin assessment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Nuclear Regulation Authority is going to establish new seismic and tsunami safety guidelines to increase the safety of NPPs. The main purpose of this research is testing structures/components important to safety and tsunami resistant structures/components, and evaluating the capacity of them against earthquake and tsunami. Those capacity data will be utilized for the seismic and tsunami back-fit review based on the new seismic and tsunami safety guidelines. The summary of the program in 2012 is as follows. 1. Component seismic capacity test and quantitative seismic capacity evaluation. PWR emergency diesel generator partial-model seismic capacity tests have been conducted and quantitative seismic capacities have been evaluated. 2. Seismic capacity evaluation of switching-station electric equipment. Existing seismic test data investigation, specification survey and seismic response analyses have been conducted. 3. Tsunami capacity evaluation of anti-inundation measure facilities. Tsunami pressure test have been conducted utilizing a small breakwater model and evaluated basic characteristics of tsunami pressure against seawall structure. (author)

  9. Seismic and tsunami safety margin assessment

    International Nuclear Information System (INIS)

    2013-01-01

    Nuclear Regulation Authority is going to establish new seismic and tsunami safety guidelines to increase the safety of NPPs. The main purpose of this research is testing structures/components important to safety and tsunami resistant structures/components, and evaluating the capacity of them against earthquake and tsunami. Those capacity data will be utilized for the seismic and tsunami back-fit review based on the new seismic and tsunami safety guidelines. The summary of the program in 2012 is as follows. 1. Component seismic capacity test and quantitative seismic capacity evaluation. PWR emergency diesel generator partial-model seismic capacity tests have been conducted and quantitative seismic capacities have been evaluated. 2. Seismic capacity evaluation of switching-station electric equipment. Existing seismic test data investigation, specification survey and seismic response analyses have been conducted. 3. Tsunami capacity evaluation of anti-inundation measure facilities. Tsunami pressure test have been conducted utilizing a small breakwater model and evaluated basic characteristics of tsunami pressure against seawall structure. (author)

  10. Viability Assessment Volume 2

    International Nuclear Information System (INIS)

    1998-01-01

    This volume describes the major design features of the Monitored Geologic Repository. This document is not intended to provide an exhaustive, detailed description of the repository design. Rather, this document summarizes the major systems and primary elements of the design that are radiologically significant, and references the specific technical documents and design analyses wherein the details can be found. Not all portions of the design are at the same level of completeness. Highest priority has been given to assigning resources to advance the design of the Monitored Geologic Repository features that are important to radiological safety and/or waste isolation and for which there is no NRC licensing precedent. Those features that are important to radiological safety and/or waste isolation, but for which there is an NRC precedent, receive second priority. Systems and features that have no impact on radiological safety or waste isolation receive the lowest priority. This prioritization process, referred to as binning, is discussed in more detail in Section 2.3. Not every subject discussed in this volume is given equal treatment with regard to the level of detail provided. For example, less detail is provided for the surface facility design than for the subsurface and waste package designs. This different level of detail is intentional. Greater detail is provided for those functions, structures, systems, and components that play key roles with regard to protecting radiological health and safety and that are not common to existing nuclear facilities already licensed by NRC. A number of radiological subjects are not addressed in the VA, (e.g., environmental qualification of equipment). Environmental qualification of equipment and other radiological safety considerations will be addressed in the LA. Non-radiological safety considerations such as silica dust control and other occupational safety considerations are considered equally important but are not addressed in

  11. Evaluation and Customization of WHO Safety Checklist for Patient Safety in Otorhinolaryngology.

    Science.gov (United States)

    Dabholkar, Yogesh; Velankar, Haritosh; Suryanarayan, Sneha; Dabholkar, Twinkle Y; Saberwal, Akanksha A; Verma, Bhavika

    2018-03-01

    The WHO has designed a safe surgery checklist to enhance communication and awareness of patient safety during surgery and to minimise complications. WHO recommends that the check-list be evaluated and customised by end users as a tool to promote safe surgery. The aim of present study was to evaluate the impact of WHO safety checklist on patient safety awareness in otorhinolaryngology and to customise it for the speciality. A prospective structured questionnaire based study was done in ENT operating room for duration of 1 month each for cases, before and after implementation of safe surgery checklist. The feedback from respondents (surgeons, nurses and anaesthetists) was used to arrive at a customised checklist for otolaryngology as per WHO guidelines. The checklist significantly improved team member's awareness of patient's identity (from 17 to 86%) and each other's identity and roles (from 46 to 94%) and improved team communication (from 73 to 92%) in operation theatre. There was a significant improvement in preoperative check of equipment and critical events were discussed more frequently. The checklist could be effectively customised to suit otolaryngology needs as per WHO guidelines. The modified checklist needs to be validated by otolaryngology associations. We conclude from our study that the WHO Surgical safety check-list has a favourable impact on patient safety awareness, team-work and communication of operating team and can be customised for otolaryngology setting.

  12. Safety Precautions. Child Health and Safety Series (Module I).

    Science.gov (United States)

    Iscoe, Louise; And Others

    This manual for parents and child care personnel in day care homes and centers provides guidelines and information on indoor and outdoor safety precautions, emergency preparation and first aid. Contents focus on monitoring arrivals and departures, prevention of suffocation and strangulation, control of pets and other animals, preventing and…

  13. 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

  14. Guidelines for the content of records to support nuclear power plant operation, maintenance, and modification (NCIG-08): Volume 1, Guidelines: Final report

    International Nuclear Information System (INIS)

    Reedy, R.F.; Hegglin, D.P.

    1988-11-01

    The record systems at many nuclear power plant sites are becoming overloaded with unnecessary and superfluous records. The reason for this overload is that although the Codes and Standards list the record types to be retained, there is no definition for the contents of the records. This encourages varied interpretations which often lead to the approach of ''save everything''. This document provides guidelines for the content of records to support nuclear power plant operation, maintenance and modification. These Guidelines are based on an engineering approach to identify which data in the records are of ''significant value'' in (1) demonstrating capability for safe operation; (2) maintaining, reworking, repairing, replacing, or modifying an item; (3) determining the cause of an accident or malfunction of an item; and (4) providing required baseline data for in-service inspection. Particular topical issues affecting record retention needs, such as plant life extension activities, may require additional evaluation of data or records. By identifying the data to be retained in the records, it is possible to modify the record management system to substantially reduce the amount of unnecessary information being retained in the records. These Guidelines will provide for more uniform interpretation of requirements. The Guidelines are meant as an interpretation of current Codes, Standards and Regulatory Guides, and not as new requirements. Should any conflict exist between these Guidelines and the specified requirements of the NRC Regulations, the regulations govern. 4 tabs

  15. Nuclear power performance and safety. V.3. Safety and international co-operation

    International Nuclear Information System (INIS)

    1988-01-01

    The International Conference on Nuclear Power Performance and Safety, organized by the International Atomic Energy Agency, was held at the Austria Centre Vienna (ACV) in Vienna, Austria, from 28 September to 2 October 1987. The objective of the Conference was to promote an exchange of worldwide information on the current trends in the performance and safety of nuclear power and its fuel cycle, and to take a forward look at the expectations and objectives for the 1990s. This objective was accomplished through presentation and discussion of about 200 papers at the Conference. Almost 500 participants and observers from 40 countries and 12 organizations discussed three major questions which were posed as the focus of this Conference: (1) What are the current trends and major issues with regard to performance and safety of nuclear power, the nuclear fuel cycle and radioactive waste management? (2) What steps are being taken or need to be taken to resolve outstanding issues in order to improve the performance of nuclear power with assured safety? (3) What performance objectives and achievements can be anticipated for the 1990s? All presentations of this Conference were divided into six volumes. This is Volume 3 which is devoted to the problems of safety and international cooperation. All presentations of Volume 3 were divided into four sessions as follows: the need for safety in nuclear power programmes (4 papers); international cooperation in nuclear safety (6 papers); technical aspects in plant safety (7 papers); approaches to safety (3 papers). A separate abstract was prepared for each of these 20 papers. Refs, figs and tabs

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-03-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-03-15

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

  18. Operational safety

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The PNL Safety, Standards and Compliance Program contributed to the development and issuance of safety policies, standards, and criteria; for projects in the nuclear and nonnuclear areas. During 1976 the major emphasis was on developing criteria, instruments and methods to assure that radiation exposure to occupational personnel and to people in the environs of nuclear-related facilities is maintained at the lowest level technically and economically practicable. Progress in 1976 is reported on the preparation of guidelines for radiation exposure; Pu dosimetry studies; the preparation of an environmental monitoring handbook; and emergency instrumentation preparedness

  19. Australasian Gastrointestinal Trials Group (AGITG) Contouring Atlas and Planning Guidelines for Intensity-Modulated Radiotherapy in Anal Cancer

    International Nuclear Information System (INIS)

    Ng, Michael; Leong, Trevor; Chander, Sarat; Chu, Julie; Kneebone, Andrew; Carroll, Susan; Wiltshire, Kirsty; Ngan, Samuel; Kachnic, Lisa

    2012-01-01

    Purpose: To develop a high-resolution target volume atlas with intensity-modulated radiotherapy (IMRT) planning guidelines for the conformal treatment of anal cancer. Methods and Materials: A draft contouring atlas and planning guidelines for anal cancer IMRT were prepared at the Australasian Gastrointestinal Trials Group (AGITG) annual meeting in September 2010. An expert panel of radiation oncologists contoured an anal cancer case to generate discussion on recommendations regarding target definition for gross disease, elective nodal volumes, and organs at risk (OARs). Clinical target volume (CTV) and planning target volume (PTV) margins, dose fractionation, and other IMRT-specific issues were also addressed. A steering committee produced the final consensus guidelines. Results: Detailed contouring and planning guidelines and a high-resolution atlas are provided. Gross tumor and elective target volumes are described and pictorially depicted. All elective regions should be routinely contoured for all disease stages, with the possible exception of the inguinal and high pelvic nodes for select, early-stage T1N0. A 20-mm CTV margin for the primary, 10- to 20-mm CTV margin for involved nodes and a 7-mm CTV margin for the elective pelvic nodal groups are recommended, while respecting anatomical boundaries. A 5- to 10-mm PTV margin is suggested. When using a simultaneous integrated boost technique, a dose of 54 Gy in 30 fractions to gross disease and 45 Gy to elective nodes with chemotherapy is appropriate. Guidelines are provided for OAR delineation. Conclusion: These consensus planning guidelines and high-resolution atlas complement the existing Radiation Therapy Oncology Group (RTOG) elective nodal ano-rectal atlas and provide additional anatomic, clinical, and technical instructions to guide radiation oncologists in the planning and delivery of IMRT for anal cancer.

  20. Operational and environmental safety

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    The responsibility of the DOE Office of Operational and Environmental Safety is to assure that DOE-controlled activities are conducted in a manner that will minimize risks to the public and employees and will provide protection for property and the environment. The program supports the various energy technologies by identifying and resolving safety problems; developing and issuing safety policies, standards, and criteria; assuring compliance with DOE, Federal, and state safety regulations; and establishing procedures for reporting and investigating accidents in DOE operations. Guidelines for the radiation protection of personnel; radiation monitoring at nuclear facilities; an assessment of criticality accidents by fault tree analysis; and the preparation of environmental, safety, and health standards applicable to geothermal energy development are discussed

  1. EPRI BWR Water Chemistry Guidelines Revision

    International Nuclear Information System (INIS)

    Garcia, Susan E.; Giannelli, Joseph F.

    2014-01-01

    BWRVIP-190: BWR Water Chemistry Guidelines – 2008 Revision has been revised. The revision committee consisted of U.S. and non-U.S. utilities (members of the BWR Vessel and Internals Protection (BWRVIP) Mitigation Committee), reactor system manufacturers, fuel suppliers, and EPRI and industry experts. The revised document, BWRVIP-190 Revision 1, was completely reformatted into two volumes, with a simplified presentation of water chemistry control, diagnostic and good practice parameters in Volume 1 and the technical bases in Volume 2, to facilitate use. The revision was developed in parallel and in coordination with preparation of the Fuel Reliability Guidelines Revision 1: BWR Fuel Cladding Crud and Corrosion. Guidance is included for plants operating under normal water chemistry (NWC), moderate hydrogen water chemistry (HWC-M), and noble metal application (GE-Hitachi NobleChem™) plus hydrogen injection. Volume 1 includes significant changes to BWR feedwater and reactor water chemistry control parameters to provide increased assurance of intergranular stress corrosion cracking (IGSCC) mitigation of reactor materials and fuel reliability during all plant conditions, including cold shutdown (≤200°F (93°C)), startup/hot standby (>200°F (93°C) and ≤ 10%) and power operation (>10% power). Action Level values for chloride and sulfate have been tightened to minimize environmentally assisted cracking (EAC) of all wetted surfaces, including those not protected by hydrogen injection, with or without noble metals. Chemistry control guidance has been enhanced to minimize shutdown radiation fields by clarifying targets for depleted zinc oxide (DZO) injection while meeting requirements for fuel reliability. Improved tabular presentations of parameter values explicitly indicate levels at which actions are to be taken and required sampling frequencies. Volume 2 provides the technical bases for BWR water chemistry control for control of EAC, flow accelerated corrosion

  2. Nuclear safety and security culture - an integrated approach to regulatory oversight

    International Nuclear Information System (INIS)

    Tronea, M.; Ciurea Ercau, C.

    2013-01-01

    The paper presents the development and implementation of regulatory guidelines for the oversight of safety and security culture within licensees organizations. CNCAN (the National Commission for Nuclear Activities of Romania) has used the International Atomic Energy Agency (IAEA) attributes for a strong safety culture as the basis for its regulatory guidelines providing support to the reviewers and inspectors for recognizing and gathering information relevant to safety culture. These guidelines are in process of being extended to address also security culture, based on the IAEA Nuclear Security Series No. 7 document Nuclear Security Culture: Implementing Guide. Recognizing that safety and security cultures coexist and need to reinforce each other because they share the common objective of limiting risk and that similar regulatory review and inspection processes are in place for nuclear security oversight, an integrated approach is considered justified, moreover since the common elements of these cultures outweigh the differences. (authors)

  3. 46 CFR Appendix B to Subpart C to... - Substance Technical Guidelines, Benzene

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Substance Technical Guidelines, Benzene B Appendix B to... Subpart C to Part 197—Substance Technical Guidelines, Benzene I. Physical and Chemical Data (a) Substance... temperature: 580 °C (1076 °F). (3) Flammable limits in air, % by volume: Lower: 1.3%, Upper: 7.5%. (4...

  4. Preparation of the requirements for the safety regulation related to human and organizational factors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The outline of the project in the current fiscal year is to investigate and analyze issues associated with Human and Organizational Factors involved in incidents of nuclear facilities, and to study and develop evaluation methods of these countermeasures. The guideline to evaluate licensee's safety culture and root cause analysis (RCA) had been developed for further improving safety on nuclear power plants at 2007. These guidelines have been used at regulatory inspection since that time. Based on experience of using these existing guidelines, some activities for improving guidelines are now under investigation; these are selecting candidate quantitative indicators for safety culture evaluation and researching good practices for RCA issues. JNES implemented human factor analysis about 18 domestic events including the Fukushima Dai-ichi nuclear power plant accident. (author)

  5. Diet during pregnancy: Women's knowledge of and adherence to food safety guidelines.

    Science.gov (United States)

    Bryant, Jamie; Waller, Amy; Cameron, Emilie; Hure, Alexis; Sanson-Fisher, Rob

    2017-06-01

    As a precaution against acquiring food-borne illnesses, guidelines recommend women avoid some foods during pregnancy. To examine among women receiving antenatal care: (i) level of knowledge and self-reported adherence to guidelines about foods that should be avoided during pregnancy; and (ii) associated socio-demographic characteristics. Women attending a public outpatient clinic who were: pregnant or had recently given birth; 18 years or older; able to complete an English language survey with minimal assistance; and had at least one prior antenatal appointment for their current pregnancy, were asked to complete a cross-sectional survey. In total 223 women (64% consent rate) participated. Knowledge of foods to avoid during pregnancy was poor, with 83% of women incorrectly identifying at least one unsafe food as safe to consume. The average knowledge score for foods to avoid during pregnancy was 7.9 (standard deviation = 3.4; median = 9; interquartile range: 6-11; n = 218) out of a possible score of 12. Having more general practice (GP) visits for antenatal care and fewer tertiary antenatal visits were significantly associated with higher knowledge. Women with a higher number of GP visits and those receiving care in a high-risk clinic were more likely to be adherent to guidelines. The majority of pregnant women have poor knowledge of food avoidance guidelines and continue to consume foods that put them at risk. © 2016 The Royal Australian and New Zealand College of Obstetricians and Gynaecologists.

  6. Outlines of guidelines for the inspection and evaluation of reactor vessel internals

    International Nuclear Information System (INIS)

    Seki, Hiroaki; Kobayashi, Hiroyuki; Nakano, Morihito; Murai, Soutarou; Nomoto, Toshiharu

    2014-01-01

    'The guideline committee for the inspection and evaluation of Reactor Vessel Internals' of JANSI (Japan Nuclear Safety Institute) has been developing many guidelines based on principle which the conservative methodology, and covered both individual inspection method of reactor internals and application of repair methods for reactor internals. In this paper, some aspects of the JANSI-VIP-03 (Guidelines for the inspection and evaluation of Reactor Vessel Internals, revised Dec.2013) which is summary document of the committee activity, are introduced. (author)

  7. Risk management guidelines for petroleum storage tank sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-10-01

    These guidelines provide a site management process designed particularly for soil and groundwater pollution originating from existing or former petroleum storage tank (PST) facilities and provide uniform standards for the remediation of polluted PST sites in Alberta. The numerical criteria, risk management objectives and technical information described in this document were compiled from four documents including Remediation Guidelines for Petroleum Storage Tank Sites 1994, the Canada-Wide Standards for Petroleum Hydrocarbons in Soil, Alberta Soil and Water Quality Guidelines for Hydrocarbons at Upstream Oil and Gas Facilities, and Guidelines for Managing Risks at Contaminated Sites in Alberta. The changes in these updated guidelines reflect new remediation criteria and provide a process for determining alternate site-specific management objectives for more petroleum storage tank sites. The guidelines were developed using a risk-based approach that ensures the protection of human health, safety and the environment. The guidelines apply to aboveground and underground storage tank facilities that contain gasoline, diesel, heating oil, and aviation fuel. The guidelines specify requirements by Alberta Environment and the Alberta Fire Code. The chapter on risk management process included information on site investigation, determination of soil type, pollution source removal, land use assessment, selection of exposure pathways, depth of remediation, human inhalation and groundwater protection pathways, and verification of remediation. figs, 4 tabs., 2 appendices.

  8. Procedure guideline for radioiodine test (version 3)

    International Nuclear Information System (INIS)

    Dietlein, M.; Schicha, H.; Eschner, W.; Deutsche Gesellschaft fuer Medizinische Physik; Koeln Univ.; Lassmann, M.; Deutsche Gesellschaft fuer Medizinische Physik; Wuerzburg Univ.; Leisner, B.; Allgemeines Krankenhaus St. Georg, Hamburg; Reiners, C.; Wuerzburg Univ.

    2007-01-01

    The version 3 of the procedure guideline for radioiodine test is an update of the guideline previously published in 2003. The procedure guideline discusses the pros and cons of a single measurement or of repeated measurements of the iodine-131 uptake and their optimal timing. Different formulas are described when one, two or three values of the radioiodine kinetic are available. The probe with a sodium-iodine crystal, alternatively or additionally the gamma camera using the ROI-technique are instrumentations for the measurement of iodine-131 uptake. A possible source of error is an inappropriate measurement (sonography) of the target volume. The patients' preparation includes the withdrawal of antithyroid drugs 2-3 days before radioiodine administration. The patient has to avoid iodine-containing medication and the possibility of additives of iodine in vitamin- and electrolyte-supplementation has to be considered. (orig.)

  9. Safety on the Job. Some Guidelines for Working Safely. Instructor's Edition.

    Science.gov (United States)

    Oklahoma State Dept. of Vocational and Technical Education, Stillwater. Curriculum and Instructional Materials Center.

    This teacher's guide was developed to help teachers (especially in Oklahoma) promote safe practices on the job. As a supplement to existing programs in the requirements for job safety, this book can also promote same basic safety attitudes and help support basic safety concepts, with an emphasis on accident prevention. The guide contains eight…

  10. Food Safety: an Integral Part of Food Security

    International Nuclear Information System (INIS)

    Kilian, Lizette

    2012-01-01

    In recent years, many countries have developed integrated and harmonized food safety and quality control guidelines in accordance with national legislation and international standards to protect the health of consumers. But food safety standards alone are not enough. Radiation technology can complement and supplement existing technologies to ensure food security, safety and quality.

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

    Science.gov (United States)

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

    1991-01-01

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

  12. Commercial grade item (CGI) dedication of generators for nuclear safety related applications

    International Nuclear Information System (INIS)

    Das, R.K.; Hajos, L.G.

    1993-01-01

    The number of nuclear safety related equipment suppliers and the availability of spare and replacement parts designed specifically for nuclear safety related application are shrinking rapidly. These have made it necessary for utilities to apply commercial grade spare and replacement parts in nuclear safety related applications after implementing proper acceptance and dedication process to verify that such items conform with the requirements of their use in nuclear safety related application. The general guidelines for the commercial grade item (CGI) acceptance and dedication are provided in US Nuclear Regulatory Commission (NRC) Generic Letters and Electric Power Research Institute (EPRI) Report NP-5652, Guideline for the Utilization of Commercial Grade Items in Nuclear Safety Related Applications. This paper presents an application of these generic guidelines for procurement, acceptance, and dedication of a commercial grade generator for use as a standby generator at Salem Generating Station Units 1 and 2. The paper identifies the critical characteristics of the generator which once verified, will provide reasonable assurance that the generator will perform its intended safety function. The paper also delineates the method of verification of the critical characteristics through tests and provide acceptance criteria for the test results. The methodology presented in this paper may be used as specific guidelines for reliable and cost effective procurement and dedication of commercial grade generators for use as standby generators at nuclear power plants

  13. The development and evaluation of guidelines for the review of advanced human-system interfaces

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Wachtel, J.

    1992-01-01

    Advanced control rooms for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes a general approach to advanced human-system interface review, development of human factors guidelines to support NRC safety reviews of advanced systems, and the results of a guideline test and evaluation program

  14. Promotion and Support of Strong Safety Culture at the Hungarian Regulatory Body

    International Nuclear Information System (INIS)

    Bódis, Z.

    2016-01-01

    The Hungarian Atomic Energy Authority (HAEA) in 2014 carried out a self-assessment in order to preparation for IAEA IRRS mission. As a result of the SWOT analysis it was concluded that for the promotion, development and improvement of safety culture at the HAEA is displayed only on the policy level. In order to obtain a greater emphasis on safety culture within the organization a working group was created. The task of the working group was to define the proposed actions to develop the organizational safety culture. The working group reviewed the current situation, the international experiences and proposed on this basis the elaboration of a guideline regarding to organizational safety culture, to integrate this guideline into the organizational training program so as to apply to all levels of the organization and presentation of the safety culture as part of the training of new comers. Results so far: The working group has defined the main tasks and the connecting milestones in order to develop and improve the organizational safety culture at the HAEA. HAEA has elaborated a guideline for performing safety culture self-assessment based on IAEA and other relevant documents.

  15. Inventory of Federal energy-related environment and safety research for FY 1979. Volume II. Project listings and indexes

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

    This volume contains summaries of FY 1979 government-sponsored environment and safety research related to energy arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each contributing agency. Information elements included in the summary listings are project title, principal investigators, research organization, project number, contract number, supporting organization, funding level, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in the back of this volume.

  16. Inventory of Federal energy-related environment and safety research for FY 1979. Volume II. Project listings and indexes

    International Nuclear Information System (INIS)

    1980-12-01

    This volume contains summaries of FY 1979 government-sponsored environment and safety research related to energy arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each contributing agency. Information elements included in the summary listings are project title, principal investigators, research organization, project number, contract number, supporting organization, funding level, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in the back of this volume

  17. The potential carcinogenic risk of tanning beds: clinical guidelines and patient safety advice

    Directory of Open Access Journals (Sweden)

    Mette Mogensen

    2010-10-01

    Full Text Available Mette Mogensen1, Gregor BE Jemec21Department of Dermatology, Gentofte Hospital, Hellerup, Denmark; 2Department of Dermatology, Roskilde Hospital, Health Sciences Faculty, University of Copenhagen, Roskilde, DenmarkIntroduction: In 2009, the WHO listed ultraviolet (UV radiation as a group 1 carcinogen. In spite of this, each year, millions of people tan indoor in Western countries. The aim of this review is to summarize evidence of tanning bed carcinogenesis and to present guidelines for use of tanning beds and patient safety advice.Methods: A narrative review of the literature was conducted based on both PubMed and Medline searches and on literature review of the retrieved papers.Results: Use of indoor tanning beds represents a significant and avoidable risk factor for the development of both melanoma and nonmelanoma skin cancers. Frequent tanners are more often adolescent females. Tanning beds have additional potential adverse effects such as burns, solar skin damage, infection, and possibly also addictive behavior.Discussion: The effort in preventing UV light-induced carcinogenesis should currently be aimed at developing new strategies for public health information. Tanning beds are one preventable source of UV radiation. In the majority of people solar UV radiation continues to be the major factor and therefore anti-tanning campaigns must always include sunbathers.Keywords: tanning beds, skin cancers, melanoma, nonmelanoma

  18. Revision of the ICH guideline on detection of toxicity to reproduction for medicinal products: SWOT analysis.

    Science.gov (United States)

    Barrow, Paul

    2016-09-01

    SWOT analysis was used to gain insights and perspectives into the revision of the ICH S5(R2) guideline on detection of toxicity to reproduction for medicinal products. The current ICH guideline was rapidly adopted worldwide and has an excellent safety record for more than 20 years. The revised guideline should aim to further improve reproductive and developmental (DART) safety testing for new drugs. Alternative methods to animal experiments should be used whenever possible. Modern technology should be used to obtain high quality data from fewer animals. Additions to the guideline should include considerations on the following: limit dose setting, maternal toxicity, biopharmaceuticals, vaccines, testing strategies by indication, developmental immunotoxicity, and male-mediated developmental toxicity. Emerging issues, such as epigenetics and the microbiome, will most likely pose challenges to DART testing in the future. It is hoped that the new guideline will be adopted even outside the ICH regions. Copyright © 2016 Elsevier Inc. All rights reserved.

  19. Development of comprehensive HFE guidelines for the evaluation of NPP human systems interfaces

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Brown, W.S.; Wachtel, J.

    1994-01-01

    Advanced control room (ACR) concepts are being developed in the commercial nuclear power industry as part of future reactor designs. The ACRs will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the ways in which the operator interacts with and supervises an increasingly complex system. The US Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The NRC is developing guidelines to support its review of these advanced designs. This paper discusses (1) the development of guidelines for advanced HSI review, (2) the integration of those guidelines with existing guidance, and (3) a methodology for further guidance development

  20. Measure Guideline: Guide to Attic Air Sealing

    Energy Technology Data Exchange (ETDEWEB)

    Lstiburek, J.

    2014-09-01

    The Guide to Attic Air Sealing was completed in 2010 and although not in the standard Measure Guideline format, is intended to be a Measure Guideline on Attic Air Sealing. The guide was reviewed during two industry stakeholders meetings held on December 18th, 2009 and January 15th, 2010, and modified based on the comments received. Please do not make comments on the Building America format of this document. The purpose of the Guide to Attic Air Sealing is to provide information and recommendations for the preparation work necessary prior to adding attic insulation. Even though the purpose of this guide is to save energy - health, safety and durability should not be compromised by energy efficiency. Accordingly, combustion safety and ventilation for indoor air quality are addressed first. Durability and attic ventilation then follow. Finally, to maximize energy savings, air sealing is completed prior to insulating. The guide is intended for home remodelers, builders, insulation contractors, mechanical contractors, general contractors who have previously done remodeling and homeowners as a guide to the work that needs to be done.

  1. Inpatient Volume and Quality of Mental Health Care Among Patients With Unipolar Depression

    DEFF Research Database (Denmark)

    Rasmussen, Line Ryberg; Mainz, Jan; Jørgensen, Mette

    2018-01-01

    OBJECTIVE: The relationship between inpatient volume and the quality of mental health care remains unclear. This study examined the association between inpatient volume in psychiatric hospital wards and quality of mental health care among patients with depression admitted to wards in Denmark...... was assessed by receipt of process performance measures reflecting national clinical guidelines for care of depression. RESULTS: Compared with patients admitted to low-volume psychiatric hospital wards, patients admitted to very-high-volume wards were more likely to receive a high overall quality of mental...... wards was associated with a greater chance of receiving guideline-recommended process performance measures for care of depression....

  2. 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.

  3. Postoperative Radiotherapy for Prostate Cancer: A Comparison of Four Consensus Guidelines and Dosimetric Evaluation of 3D-CRT Versus Tomotherapy IMRT

    International Nuclear Information System (INIS)

    Malone, Shawn; Croke, Jennifer; Roustan-Delatour, Nicolas; Belanger, Eric; Avruch, Leonard; Malone, Colin; Morash, Christopher; Kayser, Cathleen; Underhill, Kathryn; Li Yan; Malone, Kyle; Nyiri, Balazs; Spaans, Johanna

    2012-01-01

    Purpose: Despite the benefits of adjuvant radiotherapy after radical prostatectomy, approximately one-half of patients relapse. Four consensus guidelines have been published (European Organization for Research and Treatment of Cancer, Faculty of Radiation Oncology Genito-Urinary Group, Princess Margaret Hospital, Radiation Therapy Oncology Group) with the aim of standardizing the clinical target volume (CTV) delineation and improve outcomes. To date, no attempt has been made to compare these guidelines in terms of treatment volumes or organ at risk (OAR) irradiation. The extent to which the guideline-derived plans meet the dosimetric constraints of present trials or of the Quantitative Analysis of Normal Tissue Effects in the Clinic (QUANTEC) trial is also unknown. Our study also explored the dosimetric benefits of intensity-modulated radiotherapy (IMRT). Methods and Materials: A total of 20 patients treated with postoperative RT were included. The three-dimensional conformal radiotherapy (3D-CRT) plans were applied to cover the guideline-generated planning target volumes (66 Gy in 33 fractions). Dose–volume histograms (DVHs) were analyzed for CTV/planning target volume coverage and to evaluate OAR irradiation. The OAR DVHs were compared with the constraints proposed in the QUANTEC and Radiotherapy and Androgen Deprivation In Combination After Local Surgery (RADICALS) trials. 3D-CRT plans were compared with the tomotherapy plans for the Radiation Therapy Oncology Group planning target volume to evaluate the advantages of IMRT. Results: The CTV differed significantly between guidelines (p < 0.001). The European Organization for Research and Treatment of Cancer-CTVs were significantly smaller than the other CTVs (p < 0.001). Differences in prostate bed coverage superiorly accounted for the major volumetric differences between the guidelines. Using 3D-CRT, the DVHs rarely met the QUANTEC or RADICALS rectal constraints, independent of the guideline used. The RADICALS

  4. Improving Safety through Human Factors Engineering.

    Science.gov (United States)

    Siewert, Bettina; Hochman, Mary G

    2015-10-01

    Human factors engineering (HFE) focuses on the design and analysis of interactive systems that involve people, technical equipment, and work environment. HFE is informed by knowledge of human characteristics. It complements existing patient safety efforts by specifically taking into consideration that, as humans, frontline staff will inevitably make mistakes. Therefore, the systems with which they interact should be designed for the anticipation and mitigation of human errors. The goal of HFE is to optimize the interaction of humans with their work environment and technical equipment to maximize safety and efficiency. Special safeguards include usability testing, standardization of processes, and use of checklists and forcing functions. However, the effectiveness of the safety program and resiliency of the organization depend on timely reporting of all safety events independent of patient harm, including perceived potential risks, bad outcomes that occur even when proper protocols have been followed, and episodes of "improvisation" when formal guidelines are found not to exist. Therefore, an institution must adopt a robust culture of safety, where the focus is shifted from blaming individuals for errors to preventing future errors, and where barriers to speaking up-including barriers introduced by steep authority gradients-are minimized. This requires creation of formal guidelines to address safety concerns, establishment of unified teams with open communication and shared responsibility for patient safety, and education of managers and senior physicians to perceive the reporting of safety concerns as a benefit rather than a threat. © RSNA, 2015.

  5. Basic concept of fuel safety design and assessment for sodium-cooled fast reactor

    International Nuclear Information System (INIS)

    Nakae, Nobuo; Baba, Toshikazu; Kamimura, Katsuichiro

    2013-03-01

    'Philosophy in Safety Evaluation of Fast Breeder Reactors' was published as a guideline for safety design and safety evaluation of Sodium-Cooled Fast Reactor in Japan. This guideline points out that cladding creep and swelling due to internal pressure should be taken into account since the fuel is used under high temperature and high burnup, and that fuel assembly deformation and the prevention from coolant channel blockage should be taken into account in viewpoints of nuclear and thermal hydraulic design. However, the requirements including their criteria and evaluation items are not described. Two other domestic guidelines related to core design are applied for fuel design of fast reactor, but the description is considered to not be enough to practically use. In addition, technical standard for nuclear fuel used in power reactors is also applied for fuel inspection. Therefore, the technical standard and guideline for fuel design and safety evaluation are considered to be very important issue for nuclear safety regulation. This document has been developed according to the following steps: The guidelines and the technical standards, which are prepared in foreign countries and international organization, were reviewed. The technical background concerning fuel design and safety evaluation for fast reactor was collected and summarized in the world wide scale. The basic concept of fuel safety design and assessment for sodium-cooled fast reactor was developed by considering a wide range of views of the specialists in Japan. In order to discuss the content with foreign specialists IAEA Consultancy Meetings have been held on January, 2011 and January, 2012. The participants of the meeting came from USA, UK, EC, India, China and South Korea. The specialists of IAEA and JNES were also joined. Although this document is prepared for application to 'Monju'(prototype LMFR), it may be applied to experimental, demonstration and commercial types of LMFR after revising it by taking

  6. The tolerability of risk from nuclear power stations: a discussion of the HSE's guidelines

    International Nuclear Information System (INIS)

    Ryder, E.A.; Woods, P.B.

    1989-01-01

    The Health and Safety Executive's discussion document, ''The Tolerability of risk from nuclear power stations'', published just a year ago considers the concept of risk and the broad principles of risk assessment and proposes guidelines on the tolerable levels of individual and societal risks from normal operation and from accidents at nuclear power stations. This paper discusses how these guidelines might be applied in safety assessments so as to ensure an acceptable level of safety and considers some of the problems inherent in the estimation of risk from nuclear power stations. It shows how the tolerable risk levels of the Health and Safety Executive's document are related to the standards used by HM Nuclear Installations Inspectorate when licensing nuclear installations. Some of the uncertainties in the estimation of acceptable risk are discussed as are the acceptance criteria used by the Inspectorate in its assessments of both normal and accident situations. (author)

  7. Plans to adapt Point Lepreau ageing management to new industry guidelines

    International Nuclear Information System (INIS)

    Greenlaw, G.; Gendron, T.; Slade, J.; Rankin, B.

    2008-01-01

    In preparation for PLGS life extension, NBPN spent considerable effort to evaluate the impact of ageing and to develop ageing management processes to maintain the required safety functions for extended operation. These were based on INPO AP-913. Recently, the CNSC has been developing Canadian ageing management guidelines in line with the IAEA approach. In response, NBPN plans to document how current PLGS processes meet the new CNSC guidelines and to identify any areas for improvement. Best practices from utilities that have retrofitted IAEA guidelines and PLGS experience in applying risk-based methods for ageing management will be used to implement improvements. (author)

  8. Guidelines and algorithms for managing the difficult airway.

    Science.gov (United States)

    Gómez-Ríos, M A; Gaitini, L; Matter, I; Somri, M

    2018-01-01

    The difficult airway constitutes a continuous challenge for anesthesiologists. Guidelines and algorithms are key to preserving patient safety, by recommending specific plans and strategies that address predicted or unexpected difficult airway. However, there are currently no "gold standard" algorithms or universally accepted standards. The aim of this article is to present a synthesis of the recommendations of the main guidelines and difficult airway algorithms. Copyright © 2017 Sociedad Española de Anestesiología, Reanimación y Terapéutica del Dolor. Publicado por Elsevier España, S.L.U. All rights reserved.

  9. European Patient Summary Guideline: Focus on Greece.

    Science.gov (United States)

    Berler, Alexander; Tagaris, Anastassios; Chronaki, Catherine

    2016-01-01

    The European Patient Summary (PS) guideline specifies a minimal dataset of essential and important information for unplanned or emergency care initially defined in the epSOS project with aim to improve patients' safety and quality of Care. The eHealth Network of European Union (EU) Member State (MS) representatives established under Article 14 of the EU directive 2011/24 on patient rights to cross-border healthcare adopted PS guideline in November 2013 and since then the guideline has been part of MS strategic eHealth implementation plans, standardization efforts, and concrete regional, national, European and international projects. This paper reviews implementation efforts for the implementation of an operational patient summary service in Greece drawing on challenges and lessons learned for sustainable standards-based large scale eHealth deployment in Europe and abroad, as well as the reuse of best practices from international standards and integration profiles.

  10. On results of aseismatic safety examination for atomic energy facilities based on Southern Hyogo Prefecture Earthquake in 1995

    International Nuclear Information System (INIS)

    1996-01-01

    The Nuclear Safety Commission received the report on the results of examination from the ad hoc examination committee. There was no particular effect to atomic energy facilities in the Southern Hyogo Prefecture Earthquake, however, from the viewpoint of perfecting the safety confirmation for atomic energy facilities, the Nuclear Safety Commission set up the aseismatic safety examination committee to investigate the validity of the guidelines related to aseismatic design used for safety examination. The basic plan of the investigation, the outline of the guidelines related to aseismatic design, the state of Southern Hyogo Prefecture Earthquake and the obtained knowledge and the investigation of the validity of the guidelines related to aseismatic design based on the state of Southern Hyogo Prefecture Earthquake are reported. The extraction of the items to be investigated, the evaluation of earthquakes and earthquake motion, vertical earthquake force and active faults, and the way of thinking on right under type earthquakes in the guideline for aseismatic design examination are reported. It was confirmed that the validity of guidelines is not impaired by the earthquake. (K.I.)

  11. The management and disposal of radioactive wastes - safety principles and guidelines

    International Nuclear Information System (INIS)

    Linsley, G.; Bell, M.; Saire, D.

    1991-01-01

    This paper describes the current plans for the establishment of the Radioactive Waste Safety Standards (RADWASS), a new series of IAEA documents in the Safety Series category intended to set out internationally agreed approaches to the safe management and disposal or radioactive waste. RADWASS is being implemented to document the harmonization which exists in the approaches to establishing safety in the field of radioactive waste management and disposal at the international level. (au)

  12. Status of safety issues at licensed power plants

    International Nuclear Information System (INIS)

    1991-06-01

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

  13. Proposed risk evaluation guidelines for use by the DOE-AL Nuclear Explosive Safety Division in evaluating proposed shipments of nuclear components

    International Nuclear Information System (INIS)

    Just, R.A.; Love, A.F.

    1997-10-01

    The licensing requirements of 10 CFR 71 (US Code of Federal Regulations) are the primary criteria used to license proposed US Department of Energy (DOE) shipments of nuclear components. However, if a shipment cannot meet 10 CFR 71 requirements, a Transportation System Risk Assessment (TSRA) is prepared to document: (1) the degree of compliance of proposed DOE shipments of nuclear components with applicable federal regulations, and (2) the risk associated with the proposed shipments. The Nuclear Explosive Safety Division (NESD) of the Department of Energy, Albuquerque Area Office (DOE-AL) is responsible for evaluating TSRAs and for preparing Safety Evaluation Reports (SERs) to authorize the off-site transport. Hazards associated with the transport may include the presence of fissile material, chemically and radiologically toxic uranium, and ionizing radiation. The Nuclear Regulatory Commission (NRC) has historically considered only radiological hazards in licensing the transport of radiological material because the US Department of Transportation considers licensing requirements of nonradiological (i.e., chemically toxic) hazards. The requirements of 10 CFR 71 are based primarily on consideration of radiological hazards. For completeness, this report provides information for assessing the effects of chemical toxicity. Evaluating the degree of compliance with the requirements of 10 CFR 71 is relatively straightforward. However, there are few precedents associated with developing TSRA risk assessments for packages that do not comply with all of the requirements of 10 CFR 71. The objective of the task is to develop Risk Evaluation Guidelines for DOE-AL to use when evaluating a TSRA. If the TSRA shows that the Risk Evaluation Guidelines are not exceeded, then from a risk perspective the TSRA should be approved if there is evidence that the ALARA (as low as reasonably achievable) principle has been applied

  14. Total safety management: An approach to improving safety culture

    International Nuclear Information System (INIS)

    Blush, S.M.

    1993-01-01

    A little over 4 yr ago, Admiral James D. Watkins became Secretary of Energy. President Bush, who had appointed him, informed Watkins that his principal task would be to clean up the nuclear weapons complex and put the US Department of Energy (DOE) back in the business of producing tritium for the nation's nuclear deterrent. Watkins recognized that in order to achieve these objectives, he would have to substantially improve the DOE's safety culture. Safety culture is a relatively new term. The International Atomic Energy Agency (IAEA) used it in a 1986 report on the root causes of the Chernobyl nuclear accident. In 1990, the IAEA's International Nuclear Safety Advisory Group issued a document focusing directly on safety culture. It provides guidelines to the international nuclear community for measuring the effectiveness of safety culture in nuclear organizations. Safety culture has two principal aspects: an organizational framework conducive to safety and the necessary organizational and individual attitudes that promote safety. These obviously go hand in hand. An organization must create the right framework to foster the right attitudes, but individuals must have the right attitudes to create the organizational framework that will support a good safety culture. The difficulty in developing such a synergistic relationship suggests that achieving and sustaining a strong safety culture is not easy, particularly in an organization whose safety culture is in serious disrepair

  15. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 3: Thermal hydraulic research and codes; Digital instrumentation and control; Structural performance

    International Nuclear Information System (INIS)

    Monteleone, S.

    1998-04-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) thermal hydraulic research and codes; (2) digital instrumentation and control; (3) structural performance

  16. Guidelines for the structural design of experimental multi-purpose VHTR at the elevated temperature services

    International Nuclear Information System (INIS)

    Nomura, Sueo; Uga, Takeo; Miyamoto, Yoshiaki; Muto, Yasushi; Ikushima, Takeshi

    1976-02-01

    The guidelines are presented for structural design of the experimental multi-purpose VHTR(Very High Temperature Reactor) at the elevated temperature services. Covered are features of the VHTR structural design, specifications, safety design, seismic design, failure modes to be considered, stress criteria for various load combinations and the mechanical properties of the materials. The guidelines were prepared by referring to safety criteria of high-temperature gas cooled reactors, ASME Boiler and Pressure Vessel code, Section III, case 1592 and the domestic seismic design guide of nuclear power facilities. (auth.)

  17. Twenty-third water reactor safety information meeting. Volume 3, structural and seismic engineering, primary systems integrity, equipment operability and aging, ECCS strainer blockage research and regulatory issues

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 3, presents topics in Structural & Seismic Engineering, Primary Systems Integrity, Equipment Operability and Aging, and ECCS Strainer Blockage Research & Regulatory Issues. Individual papers have been cataloged separately.

  18. Twenty-third water reactor safety information meeting. Volume 3, structural and seismic engineering, primary systems integrity, equipment operability and aging, ECCS strainer blockage research and regulatory issues

    International Nuclear Information System (INIS)

    Monteleone, S.

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 3, presents topics in Structural ampersand Seismic Engineering, Primary Systems Integrity, Equipment Operability and Aging, and ECCS Strainer Blockage Research ampersand Regulatory Issues. Individual papers have been cataloged separately

  19. Seismic Safety Guide

    International Nuclear Information System (INIS)

    Eagling, D.G.

    1985-01-01

    The Seismic Safety Guide provides facilities managers with practical guidelines for administering a comprehensive earthquake safety program. Most facilities managers, unfamiliar with earthquake engineering, tend to look for answers in techniques more sophisticated than required to solve the actual problems in earthquake safety. Often the approach to solutions to these problems is so academic, legalistic, and financially overwhelming that mitigation of actual seismic hazards simply does not get done in a timely, cost-effective way. The objective of the Guide is to provide practical advice about earthquake safety so that managers and engineers can get the job done without falling into common pitfalls, prolonged diagnosis, and unnecessary costs. It is comprehensive with respect to earthquakes in that it covers the most important aspects of natural hazards, site planning, rehabilitation of existing buildings, design of new facilities, operational safety, emergency planning, non-structural elements, life lines, and risk management. 5 references

  20. Guidelines for optimization of planar HDR implants

    International Nuclear Information System (INIS)

    Zwicker, R.D.; Schmidt-Ullrich, R.

    1996-01-01

    Purpose: Conventional low dose rate (LDR) planar Ir-192 implants are typically carried out using at most a few different source strengths. Remote afterloading offers a much higher degree of flexibility with individually programmable dwell times. Dedicated software is available to generate individual dwell times producing isodose surfaces which contour as closely as possible the target volume. The success of these algorithms in enclosing the target volume while sparing normal tissues is dependent on the positioning of the source guides which constrain the dwell points. In this work we provide source placement guidelines for optimal coverage and dose uniformity in planar high dose rate (HDR) implants. The resulting distributions are compared with LDR treatments in terms of dose uniformity and early and late tissue effects. Materials and methods: Computer studies were undertaken to determine source positions and dwell times for optimal dose uniformity in planar HDR implants, and the results were compared to those obtained using corresponding LDR implant geometries. The improvements in the dose distributions achieved with the remote after loader are expected to help offset the increased late tissue effects which can occur when LDR irradiation is replaced with a few large HDR fractions. Equivalent differential volume-dose (DVD) curves for early and late effects were calculated for different numbers of HDR fractions using a linear-quadratic model and compared to the corresponding curves for the LDR regime. Results: Tables of source placement parameters were generated as guidelines for achieving highly homogeneous planar HDR dose distributions. Differential volume-dose data generated inside the target volume provide a quantitative measure of the improvement in real dose homogeneity obtained with remote afterloading. The net result is a shift of the peak in the DVD curve toward lower doses relative to the LDR implant. The equivalent DVD curves for late effects obtained

  1. Rethinking wood dust safety standards

    OpenAIRE

    Ratnasingam, Jega; Wai, Lim Tau; Ramasamy, Geetha; Ioras, Florin; Tadin, Ishak; Universiti Putra Malaysia; Buckinghamshire New University; Centre for Occupational Safety and Health Singapore

    2015-01-01

    The current universal work safety and health standards pertaining to wood dust in factories lack the localisation required. As a study has shown, there is a urgent need to reevaluate the current guidelines and practices.

  2. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-20

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

  3. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    International Nuclear Information System (INIS)

    1994-01-01

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

  4. On application of CFD codes to problems of nuclear reactor safety

    International Nuclear Information System (INIS)

    Muehlbauer, Petr

    2005-01-01

    The 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems' held in May 2002 at Aix-en-Province, France, recommended formation of writing groups to report the need of guidelines for use and assessment of CFD in single-phase nuclear reactor safety problems, and on recommended extensions to CFD codes to meet the needs of two-phase problems in nuclear reactor safety. This recommendations was supported also by Working Group on the Analysis and Management of Accidents and led to formation oaf three Writing Groups. The first writing Group prepared a summary of existing best practice guidelines for single phase CFD analysis and made a recommendation on the need for nuclear reactor safety specific guidelines. The second Writing Group selected those nuclear reactor safety applications for which understanding requires or is significantly enhanced by single-phase CFD analysis, and proposed a methodology for establishing assesment matrices relevant to nuclear reactor safety applications. The third writing group performed a classification of nuclear reactor safety problems where extension of CFD to two-phase flow may bring real benefit, a classification of different modeling approaches, and specification and analysis of needs in terms of physical and numerical assessments. This presentation provides a review of these activities with the most important conclusions and recommendations (Authors)

  5. [Evidence-based clinical oral healthcare guidelines 4. Adherence requires an implementation strategy].

    Science.gov (United States)

    Braspenning, J C C; Mettes, T G P H; van der Sanden, W J M; Wensing, M J P

    2015-03-01

    Adherence to clinical guidelines requires support in practice. However, systematic implementation of evidence-based guidelines is not common practice in oral healthcare. The Knowledge Institute Oral Care (KiMo) offers the opportunity to take into account potential barriers and facilitators during the development of evidence-based clinical practice guidelines. These factors which are relevant to the guideline and the oral healthcare practice provide the ingredients for a tailor-made programme of implementation that has a scientific basis. Elements of any implementation programme are the quality indicators derived from the oral healthcare guidelines. These indicators should fit, on the one hand, the specific goals of the guidelines (patient safety, effectiveness, efficiency, patient-centred, timeliness, accessibility) and, onthe other hand, the various perspectives of the different stakeholders, such as patients, caregivers, health insurers and inspectorate. These quality indicators provide information on adherence to the guidelines, the results of a certain treatment and the success of the implementation strategy, all with the aim to improve the quality of oral healthcare.

  6. Guideline for the procedure of preparing and executing of maintenance and modifications in nuclear power plants (dated May 10th, 1978)

    International Nuclear Information System (INIS)

    1978-01-01

    Based on the terms defined for this guideline and on legal provisions, it is the purpose of this guideline to render a contribution to the guaranteeing of safe operation and to foster the safety of work while taking the safety of the plant into account by means of a uniform procedure for the preparation and execution of maintenance and modifications carried out in nuclear power plants. The criteria to be taken into account and the procedural steps necessary, organisational measures and controls, technical aspects to be taken into account and determinations to be made are given. Matters concerning plant safety (protection of objects) are pointed out, if they are to be taken into account as marginal conditions when determining measures for the safety of work and the safety of the plant. The guideline serves as a basis for the set-up and assessment of a maintenance-regulation adapted to the resp. organisation of the plant and for the elaboration and check-up of the detailed complementary documents as e.g. accident report blanks, cut-off blanks and safety certificates. (orig.) [de

  7. 41 CFR 102-34.250 - Do Federal employees in Government motor vehicles have to use all safety devices and follow all...

    Science.gov (United States)

    2010-07-01

    ... safety devices and follow all safety guidelines? Yes, Federal employees in Government motor vehicles have... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Do Federal employees in Government motor vehicles have to use all safety devices and follow all safety guidelines? 102-34.250 Section...

  8. Cycling in the African American Community : safety training guidelines and findings.

    Science.gov (United States)

    2013-08-01

    This report is a program users manual for the Cycling in the African American Community (CAAC) safety training intervention. The CAAC safety training intervention was designed to nudge more African Americans, who are often beginning cyclists...

  9. Management response plan for the Chemical Safety Vulnerability Working Group report. Volume 2

    International Nuclear Information System (INIS)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 146 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. To address the facility-specific and site-specific vulnerabilities, responsible DOE and site-contractor line organizations have developed initial site response plans. These plans, presented as Volume 2 of this Management Response Plan, describe the actions needed to mitigate or eliminate the facility- and site-specific vulnerabilities identified by the CSV Working Group field verification teams. Initial site response plans are described for: Brookhaven National Lab., Hanford Site, Idaho National Engineering Lab., Lawrence Livermore National Lab., Los Alamos National Lab., Oak Ridge Reservation, Rocky Flats Plant, Sandia National Laboratories, and Savannah River Site

  10. Layout of the safety analysis report for nuclear power plants with pressurized water reactor or boiling water reactor in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Albrecht, E.

    1980-01-01

    For a licence according to paragraph 7 of the Atomic Energy Act to construct and operate a nuclear power plant, the applicant has to submit a safety analysis report, which must describe the site, the plant, all hazards in connection with the plant and the proposed safety precautions. For the structure and the content of a safety analysis report, a first guideline was published in 1959. Only a few safety analysis reports were prepared nearly strictly according to this guideline. In 1976 a second guideline was published for a standard safety analysis report. The lecture deals with the guidelines. A survey over the structure and content of the German safety analysis reports will be given. The experience gained by the new safety analysis reports will be discussed. (orig.)

  11. Guidelines for the verification and validation of expert system software and conventional software: Project summary. Volume 1

    International Nuclear Information System (INIS)

    Mirsky, S.M.; Hayes, J.E.; Miller, L.A.

    1995-03-01

    This eight-volume report presents guidelines for performing verification and validation (V ampersand V) on Artificial Intelligence (Al) systems with nuclear applications. The guidelines have much broader application than just expert systems; they are also applicable to object-oriented programming systems, rule-based systems, frame-based systems, model-based systems, neural nets, genetic algorithms, and conventional software systems. This is because many of the components of AI systems are implemented in conventional procedural programming languages, so there is no real distinction. The report examines the state of the art in verifying and validating expert systems. V ampersand V methods traditionally applied to conventional software systems are evaluated for their applicability to expert systems. One hundred fifty-three conventional techniques are identified and evaluated. These methods are found to be useful for at least some of the components of expert systems, frame-based systems, and object-oriented systems. A taxonomy of 52 defect types and their delectability by the 153 methods is presented. With specific regard to expert systems, conventional V ampersand V methods were found to apply well to all the components of the expert system with the exception of the knowledge base. The knowledge base requires extension of the existing methods. Several innovative static verification and validation methods for expert systems have been identified and are described here, including a method for checking the knowledge base open-quotes semanticsclose quotes and a method for generating validation scenarios. Evaluation of some of these methods was performed both analytically and experimentally. A V ampersand V methodology for expert systems is presented based on three factors: (1) a system's judged need for V ampersand V (based in turn on its complexity and degree of required integrity); (2) the life-cycle phase; and (3) the system component being tested

  12. Guidelines for the verification and validation of expert system software and conventional software: Project summary. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Mirsky, S.M.; Hayes, J.E.; Miller, L.A. [Science Applications International Corp., McLean, VA (United States)

    1995-03-01

    This eight-volume report presents guidelines for performing verification and validation (V&V) on Artificial Intelligence (Al) systems with nuclear applications. The guidelines have much broader application than just expert systems; they are also applicable to object-oriented programming systems, rule-based systems, frame-based systems, model-based systems, neural nets, genetic algorithms, and conventional software systems. This is because many of the components of AI systems are implemented in conventional procedural programming languages, so there is no real distinction. The report examines the state of the art in verifying and validating expert systems. V&V methods traditionally applied to conventional software systems are evaluated for their applicability to expert systems. One hundred fifty-three conventional techniques are identified and evaluated. These methods are found to be useful for at least some of the components of expert systems, frame-based systems, and object-oriented systems. A taxonomy of 52 defect types and their delectability by the 153 methods is presented. With specific regard to expert systems, conventional V&V methods were found to apply well to all the components of the expert system with the exception of the knowledge base. The knowledge base requires extension of the existing methods. Several innovative static verification and validation methods for expert systems have been identified and are described here, including a method for checking the knowledge base {open_quotes}semantics{close_quotes} and a method for generating validation scenarios. Evaluation of some of these methods was performed both analytically and experimentally. A V&V methodology for expert systems is presented based on three factors: (1) a system`s judged need for V&V (based in turn on its complexity and degree of required integrity); (2) the life-cycle phase; and (3) the system component being tested.

  13. Impact of Construction Health & Safety Regulations on Project ...

    African Journals Online (AJOL)

    Impact of Construction Health & Safety Regulations on Project Parameters in Nigeria: Consultants and Contractors View. ... The study recommends that better attention is given to health and safety should as a project parameter and that related practice notes and guidelines should be evolved for all project stakeholders.

  14. Steam generator tube fitness-for-service guidelines

    International Nuclear Information System (INIS)

    Gorman, J.A.; Harris, J.E.; Lowenstein, D.B.

    1995-07-01

    The objectives of this project were to characterize defect mechanisms which could affect the integrity of steam generator tubes, to review and critique state-of-the-art Canadian and international steam generator tube fitness-for-service criteria and guidelines, and to obtain recommendations for criteria that could be used to assess fitness-for service guidelines for steam generator tubes containing defects in Canadian power plant service. Degradation mechanisms, that could affect CANDU steam generator tubes in Canada, have been characterized. The design standards and safety criteria that apply to steam generator tubing in nuclear power plant service in Canada and in Belgium, France, Japan, Spain, Sweden, and the USA have been reviewed and described. The fitness-for-service guidelines used for a variety of specific defect types in Canada and internationally have been evaluated and described in detail in order to highlight the considerations involved in developing such defect specific guidelines. Existing procedures for defect assessment and disposition have been identified, including inspection and examination practices. The approaches used in Canada and in Belgium, France, Japan, Spain, Sweden, and the USA for fitness-for-service guidelines were compared and contrasted for a variety of defect mechanisms. The strengths and weaknesses of the various approaches have been assessed. The report presents recommendations on approaches that may be adopted in the development of fitness-for-service guidelines for use in the dispositioning of steam generator tubing defects in Canada. (author). 175 refs., 2 tabs., 28 figs

  15. Development of guidelines to review advanced human-system interfaces

    International Nuclear Information System (INIS)

    O'Hara, J.M.

    1993-01-01

    Advanced control rooms (ACRS) will utilize advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operators overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The US Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well prior to these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this paper is to discuss the development, evaluation, and current status of the Advanced HSI Design Review Guideline, hereafter referred to as the ''Guideline.''

  16. Improved safety at CERN

    CERN Multimedia

    2006-01-01

    As announced in Weekly Bulletin No. 43/2006, a new approach to the implementation of Safety at CERN has been decided, which required taking some managerial decisions. The guidelines of the new approach are described in the document 'New approach to Safety implementation at CERN', which also summarizes the main managerial decisions I have taken to strengthen compliance with the CERN Safety policy and Rules. To this end I have also reviewed the mandates of the Safety Commission and the Safety Policy Committee (SAPOCO). Some details of the document 'Safety Policy at CERN' (also known as SAPOCO42) have been modified accordingly; its essential principles, unchanged, remain the basis for the safety policy of the Organisation. I would also like to inform you that I have appointed Dr M. Bona as the new Head of the Safety Commission until 31.12.2008, and that I will proceed soon to the appointment of the members of the new Safety Policy Committee. All members of the personnel are deemed to have taken note of the d...

  17. Application of the international guidelines for machinery breakdown prevention at nuclear power plants

    International Nuclear Information System (INIS)

    Wendland, W.G.

    2001-01-01

    For more than forty years as a specialized branch of the worldwide insurance industry, the nuclear insurance pools have underwritten property damage protection for nuclear facilities throughout the world. At power plants insured by the pools, an enviable record of operational safety has been attained. Nevertheless, electrical and mechanical equipment does break down occasionally. Although these failures do not necessarily compromise nuclear safety, they can cause significant damage to equipment, leading to a considerable loss of generating revenue and causing sizeable insurance losses. Since insurance companies have a large financial stake in nuclear power plants, their goal is to minimize insurance losses, including the failure of systems and equipment and ensuing consequential damages. To ensure that the insurance risk is properly underwritten, insurance companies analyze loss information, develop loss prevention guidelines and focus loss control activities on those areas where insurance risk is most significant. This paper provides a chronology of the development of the ''International Guidelines for Machinery Breakdown Prevention at Nuclear Power Plants'' and describes the results of insurance inspections conducted using these guidelines. Included is a summary of guideline content and of insurance loss experience between 1962 and 1999. (author)

  18. Measure Guideline: Guide to Attic Air Sealing

    Energy Technology Data Exchange (ETDEWEB)

    Lstiburek, Joseph [Building Science Corporation, Westford, MA (United States)

    2014-09-01

    The purpose of this measure guideline is to provide information and recommendations for the preparation work necessary prior to adding attic insulation. Even though the purpose of this guide is to save energy, health, safety, and durability should not be compromised by energy efficiency. Accordingly, combustion safety and ventilation for indoor air quality are addressed first. Durability and attic ventilation then follow. Finally, to maximize energy savings, air sealing is completed prior to insulating. The guide is intended for home remodelers, builders, insulation contractors, mechanical contractors, general contractors who have previously done remodeling and homeowners as a guide to the work that needs to be done.

  19. Study on 'Safety qualification of process computers used in safety systems of nuclear power plants'

    International Nuclear Information System (INIS)

    Bertsche, K.; Hoermann, E.

    1991-01-01

    The study aims at developing safety standards for hardware and software of computer systems which are increasingly used also for important safety systems in nuclear power plants. The survey of the present state-of-the-art of safety requirements and specifications for safety-relevant systems and, additionally, for process computer systems has been compiled from national and foreign rules. In the Federal Republic of Germany the KTA safety guides and the BMI/BMU safety criteria have to be observed. For the design of future computer-aided systems in nuclear power plants it will be necessary to apply the guidelines in [DIN-880] and [DKE-714] together with [DIN-192]. With the aid of a risk graph the various functions of a system, or of a subsystem, can be evaluated with regard to their significance for safety engineering. (orig./HP) [de

  20. The approaches of safety design and safety evaluation at HTTR (High Temperature Engineering Test Reactor)

    International Nuclear Information System (INIS)

    Iigaki, Kazuhiko; Saikusa, Akio; Sawahata, Hiroaki; Shinozaki, Masayuki; Tochio, Daisuke; Honma, Fumitaka; Tachibana, Yukio; Iyoku, Tatsuo; Kawasaki, Kozo; Baba, Osamu

    2006-06-01

    Gas Cooled Reactor has long history of nuclear development, and High Temperature Gas Cooled Reactor (HTGR) has been expected that it can be supply high temperature energy to chemical industry and to power generation from the points of view of the safety, the efficiency, the environment and the economy. The HTGR design is tried to installed passive safety equipment. The current licensing review guideline was made for a Low Water Reactor (LWR) on safety evaluation therefore if it would be directly utilized in the HTGR it needs the special consideration for the HTGR. This paper describes that investigation result of the safety design and the safety evaluation traditions for the HTGR, comparison the safety design and safety evaluation feature for the HTGT with it's the LWR, and reflection for next HTGR based on HTTR operational experiment. (author)

  1. Consensus Guidelines and Contouring Atlas for Pelvic Node Delineation in Prostate and Pelvic Node Intensity Modulated Radiation Therapy

    Energy Technology Data Exchange (ETDEWEB)

    Harris, Victoria A. [Academic Urology Unit, Institute of Cancer Research and Royal Marsden NHS Foundation Trust, London (United Kingdom); Staffurth, John [Institute of Cancer and Genetics, School of Medicine, Cardiff University, Cardiff, Wales (United Kingdom); Naismith, Olivia [Joint Department of Physics, Institute of Cancer Research, and Royal Marsden NHS Foundation Trust, London (United Kingdom); Esmail, Alikhan [Ipswich Hospital NHS Foundation Trust, Ipswich (United Kingdom); Gulliford, Sarah [Joint Department of Physics, Institute of Cancer Research, and Royal Marsden NHS Foundation Trust, London (United Kingdom); Khoo, Vincent [Department of Radiotherapy, The Royal Marsden NHS Foundation Trust, London (United Kingdom); Lewis, Rebecca [Clinical Trials and Statistics Unit, Institute of Cancer Research, London (United Kingdom); Littler, John [Clatterbridge Cancer Centre, Liverpool (United Kingdom); McNair, Helen [Department of Radiotherapy, The Royal Marsden NHS Foundation Trust, London (United Kingdom); Sadoyze, Azmat [Beatson West of Scotland Cancer Centre, Scotland, Glasgow (United Kingdom); Scrase, Christopher [Ipswich Hospital NHS Foundation Trust, Ipswich (United Kingdom); Sohaib, Aslam [Department of Radiology, The Royal Marsden NHS Foundation Trust, London (United Kingdom); Syndikus, Isabel [Clatterbridge Cancer Centre, Liverpool (United Kingdom); Zarkar, Anjali [University Hospitals Birmingham NHS Foundation Trust, Birmingham (United Kingdom); Hall, Emma [Clinical Trials and Statistics Unit, Institute of Cancer Research, London (United Kingdom); Dearnaley, David, E-mail: David.Dearnaley@icr.ac.uk [Academic Urology Unit, Institute of Cancer Research and Royal Marsden NHS Foundation Trust, London (United Kingdom)

    2015-07-15

    Purpose: The purpose of this study was to establish reproducible guidelines for delineating the clinical target volume (CTV) of the pelvic lymph nodes (LN) by combining the freehand Royal Marsden Hospital (RMH) and Radiation Therapy Oncology Group (RTOG) vascular expansion techniques. Methods and Materials: Seven patients with prostate cancer underwent standard planning computed tomography scanning. Four different CTVs (RMH, RTOG, modified RTOG, and Prostate and pelvIs Versus prOsTate Alone treatment for Locally advanced prostate cancer [PIVOTAL] trial) were created for each patient, and 6 different bowel expansion margins (BEM) were created to assess bowel avoidance by the CTV. The resulting CTVs were compared visually and by using Jaccard conformity indices. The volume of overlap between bowel and planning target volume (PTV) was measured to aid selection of an appropriate BEM to enable maximal LN yet minimal normal tissue coverage. Results: In total, 84 nodal contours were evaluated. LN coverage was similar in all groups, with all of the vascular-expansion techniques (RTOG, modified RTOG, and PIVOTAL), resulting in larger CTVs than that of the RMH technique (mean volumes: 287.3 cm{sup 3}, 326.7 cm{sup 3}, 310.3 cm{sup 3}, and 256.7 cm{sup 3}, respectively). Mean volumes of bowel within the modified RTOG PTV were 19.5 cm{sup 3} (with 0 mm BEM), 17.4 cm{sup 3} (1-mm BEM), 10.8 cm{sup 3} (2-mm BEM), 6.9 cm{sup 3} (3-mm BEM), 5.0 cm{sup 3} (4-mm BEM), and 1.4 cm{sup 3} (5-mm BEM) in comparison with an overlap of 9.2 cm{sup 3} seen using the RMH technique. Evaluation of conformity between LN-CTVs from each technique revealed similar volumes and coverage. Conclusions: Vascular expansion techniques result in larger LN-CTVs than the freehand RMH technique. Because the RMH technique is supported by phase 1 and 2 trial safety data, we proposed modifications to the RTOG technique, including the addition of a 3-mm BEM, which resulted in LN-CTV coverage similar

  2. Draft revision of human factors guideline HF-010

    International Nuclear Information System (INIS)

    Lee, Hyun Chul; Lee, Yong Hee; Oh, In Seok; Lee, Jung Woon; Cha, Woo Chang; Lee, Dhong Ha

    2003-05-01

    The Application of Human Factors to the design of Man-Machine Interfaces System(MMIS) in the nuclear power plant is essential to the safety and productivity of the nuclear power plants, human factors standards and guidelines as well as human factors analysis methods and experiments are weightily used to the design application. A Korean engineering company has developed a human factors engineering guideline, so-call HF-010, and has used it for human factors design, however the revision of HF-010 is necessary owing to lack of the contents related to the advanced MMI(Man-Machine Interfaces). As the results of the reviews of HF-010, it is found out that the revision of Section 9. Computer Displays of HF-010 is urgent, thus the revision was drafted on the basis of integrated human factors design guidelines for VDT, human factors design guidelines for PMAS SPADES display, human factors design guidelines for PMAS alarm display, and human factors design guidelines for electronic displays developed by the surveillance and operation support project of KOICS. The draft revision of HF-010 Section 9 proposed in this report can be utilized for the human factors design of the advanced MMI, and the high practical usability of the draft can be kept up through the continuous revision according to the advancement of digital technology

  3. Trends in fuel reprocessing safety research

    International Nuclear Information System (INIS)

    Tsujino, Takeshi

    1981-01-01

    With the operation of a fuel reprocessing plant in the Power Reactor and Nuclear Fuel Development Corporation (PNC) and the plan for a second fuel reprocessing plant, the research on fuel reprocessing safety, along with the reprocessing technology itself, has become increasingly important. As compared with the case of LWR power plants, the safety research in this field still lags behind. In the safety of fuel reprocessing, there are the aspects of keeping radiation exposure as low as possible in both personnel and local people, the high reliability of the plant operation and the securing of public safety in accidents. Safety research is then required to establish the safety standards and to raise the rate of plant operation associated with safety. The following matters are described: basic ideas for the safety design, safety features in fuel reprocessing, safety guideline and standards, and safety research for fuel reprocessing. (J.P.N.)

  4. Computer codes for level 1 probabilistic safety assessment

    International Nuclear Information System (INIS)

    1990-06-01

    Probabilistic Safety Assessment (PSA) entails several laborious tasks suitable for computer codes assistance. This guide identifies these tasks, presents guidelines for selecting and utilizing computer codes in the conduct of the PSA tasks and for the use of PSA results in safety management and provides information on available codes suggested or applied in performing PSA in nuclear power plants. The guidance is intended for use by nuclear power plant system engineers, safety and operating personnel, and regulators. Large efforts are made today to provide PC-based software systems and PSA processed information in a way to enable their use as a safety management tool by the nuclear power plant overall management. Guidelines on the characteristics of software needed for management to prepare a software that meets their specific needs are also provided. Most of these computer codes are also applicable for PSA of other industrial facilities. The scope of this document is limited to computer codes used for the treatment of internal events. It does not address other codes available mainly for the analysis of external events (e.g. seismic analysis) flood and fire analysis. Codes discussed in the document are those used for probabilistic rather than for phenomenological modelling. It should be also appreciated that these guidelines are not intended to lead the user to selection of one specific code. They provide simply criteria for the selection. Refs and tabs

  5. Relationship of safety culture and process safety

    International Nuclear Information System (INIS)

    Olive, Claire; O'Connor, T. Michael; Mannan, M. Sam

    2006-01-01

    Throughout history, humans have gathered in groups for social, religious, and industrial purposes. As the conglomeration of people interact, a set of underlying values, beliefs, and principles begins to develop that serve to guide behavior within the group. These 'guidelines' are commonly referred to as the group culture. Modern-day organizations, including corporations, have developed their own unique cultures derived from the diversity of the organizational interests and the background of the employees. Safety culture, a sub-set of organizational culture, has been a major focus in recent years. This is especially true in the chemical industry due to the series of preventable, safety-related disasters that occurred in the late seventies and eighties. Some of the most notable disasters, during this time period, occurred at Bhopal, Flixborough, and Seveso. However, current events, like the September 11th terrorist attacks and the disintegration of the Columbia shuttle, have caused an assessment of safety culture in a variety of other organizations

  6. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  7. Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

    International Nuclear Information System (INIS)

    Monteleone, S.

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

  8. Perspectives on dam safety in Canada

    International Nuclear Information System (INIS)

    Halliday, R.

    2004-01-01

    Canadian dam safety issues were reviewed from the perspective of a water resources engineer who is not a dam safety practitioner. Several external factors affecting dam safety were identified along with perceived problems in dam safety administration. The author claims that the main weakness in safety practices can be attributed to provincial oversights and lack of federal engagement. Some additions to the Canadian Dam Safety Guidelines were proposed to address these weaknesses. Canada has hundreds of large dams and high hazard dams whose failure would result in severe downstream consequences. The safety of dams built on boundary waters shared with the United States have gained particular attention from the International Joint Commission. This paper also examined safety criteria for concerns such as aging dams, sabotage and global climate change that may compromise the safety of a dam. 26 refs

  9. Computer-Based CPR Simulation Towards Validation of AHA/ERC Guidelines.

    Science.gov (United States)

    John, Alka Rachel; Manivannan, M; Ramakrishnan, T V

    2017-06-01

    As per the AHA 2015 and ERC 2015 guidelines for resuscitation, chest compression depth should be between 5 and 6 cm with a rate of 100-120 compressions per minute. Theoretical validation of these guidelines is still elusive. We developed a computer model of the cardiopulmonary resuscitation (CPR) system to validate these guidelines. A lumped element computer model of the cardiovascular system was developed to simulate cardiac arrest and CPR. Cardiac output was compared for a range of compression pressures and frequencies. It was observed from our investigation that there is an optimum compression pressure and rate. The maximum cardiac output occurred at 100 mmHg, which is approximately 5.7 cm, and in the range of 100 to 120 compressions per minute with an optimum value at 110 compressions per minute, validating the guidelines. Increasing the pressure or the depth of compression beyond the optimum, limits the blood flow by depleting the volume in the cardiac chambers and not allowing for an effective stroke volume. Similarly increasing the compression rate beyond the optimum degrades the ability of the chambers to pump blood. The results also bring out the importance of complete recoil of the chest after each compression with more than 400% increase in cardiac output from 90% recoil to 100% recoil. Our simulation predicts that the recommendation to compress harder and faster is not the best counsel as there is an optimum compression pressure and rate for high-quality CPR.

  10. Guidelines for the verification and validation of expert system software and conventional software. Volume 1: Project summary. Final report

    International Nuclear Information System (INIS)

    Miller, L.A.; Hayes, J.E.; Mirsky, S.M.

    1995-05-01

    This eight-volume report presents guidelines for performing verification and validation (V ampersand V) on Artificial Intelligence (AI) systems with nuclear applications. The guidelines have much broader application than just expert systems; they are also applicable to object-oriented programming systems, rule-based systems, frame-based systems, model-based systems, neural nets, genetic algorithms, and conventional software systems. This is because many of the components of AI systems are implemented in conventional procedural programming languages, so there is no real distinction. The report examines the state of the art in verifying and validating expert systems. V ampersand V methods traditionally applied to conventional software systems are evaluated for their applicability to expert systems. One hundred fifty-three conventional techniques are identified and evaluated. These methods are found to be useful for at least some of the components of expert systems, frame-based systems, and object-oriented systems. A taxonomy of 52 defect types and their delectability by the 153 methods is presented. With specific regard to expert systems, conventional V ampersand V methods were found to apply well to all the components of the expert system with the exception of the knowledge base. The knowledge base requires extension of the existing methods. Several innovative static verification and validation methods for expert systems have been identified and are described here, including a method for checking the knowledge base open-quotes semanticsclose quotes and a method for generating validation scenarios. Evaluation of some of these methods was performed both analytically and experimentally

  11. Shutdown Safety in NEK

    International Nuclear Information System (INIS)

    Gluhak, Mario; Senegovic, Marko

    2014-01-01

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

  12. NASA Aerospace Flight Battery Program: Generic Safety, Handling and Qualification Guidelines for Lithium-Ion (Li-Ion) Batteries; Availability of Source Materials for Lithium-Ion (Li-Ion) Batteries; Maintaining Technical Communications Related to Aerospace Batteries (NASA Aerospace Battery Workshop). Volume 2, Part 1

    Science.gov (United States)

    Manzo, Michelle A.; Brewer, Jeffrey C.; Bugga, Ratnakumar V.; Darcy, Eric C.; Jeevarajan, Judith A.; McKissock, Barbara I.; Schmitz, Paul C.

    2010-01-01

    This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This report contains the Appendices to the findings from the first year of the program's operations.

  13. Civilian use transport of radioactive substances on public road. Volume 1: Shipment accreditation and approval requests. Guide Nr 7, Revision 2 of 15 February 2016. Volume 2: safety file of package models, European guide 'Package Design Safety Report'. Civilian use transport of radioactive packages or substances on public road. Volume 3: Compliance of package models not subject to accreditation. Guide Nr 7, Revision 7 of the 2015/11/13

    International Nuclear Information System (INIS)

    2016-01-01

    After having recalled the regulatory context and sanctions susceptible to be applied, the first volume presents the accreditation process for a package model: file content, tests programme, safety file, certification studies, documents to be produced, accreditation prorogation request, accreditation extension or package model modifications, instruction delays. Some peculiar cases are described. Models of accreditation certificate are provided, and obligations concerning packaging design, fabrication, use and maintenance are briefly discussed. The second volume is a European technical guide which is intended to assist in the preparation of the Package Design Safety Report (PDSR) to demonstrate compliance of a package design for the transport of radioactive material with the regulatory requirements. It covers package designs requiring competent authority approval, and also covers package designs not requiring competent authority approval. In its first two chapters, this document provides a generic structure and contents of a PDSR which applies to all package types. The contents are described in a comprehensive way to cover all important aspects. Some of these aspects may not be applicable to specific package type and details can be found in the annexes which provide further guidance for the scope of the contents of a PDSR, specifically for each package type. The third volume presents recommendations made by the ASN for all stakeholders to guarantee the compliance to regulation of package models which are 'not submitted to competent authority approval'. After an indication and a comment of the regulatory context, it presents requirements to be applied for the design of those package models, and then describes and comments the structure and content of a safety file for such package models (generalities, authorised contents, packaging description, safety demonstration, receipt, use and maintenance instruction, management system). The last part presents the

  14. [Implementation of a safety and health planning system in a teaching hospital].

    Science.gov (United States)

    Mariani, F; Bravi, C; Dolcetti, L; Moretto, A; Palermo, A; Ronchin, M; Tonelli, F; Carrer, P

    2007-01-01

    University Hospital "L. Sacco" had started in 2006 a two-year project in order to set up a "Health and Safety Management System (HSMS)" referring to the technical guideline OHSAS 18001:1999 and the UNI and INAIL "Guidelines for a health and safety management system at workplace". So far, the following operations had been implemented: Setting up of a specific Commission within the Risk Management Committee; Identification and appointment of Departmental Representatives of HSMS; Carrying out of a training course addressed to Workers Representatives for Safety and Departmental Representatives of HSMS; Development of an Integrated Informative System for Prevention and Safety; Auditors qualification; Inspection of the Occupational Health Unit and the Prevention and Safety Service: reporting of critical situations and monitoring solutions adopted. Short term objectives are: Self-evaluation through check-lists of each department; Sharing of the Improvement Plan among the departments of the hospital; Planning of Health and Safety training activities in the framework of the Hospital Training Plan; Safety audit.

  15. Guidelines regarding National Reports 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 regarding material which it may be useful to include in the national reports required by Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention

  16. Guidelines regarding national reports 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 regarding material which it may be useful to include in the national reports required by Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention

  17. Guidelines regarding National Reports under the Convention on Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-10-15

    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 regarding material which it may be useful to include in the national reports required by Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention.

  18. SPORT AND EXERCISE PHYSIOLOGY TESTING Volume one: Sport Testing Volume two: Exercise and Clinical Testing

    Directory of Open Access Journals (Sweden)

    Edward M. Winter

    2007-03-01

    Full Text Available DESCRIPTION The objective of the book is to discuss the theoretical and practical aspects of physiological testing in exercise and sports which is essential to evaluate and monitor developing exercise performance for athletes and public health, and improving quality of life for patients.A board of leading sport and exercise physiologists and scientists are gathered to discuss physiological assessments that have proven validity and reliability, both in sport and health relevant issues. Incidentally, it updates the reader about the current subjects of physiological exertion testing in both research and clinical procedures. Both volumes individually cover the increasing number of available research and review publications, and theoretical explanations are supported by practical examples. A step-by-step and/or checklist method is used in appropriate sections which make the guides more user-friendly than most. PURPOSE The first volume is designed to help readers develop an understanding of the essential concepts of sport specific testing whereas the second volume aims at making the exercise and clinical specific testing comprehensible, dealing with both technical terms and the theories underlying the importance of these tests. AUDIENCE As Guidelines books of the British Association of Sport and Exercise Sciences, it will be of interest to a wide range of students, researchers and practitioners in the sport and exercise disciplines whether they work in the laboratory or in the field. FEATURES The first volume features immediate practical requirements particularly in sport testing. It is composed of five parts with detailed sub-sections in all of them. The topics of the parts are: i general principles, ii methodological issues, iii general procedures, iv sport specific procedures, v special populations.The second volume is also presented in five parts, again with sub-sections in all of them, but considering the requirements in clinical and exercise

  19. Safety philosophy for nuclear power plants in egypt

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  20. Tank Farms Technical Safety Requirements. Volume 1 and 2

    International Nuclear Information System (INIS)

    CASH, R.J.

    2000-01-01

    The Technical Safety Requirements (TSRs) define the acceptable conditions, safe boundaries, basis thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR)