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Sample records for review plan nureg-0800

  1. Technical issues related to NUREG 0800, Chapter 18: Human Factors Engineering/Standard Review Plan

    International Nuclear Information System (INIS)

    Savage, J.W.

    1982-01-01

    The revision of Chapter 18 of NUREG 0800, Human Factors Engineering Standard Review Plan (SRP) will be based on SECY 82-111 and guidance contained in NUREG 0700, NUREG 0801 and NUREG 0835, plus other references. In conducting field reviews of control rooms, the NRC has identified technical issues which can be used to enhance the development of the revised version of NUREG 0800, and to establish priorities among the list of possible Branch Technical Positions (BTP) in NUREG 0800, Rev. 0, Table 18.0-2. This report is a compilation of comments and suggestions from the people who used NUREG 0700 in the Control Room field reviews. This information was used to establish possible BTP topic priorities so that the most important BTPs could be issued first. The comments and suggestions are included for HFEB review in conjunction with the table of priorities

  2. Comparisons of ANSI standards cited in the NRC standard review plan, NUREG-0800 and related documents

    International Nuclear Information System (INIS)

    Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Pawlowski, R.A.; Spiesman, J.B.

    1995-11-01

    This report provides the results of comparisons of the cited and latest versions of ANSI standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC's Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review

  3. Comparisons of ASTM standards cited in the NRC standard review plan, NUREG-0800 and related documents

    International Nuclear Information System (INIS)

    Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Pawlowski, R.A.; Spiesman, J.B.

    1995-10-01

    This report provides the results of comparisons of the cited and latest versions of ASTM standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC's Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review

  4. Comparisons of ANS, ASME, AWS, and NFPA standards cited in the NRC standard review plan, NUREG-0800, and related documents

    International Nuclear Information System (INIS)

    Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Spiesman, J.B.

    1995-11-01

    This report provides the results of comparisons of the cited and latest versions of ANS, ASME, AWS and NFPA standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC's Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review

  5. Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Poore, III, Willis P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Moe, Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-03-01

    This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

  6. 75 FR 6413 - Office of New Reactors; Proposed Revision to Standard Review Plan, Section 14.3.12 on Physical...

    Science.gov (United States)

    2010-02-09

    ... Standard Review Plan, Section 14.3.12 on Physical Security Hardware Inspections, Tests, Analyses, and.... SUMMARY: The NRC is soliciting public comment on NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,'' on a proposed Revision 1 to Standard Review Plan (SRP...

  7. 75 FR 29588 - Office of New Reactors: Proposed NUREG-0800; Standard Review Plan Section 13.6.6, Draft Revision...

    Science.gov (United States)

    2010-05-26

    ...; Standard Review Plan Section 13.6.6, Draft Revision 0 on Cyber Security Plan AGENCY: Nuclear Regulatory... Plants,'' on a proposed Standard Review Plan (SRP) Section 13.6.6 on ``Cyber Security Plan'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093560837). The Office of Nuclear Security...

  8. 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

  9. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Standard review plan and acceptance criteria. NUREG - 1537, Part 2

    International Nuclear Information System (INIS)

    1996-02-01

    NUREG - 1537, Part 2 gives guidance on the conduct of licensing action reviews to NRC staff who review non-power reactor licensing applications. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination

  10. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Standard review plan and acceptance criteria. NUREG - 1537, Part 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    NUREG - 1537, Part 2 gives guidance on the conduct of licensing action reviews to NRC staff who review non-power reactor licensing applications. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination.

  11. Special committee review of the Nuclear Regulatory Commission's severe accident risks report (NUREG--1150)

    International Nuclear Information System (INIS)

    Kouts, H.J.C.; Apostolakis, G.; Kastenberg, W.E.; Birkhofer, E.H.A.; Hoegberg, L.G.; LeSage, L.G.; Rasmussen, N.C.; Teague, H.J.; Taylor, J.J.

    1990-08-01

    In April 1989, the Nuclear Regulatory Commission's (NRC) Office of Nuclear Regulatory Research (RES) published a draft report ''Severe Accident Risks: An Assessment for Five US Nuclear Power Plants,'' NUREG-1150. This report updated, extended and improved upon the information presented in the 1974 ''Reactor Safety Study,'' WASH-1400. Because the information in NUREG-1150 will play a significant role in implementing the NRC's Severe Accident Policy, its quality and credibility are of critical importance. Accordingly, the Commission requested that the RES conduct a peer review of NUREG-1150 to ensure that the methods, safety insights and conclusions presented are appropriate and adequately reflect the current state of knowledge with respect to reactor safety. To this end, RES formed a special committee in June of 1989 under the provisions of the Federal Advisory Committee Act. The Committee, composed of a group of recognized national and international experts in nuclear reactor safety, was charged with preparing a report reflecting their review of NUREG-1150 with respect to the adequacy of the methods, data, analysis and conclusions it set forth. The report which precedes reflects the results of this peer review

  12. 75 FR 5356 - Office of New Reactors; Final Interim Staff Guidance on Post-Combined License Commitments

    Science.gov (United States)

    2010-02-02

    ... the guidance provided to the NRC staff in Section 1.0, ``Introduction and Interfaces,'' of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,'' concerning the... maintains ADAMS, which provides text and image files of NRC's public documents. These documents may be...

  13. 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.

  14. The use of U.S. NRC licensing practices for VVERs

    International Nuclear Information System (INIS)

    Popp, D.M.

    2000-01-01

    The licensing process for the upgraded Temelin I and C and Fuel designs were enhanced with the introduction of U.S. Nuclear Regulatory Commission, NRC practices. Specifically, the use of the NRC Regulatory Guide 1.70, 'Standard Format and Content Guide for Safety Analyses Reports' and NRC NUREG 0800, 'Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants', were beneficial in the development and review of Temelin licensing documentation. These standards have been used for the preparation and review of Safety Analysis Reports in the United States and also in a large number of licensing applications around the world. Both Regulatory Guide 1.70 and NUREG 0800 were developed to provide a predictable and structured approach to licensing. This paper discusses this approach and identifies the benefits to designers, writers of licensing documentation and reviewers of licensing documents. (author)

  15. A basic study for development of environmental standard review plan of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chang Hyun; Cho, Jae Seon; You, Young Woo [Seoul Nationl Univ., Seoul (Korea, Republic of)] (and others)

    1999-12-15

    In this study is performed a basic study to be ready for the development and detail analysis of NUREG-1555 ESRP. As a fundamental research for literature survey and development of draft review plan, review and translation of NUREG-1555 published by NRC, and which is applied to licensing procedure of Nuclear Power Plants are included. These provided the basic information for the developments of the environmental standard review plan.

  16. Proposed Guidance for Preparing and Reviewing Molten Salt Nonpower Reactor Licence Applications (NUREG-1537)

    Energy Technology Data Exchange (ETDEWEB)

    Belles, Randy [ORNL; Flanagan, George F. [ORNL; Voth, Marcus [Boston Government Services, LLC

    2018-05-01

    Development of non-power molten salt reactor (MSR) test facilities is under consideration to support the analyses needed for development of a full-scale MSR. These non-power MSR test facilities will require review by the US Nuclear Regulatory Commission (NRC) staff. This report proposes chapter adaptations for NUREG-1537 in the form of interim staff guidance to address preparation and review of molten salt non-power reactor license applications. The proposed adaptations are based on a previous regulatory gap analysis of select chapters from NUREG-1537 for their applicability to non-power MSRs operating with a homogeneous fuel salt mixture.

  17. Guidelines and workbook for of organization and administration of utilities seeking operating license for a nuclear power plant. Workbook for assessment of organization and management. Volume, 2, Revision 1

    International Nuclear Information System (INIS)

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

    1986-09-01

    This report is 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 is designed to serve as a basis for replacing the earlier NUREG-0731, ''Guidelines for Utility Management Structure and Technical Resources.'' The 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 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 incorporated in the SRP

  18. Guidelines for evaluating software configuration management plans for digital instrumentation and control systems

    International Nuclear Information System (INIS)

    Cheon, Se Woo; Park, Jong Kyun; Lee, Ki Young; Lee, Jang Soo; Kim, Jang Yeon

    2001-08-01

    Software configuration management (SCM) is the process for identifying software configuration items (CIs), controlling the implementation and changes to software, recording and reporting the status of changes, and verifying the completeness and correctness of the released software. SCM consists of two major aspects: planning and implementation. Effective SCM involves planning for how activities are to be performed, and performing these activities in accordance with the Plan. This report first reviews the background of SCM that include key standards, SCM disciplines, SCM basic functions, baselines, software entity, SCM process, the implementation of SCM, and the tools of SCM. In turn, the report provides the guidelines for evaluating the SCM Plan for digital I and C systems of nuclear power plants. Most of the guidelines in the report are based on IEEE Std 828 and ANSI/IEEE Std 1042. According to BTP-14, NUREG-0800, the evaluation topics on the SCM Plan is classified into three categories: management, implementation, and resource characteristics

  19. Technical evaluation report, TMI action NUREG-0737 (II.D.1), relief and safety valve testing, Comanche Peak, Unit 2, Docket No. 50-446

    International Nuclear Information System (INIS)

    Fineman, C.P.

    1993-01-01

    In the past, safety and relief valves installed in the primary coolant system of light water reactors have performed improperly. As a result, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations) and, subsequently, NUREG-0737 (Clarification of TMI Action Plan Requirements) recommended development and completion of programs to do two things. First, the programs should reevaluate the functional performance capabilities of pressurized water reactor safety, relief, and block valves. Second, they should verify the integrity of the pressurizer safety and relief valve piping systems for normal, transient, and accident conditions. This report documents the review of those programs by EG ampersand G Idaho, Inc. Specifically, this report documents the review of the Comanche Peak, Unit 2, Applicant response to the requirement of NUREG-0578 and NUREG-0737. This review found the Applicant provided an acceptable response reconfirming they met General Design Criteria 14, 15 and 30 of Appendix A to 10 CFR 50 for the subject equipment

  20. NRC Reviewer Aid for Evaluating the Human Factors Engineering Aspects of Small Modular Reactors

    International Nuclear Information System (INIS)

    OHara, J.M.; Higgins, J.C.

    2012-01-01

    Small modular reactors (SMRs) are a promising approach to meeting future energy needs. Although the electrical output of an individual SMR is relatively small compared to that of typical commercial nuclear plants, they can be grouped to produce as much energy as a utility demands. Furthermore, SMRs can be used for other purposes, such as producing hydrogen and generating process heat. The design characteristics of many SMRs differ from those of current conventional plants and may require a distinct concept of operations (ConOps). The U.S. Nuclear Regulatory Commission (NRC) conducted research to examine the human factors engineering (HFE) and the operational aspects of SMRs. The research identified thirty potential human-performance issues that should be considered in the NRC's reviews of SMR designs and in future research activities. The purpose of this report is to support NRC HFE reviewers of SMR applications by identifying some of the questions that can be asked of applicants whose designs have characteristics identified in the issues. The questions for each issue were identified and organized based on the review elements and guidance contained in Chapter 18 of the Standard Review Plan (NUREG-0800), and the Human Factors Engineering Program Review Model (NUREG-0711).

  1. Application of NUREG-1150 methods and results to accident management

    International Nuclear Information System (INIS)

    Dingman, S.; Sype, T.; Camp, A.; Maloney, K.

    1991-01-01

    The use of NUREG-1150 and similar probabilistic risk assessments in the Nuclear Regulatory Commission (NRC) and industry risk management programs is discussed. Risk management is more comprehensive than the commonly used term accident management. Accident management includes strategies to prevent vessel breach, mitigate radionuclide releases from the reactor coolant system, and mitigate radionuclide releases to the environment. Risk management also addresses prevention of accident initiators, prevention of core damage, and implementation of effective emergency response procedures. The methods and results produced in NUREG-1150 provide a framework within which current risk management strategies can be evaluated, and future risk management programs can be developed and assessed. Examples of the use of the NUREG-1150 framework for identifying and evaluating risk management options are presented. All phases of risk management are discussed, with particular attention given to the early phases of accidents. Plans and methods for evaluating accident management strategies that have been identified in the NRC accident management program are discussed

  2. Application of NUREG-1150 methods and results to accident management

    International Nuclear Information System (INIS)

    Dingman, S.; Sype, T.; Camp, A.; Maloney, K.

    1990-01-01

    The use of NUREG-1150 and similar Probabilistic Risk Assessments in NRC and industry risk management programs is discussed. ''Risk management'' is more comprehensive than the commonly used term ''accident management.'' Accident management includes strategies to prevent vessel breach, mitigate radionuclide releases from the reactor coolant system, and mitigate radionuclide releases to the environment. Risk management also addresses prevention of accident initiators, prevention of core damage, and implementation of effective emergency response procedures. The methods and results produced in NUREG-1150 provide a framework within which current risk management strategies can be evaluated, and future risk management programs can be developed and assessed. Examples of the use of the NUREG-1150 framework for identifying and evaluating risk management options are presented. All phases of risk management are discussed, with particular attention given to the early phases of accidents. Plans and methods for evaluating accident management strategies that have been identified in the NRC accident management program are discussed. 2 refs., 3 figs

  3. Review of public comments on proposed seismic design criteria

    International Nuclear Information System (INIS)

    Philippacopoulos, A.J.; Shaukat, S.K.; Chokshi, N.C.; Bagchi, G.; Nuclear Regulatory Commission, Washington, DC; Nuclear Regulatory Commission, Washington, DC

    1989-01-01

    During the first quarter of 1988, the Nuclear Regulatory Commission (NRC) prepared a proposed Revision 2 to the NUREG-0800 Standard Review Plan (SRP) Sections 2.5.2 (Vibratory Ground Motion), 3.7.1 (Seismic Design Parameters), 3.7.2 (Seismic Systems Analysis) and 3.7.3 (Seismic Subsystem Analysis). The proposed Revision 2 to the SRP was a result of many years' work carried out by the NRC and the nuclear industry on the Unresolved Safety Issue (USI) A-40: ''Seismic Design Criteria.'' The background material related to NRC's efforts for resolving the A-40 issue is described in NUREG-1233. In June 1988, the proposed Revision 2 of the SRP was issued by NRC for public review and comments. Comments were received from Sargent and Lundy Engineers, Westinghouse Electric Corporation, Stevenson and Associates, Duke Power Company, General Electric Company and Electric Power Research Institute. In September 1988, Brookhaven National Laboratory (BNL) and its consultants (C.J. Costantino, R.P. Kennedy, J. Stevenson, M. Shinozuka and A.S. Veletsos) were requested to carry out a review of the comments received from the above six organizations. The objective of this review was to assist the NRC staff with the evaluation and resolution of the public comments. This review was initiated during October 1988 and it was completed on January 1989. As a result of this review, a set of modifications to the above mentioned sections of the SRP were recommended by BNL and its consultants. This paper summarizes the recommended modifications. 4 refs

  4. Research on the evaluation model of the software reliability in nuclear safety class digital instrumentation and control system

    International Nuclear Information System (INIS)

    Liu Ying; Yang Ming; Li Fengjun; Ma Zhanguo; Zeng Hai

    2014-01-01

    In order to analyze the software reliability (SR) in nuclear safety class digital instrumentation and control system (D-I and C), firstly, the international software design standards were analyzed, the standards' framework was built, and we found that the D-I and C software standards should follow the NUREG-0800 BTP7-14, according to the NRC NUREG-0800 review of requirements. Secondly, the quantitative evaluation model of SR using Bayesian Belief Network and thirteen sub-model frameworks were established. Thirdly, each sub-models and the weight of corresponding indexes in the evaluation model were analyzed. Finally, the safety case was introduced. The models lay a foundation for review and quantitative evaluation on the SR in nuclear safety class D-I and C. (authors)

  5. Advanced control room design review guidelines: Integration of the NUREG-0700 guidelines and development of new human-system interface guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Carter, R.J.

    1997-07-01

    This report documents the work conducted in four tasks of the Nuclear Regulatory Commission (NRC) project entitled Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation. The purpose of the first task was to integrate the applicable sections of NUREG-0700 into the advanced control room design review (ACRDR) guidelines to ensure that all applicable guidelines are together in one document and conveniently accessible to users. The primary objective of the second task was to formulate a strategy for the development of new ACRDR guidelines that have not otherwise been identified. The main focus of the third task was to modify the individual ACRDR guidelines generated to date to ensure that they are suitable for the intended nuclear power plant (NPP) control station system application. The goal of the fourth task was to develop human factors guidelines for two human-system interface categories that are missing from the current ACRDR guidelines document. During the first task those areas in NUREG-0700 that are not addressed by the ACRDR guidelines document were identified, the areas were subsequently reviewed against six recent industry human factors engineering review guidelines, and the NUREG-0700 guidelines were updated as necessary. In the second task 13 general categories of human-system interface guidelines that are either missing from or not adequately addressed by the ACRDR document were discovered. An approach was derived for the development of new ACRDR guidelines, a preliminary assessment of the available sources that may be useful in the creation of new guidelines and their applicability to the identified human-system interface categories was performed, and an estimate was made of the amount of time and level of effort required to complete the development of needed new ACRDR guidelines. During the third task those NPP control station systems to which the NUREG-0700 and ACRDR guidelines apply were identified, matrices of such

  6. Advanced control room design review guidelines: Integration of the NUREG-0700 guidelines and development of new human-system interface guidelines

    International Nuclear Information System (INIS)

    Carter, R.J.

    1997-07-01

    This report documents the work conducted in four tasks of the Nuclear Regulatory Commission (NRC) project entitled Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation. The purpose of the first task was to integrate the applicable sections of NUREG-0700 into the advanced control room design review (ACRDR) guidelines to ensure that all applicable guidelines are together in one document and conveniently accessible to users. The primary objective of the second task was to formulate a strategy for the development of new ACRDR guidelines that have not otherwise been identified. The main focus of the third task was to modify the individual ACRDR guidelines generated to date to ensure that they are suitable for the intended nuclear power plant (NPP) control station system application. The goal of the fourth task was to develop human factors guidelines for two human-system interface categories that are missing from the current ACRDR guidelines document. During the first task those areas in NUREG-0700 that are not addressed by the ACRDR guidelines document were identified, the areas were subsequently reviewed against six recent industry human factors engineering review guidelines, and the NUREG-0700 guidelines were updated as necessary. In the second task 13 general categories of human-system interface guidelines that are either missing from or not adequately addressed by the ACRDR document were discovered. An approach was derived for the development of new ACRDR guidelines, a preliminary assessment of the available sources that may be useful in the creation of new guidelines and their applicability to the identified human-system interface categories was performed, and an estimate was made of the amount of time and level of effort required to complete the development of needed new ACRDR guidelines. During the third task those NPP control station systems to which the NUREG-0700 and ACRDR guidelines apply were identified, matrices of such

  7. Review of regulatory requirements for digital I and C systems

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee Choon; Lee, Cheol Kwon; Lee, Jang Soo [and others

    2001-11-01

    This work analyzed and summarized systematically various regulatory requirements that are necessary to develop digital nuclear instrumentation and control (I and C) systems, especially safety systems. The requirements are categorized into system, hardware, software, and quality assurance aspects. This report provides the explanations of terms and abbreviations to help readers understand. Furthermore, appendices of this report summarize the code and standards corresponding to each principal regulatory requirement. The hierarchical structure of regulatory requirements has Nuclear Energy Laws, Enforcement Regulations of Nuclear Energy Laws, and Notifications of Ministry of Science and Technology as utmost level requirements [In case of the US, 10 CFR 50 Appendix A, 10 CFR 50 Appendix B, 10 CFR 50.55a(h), 10 CFR 50.49, etc.]. The requirements include the Draft Regulatory Guidelines for Digital I and C Systems [In case of the US, Standard Review Plan (NUREG-0800), Regulatory Guide, Branch Technical Position (BTP)], KEPIC as standards [In case of the US, IEEE Standards, IEC Standards, ISA, Military Standard, etc.], and various reports issued by Korea Institute of Nuclear Safety [In case of the US, NUREG reports, EPRI reports, etc.]. This report can be referred for the development of safety grade control equipment, plant protection system, and engineered safety feature actuation system.

  8. Review of regulatory requirements for digital I and C systems

    International Nuclear Information System (INIS)

    Kwon, Kee Choon; Lee, Cheol Kwon; Lee, Jang Soo

    2001-11-01

    This work analyzed and summarized systematically various regulatory requirements that are necessary to develop digital nuclear instrumentation and control (I and C) systems, especially safety systems. The requirements are categorized into system, hardware, software, and quality assurance aspects. This report provides the explanations of terms and abbreviations to help readers understand. Furthermore, appendices of this report summarize the code and standards corresponding to each principal regulatory requirement. The hierarchical structure of regulatory requirements has Nuclear Energy Laws, Enforcement Regulations of Nuclear Energy Laws, and Notifications of Ministry of Science and Technology as utmost level requirements [In case of the US, 10 CFR 50 Appendix A, 10 CFR 50 Appendix B, 10 CFR 50.55a(h), 10 CFR 50.49, etc.]. The requirements include the Draft Regulatory Guidelines for Digital I and C Systems [In case of the US, Standard Review Plan (NUREG-0800), Regulatory Guide, Branch Technical Position (BTP)], KEPIC as standards [In case of the US, IEEE Standards, IEC Standards, ISA, Military Standard, etc.], and various reports issued by Korea Institute of Nuclear Safety [In case of the US, NUREG reports, EPRI reports, etc.]. This report can be referred for the development of safety grade control equipment, plant protection system, and engineered safety feature actuation system

  9. Calculation of source terms for NUREG-1150

    International Nuclear Information System (INIS)

    Breeding, R.J.; Williams, D.C.; Murfin, W.B.; Amos, C.N.; Helton, J.C.

    1987-10-01

    The source terms estimated for NUREG-1150 are generally based on the Source Term Code Package (STCP), but the actual source term calculations used in computing risk are performed by much smaller codes which are specific to each plant. This was done because the method of estimating the uncertainty in risk for NUREG-1150 requires hundreds of source term calculations for each accident sequence. This is clearly impossible with a large, detailed code like the STCP. The small plant-specific codes are based on simple algorithms and utilize adjustable parameters. The values of the parameters appearing in these codes are derived from the available STCP results. To determine the uncertainty in the estimation of the source terms, these parameters were varied as specified by an expert review group. This method was used to account for the uncertainties in the STCP results and the uncertainties in phenomena not considered by the STCP

  10. Standard review plan on antitrust reviews. Final report

    International Nuclear Information System (INIS)

    Lambe, W.M.; Davis, M.J.

    1997-12-01

    This standard review plan describes the procedures used by NRC staff to implement the antitrust review and enforcement provisions in Sections 105 and 186 of the Atomic Energy Act of 1954, as amended (the Act), and replaces NUREG-0970. These procedures are principally derived from the Commission's Rules and Regulations in 10 CFR Sections 2.101, 2.102, Part 2-Appendix A, Section X, 50.33a, 50.80, 50.90, and 52.77. These procedures set forth the steps and criteria the staff uses in antitrust reviews of construction permit applications, operating license applications, combined construction permit/operating license applications, combined construction permit/operating license applications, and applications for approval of the transfer of construction permits, operating licenses, and combined licenses. In addition, the procedures describe how the staff enforces compliance with antitrust conditions appended to licenses

  11. Human factors engineering evaluation of the UTR-10 Reactor

    International Nuclear Information System (INIS)

    Lahti, D.; Nilius, D.; Heithoff, D.; Roche, G.; Sage, S.

    1982-01-01

    This paper is a description of a student design team's review and evaluation of Iowa State University's University Test Reactor (UTR-10). The review was based on how well the control room of the UTR-10 measured up to selected portions of NUREG-0800, chapter 18, Human Factor Engineering/Standard Review Plan Development. The review was conducted by inspecting the reactor and interviewing reactor operators. The control room workspace, instrumentation controls and other equipment were evaluated from a human factors engineering point of view that takes into account both system demands and operator capabilities. Identification, assessment, and suggestion for control room design modifications that correct inadequate or unsuitable items was made

  12. Technical evaluation report TMI action: NUREG-0737 (II.D.1) relief and safety valve testing,. Diablo Canyon Units 1 and 2 (Docket Nos. 50-275, 50-323)

    International Nuclear Information System (INIS)

    Miller, G.K.; Magleby, H.L.; Nalezny, C.L.

    1984-07-01

    Light water reactor operators have experienced a number of occurrences of improper performance of safety and relief valves installed in their primary coolant systems. Because of this, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Status Report and Short-Term Recommendations) and subsequently NUREG-0737 (Clarification of TMI Action Plan Requirements) recommended that programs be developed and completed which would reevaluate the functional performance capabilities of Pressurized Water Reactor (PWR) safety, relief, and block valves and which would verify the integrity of the piping systems for normal, transient and accident conditions. This report provides the results of the review of these programs and their results by the Nuclear Regulatory Commission (NRC) and their consultant, EG and G Idaho, Inc. Specifically, this report has examined the response of the Licensee for Diablo Canyon Units 1 and 2, to the requirements of NUREG-0578 and NUREG-0737 and finds that the Licensee has provided an acceptable response, reconfirming that the General Design Criteria 14, 15 and 30 of Appendix A to 10 CRF 50 have been met. 18 refs

  13. Clarification of TMI action plan requirements. Technical report

    International Nuclear Information System (INIS)

    1980-11-01

    This document, NUREG-0737, is a letter from D.G. Eisenhut, Director of the Division of Licensing, NRR, to licensees of operating power reactors and applicants for operating licenses forwarding post-TMI requirements which have been approved for implementation. Following the accident at Three Mile Island Unit 2, the NRC staff developed the Action Plan, NUREG-0660, to provide a comprehensive and integrated plan to improve safety at power reactors. Specific items from NUREG-0660 have been approved by the Commission for implementation at reactors. In this NRC report, these specific items comprise a single document which includes additional information about schedules, applicability, method of implementation review, submittal dates, and clarification of technical positions. It should be noted that the total set of TMI-related actions have been collected in NUREG-0660, but only those items that the Commission has approved for implementation to date are included in this document, NUREG-0737

  14. IDENTIFICATION OF AIRCRAFT HAZARDS

    International Nuclear Information System (INIS)

    K.L. Ashley

    2005-01-01

    Aircraft hazards were determined to be potentially applicable to a repository at Yucca Mountain in the ''Monitored Geological Repository External Events Hazards Screening Analysis'' (BSC 2004, Section 6.4.1). That determination was conservatively based on limited knowledge of flight data in the area of concern and on crash data for aircraft of the type flying near Yucca Mountain. The purpose of this report is to identify specific aircraft hazards that may be applicable to a Monitored Geologic Repository (MGR) at Yucca Mountain using NUREG-0800, ''Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (NRC 1987, Section 3.5.1.6), as guidance for the inclusion or exclusion of identified aircraft hazards. NUREG-0800 is being used here as a reference because some of the same considerations apply. The intended use of this report is to provide inputs for further screening and analysis of the identified aircraft hazards based on the criteria that apply to Category 1 and 2 event sequence analyses as defined in 10 CFR 63.2 (see Section 4). The scope of this technical report includes the evaluation of military, private, and commercial use of airspace in the 100-mile regional setting of the MGR at Yucca Mountain with the potential for reducing the regional setting to a more manageable size after consideration of applicable screening criteria (see Section 7)

  15. Analysis of Precipitation (Rain and Snow) Levels and Straight-line Wind Speeds in Support of the 10-year Natural Phenomena Hazards Review for Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, Elizabeth J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dewart, Jean Marie [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Deola, Regina [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-10

    This report provides site-specific return level analyses for rain, snow, and straight-line wind extreme events. These analyses are in support of the 10-year review plan for the assessment of meteorological natural phenomena hazards at Los Alamos National Laboratory (LANL). These analyses follow guidance from Department of Energy, DOE Standard, Natural Phenomena Hazards Analysis and Design Criteria for DOE Facilities (DOE-STD-1020-2012), Nuclear Regulatory Commission Standard Review Plan (NUREG-0800, 2007) and ANSI/ ANS-2.3-2011, Estimating Tornado, Hurricane, and Extreme Straight-Line Wind Characteristics at Nuclear Facility Sites. LANL precipitation and snow level data have been collected since 1910, although not all years are complete. In this report the results from the more recent data (1990–2014) are compared to those of past analyses and a 2004 National Oceanographic and Atmospheric Administration report. Given the many differences in the data sets used in these different analyses, the lack of statistically significant differences in return level estimates increases confidence in the data and in the modeling and analysis approach.

  16. Codes and standards and other guidance cited in regulatory documents. Revision 1

    International Nuclear Information System (INIS)

    Ankrum, A.; Nickolaus, J.; Vinther, R.; Maguire-Moffitt, N.; Hammer, J.; Sherfey, L.; Warner, R.

    1994-08-01

    As part of the US Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program, Pacific Northwest Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. In addition to updating previous information, Revision 1 adds citations from the NRC Inspection Manual and the Improved Standard Technical Specifications. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC's Bulletins, Information Notices, Circulars, Generic Letters, Policy Statements, Regulatory Guides, and the Standard Review Plan (NUREG-0800)

  17. Codes and standards and other guidance cited in regulatory documents. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Ankrum, A.; Nickolaus, J.; Vinther, R.; Maguire-Moffitt, N.; Hammer, J.; Sherfey, L.; Warner, R. [Pacific Northwest Lab., Richland, WA (United States)

    1994-08-01

    As part of the US Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program, Pacific Northwest Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. In addition to updating previous information, Revision 1 adds citations from the NRC Inspection Manual and the Improved Standard Technical Specifications. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC`s Bulletins, Information Notices, Circulars, Generic Letters, Policy Statements, Regulatory Guides, and the Standard Review Plan (NUREG-0800).

  18. Standard Review Plan for the review of a license application for a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    1994-04-01

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

  19. The Gas Turbine Modular Helium Reactor Optimum Design for Instrumentation and Control

    International Nuclear Information System (INIS)

    Quinn, Edward 'Ted'; Rodriguez, Carmelo

    2002-01-01

    Nuclear power plants rely on instrumentation and control (I and C) systems for monitoring, control and protection. While the earlier generations of nuclear plants were built with largely analog instrumentation systems, the industrial base has moved to digital based system. The reason for this transition to digital I and C systems lies in their important advantage over existing analog systems. In essence, the challenge is to prove that the new digital guidelines included in NUREG 0800, Standard Review Plan Chapter 7 and all associated documents provided adequate direction and safety review for an advanced control design for a new nuclear plant in the United States. This paper focuses on how one of the new designs incorporates the latest technology and meets the new NRC requirements. (authors)

  20. Interim guidance on the Standard Review Plan for the review of financial assurance mechanisms for decommissioning under 10 CFR Parts 30, 40, and 70

    International Nuclear Information System (INIS)

    1988-12-01

    Interim Guidance on the Standard Review Plan (SRP) for the Review of Financial Assurance Mechanisms for Decommissioning under 10 CFR Parts 30, 40, and 70 is prepared for the guidance of Nuclear Regulatory Commission staff reviewers in performing reviews of applications from material licensees affected by the decommissioning regulations established June 27, 1988 (53FR24018). The principal purpose of the SRP is to assure the quality and uniformity of staff reviews and to present a base from which to evaluate the financial assurance aspects of the applications. NUREG-1337, identifies who performs the review, the matters that are reviewed, the basis of the review, how the review is performed, and the conclusions that are sought. 3 refs

  1. Use of expert judgement in NUREG-1150

    International Nuclear Information System (INIS)

    Ortiz, N.R.; Wheeler, T.A.; Breeding, R.J.; Hora, S.; Meyer, M.A.; Kenney, R.L.

    1991-01-01

    The explicit expert judgment process used in NUREG-1150, 'Severe Accident Risks: An Assessment for Five US Nuclear Plants', is discussed in this paper. The main steps of the process are described, including selection of issues and experts, elicitation training, presentation of issues to the experts, preparation of issue analyses by the experts, discussion of issue analyses and elicitation, and recomposition and aggregation of results. To demonstrate the application of the expert judgment process to NUREG-1150, two issues are summarized: one from the accident frequency analysis, and one from the accident progression analysis. Recommendations and insights are provided to improve the use of explicit expert judgment in complex technical issues. (orig.)

  2. Standard Review Plan for the review of a license application for a low-level radioactive waste disposal facility. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

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

  3. NRC perspectives on the digital system review process

    International Nuclear Information System (INIS)

    Mauck, J.L.

    1998-01-01

    Since about 1988, the USNRC has been involved in the review of digital retrofits to instrumentation and control (I and C) systems in nuclear power plants. Initially, this involvement was limited but with the advent of the 1990s, NRC involvement has become greater because of increased interest in and application of digital systems as existing analog systems become obsolete. Criteria for the design of such systems to ensure safety has been promulgated over the years and the USNRC has been actively involved both nationally and internationally with this effort. With the publication of the Zion Eagle 21 Safety Evaluation Report in 1992, Generic Letter 95-02 in April 1995 which endorses EPRI guidance document TR-102348 on digital upgrades and the latest revision to Regulatory Guide 1.152 which endorses IEEE 7.4.3.2-1993; a basic digital system review process was established. The NRC supplemented this review process with recently issued inspection procedures for use by NRC inspectors when conducting onsite reviews of digital modifications. In addition, the NRC undertook a major effort to codify the above guidance and the experience gained from digital system reviews of both operating plant modifications and advanced reactor designs, over these years into a revision to Standard Review Plan, (SRP), NUREG-0800, Chapter 7, Instrumentation and Control. This SRP revision was published in June, 1997, and included new SRP sections, branch technical positions and six new regulatory guides endorsing IEEE standards on software quality. The NRC staff believes that a stable digital system review process is now in place. (author)

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

    International Nuclear Information System (INIS)

    1988-01-01

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

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

    International Nuclear Information System (INIS)

    1987-01-01

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

  6. Codes and standards and other guidance cited in regulatory documents

    International Nuclear Information System (INIS)

    Nickolaus, J.R.; Bohlander, K.L.

    1996-08-01

    As part of the U.S. Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program (SRP-UDP), Pacific Northwest National Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. The SRP-UDP has been completed and the SRP-Maintenance Program (SRP-MP) is now maintaining this listing. Besides updating previous information, Revision 3 adds approximately 80 citations. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC's Bulletins, Information Notices, Circulars, Enforcement Manual, Generic Letters, Inspection Manual, Policy Statements, Regulatory Guides, Standard Technical Specifications and the Standard Review Plan (NUREG-0800)

  7. Codes and standards and other guidance cited in regulatory documents

    Energy Technology Data Exchange (ETDEWEB)

    Nickolaus, J.R.; Bohlander, K.L.

    1996-08-01

    As part of the U.S. Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program (SRP-UDP), Pacific Northwest National Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. The SRP-UDP has been completed and the SRP-Maintenance Program (SRP-MP) is now maintaining this listing. Besides updating previous information, Revision 3 adds approximately 80 citations. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC`s Bulletins, Information Notices, Circulars, Enforcement Manual, Generic Letters, Inspection Manual, Policy Statements, Regulatory Guides, Standard Technical Specifications and the Standard Review Plan (NUREG-0800).

  8. Ex-plant consequence assessment for NUREG-1150: models, typical results, uncertainties

    International Nuclear Information System (INIS)

    Sprung, J.L.

    1988-01-01

    The assessment of ex-plant consequences for NUREG-1150 source terms was performed using the MELCOR Accident Consequence Code System (MACCS). This paper briefly discusses the following elements of MACCS consequence calculations: input data, phenomena modeled, computational framework, typical results, controlling phenomena, and uncertainties. Wherever possible, NUREG-1150 results will be used to illustrate the discussion. 28 references

  9. Organizational environment and operator culture

    International Nuclear Information System (INIS)

    Morisseau, D.S.; Schoenfeld, I.E.

    1988-01-01

    The Nuclear Regulatory Commission has historically reviewed corporate and plant level management and organization against the criteria of NUREG-0800, The Standard Review Plan. These criteria address the organizational structure, management control, lines of authority and communication, the range and level of experience, and the availability of manpower to effectively and safely operate the facility. Now that most nuclear power plants have received their operating licenses, the emphasis for review has shifted to the day-to-day operation of the facilities. Along with this has come greater recognition that hardware and engineering systems, through vitally important, are not the only components needed for safe operation of power plants. The people who run and operate these plants are a vitally important component and are an integral part of the entire system, i.e., machinery does not operate in isolation

  10. External event analysis methods for NUREG-1150

    International Nuclear Information System (INIS)

    Bohn, M.P.; Lambright, J.A.

    1989-01-01

    The US Nuclear Regulatory Commission is sponsoring probabilistic risk assessments of six operating commercial nuclear power plants as part of a major update of the understanding of risk as provided by the original WASH-1400 risk assessments. In contrast to the WASH-1400 studies, at least two of the NUREG-1150 risk assessments will include an analysis of risks due to earthquakes, fires, floods, etc., which are collectively known as eternal events. This paper summarizes the methods to be used in the external event analysis for NUREG-1150 and the results obtained to date. The two plants for which external events are being considered are Surry and Peach Bottom, a PWR and BWR respectively. The external event analyses (through core damage frequency calculations) were completed in June 1989, with final documentation available in September. In contrast to most past external event analyses, wherein rudimentary systems models were developed reflecting each external event under consideration, the simplified NUREG-1150 analyses are based on the availability of the full internal event PRA systems models (event trees and fault trees) and make use of extensive computer-aided screening to reduce them to sequence cut sets important to each external event. This provides two major advantages in that consistency and scrutability with respect to the internal event analysis is achieved, and the full gamut of random and test/maintenance unavailabilities are automatically included, while only those probabilistically important survive the screening process. Thus, full benefit of the internal event analysis is obtained by performing the internal and external event analyses sequentially

  11. Guidelines for the preparation of emergency operating procedures. Resolution of comments on NUREG-0799

    International Nuclear Information System (INIS)

    1982-08-01

    The purpose of this document is to identify the elements necessary for utilities to prepare and implement a program of Emergency Operating Procedures (EOPs) for use by control room personnel to assist in mitigating the consequences of a broad range of accidents and multiple equipment failures. This document applies only to the EOPs so designated; it does not address emergency preparedness or emergency planning. It also represents the resolution of comments on NUREG-0799, Draft Criteria for Preparation of Emergency Operating Procedures

  12. Application of NUREG-1150 methods and results to accident management

    International Nuclear Information System (INIS)

    Dingman, S.E.; Sype, T.T.; Camp, A.L.

    1990-01-01

    The risk from five nuclear power plants was examined during the NUREG-1150 program. When the analyses of the plants were complete, an effort was undertaken to examine the implications of NUREG-1150 for accident management initiatives. The framework provided by the NUREG-1150 analysis presented a means within which current accident management strategies could be evaluated and future accident management strategies could be developed and assessed. Five separate but interrelated phases of risk management were considered: (1) prevention of accident initiators, (2) prevention of core damage, (3) implementation of an effective emergency response, (4) prevention of vessel breach and mitigation of radionuclide releases from the reactor coolant system, and (5) retention of fission products in the containment and other surrounding buildings. A risk-based methodology was developed to identify and evaluate risk management options for each of these five phases. The methodology was demonstrated through quantitative examples for the first two phases of risk management listed above. In addition, the reduction in risk for several currently implemented risk management strategies at operating plants was quantified

  13. Environmental Standard Review Plan for the review of a license application for a low-level radioactive waste disposal facility: Environmental report

    International Nuclear Information System (INIS)

    1987-04-01

    The Environmental Standard Review Plan (ESRP) (NUREG-1300) provides guidance to staff reviewers in the Office of Nuclear Material Safety and Safeguards who perform environmental reviews of environmental reports prepared by applicants in support of license applications to construct and operate new low-level radioactive waste disposal facilities. The individual ESRPs that constitute this document identify the information considered necessary to conduct the review, the purpose and scope of the review, the analysis procedure and evaluation, the formal input to the environmental statement, and the references considered appropriate for each review. The ESRP is intended to ensure quality and uniformity of approach in individual reviews as well as compliance with the National Environmental Policy Act of 1969. In addition, the ESRP will make information about the environmental component of the licensing process more readily available and thereby will serve to improve the understanding of this process among the public, States and regional compacts, and the regulated community

  14. US Nuclear Regulatory Commission Human Factors Program Plan. Revision 1

    International Nuclear Information System (INIS)

    1984-09-01

    The purpose of the NRC Human Factors Program Plan (NUREG-0985) is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This revised plan addresses nuclear power plants (NPPs) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, THE NRC Action Plan developed as a result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention; (3) conduct of developmental activities specified in NUREG-0985 during FY-83; and (4) the impact of Section 306 of the Nuclear Waste Policy Act of 1982, PL 97-425. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-84 through FY-86 time frame

  15. Sealed source peer review plan

    International Nuclear Information System (INIS)

    Feldman, Alexander; Leonard, Lee; Burns, Ron

    2009-01-01

    Sealed sources are known quantities of radioactive materials that have been encapsulated in quantities that produce known radiation fields. Sealed sources have multiple uses ranging from instrument calibration sources to sources that produce radiation fields for experimental applications. The Off-Site Source Recovery (OSR) Project at Los Alamos National Laboratory (LANL), created in 1999, under the direction of the Waste Management Division of the U.S. Department of Energy (DOE) Albuquerque has been assigned the responsibility to recover and manage excess and unwanted radioactive sealed sources from the public and private sector. LANL intends to ship drums containing qualified sealed sources to the Waste Isolation Pilot Plant (WIPP) for disposal. Prior to shipping, these drums must be characterized with respect to radiological content and other parameters. The U. S. Environmental Protection Agency (EPA) requires that ten radionulcides be quantified and reported for every container of waste to be disposed in the WIPP. The methods traditionally approved by the EPA include non-destructive assay (NDA) in accordance with Appendix A of the Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (DOE, 2002) (CH WAC). However, because of the nature and pedigree of historical records for sealed sources and the technical infeasibility of performing NDA on these sources, LANL proposes to characterize the content of these waste drums using qualified existing radiological data in lieu of direct measurement. This plan describes the process and documentation requirements for the use of the peer review process to qualify existing data for sealed radiological sources in lieu of perfonning radioassay. The peer review process will be performed in accordance with criteria provided in 40 CFR (section) 194.22 which specifies the use of the NUREG 1297 guidelines. The plan defines the management approach, resources, schedule, and technical requirements

  16. Aging/Systems Interaction Study, Component Residual Lifetime Evaluation and Feasibility of Relicensing. Progress report, FY 1985

    International Nuclear Information System (INIS)

    Close, J.A.; Jacobs, P.T.; Korth, G.E.; Mudlin, J.M.; Server, W.L.; Spaletta, H.W.

    1985-10-01

    This report documents the work performed on four research tasks in Fiscal Year 1985 (FY-1985) which were part of the Aging/Systems Interaction Study, Component Residual Lifetime Evaluation and Feasibility of Relicensing Project. The technical and management/institutional objectives for the project are described, followed by a description of the results of each task. The work on Task 1 involved identifying and prioritizing new research activities for the Nuclear Regulatory Commission (NRC) Nuclear Plant Aging Research (NPAR) Program. A proposed methodology and plan for aging-system interaction studies was developed in Task 2. The description of Task 3 work comprises a summary of nuclear plant life extension activities in the US, the technical basis associated with the residual life of metallic materials and a proposed plan for research on residual life assessment. Task 4 describes the initial evaluation of selected Standard Review Plan (NUREG-0800) sections to investigate the feasibility of relicensing. 14 refs., 13 figs., 20 tabs

  17. A Qualitative Assessment of Current CCF Guidance Based on a Review of Safety System Digital Implementation Changes with Evolving Technology

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, Kofi [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Muhlheim, Michael David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wood, Richard [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    The US Nuclear Regulatory Commission (NRC) is initiating a new rulemaking project to develop a digital system common-cause failure (CCF) rule. This rulemaking will review and modify or affirm the NRC's current digital system CCF policy as discussed in the Staff Requirements Memorandum to the Secretary of the Commission, Office of the NRC (SECY) 93-087, Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light Water Reactor (ALWR) Designs, and Branch Technical Position (BTP) 7-19, Guidance on Evaluation of Defense-in-Depth and Diversity in Digital Computer-Based Instrumentation and Control Systems, as well as Chapter 7, Instrumentation and Controls, in NRC Regulatory Guide (NUREG)-0800, Standard Review Plan for Review of Safety Analysis Reports for Nuclear Power Plants (ML033580677). The Oak Ridge National Laboratory (ORNL) is providing technical support to the NRC staff on the CCF rulemaking, and this report is one of several providing the technical basis to inform NRC staff members. For the task described in this report, ORNL examined instrumentation and controls (I&C) technology implementations in nuclear power plants in the light of current CCF guidance. The intent was to assess whether the current position on CCF is adequate given the evolutions in digital safety system implementations and, if gaps in the guidance were found, to provide recommendations as to how these gaps could be closed.

  18. 76 FR 28819 - NUREG/CR-XXXX, Development of Quantitative Software Reliability Models for Digital Protection...

    Science.gov (United States)

    2011-05-18

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0109] NUREG/CR-XXXX, Development of Quantitative Software...: The Nuclear Regulatory Commission has issued for public comment a document entitled: NUREG/CR-XXXX...-XXXX is available electronically under ADAMS Accession Number ML111020087. Federal Rulemaking Web Site...

  19. Insights from Siting New Nuclear Power Plants in the Central and Eastern United States

    International Nuclear Information System (INIS)

    Munson, Clifford G.; Kugler, Andrew J.

    2011-01-01

    The staff of the U.S. Nuclear Regulatory Commission (NRC) has completed its review for four early site permits and for four standard reactor designs. It is currently reviewing applications for fourteen combined license applications and three additional reactor designs. The staff is applying lessons it has learned from the reviews to date to the review work going forward. The licensing process being used by current applicants differs significantly from that used by the current operating fleet. The previous process required two steps. First an applicant had to obtain a construction permit to build the plant. Then, near the end of construction, the applicant had to obtain an operating license. Under the process in Part 52, an applicant can apply for a combined license (COL) that allows construction and (once certain conditions are met) operation of a new plant - a one-step process. An applicant for a COL may reference an early site permit (ESP13), a standard design certification, both, or neither. In addition to developing Part 52, the NRC also revised CFR Part 100 by adding Subpart B, which includes sections 100.21, 'Non-seismic siting criteria', and 100.23, 'Geologic and seismic siting criteria'. The NRC staff also revised the Standard Review Plan (NUREG-0800) and developed Regulatory Guide (RG) 1.206, 'Combined License Applications for Nuclear Power Plants (LWR Edition).' The NRC staff incorporated into the revision of NUREG-0800 and development of RG 1.206 some early lessons learned from its review of the first three ESPs. Staff work begins before the application is received, as the staff interacts with the applicant to identify issues that will require special treatment or specific staff resources. After the application is submitted, if the NRC finds the application acceptable, the safety and environmental reviews begin, proceeding in parallel. The safety review culminates in the issuance of a safety evaluation report (SER) after it

  20. 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

  1. 76 FR 61402 - Draft Nuclear Regulatory Commission Fiscal Year 2012-2016 Strategic Plan

    Science.gov (United States)

    2011-10-04

    ...-2016 Strategic Plan AGENCY: Nuclear Regulatory Commission. ACTION: Draft NUREG; request for comment... comment on draft NUREG-1614, Volume 5. ``U.S. Nuclear Regulatory Commission, FY 2012-2016 Strategic Plan,'' dated September 2011. The NRC's draft FY 2012-2016 strategic plan describes the agency's mission and...

  2. TANK FARM CLOSURE - A NEW TWIST ON REGULATORY STRATEGIES FOR CLOSURE OF WASTE TANK RESIDUALS FOLLOWING NUREG

    International Nuclear Information System (INIS)

    LEHMAN LL

    2008-01-01

    Waste from a number of single-shell tanks (SST) at the U.S. Department of Energy's (DOE) Hanford Site has been retrieved by CH2M HILL Hanford Group to fulfill the requirements of the 'Hanford Federal Facility Agreement and Consent Order (HFFACO) [1]. Laboratory analyses of the Hanford tank residual wastes have provided concentration data which will be used to determine waste classification and disposal options for tank residuals. The closure of tank farm facilities remains one of the most challenging activities faced by the DOE. This is due in part to the complicated regulatory structures that have developed. These regulatory structures are different at each of the DOE sites, making it difficult to apply lessons learned from one site to the next. During the past two years with the passage of the Section 3116 of the 'Ronald Reagan Defense Authorization Act of 2005' (NDAA) [2] some standardization has emerged for Savannah River Site and the Idaho National Laboratory tank residuals. Recently, with the issuance of 'NRC Staff Guidance for Activities Related to US. Department of Energy Waste Determinations' (NUREG-1854) [3] more explicit options may be considered for Hanford tank residuals than are presently available under DOE Orders. NUREG-1854, issued in August 2007, contains several key pieces of information that if utilized by the DOE in the tank closure process, could simplify waste classification and streamline the NRC review process by providing information to the NRC in their preferred format. Other provisions of this NUREG allow different methods to be applied in determining when waste retrieval is complete by incorporating actual project costs and health risks into the calculation of 'technically and economically practical'. Additionally, the NUREG requires a strong understanding of the uncertainties of the analyses, which given the desire of some NRC/DOE staff may increase the likelihood of using probabilistic approaches to uncertainty analysis. The purpose

  3. 2018 NDIA Precision Strike Annual Review (PSAR-18)

    Science.gov (United States)

    2018-03-20

    Planning Agenda as of 9 MAR 18 Ginny Sniegon: 703-575-6653 PRECISION STRIKE ANNUAL REVIEW (PSAR-18) 20 MARCH 2018...Ginny Sniegon PSA Programs Vice-Chair: Captain David “Jumbo” Baird, USN Annual Review Chair: Kurt Chankaya Congressional & William J. Perry...0745 PSA ANNUAL REVIEW WELCOME: Ken Masson—PSA Chairman 0755 PSAR-18 OPENING REMARKS: Kurt Chankaya—PSAR-18 Event Chair 0800 CONGRESSIONAL

  4. Vogtle Electric Generating Plant ETE Analysis Review

    Energy Technology Data Exchange (ETDEWEB)

    Diediker, Nona H.; Jones, Joe A.

    2006-12-09

    Under contract with the Nuclear Regulatory Commission (NRC), staff from Pacific Northwest National Laboratory (PNNL) and Sandia National Laboratory (SNL)-Albuquerque reviewed the evacuation time estimate (ETE) analysis dated April 2006 prepared by IEM for the Vogtle Electric Generating Plant (VEGP). The ETE analysis was reviewed for consistency with federal regulations using the NRC guidelines in Review Standard (RS)-002, Supplement 2 and Appendix 4 to NUREG-0654, and NUREG/CR-4831. Additional sources of information referenced in the analysis and used in the review included NUREG/CR-6863 and NUREG/CR-6864. The PNNL report includes general comments, data needs or clarifications, and requests for additional information (RAI) resulting from review of the ETE analysis.

  5. 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.

  6. 76 FR 52995 - Draft License Renewal Interim Staff Guidance LR-ISG-2011-05: Ongoing Review of Operating...

    Science.gov (United States)

    2011-08-24

    ... Rulemaking Web Site: Go to http://www.regulations.gov and search for documents filed under Docket ID NRC... Lessons Learned (GALL) Report,'' and the NRC staff's aging management review procedures and acceptance criteria in NUREG-1800, Revision 2, ``Standard Review Plan for Review of License Renewal Applications for...

  7. Use of NUREG-1150 and IPEs in accident management

    International Nuclear Information System (INIS)

    Mauersberger

    1992-01-01

    The fundamental objective of the accident management program is to assure, in the event of a severe accident at a nuclear plant, that the effectiveness of personnel and equipment is maximized in preventing or mitigating the consequences of the accident. This document studies the use of NUREG-1150 and IPEs in accident management. Figs

  8. Peer-review study of the draft handbook for human-reliability analysis with emphasis on nuclear-power-plant applications, NUREG/CR-1278

    Energy Technology Data Exchange (ETDEWEB)

    Brune, R. L.; Weinstein, M.; Fitzwater, M. E.

    1983-01-01

    This report describes a peer review of the draft Handbook for Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications, NUREG/CR-1278. The purpose of the study was to determine to what extent peers agree with the human behavior models and estimates of human error probabilities (HEPs) contained in the Handbook. Twenty-nine human factors experts participated in the study. Twenty of the participants were Americans; nine were from other countries. The peers performed human reliability analyses of a variety of human performance scenarios describing operator activities in nuclear power plant settings. They also answered questionnaires pertaining to the contents and application of the Handbook. An analysis of peer solutions to the human reliability analysis problems and peer responses to the questionnaire was performed. Recommendations regarding the format and contents of the Handbook were developed from the study findings.

  9. Technical evaluation report - TMI action: NUREG-0737 (II.D.1) relief and safety valve testing for Grand Gulf Nuclear Station Unit No. 1 (Docket No. 50-416)

    International Nuclear Information System (INIS)

    Burr, T.K.; Nalezny, C.L.

    1985-09-01

    Light water reactors operators have experienced a number of occurrences of improper performance by safety and relief valves installed in their primary coolant systems. Because of this, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations) recommended that programs be developed and completed which would reevaluate the performance capabilities of BWR safety and relief valves. This report provides the results of the review of these programs and their results by the NRC and their consultant, EG and G Idaho, Inc. Specifically, this report has examined the response of the Licensee for the Grand Gulf Nuclear Station, Unit 1 to the requirements of NUREG-0578 and subsequently NUREG-0737 and finds that the Licensee has provided an acceptable response, reconfirming that the General Design Criteria 14, 15 and 30 of Appendix A to 10 CFR-50 have been met

  10. Safety evaluation review of the prototype license application safety analysis report

    International Nuclear Information System (INIS)

    1991-08-01

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

  11. 78 FR 71676 - NUREG-1482, Revision 2, “Guidelines for Inservice Testing at Nuclear Power Plants, Final Report”

    Science.gov (United States)

    2013-11-29

    ... Testing at Nuclear Power Plants, Final Report'' AGENCY: Nuclear Regulatory Commission. ACTION: Notice of... entitled: NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at Nuclear Power Plants,'' and... Restraints (Snubbers) at Nuclear Power Plants.'' In the previous Revisions 0 and 1 of NUREG-1482, the NRC...

  12. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Format and Content. NUREG-1537, Part 1

    International Nuclear Information System (INIS)

    1996-02-01

    NUREG - 1537, Part 1 gives guidance to non-power reactor licensees and applicants on the format and content of applications to the Nuclear Regulatory Commission for licensing actions. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination

  13. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Format and Content. NUREG-1537, Part 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    NUREG - 1537, Part 1 gives guidance to non-power reactor licensees and applicants on the format and content of applications to the Nuclear Regulatory Commission for licensing actions. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination.

  14. 76 FR 75771 - Emergency Planning Guidance for Nuclear Power Plants

    Science.gov (United States)

    2011-12-05

    ... Guidance for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Issuance of NUREG... Support of Nuclear Power Plants;'' NSIR/DPR-ISG-01, ``Interim Staff Guidance Emergency Planning for Nuclear Power Plants;'' and NUREG/CR-7002, ``Criteria for Development of Evacuation Time Estimate Studies...

  15. Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants: Criteria for utility offsite planning and preparedness: Final report

    International Nuclear Information System (INIS)

    Podolak, E.M. Jr.; Sanders, M.E.; Wingert, V.L.; Donovan, R.W.

    1988-09-01

    The Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) have added a supplement to NUREG-0654/FEMA-REP-1, Rev. 1 that provides guidance for the development, review, and evaluation of utility offsite radiological emergency response planning and preparedness for those situations in which state and/or local governments decline to participate in emergency planning. While this guidance primarily applies to plants that do not have full-power operating licenses, it does have relevance to operating nuclear power plants

  16. Reactor siting risk comparisons related to recommendations of NUREG-0625

    International Nuclear Information System (INIS)

    Barsell, A.W.; Dombek, F.S.; Orvis, D.D.

    1980-11-01

    This document evaluates how implementing the remote siting recommendations for nuclear reactors (NUREG-0625) made by the Siting Policy Task Force of the US Nuclear Regulatory Commission (NRC) can reduce potential public risk. The document analyzes how population density affects site-specific risk for both light water reactors (LWRs) and high-temperature gas-cooled reactors

  17. Risk uncertainty analysis methods for NUREG-1150

    International Nuclear Information System (INIS)

    Benjamin, A.S.; Boyd, G.J.

    1987-01-01

    Evaluation and display of risk uncertainties for NUREG-1150 constitute a principal focus of the Severe Accident Risk Rebaselining/Risk Reduction Program (SARRP). Some of the principal objectives of the uncertainty evaluation are: (1) to provide a quantitative estimate that reflects, for those areas considered, a credible and realistic range of uncertainty in risk; (2) to rank the various sources of uncertainty with respect to their importance for various measures of risk; and (3) to characterize the state of understanding of each aspect of the risk assessment for which major uncertainties exist. This paper describes the methods developed to fulfill these objectives

  18. US Nuclear Regulatory Commission human-factors program plan

    International Nuclear Information System (INIS)

    1983-08-01

    The purpose of the NRC Human Factors Program Plan is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This initial plan addresses nuclear power plants (NPP) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, The NRC Action Plan Developed as a Result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements, and (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-83 through FY-85 time frame

  19. validering af det noninvasive terumo digital termometer 0800H5- et case control studie

    DEFF Research Database (Denmark)

    Vamosi, Marianne

    2014-01-01

    , Parret T-test, P-værdi og BlandAltman. Statistik programmet R version. 3.0.0 er anvendt. Resultater I dette studie har analysen af Thermofocus 0800H5 og Terumo–digital c405 og vist standard deviasion (SD) på ± 0,46. ANOVA analysen viste en styrke (p værdi) p

  20. 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

  1. 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.

  2. 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.

  3. The NUREG-1150 probabilistic risk assessment for the Grand Gulf nuclear station

    International Nuclear Information System (INIS)

    Brown, T.D.; Breeding, R.J.; Jow, H.N.; Higgins, S.J.; Shiver, A.W.; Helton, J.C.

    1992-01-01

    This paper summarizes the findings of the probabilistic risk assessment (PRA) for Unit 1 of the Grand Gulf Nuclear Station performed in support of NUREG-1150. The emphasis is on the 'back-end' analyses, that is, the acident progression, source term, consequence analsyes, and risk results obtained when the results of these analyses are combined with the accident frequency analysis. The offsite risk from internal initiating events was found to be quite low, both with respect to the safety goals and to the other plants analyzed in NUREG-1150. The offsite risk is dominated by short-term station blackout plant damage states. The long-term blackout group and the anticiptated transients without scram (ATWS) group contribute considerably less to risk. Transients in which the power conversion system is unavailable are very minor contributors to risk. The low values for risk can be attributed to low core damage frequency, good emergency response, and plant features that reduce the potential source term. (orig.)

  4. A Framework for Evaluating the Effects of Degraded Digital I and C Systems on Human Performance

    International Nuclear Information System (INIS)

    OHara, J.; Gunther, B.; Hughes, N.; Barnes, V.

    2009-01-01

    New and advanced reactors will use integrated digital instrumentation and control (I and C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator situation awareness and performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission has initiated a research project to investigate the effects of degraded I and C systems on human performance and plant operations. The ultimate objective of this project is to develop the technical basis for human factors review guidance for conditions of degraded I and C, including complete failure. Based on the results of this effort, NRC will determine the need for developing new guidance or revising NUREG-0800, NUREG-0711, NUREG-0700 and other pertinent NRC review guidance. This paper reports on the first phase of the research, the development of a framework for linking degraded I and C system conditions to human performance. The framework consists of three levels: I and C subsystems, human-system interfaces, and human performance. Each level is composed of a number of discrete elements. This paper will describe the elements at each level and their integration. In the next phase of the research, the framework will be used to systematically investigate the human performance consequences of various classes of failures

  5. Developing and assessing accident management plans for nuclear power plants

    International Nuclear Information System (INIS)

    Hanson, D.J.; Johnson, S.P.; Blackman, H.S.; Stewart, M.A.

    1992-07-01

    This document is the second of a two-volume NUREG/CR that discusses development of accident management plans for nuclear power plants. The first volume (a) describes a four-phase approach for developing criteria that could be used for assessing the adequacy of accident management plans, (b) identifies the general attributes of accident management plans (Phase 1), (c) presents a prototype process for developing and implementing severe accident management plans (Phase 2), and (d) presents criteria that can be used to assess the adequacy of accident management plans. This volume (a) describes results from an evaluation of the capabilities of the prototype process to produce an accident management plan (Phase 3) and (b), based on these results and preliminary criteria included in NUREG/CR-5543, presents modifications to the criteria where appropriate

  6. U.S. Nuclear Regulatory Commission human factors program plan

    International Nuclear Information System (INIS)

    1986-04-01

    The purpose of the U.S. Nuclear Regulatory Commission (NRC) Human Factors Program Plan is to ensure that proper consideration is given to human factors in the design and operation of nuclear facilities. This revised plan addresses human factors issues related to the operation of nuclear power plants (NPPs). The three issues of concern are (1) the activities planned to provide the technical bases to resolve the remaining tasks related to human factors as described in NUREG-0660, The NRC Action Plan Developed as a Result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the need to address the additional human factors efforts that were identified during implementation of the Action Plan; and (3) the actual fulfillment of those developmental activities specified in Revision 1 of this plan. The plan represents a systematic approach for addressing high priority human factors concerns important to NPP safety in FY 1986 through 1987

  7. Operating experience review in development of SMART MMIS

    International Nuclear Information System (INIS)

    Suh, S. M.; Jang, G. S.; Lee, J. G.; Park, G. O.; Ko, J. H.

    2004-01-01

    We have developed HFE(Human Factors Engineering) program plan for the purpose of implementing man-machine interface system in SMART plant systematically. Elements of the plan are compatible to those of NUREG-0711, Rev.1, and OER(Operating Experience Review) is one of them. The main purpose of conducting an OER as part of HFE review is to identify HFE-related safety issues. If identified, design alternatives are carefully reviewed and selected as the way of resolution for those issues. The performing model of OER is described in this paper, showing a series of works must be done to identify and resolve HFE-related issues within the scope of SMART HFE works. Then two key issues and design alternatives resolving them are presented for examples

  8. 77 FR 8751 - Guidance for Decommissioning Planning During Operations

    Science.gov (United States)

    2012-02-15

    ..., 40, 50, 70, and 72 [NRC-2011-0286] Guidance for Decommissioning Planning During Operations AGENCY... Guide, DG-4014, ``Decommissioning Planning During Operations'' in the Federal Register with a public... Guide DG-4014, ``Decommissioning Planning During Operations.'' This DG refers to NUREG-1757 Volume 3...

  9. Implementation of NUREG-1318 guidance within the Yucca Mountain Project

    International Nuclear Information System (INIS)

    La Monica, L.B.; Waddell, J.D.; Hardin, E.L.

    1990-01-01

    The US Department of Energy's Yucca Mountain Project is implementing a quality assurance program that fulfills the requirements of the US Nuclear Regulatory Commission (NRC). Additional guidance for this program was provided in NUREG 1318, ''Technical Position on Items and Activities in the High-Level Waste Geologic Repository Program Subject to Quality Assurance Requirements'' for identification of items and activities important to public radiological safety and waste isolation. The process and organization for implementing this guidance is discussed. 3 refs., 2 figs

  10. Technical note: Erroneous data in open-quotes Nuclear Safety Guide, TID-7016, Revision 2,close quotes NUREG/CR-0095, ORNL/NUREG/CSD-6 (1978)

    International Nuclear Information System (INIS)

    Whitesides, G.E.

    1991-01-01

    Nuclear Safety Guide, TID-7016 Rev 2 was issued as NUREG/CR-0095 in 1978. Table 2.8 of this report has been found to contain errors. The table was designed to indicate configurations with effective multipliction factors of 0.95. Because of an error in configuration descriptions, some of the configurations have multiplication factors as high as 1.09. A corrected table is available from the undersigned, and Revision 3 of the report is being prepared. Norman L. Pruvost, LANL HSE-6, P. O. Box 1663, M/S-F691, Los Alamos, NM 87545

  11. Evaluation of Component Failure Data of the Operating Nuclear Power Plants in Korea Based on NUREG/CR-6928

    International Nuclear Information System (INIS)

    Jeon, Hojun; Na, Janghwan; Shin, Taeyoung

    2014-01-01

    This paper focuses on ensuring the quality of component failure data. When performing data analysis in PSA, we have customized the component failure data based on Bayesian analysis using plant specific experiences and the generic data of Advanced Light Water Reactor Utility Requirements Document (ALWR URD). However, ALWR URD was established by collecting US nuclear power plant (NPP) practices from mid 1980s to early 1990s. We analyzed the component failure data using the raw data of component failures in Pressurized Water Reactor (PWR) plants by 2012. This paper presents the results from analyzing the component failure data based on the new generic data and the latest specific failure data. We also compare the new component failure data to the existing data of PSA models, and evaluate the risk impacts by applying the new data to the PSA models of reference NPPs in this paper. To apply the new generic data source to PSA models, we reviewed and compared NUREG/CR-6928 and the existing generic data source, ALWR URD. In addition, we analyzed the component failure data generated from 16 PWR plants by the end of 2012, and performed the Bayesian update with these raw data based on the new generic data source of NUREG/CR-6928. Also, we reviewed the PSA models of the reference NPP, and identified some important components to CDF. The failure data of the major components decreased in general by applying the new generic data and the latest plant specific data. As a result, the CDF of the reference NPP decreased over 30% compared to the value of the existing CDF

  12. Relation between source term and emergency planning for nuclear power plants

    International Nuclear Information System (INIS)

    Shi Zhongqi; Yang Ling

    1992-01-01

    Some background information of the severe accidents and source terms related to the nuclear power plant emergency planning are presented. The new source term information in NUREG-0956 and NUREG-1150, and possible changes in emergency planning requirements in U.S.A. are briefly provided. It is suggested that a principle is used in selecting source terms for establishing the emergency planning policy and a method is used in determining the Emergency Planning Zone (EPZ) size in China. Based on the research results of (1) EPZ size of PWR nuclear power plants being built in China, and (2) impact of reactor size and selected source terms on the EPZ size, it is concluded that the suggested principle and the method are suitable and feasible for PWR nuclear power plants in China

  13. Implementation of NUREG 1318 guidance within the Yucca Mountain Project

    International Nuclear Information System (INIS)

    La Monica, L.B.; Waddell, J.D.; Hardin, E.L.

    1990-01-01

    This paper discusses the implementation of a quality assurance program that fulfills the requirements of the U.S. Nuclear Regulatory Commission (NRC). Additional guidance for this program was provided in NUREG 1318, Technical Position on Items and Activities in the High-Level Waste Geologic Repository Program Subject to Quality Assurance Requirements for the identification of items and activities important to public radiological safety and waste isolation for placement on a Q-List and Quality Activities List and also for graded application of QA measures. The process and organization for implementing this guidance is discussed

  14. Summary and analysis of public comments on NUREG-1317: Regulatory options for nuclear plant license renewal: Final report

    International Nuclear Information System (INIS)

    Ligon, D.M.; Seth, S.S.

    1989-03-01

    On August 29, 1988, the US Nuclear Regulatory Commission (NRC) issued an Advance Notice of Proposed Rulemaking on nuclear plant license renewal and solicited public comments on NUREG-1317, ''Regulatory Options for Nuclear Plant License Renewal.'' NUREG-1317 presents a discussion of fifteen topics involving technical, environmental, and procedural issues and poses a set of related questions. As part of its ongoing task for the NRC, The MITRE Corporation has summarized and analyzed the public comments received. Fifty-three written comments were received. Of these, 83 percent were from nuclear industry representatives; the remaining comments represented federal and state agencies, public interest groups, and a private citizen

  15. Human reliability analysis for advanced control room of KNGR

    International Nuclear Information System (INIS)

    Kim, Myung-Ro; Park, Seong-Kyu

    2000-01-01

    There are two purposes in Human Reliability Analysis (HRA) which was performed during Korean Next Generation Reactor (KNGR) Phase 2 research project. One is to present the human error probability quantification results for Probabilistic Safety Assessment (PSA) and the other is to provide a list of the critical operator actions for Human Factor Engineering (HFE). Critical operator actions were identified from the KNGR HRA/RSA based on selection criteria and incorporated in the MMI Task Analysis, where they receive additional treatment. The use of HRA/PSA results in design, procedure development, and training was ensured by their incorporation in the MMI task analysis and MCR design such as fixed position alarms, displays and controls. Any dominant PSA sequence that takes credit for human performance to achieve acceptable results was incorporated in MMIS validation activities through the PSA-based critical operator actions. The integration of KNGR HRA into MMI design was sufficiently addressed all applicable review criteria of NUREG-0800, Chapter 18, Section 2 F and NUREG-0711. (S.Y.)

  16. Human Resource Managements as a part of the Human Factors Management Program(HFMP) for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, DaeHo; Lee, YongHee; Lee, JungWoon; Kim, Younggab

    2007-01-01

    Programs for the effective implementation and management of human factor issues in nuclear power plants (NPPs) should contain technical criteria, an establishment of a job process, and activities for job improvements and be a system through which human factors can be managed in an integrated way. Human factors to be managed should include those related to an operation of plants as well as those related to a plant design as mentioned in NUREG-0800(2004), NUREG- 0711(2004), and NUREG-0700(2002). Human factor items to be managed for an operation of plants are listed in the PSR (Periodic Safety Review) items defined in the Enforcement of Regulation of the Atomic Energy Act. They are procedures, a work management system including a shift work management, a qualification management of plant personnel, training, a work amount assessment, a MMI (Man Machine Interface), and the use of experience. Among these factors, factors related to a human resource management include work management systems and the status of a work management including shift work, a qualification management ensuring qualified workers on duty at all times, and the systems for and the status of training and education. This paper addresses the scope of a human resource management, guidelines and procedures to be developed for a human resource management, and considerations critical in the development of guidelines and procedures

  17. Technical evaluation report TMI action - NUREG-0737 (II.D.1) relief and safety valve testing for Clinton Power Station Unit 1. (Docket No. 50-461)

    International Nuclear Information System (INIS)

    Burr, T.K.; Magleby, H.L.

    1985-05-01

    Light water reactors operators have experienced a number of occurrences of improper performance by safety and relief valves installed in their primary coolant systems. Because of this, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations) recommended that programs be developed and completed which would reevaluate the performance capabilities of BWR safety and relief valves. This report has examined the response of the Licensee for the Clinton Power Station, Unit 1 to the requirements of NUREG-0578 and subsequently NUREG-0737 and finds that the Licensee has provided an acceptable response, reconfirming that the General Design Criteria 14, 15 and 30 of Appendix A to 10 CFR-50 have been met

  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. 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

  20. 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

  1. 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.

  2. 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

  3. Containment integrity research program plan

    International Nuclear Information System (INIS)

    1987-08-01

    This report presents a plan for research on the question of containment performance in postulated severe accident scenarios. It focuses on the research being performed by the Structural and Seismic Engineering Branch, Division of Engineering, Office of Nuclear Regulatory Research. Summaries of the plans for this work have previously been published in the ''Nuclear Power Plant Severe Accident Research Plan'' (NUREG-0900). This report provides an update to reflect current status. This plan provides a summary of results to date as well as an outline of planned activities and milestones to the contemplated completion of the program in FY 1989

  4. NRC plan for cleanup operations at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    Lo, R.; Snyder, B.

    1982-02-01

    This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup operations as well as NRC's interface with the Department of Energy's involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC's role in ongoing and future cleanup activities

  5. Implications of NUREG-1150 for equipment qualification

    International Nuclear Information System (INIS)

    Siu, R.P.; Sarram, M.

    1988-01-01

    Current USNRC regulations in 10CFR50 requires that structures, systems and components important to safety in a nuclear power plant are to be designed to accommodate the effects of harsh environments associated with potential accidents. Detailed regulatory requirements are as discussed in Regulatory Guide 1.89. Some of these regulatory requirements have been based upon rather outdated understanding of the phenomenology of severe accidents -- e.g., the radiation source terms for equipment qualification can be traced to TID-14844 which was originally published in 1962. Furthermore, the definition of important-to-safety in these regulatory requirements is rather broad, usually resulting in a long Q-list of equipment to be qualified for the design-basis Large LOCA. In the past few years, extensive research/analysis on severe accidents have been conducted -- from the IREP/NREP activities, the IDCOR programs, to the NUREG-1150 efforts. This paper reports that as a result of all these PRA-related activities, a much-improved understanding of the phenomenology and environmental conditions associated with severe accidents has been gained

  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. Review of Quantitative Software Reliability Methods

    Energy Technology Data Exchange (ETDEWEB)

    Chu, T.L.; Yue, M.; Martinez-Guridi, M.; Lehner, J.

    2010-09-17

    The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on deterministic engineering criteria. In its 1995 probabilistic risk assessment (PRA) policy statement, the Commission encouraged the use of PRA technology in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data. Although many activities have been completed in the area of risk-informed regulation, the risk-informed analysis process for digital systems has not yet been satisfactorily developed. Since digital instrumentation and control (I&C) systems are expected to play an increasingly important role in nuclear power plant (NPP) safety, the NRC established a digital system research plan that defines a coherent set of research programs to support its regulatory needs. One of the research programs included in the NRC's digital system research plan addresses risk assessment methods and data for digital systems. Digital I&C systems have some unique characteristics, such as using software, and may have different failure causes and/or modes than analog I&C systems; hence, their incorporation into NPP PRAs entails special challenges. The objective of the NRC's digital system risk research is to identify and develop methods, analytical tools, and regulatory guidance for (1) including models of digital systems into NPP PRAs, and (2) using information on the risks of digital systems to support the NRC's risk-informed licensing and oversight activities. For several years, Brookhaven National Laboratory (BNL) has worked on NRC projects to investigate methods and tools for the probabilistic modeling of digital systems, as documented mainly in NUREG/CR-6962 and NUREG/CR-6997. However, the scope of this research principally focused on hardware failures, with limited reviews of software failure experience and software reliability methods. NRC also sponsored research at the Ohio State University investigating the modeling of

  8. 76 FR 46330 - NUREG-1934, Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG); Second Draft...

    Science.gov (United States)

    2011-08-02

    ... NUCLEAR REGULATORY COMMISSION [NRC-2009-0568] NUREG-1934, Nuclear Power Plant Fire Modeling... 1023259), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft Report for...), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft for Comment,'' is...

  9. Identification of Aircraft Hazards

    International Nuclear Information System (INIS)

    K. Ashley

    2006-01-01

    Aircraft hazards were determined to be potentially applicable to a repository at Yucca Mountain in ''Monitored Geological Repository External Events Hazards Screening Analysis'' (BSC 2005 [DIRS 174235], Section 6.4.1). That determination was conservatively based upon limited knowledge of flight data in the area of concern and upon crash data for aircraft of the type flying near Yucca Mountain. The purpose of this report is to identify specific aircraft hazards that may be applicable to a monitored geologic repository (MGR) at Yucca Mountain, using NUREG-0800, ''Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (NRC 1987 [DIRS 103124], Section 3.5.1.6), as guidance for the inclusion or exclusion of identified aircraft hazards. The intended use of this report is to provide inputs for further screening and analysis of identified aircraft hazards based upon the criteria that apply to Category 1 and Category 2 event sequence analyses as defined in 10 CFR 63.2 [DIRS 176544] (Section 4). The scope of this report includes the evaluation of military, private, and commercial use of airspace in the 100-mile regional setting of the repository at Yucca Mountain with the potential for reducing the regional setting to a more manageable size after consideration of applicable screening criteria (Section 7)

  10. Radiological characterization and challenges at decommissioning sites

    International Nuclear Information System (INIS)

    Moore, Scott

    2002-01-01

    Scott Moore described the dose-based radiological characterisation process used in the USA, and four current characterisation issues faced there. His paper emphasized the importance of characterisation to control decommissioning hazards and costs: The License Termination Rule (LTR), Subpart E to 10 CFR Part 20, provides the dose-based criteria that the U.S. Nuclear Regulatory Commission (NRC) uses as the basis for regulating cleanup at material and reactor sites. The LTR permits the release of sites for unrestricted use, if the radioactivity that is distinguishable from background results in a total effective dose equivalent to an average member of a critical group that does not exceed 0.25 milli-Sievert per year (mSv/yr) (25 milli-rem/year) and the residual radioactivity has been reduced to levels that are as low as reasonably achievable. Additionally, the LTR establishes criteria for license termination with restrictions on future land use, which allow for a dose to the critical group of 0.25 mSv/yr (25 milli-rem/year) with restrictions in place, and 1 mSv/yr (100 milli-rem/year) if the restrictions fail. In certain circumstances as outlined in Subpart E, a dose as high as 5 mSv/yr (500 milli-rem/year) is permitted if restrictions fail. Following issuance of the dose-based LTR in 1997, NRC staff developed the Standard Review Plan for Decommissioning Plans (NUREG-1727). NUREG-1727 is a guidance document that describes the methods that NRC has determined are acceptable for implementing the LTR and other decommissioning regulations. While NUREG-1727 is focused on the review of decommissioning plans for nuclear material sites, it provides general guidance that in many cases is applicable to reactor sites (e.g., review criteria for dose-modeling and radiological surveys). In addition to NUREG-1727, staff developed the Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans (NUREG-1700) as specific guidance for reactor decommissioning. NUREG

  11. Performance assessment review guide for DOE low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Dodge, R.L.; Hansen, W.R.; Kennedy, W.E. Jr.; Layton, D.W.; Lee, D.W.; Maheras, S.T.; Neuder, S.M.; Wilhite, E.L.; Curl, R.U.; Grahn, K.F.; Heath, B.A.; Turner, K.H.

    1991-10-01

    This report was prepared under the direction of the Performance Assessment Peer Review Panel. The intent is to help Department of Energy sites prepare performance assessments that meet the Panel's expectations in terms of detail, quality, content, and consistency. Information on the Panel review process and philosophy are provided, as well as important technical issues that will be focused on during a review. This guidance is not intended to provide a detailed review plan as in NUREG-1200, Standard Review Plan for Review of a License Application for a Low-Level Radioactive Waste Disposal Facility (January 1988). The focus and intent of the Panel's reviews differ significantly from a regulatory review. The review of a performance assessment by the Panel uses the collective professional judgment of the members to ascertain that the approach taken the methodology used, the assumptions made, etc., are technically sound and adequately justified. The results of the Panel's review will be used by Department of Energy Headquarters in determining compliance with the requirements of DOE Order 5820.2A, ''Radioactive Waste Management.''

  12. 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.

  13. Containment Emergency Sump Performance. Technical findings related to Unresolved Safety Issue A-43. Revision 1

    International Nuclear Information System (INIS)

    1985-10-01

    This report summarizes key technical findings related to Unresolved Safety Issue (USI) A-43, Containment Emergency Sump Performance. Both BWRs and PWRs are considered in this report. Emergency core cooling systems require a clean, reliable water source to maintain long-term recirculation following a loss-of-coolant accident (LOCA). PWRs rely on the containment emergency sump to provide such a water supply to residual heat removal pumps and containment spray pumps. BWRs rely on pump suction intakes in the suppression pool or wet well to provide water to residual heat removal and core spray systems. Thus, the technical findings in this report provide information on post-LOCA recirculation. These findings have been derived from extensive experimental studies, generic plant studies, and assessments of sumps used for long-term cooling. Results of hydraulic tests have shown that the potential for air ingestion is less severe than previously hypothesized. The effects of debris blockage on NPSH margin must be dealt with on a plant-specific basis. These findings have been used to develop revisions to Regulatory Guide 1.82 and Standard Review Plan Section 6.2.2 (NUREG-0800)

  14. Light Water Reactor Sustainability Program A Reference Plan for Control Room Modernization: Planning and Analysis Phase

    Energy Technology Data Exchange (ETDEWEB)

    Jacques Hugo; Ronald Boring; Lew Hanes; Kenneth Thomas

    2013-09-01

    The U.S. Department of Energy’s Light Water Reactor Sustainability (LWRS) program is collaborating with a U.S. nuclear utility to bring about a systematic fleet-wide control room modernization. To facilitate this upgrade, a new distributed control system (DCS) is being introduced into the control rooms of these plants. The DCS will upgrade the legacy plant process computer and emergency response facility information system. In addition, the DCS will replace an existing analog turbine control system with a display-based system. With technology upgrades comes the opportunity to improve the overall human-system interaction between the operators and the control room. To optimize operator performance, the LWRS Control Room Modernization research team followed a human-centered approach published by the U.S. Nuclear Regulatory Commission. NUREG-0711, Rev. 3, Human Factors Engineering Program Review Model (O’Hara et al., 2012), prescribes four phases for human factors engineering. This report provides examples of the first phase, Planning and Analysis. The three elements of Planning and Analysis in NUREG-0711 that are most crucial to initiating control room upgrades are: • Operating Experience Review: Identifies opportunities for improvement in the existing system and provides lessons learned from implemented systems. • Function Analysis and Allocation: Identifies which functions at the plant may be optimally handled by the DCS vs. the operators. • Task Analysis: Identifies how tasks might be optimized for the operators. Each of these elements is covered in a separate chapter. Examples are drawn from workshops with reactor operators that were conducted at the LWRS Human System Simulation Laboratory HSSL and at the respective plants. The findings in this report represent generalized accounts of more detailed proprietary reports produced for the utility for each plant. The goal of this LWRS report is to disseminate the technique and provide examples sufficient to

  15. Re-evaluation of emergency planning zone for 3 NPPS in Taiwan

    International Nuclear Information System (INIS)

    Chiou, S.-T.; Yin, H.-L.; Chen, C.-S.; Shih, C.-L.

    2004-01-01

    The emergency planning zone for the 3 nuclear power plants in Taiwan are re-evaluated. The analysis is performed by the CRAC2 code and the basic approach follows the NUREG-0396 evaluation procedure. Meteorological data are provided by Taiwan Power Company and reviewed by Taiwan University and Central Weather Bureau. Accident source terms are also provided by Institute of Nuclear Energy Research (INER) by probabilistic risk assessment method with consideration of actual plant system improvement and/or modification. The dose rate distribution, acute and latent cancer fatality are evaluated and compared with proposed EPZ decision criteria including protective action guide dose levels, individual and societal risk safety goal. (author)

  16. Engineering Technical Review Planning Briefing

    Science.gov (United States)

    Gardner, Terrie

    2012-01-01

    The general topics covered in the engineering technical planning briefing are 1) overviews of NASA, Marshall Space Flight Center (MSFC), and Engineering, 2) the NASA Systems Engineering(SE) Engine and its implementation , 3) the NASA Project Life Cycle, 4) MSFC Technical Management Branch Services in relation to the SE Engine and the Project Life Cycle , 5) Technical Reviews, 6) NASA Human Factor Design Guidance , and 7) the MSFC Human Factors Team. The engineering technical review portion of the presentation is the primary focus of the overall presentation and will address the definition of a design review, execution guidance, the essential stages of a technical review, and the overall review planning life cycle. Examples of a technical review plan content, review approaches, review schedules, and the review process will be provided and discussed. The human factors portion of the presentation will focus on the NASA guidance for human factors. Human factors definition, categories, design guidance, and human factor specialist roles will be addressed. In addition, the NASA Systems Engineering Engine description, definition, and application will be reviewed as background leading into the NASA Project Life Cycle Overview and technical review planning discussion.

  17. An evaluation of internal event Level 1 PRA methods used in NUREG-1150

    International Nuclear Information System (INIS)

    Camp, A.L.; Cramond, W.R.

    1989-01-01

    As part of the effort to support NUREG-1150, Sandia National Laboratories and its subcontractors have developed innovative techniques for efficiently performing internal event Level I probabilistic risk assessments. This methodology is one of the alternatives for industry to use in performing individual plant evaluations in the future. While this new methodology was very successful, there are some areas where improvements can be made. This paper evaluates the strengths and weaknesses of the methodology and makes some important recommendations for modifications in order to provide insights to future users

  18. Advanced control room design review guidelines: Merging old and new

    International Nuclear Information System (INIS)

    Carter, R.J.; Wachtel, J.A.

    1992-01-01

    The nuclear power industry is currently developing operator interface systems based on innovative applications of digital computers. To assure that this advanced technology is incorporated in a way that maximizes the potential safety benefits of the technology and minimizes the potential negative effects on human performance, human factors principles must be considered. NUREG-0700 contains guidelines for the review of operator interfaces. However, in light of the rapid technological advances in digital technology which have taken place in the eleven years since its publication, it is no longer adequate to assess the rapidly changing human-system interfaces. A research program, the purpose of which is to upgrade NUREG-0700, has been initiated. Thus far a set of draft advanced control room design review (ACRDR) guidelines has been complied. Three tasks, which were oriented towards integrating the applicable guidelines in NUREG-0700 into the ACRDR document, are described in the paper

  19. Comparative Study on Atmospheric Dispersion Module of Level 3 PSA

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Dahye; Jang, Misuk; Kang, Hyun Sik; Kim, Seoung Rae [NESS, Daejeon (Korea, Republic of)

    2016-10-15

    Some regulation documents such as Regulatory Guides and NUREG publications from the U.S. Nuclear Regulatory Commission (NRC) have influences on domestic radiation environmental analyses. As renewal versions of NUREG-0800 and NUREG-1555 have issued lately, the assessment for Severe Accident (SA) with Probabilistic Safety Assessment (PSA) should be added to Safety Analysis Report (SAR) and Radiation Environmental Report (RER). Because these reports are the required documents for obtaining the construction permit and operating license, it is important to understand the PSA methodology and it needs to improve the site-specific input data of L3PSA codes for SA. First, our review focuses on the atmospheric dispersion and deposition related input data of L3PSA code in this paper. Then we will continue to review the improvements of other input data. Two atmospheric dispersion models, which are PAVAN developed for design basis accident and ATMOS of MACCS2 code developed for SA, were reviewed in this paper. L3PSA deals with the effects of severe accidents and basically includes the evaluation of both short- and long-term effects. Therefore, both the deposition effects and nuclide information(type, amount, and chemical characteristics of released radionuclide) would be considered as the input parameters of atmospheric dispersion model for L3PSA. Additionally, the meteorological data would be sampled randomly to meet the purpose of probabilistic method. However, the sampling method would be selected according to analysis purpose. After review, ATMOS module and its input data are suitably developed for the atmospheric dispersion analysis of L3PSA. However, ATMOS module was developed using the site-specific terrain and environment characteristics. For the domestic application, it needs to study the input data reflecting the Korean terrain and environment characteristics. It would be also continuously improved in response to the time- and site-specific changes of weather

  20. Identification of Aircraft Hazards

    Energy Technology Data Exchange (ETDEWEB)

    K. Ashley

    2006-12-08

    Aircraft hazards were determined to be potentially applicable to a repository at Yucca Mountain in ''Monitored Geological Repository External Events Hazards Screening Analysis'' (BSC 2005 [DIRS 174235], Section 6.4.1). That determination was conservatively based upon limited knowledge of flight data in the area of concern and upon crash data for aircraft of the type flying near Yucca Mountain. The purpose of this report is to identify specific aircraft hazards that may be applicable to a monitored geologic repository (MGR) at Yucca Mountain, using NUREG-0800, ''Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (NRC 1987 [DIRS 103124], Section 3.5.1.6), as guidance for the inclusion or exclusion of identified aircraft hazards. The intended use of this report is to provide inputs for further screening and analysis of identified aircraft hazards based upon the criteria that apply to Category 1 and Category 2 event sequence analyses as defined in 10 CFR 63.2 [DIRS 176544] (Section 4). The scope of this report includes the evaluation of military, private, and commercial use of airspace in the 100-mile regional setting of the repository at Yucca Mountain with the potential for reducing the regional setting to a more manageable size after consideration of applicable screening criteria (Section 7).

  1. Preliminary Study on Effect of the Crud Deposits during LBLOCA Condition

    Energy Technology Data Exchange (ETDEWEB)

    Huh, Byung Gil; Lee, Joo Suk; Bang, Young Seok; Oh, Deog Yeon; Woo, Sweng Woong [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2008-10-15

    The severe crud deposits on fuel rod could result in the increment of the fuel temperature during the operation of nuclear power plants. The crud inhibits heat transfer, causing the cladding temperature to increase due to the low thermal conductivity. In the event of LBLOCA at the NPP operated with heavy crud layers, the peak cladding temperature (PCT) will be higher than it would be if the cladding were clean. Therefore, NRC has been reviewing a petition for rule making to set the limit of crud and/or oxide thickness. Also, it requires that LOCA analysis be calculated by factoring the role of crud. Since the crud deposits caused the stored energy in the fuel to increase, it could influence the following requirement: The Initial Stored Energy in the Fuel in Appendix K to Part 50. ECCS Evaluation Models, to require that the steady-state temperature distribution and stored energy in the fuel at the onset of a postulated LOCA. Also, safety review guidelines in NUREG-0800.

  2. Planning Electric Transmission Lines: A Review of Recent Regional Transmission Plans

    Energy Technology Data Exchange (ETDEWEB)

    Eto, Joseph H. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2017-04-13

    The first Quadrennial Energy Review (QER) recommends that the U.S. Department of Energy (DOE) conduct a national review of transmission plans and assess the barriers and incentives to their implementation. DOE tasked Lawrence Berkeley National Laboratory (LBNL) to prepare two reports to support the agency’s response to this recommendation. This report reviews regional transmission plans and regional transmission planning processes that have been directed by Federal Energy Regulatory Commission (FERC) Order Nos. 890 and 1000. We focus on the most recent regional transmission plans (those issued in 2015 and through approximately mid-year 2016) and current regional transmission planning processes. A companion report focuses on non-plan-related factors that affect transmission projects.

  3. USCG Security Plan Review

    Data.gov (United States)

    Department of Homeland Security — The Security Plan Review module is intended for vessel and facility operators to check on the status of their security plans submitted to the US Coast Guard. A MISLE...

  4. Human Factors Review Plan

    International Nuclear Information System (INIS)

    Paramore, B.; Peterson, L.R.

    1985-12-01

    ''Human Factors'' is concerned with the incorporation of human user considerations into a system in order to maximize human reliability and reduce errors. This Review Plan is intended to assist in the assessment of human factors conditions in existing DOE facilities. In addition to specifying assessment methodologies, the plan describes techniques for improving conditions which are found to not adequately support reliable human performance. The following topics are addressed: (1) selection of areas for review describes techniques for needs assessment to assist in selecting and prioritizing areas for review; (2) human factors engineering review is concerned with optimizing the interfaces between people and equipment and people and their work environment; (3) procedures review evaluates completeness and accuracy of procedures, as well as their usability and management; (4) organizational interface review is concerned with communication and coordination between all levels of an organization; and (5) training review evaluates training program criteria such as those involving: trainee selection, qualification of training staff, content and conduct of training, requalification training, and program management

  5. Human Factors Review Plan

    Energy Technology Data Exchange (ETDEWEB)

    Paramore, B.; Peterson, L.R. (eds.)

    1985-12-01

    ''Human Factors'' is concerned with the incorporation of human user considerations into a system in order to maximize human reliability and reduce errors. This Review Plan is intended to assist in the assessment of human factors conditions in existing DOE facilities. In addition to specifying assessment methodologies, the plan describes techniques for improving conditions which are found to not adequately support reliable human performance. The following topics are addressed: (1) selection of areas for review describes techniques for needs assessment to assist in selecting and prioritizing areas for review; (2) human factors engineering review is concerned with optimizing the interfaces between people and equipment and people and their work environment; (3) procedures review evaluates completeness and accuracy of procedures, as well as their usability and management; (4) organizational interface review is concerned with communication and coordination between all levels of an organization; and (5) training review evaluates training program criteria such as those involving: trainee selection, qualification of training staff, content and conduct of training, requalification training, and program management.

  6. 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

  7. Assessment of emergency response planning and implementation in the aftermath of major natural disasters and technological accidents

    International Nuclear Information System (INIS)

    Milligan, Patricia A.; Jones, Joseph; Walton, F.; Smith, J.D.

    2008-01-01

    Emergency planning around nuclear power plants represents some of the most mature and well developed emergency planning in the United States. Since the implementation of NUREG-0654 / FEMA-REP-1, Rev. 1, A Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (NRC, 1980a) the licensees, local, and State agencies have developed detailed Radiological Emergency Response Programs. An important component of these plans is the evacuation of the population in the event of a general emergency condition at the plant. In January 2005, the U.S. Nuclear Regulatory Commission (NRC) published the landmark report, 'Identification and Analysis of Factors Affecting Emergency Evacuations' (NUREG/CR 6864/), which represented the most comprehensive investigation of public evacuations in the United States in more than 15 years. Since the completion of this research, several high profile evacuations have occurred, including Hurricane Katrina in New Orleans, Hurricane Rita in Houston, as well as major wildfires across the western U.S. The NRC commissioned an update to its 2005 evacuation case study publication to evaluate the evacuation experience of the selected communities (e.g., timeliness, related injuries, hazard avoidance); the level of preplanning that was in place for the affected areas and extent that the pre planned requirements were implemented during the emergency response; the critical factors contributing to the efficiency of or impediments to the evacuations (e.g., training, drills, preparedness, experience, resources, facilities, and organizational structure); and additional factors that may have contributed to less than satisfactory public response (i.e., availability of personal transportation, use of public transportation, lack of availability of shelters, etc.). The comprehensive report will be published in fall of 2008 as NUREG/CR-6981, Assessment of Emergency Response Planning and

  8. 76 FR 59066 - Notice of Regulatory Review Plan

    Science.gov (United States)

    2011-09-23

    ... [No. 2011-N-10] Notice of Regulatory Review Plan AGENCY: Federal Housing Finance Agency. ACTION... of and requesting comments on the FHFA interim regulatory review plan for review of existing... comments on all aspects of the interim regulatory review plan, including legal and policy considerations...

  9. Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

    Energy Technology Data Exchange (ETDEWEB)

    Dwyer, P.A.

    1991-10-01

    This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material.

  10. Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

    International Nuclear Information System (INIS)

    Dwyer, P.A.

    1991-10-01

    This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material

  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. Tables of cross references among SECY 82-111, NUREG 0700, NUREG 0835, NUREG 0801

    International Nuclear Information System (INIS)

    Savage, J.W.

    1982-01-01

    This memorandum cross references topical statements extracted from four NRC documents that are useful for guidance in reviewing the Human Factors Engineering designs of main control rooms and control centers outside the main control rooms

  14. Digial Technology Qualification Task 2 - Suitability of Digital Alternatives to Analog Sensors and Actuators

    Energy Technology Data Exchange (ETDEWEB)

    Ted Quinn; Jerry Mauck

    2012-09-01

    The next generation reactors in the U.S. are an opportunity for vendors to build new reactor technology with advanced Instrumentation and Control Systems (control rooms, DCS, etc.). The advances made in the development of many current generation operating reactors in other parts of the world are being used in the design and construction of new plants. These new plants are expected to have fully integrated digital control rooms, computerized procedures, integrated surveillance testing with on-line monitoring and a major effort toward improving the O&M and fault survivability of the overall systems. In addition the designs are also incorporating major improvements in the man-machine interface based on lessons learned in nuclear and other industries. The above relates primarily to the scope of supply in instrumentation and control systems addressed by Chapter 7 of the Standard Review Plan (SRP) NUREG-0800 (Reference 9.5), and the associated Balance of Plant (BOP) I&C systems. This does not relate directly to the actuator and motor, breaker, initiation circuitry, valve position, etc. which is the subject of this report and normally outside of the traditional Distributed Control System (DCS), for both safety and non-safety systems. The recommendations presented in this report will be used as input to I&C research programming for the implementation of lessons learned during the early phases of new build both for large light water reactors (LWR) and also small modular reactors (SMR). This report is intended to support current research plans and provide user (vendor, owner-operator) input to the optimization of these research plans.

  15. Standard review plan for the review of environmental restoration remedial action quality assurance program plans

    International Nuclear Information System (INIS)

    1991-09-01

    This plan establishes both the scope of the review and the acceptance criteria to be utilized for the review of Quality Assurance Program Plans (QAPPs) developed in accordance with the requirements of DOE/RL-90-28. DOE/RL-90-28, the Environmental Restoration Remedial Action Quality Assurance Requirements Document (QARD) defines all quality assurance (QA) requirements governing activities that affect the quality of the Environmental Restoration Remedial Action (ERRA) program at the Hanford Site. These requirements are defined in three parts, Part 1 of Quality Management and Administration tasks, Part 2 for Environmental Data Operations, and Part 3 of the Design and Construction of items, systems, and facilities. The purpose of this document is to identify the scope of the review by the DOE Field Office, Richland staff, and establish the acceptance criteria (Parts 1, 2, and 3) that the DOE Field Office, Richland staff will utilize to evaluate the participant QAPPs. Use of the standard review plan will (1) help ensure that participant QAPPs contain the information required by DOE/RL-90-28, (2) aid program participant and DOE Field Office, Richland staff is ensuring that the information describing the participant's QAPP is complete, (3) help persons regarding DOE/RL- 90-28 to locate information, and (4) contribute to decreasing the time needed for the review process. In addition, the Standard Review Plan (SRP) ensures the quality and uniformity of the staff reviews and presents a well-defined base from which to evaluate compliance of participant quality programs against DOE/RL-90-28

  16. Clarification of TMI action plan requirements. Requirements for emergency response capability

    International Nuclear Information System (INIS)

    1983-01-01

    This document, Supplement 1 to NUREG-0737, is a letter from D. G. Eisenhut, Director of the Division of Licensing, NRR, to licensees of operating power reactors, applicants for operating licenses, and holders of construction permits forwarding post-TMI requirements for emergency response capability which have been approved for implementation. On October 30, 1980, the NRC staff issued NUREG-0737, which incorporated into one document all TMI-related items approved for implementation by the Commission at that time. In this NRC report, additional clarification is provided regarding Safety Parameter Display Systems, Detailed Control Room Design Reviews, Regulatory Guide 1.97 (Revision 2) - Application to Emergency Response Facilities, Upgrade of Emergency Operating Procedures, Emergency Response Facilities, and Meteorological Data

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

    International Nuclear Information System (INIS)

    McGevna, V.; Peterson, L.R.

    1981-01-01

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

  18. Experiences in the TC IAEA MEX4/058 project: RCIC Ageing Management Review

    International Nuclear Information System (INIS)

    Diaz, A.; Mendoza, G.; Viais, J.; Arganis, C.; Contreras, A.; Fernandez, G.; Medina, G.

    2012-01-01

    The present paper, describes the experiences in the Technical Cooperation Project with the IAEA MEX 4/058 related with the Licensed Renewal Process, according with 10 CFR 54, NEI-95-10, NUREG 1800 and NUREG 1801. A domestic data base using Microsoft ACCESS was made following the methodology suggest by 10 CFR 54, and the Reactor Core Isolation Cooling (RCIC) System was selected like a pilot system. The mechanical components within the scope of license renewal and their intended functions were selected and the components subject to Aging Management Review (AMR) were identified. Commodities groups of similar material, environment and intended function were used and the main Ageing Mechanisms were identified. The results were compared with the NUREG 1801 rev. 2 experiences and the possible AMP was addressed. In the case of Laguna Verde Nuclear Power Plant (LVNPP) U1, some of these programs are according with the Generic Aging Lesson Learned of NUREG 1801, while others AMP require modifications. It is important to mention that the application of this methodology will support activities related with long term operation in LVNPP. (author)

  19. Safety evaluation report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan

    International Nuclear Information System (INIS)

    1991-01-01

    This safety evaluation report (SER) was prepared by the US Nuclear Regulatory Commission (NRC) staff and represents the second and last supplement (SSER 2) to the staff's original SER published as Volume 3 of NUREG-1232 in April 1989. Supplement 1 of Volume 3 of NUREG-1232 (SSER 1) was published in October 1989. Like its predecessors, SSER 2 is composed of numerous safety evaluations by the staff regarding specific elements contained in the Browns Ferry Nuclear Performance Plan (BFNPP), Volume 3 (up to and including Revision 2), submitted by the Tennessee Valley Authority (TVA) for the Browns Ferry Nuclear Plant (BFN). The Browns Ferry Nuclear Plant consists of three boiling-water reactors (BWRs) at a site in Limestone County, Alabama. The BFNPP describes the corrective action plans and commitments made by TVA to resolve deficiencies with its nuclear programs before the startup of Unit 2. The staff has inspected and will continue to inspect TVA's implementation of these BFNPP corrective action plans that address staff concerns about TVA's nuclear program. SSER 2 documents the NRC staff's safety evaluations and conclusions for those elements of the BFNPP that were not previously addressed by the staff or that remained open as a result of unresolved issues identified by the staff in previous SERs and inspections

  20. Standard review plan for the review and evaluation of emergency plans for research and test reactors

    International Nuclear Information System (INIS)

    1983-10-01

    This document provides a Standard Review Plan to assure that complete and uniform reviews are made of research and test reactor radiological emergency plans. The report is organized under ten planning standards which correspond to the guidance criteria in American National Standard ANSI/ANS 15.16 - 1982 as endorsed by Revision 1 to Regulatory Guide 2.6. The applicability of the items under each planning standard is indicated by subdivisions of the steady-state thermal power levels at which the reactors are licensed to operate. Standard emergency classes and example action levels for research and test reactors which should initiate these classes are given in an Appendix. The content of the emergency plan is as follows: the emergency plan addresses the necessary provisions for coping with radiological emergencies. Activation of the emergency plan is in response to the emergency action levels. In addition to addressing those severe emergencies that will fall within one of the standard emergency classes, the plan also discusses the necessary provisions to deal with radiological emergencies of lesser severity that can occur within the operations boundary. The emergency plan allows for emergency personnel to deviate from actions described in the plan for unusual or unanticipated conditions

  1. NPP Krsko Periodic Safety Review action plan

    International Nuclear Information System (INIS)

    Bilic Zabric, T.

    2006-01-01

    In the current, internationally accepted, safety philosophy Periodic Safety Reviews (PSRs) are comprehensive reviews aimed at the verification that an operating NPP remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain an acceptable level of safety. These reviews are complementary to the routine and special safety reviews. They are long time-scale reviews intended to deal with the cumulative effects of plant ageing, modifications, operating experience and technical developments, which are not so easily comprehended over the shorter time-scale routine of safety reviews. The review was completed in 2005 and the next period will see the implementation of the action plan including some plant upgrades. The action plan lists issues that should be implemented at NPP Krsko together with associated milestones. The milestones were assumed based on best estimate resource availability and their ends can be potentially floated. In some cases, multiple corrective measures may be postulated to provide resolution for a given safety issue. The Slovenian Nuclear Safety Administration by decree approved the first periodic safety review and the implementation plan of activities arising from it. The entire implementation plan must be carried out by 15 October 2010. Report on the second periodic safety review must be submitted by the NEK not later than 15 December 2013. (author)

  2. Healthcare succession planning: an integrative review.

    Science.gov (United States)

    Carriere, Brian K; Muise, Melanie; Cummings, Greta; Newburn-Cook, Chris

    2009-12-01

    Succession planning is a business strategy that has recently gained attention in the healthcare literature, primarily because of nursing shortage concerns and the demand for retaining knowledgeable personnel to meet organizational needs. Little research has been conducted in healthcare settings that clearly defines best practices for succession planning frameworks. To effectively carry out such organizational strategies during these challenging times, an integrative review of succession planning in healthcare was performed to identify consistencies in theoretical approaches and strategies for chief nursing officers and healthcare managers to initiate. Selected articles were compared with business succession planning to determine whether healthcare strategies were similar to best practices already established in business contexts. The results of this integrative review will aid leaders and managers to use succession planning as a tool in their recruitment, retention, mentoring, and administration activities and also provide insights for future development of healthcare succession planning frameworks.

  3. Sulfur Dioxide (SO2) Primary NAAQS Review: Integrated Review Plan - Advisory with CASAC

    Science.gov (United States)

    The SO2 Integrated Review Plan is the first document generated as part of the National Ambient Air Quality Standards (NAAQS) review process. The Plan presents background information, the schedule for the review, the process to be used in conducting the review, and the key policy-...

  4. Experience gained in the application of the methodology of NUREG / CR-6850 in the APS fire of Cofrentes; Experiencia adquirida en la aplicacion de la metodologia del NUREG/CR- 6850 en el APS de incendios de C. N. Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Benito Roberti, M.; Celaya Meler, M.; Gonzalo Gonzalo, M. J.; Moreno Matarranz, M. A.; Palma Laorden, A.; Viniegra Cabello, I.

    2014-07-01

    The NUREG / CR-6850 provides a well-structured development methodology in different stages directly applicable in all cases, as a basis of input parameters, assumptions and modeling solutions which allow a very small probabilistic analysis needs to resort to other sources. However, the state of the art on this type of analysis is still evolving today, mainly in the US, as results of the various ongoing research programs and consensus derived from the evaluation and approval are obtained by the FAQ NRC different proposals by industry, owning companies, laboratories and technical institutes. (Author)

  5. Consolidated guidance about materials licenses: Program-specific guidance about portable gauge licenses. Final report; Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Vacca, P.C.; Whitten, J.E.; Pelchat, J.M.; Arredondo, S.A.; Matson, E.R.; Lewis, S.H.; Collins, D.J.; Santiago, P.A. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Industrial and Medical Nuclear Safety; Tingle, W. [Dept. of Environment, Health, and Natural Resources, Raleigh, NC (United States). Div. of Radiation Protection

    1997-05-01

    As part of its redesign of the materials licensing process, NRC is consolidating and updating numerous guidance documents into a single comprehensive repository as described in NUREG-1539 and draft NUREG-1541. NUREG-1556, Vol. 1, is the first program-specific guidance developed for the new process and will serve as a template for subsequent program-specific guidance. This document is intended for use by applicants, licensees, and NRC staff and will also be available to Agreement States. This document supersedes the guidance previously found in draft Regulatory Guide DG-0008, ``Applications for the Use of Sealed Sources in Portable Gauging Devices,`` and in NMSs Policy and guidance Directive 2-07, ``Standard Review Plan for Applications for Use of Sealed Sources in Portable Gauging Devices.`` This final report takes a more risk-informed, performance-based approach to licensing portable gauges, and reduces the information(amount and level of detail) needed to support an application to use these devices. It incorporates many suggests submitted during the comment period on draft NUREG-1556, Volume 1. When published, this final report should be used in preparing portable gauge license applications. NRC staff will use this final report in reviewing these applications.

  6. Consolidated guidance about materials licenses: Program-specific guidance about portable gauge licenses. Final report; Volume 1

    International Nuclear Information System (INIS)

    Vacca, P.C.; Whitten, J.E.; Pelchat, J.M.; Arredondo, S.A.; Matson, E.R.; Lewis, S.H.; Collins, D.J.; Santiago, P.A.; Tingle, W.

    1997-05-01

    As part of its redesign of the materials licensing process, NRC is consolidating and updating numerous guidance documents into a single comprehensive repository as described in NUREG-1539 and draft NUREG-1541. NUREG-1556, Vol. 1, is the first program-specific guidance developed for the new process and will serve as a template for subsequent program-specific guidance. This document is intended for use by applicants, licensees, and NRC staff and will also be available to Agreement States. This document supersedes the guidance previously found in draft Regulatory Guide DG-0008, ''Applications for the Use of Sealed Sources in Portable Gauging Devices,'' and in NMSs Policy and guidance Directive 2-07, ''Standard Review Plan for Applications for Use of Sealed Sources in Portable Gauging Devices.'' This final report takes a more risk-informed, performance-based approach to licensing portable gauges, and reduces the information(amount and level of detail) needed to support an application to use these devices. It incorporates many suggests submitted during the comment period on draft NUREG-1556, Volume 1. When published, this final report should be used in preparing portable gauge license applications. NRC staff will use this final report in reviewing these applications

  7. Development of generic soil profiles and soil data development for SSI analyses

    Energy Technology Data Exchange (ETDEWEB)

    Parker, Josh, E-mail: jparker@nuscalepower.com [NuScale Power, 1000 NE Circle Boulevard, Suite 10310, Corvallis, OR 97330 (United States); Khan, Mohsin; Rajagopal, Raj [ARES Corporation, 1990N California Boulevard, Suite 500, Walnut Creek, CA 94596 (United States); Groome, John [NuScale Power, 1000 NE Circle Boulevard, Suite 10310, Corvallis, OR 97330 (United States)

    2014-04-01

    This paper presents the approach to developing generic soil profiles for the design of reactor building for small modular reactor (SMR) nuclear power plant developed by NuScale Power. The reactor building is a deeply embedded structure. In order to perform soil structure interaction (SSI) analyses, generic soil profiles are required to be defined for the standardized Nuclear Power Plant (NPP) designs for the United States Nuclear Regulatory Commission (NRC) in a design control document (DCD). The development of generic soil profiles is based on utilization of information on generic soil profiles from the new standardized nuclear power plant designs already submitted to the NRC for license certification. Eleven generic soil profiles have been recommended, and those profiles cover a wide range of parameters such as soil depth, shear wave velocity, unit weight, Poisson's ratio, water table, and depth to rock strata. The soil profiles are developed for a range of shear wave velocities between bounds of 1000 fps and 8000 fps as inferred from NRC Standard Review Plan (NUREG 0800) Sections 3.7.1 and 3.7.2. To account for the soil degradation due to seismic events, the strain compatible soil properties are based on the EPRI generic soil degradation curves. In addition, one dimensional soil dynamic response analyses were performed to study the soil layer input motions for performing the SSI analyses.

  8. 42 CFR 457.150 - CMS review of State plan material.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false CMS review of State plan material. 457.150 Section... Introduction; State Plans for Child Health Insurance Programs and Outreach Strategies § 457.150 CMS review of State plan material. (a) Basis for action. CMS reviews each State plan and plan amendment to determine...

  9. Risk-assessment methodology development for waste isolation in geologic media

    International Nuclear Information System (INIS)

    Stevens, C.A.; Fullwood, R.R.; Amirijafari, B.; Basin, S.L.; Cohen, J.

    1982-12-01

    A review of three documents prepared for the USNRC by Sandia National Laboratories (SNL) is presented. These are NUREG/CR-1634, Volume 4 concerned with the effects of variable hydrology on waste migration; NUREG/CR-2324, a user's manual for SWIFT; and NUREG/2343, a user's manual for DNET. This review completes Task 4 of the detailed technical review of the SNL program for Risk Assessment Methodology Development for Waste Isolation in Geologic Media. In general, these reports exhibit high technical quality that characterizes the SNL work. They are tersely written with little condescension to the non-expert reader for understanding the physical situation being modeled. Indeed, the emphasis is on the mathematical procedures rather than the repository physics, leaving the adequacy of the results presented in many computer plots, pretty much to the interpretation of the reader. Other general comments have been presented previously, such as the data conservatisms, need for data that cannot be measured without disturbing the geometry, and the overall plan for use of the many codes developed in the program

  10. Severe Accident Research Program plan update

    International Nuclear Information System (INIS)

    1992-12-01

    In August 1989, the staff published NUREG-1365, ''Revised Severe Accident Research Program Plan.'' Since 1989, significant progress has been made in severe accident research to warrant an update to NUREG-1365. The staff has prepared this SARP Plan Update to: (1) Identify those issues that have been closed or are near completion, (2) Describe the progress in our understanding of important severe accident phenomena, (3) Define the long-term research that is directed at improving our understanding of severe accident phenomena and developing improved methods for assessing core melt progression, direct containment heating, and fuel-coolant interactions, and (4) Reflect the growing emphasis in two additional areas--advanced light water reactors, and support for the assessment of criteria for containment performance during severe accidents. The report describes recent major accomplishments in understanding the underlying phenomena that can occur during a severe accident. These include Mark I liner failure, severe accident scaling methodology, source term issues, core-concrete interactions, hydrogen transport and combustion, TMI-2 Vessel Investigation Project, and direct containment heating. The report also describes the major planned activities under the SARP over the next several years. These activities will focus on two phenomenological issues (core melt progression, and fuel-coolant interactions and debris coolability) that have significant uncertainties that impact our understanding and ability to predict severe accident phenomena and their effect on containment performance SARP will also focus on severe accident code development, assessment and validation. As the staff completes the research on severe accident issues that relate to current generation reactors, continued research will focus on efforts to independently evaluate the capability of new advanced light water reactor designs to withstand severe accidents

  11. Preliminary Analysis of a Loss of Condenser Vacuum Accident Using the MARS-KS Code

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jieun Kim; Bang, Young Seok; Oh, Deog Yeon; Kim, Kap; Woo, Sweng-Wong [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    In accordance with revision of NUREG-0800 of USNRC, the area of review for loss of condenser vacuum(LOCV) accident has been expanded to analyze both peak pressures of primary and secondary system separately. Currently, the analysis of LOCV accident, which is caused by malfunction of condenser, has been focused to fuel cladding integrity and peak pressure in the primary system. In this paper, accident analysis for LOCV using MARS-KS code were conducted to support the licensing review on transient behavior of secondary system pressure of APR1400 plant. The accident analysis for the loss of condenser vacuum (LOCV) of APR1400 was conducted with the MARS-KS code to support the review on the pressure behavior of primary and secondary system. Total four cases which have different combination of availability of offsite power and the pressurizer spray are considered. The preliminary analysis results shows that the initial conditions or assumptions which concludes the severe consequence are different for each viewpoint, and in some cases, it could be confront with each viewpoint. Therefore, with regard to the each acceptance criteria, figuring out and sensitivity analysis of the initial conditions and assumptions for system pressure would be necessary.

  12. Comparison of implementation of selected TMI action plan requirements on operating plants designed by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Thoma, J.O.

    1984-05-01

    This report provides the results of a study conducted by the US Nuclear Regulatory Commission staff to compare the degree to which eight Babcock and Wilcox (B and W) designed licensed nuclear power plants have complied with the requirements in NUREG-0737, Clarification of TMI Action Plan Requirements. The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1). The purpose of this audit was to establish the progress of the TMI-1 licensee, General Public Utilities (GPU) Nuclear Corporation, in completing the long-term requirements in NUREG-0737 relative to the other B and W licensees examined

  13. Standard review plan for the review and evaluation of emergency plans for research and test reactors. Technical report

    International Nuclear Information System (INIS)

    Bates, E.F.; Grimes, B.K.; Ramos, S.L.

    1982-05-01

    This document provides a Standard Review Plan for the guidance of the NRC staff to assure that complete and uniform reviews are made of research and test reactor emergency plans. The report is organized under ten planning standards which correspond to the guidance criteria in Draft II of ANSI/ANS 15.16 as endorsed by Revision 1 to Regulatory Guide 2.6. The applicability of the items under each planning standard is indicated by subdivisions of the steady state thermal power levels at which the reactors are licensed to operate. Standard emergency classes and example action levels for research and test reactors which should initiate these classes are given in an Appendix

  14. Application of the NUREG/CR-6850 EPRI/NRC Fire PRA Methodology to a DOE Facility

    International Nuclear Information System (INIS)

    Elicson, Tom; Harwood, Bentley; Yorg, Richard; Lucek, Heather; Bouchard, Jim; Jukkola, Ray; Phan, Duan

    2011-01-01

    The application NUREG/CR-6850 EPRI/NRC fire PRA methodology to DOE facility presented several challenges. This paper documents the process and discusses several insights gained during development of the fire PRA. A brief review of the tasks performed is provided with particular focus on the following: Tasks 5 and 14: Fire-induced risk model and fire risk quantification. A key lesson learned was to begin model development and quantification as early as possible in the project using screening values and simplified modeling if necessary. Tasks 3 and 9: Fire PRA cable selection and detailed circuit failure analysis. In retrospect, it would have been beneficial to perform the model development and quantification in 2 phases with detailed circuit analysis applied during phase 2. This would have allowed for development of a robust model and quantification earlier in the project and would have provided insights into where to focus the detailed circuit analysis efforts. Tasks 8 and 11: Scoping fire modeling and detailed fire modeling. More focus should be placed on detailed fire modeling and less focus on scoping fire modeling. This was the approach taken for the fire PRA. Task 14: Fire risk quantification. Typically, multiple safe shutdown (SSD) components fail during a given fire scenario. Therefore dependent failure analysis is critical to obtaining a meaningful fire risk quantification. Dependent failure analysis for the fire PRA presented several challenges which will be discussed in the full paper.

  15. Standard Review Plan for Environmental Restoration Program Quality Management Plans

    International Nuclear Information System (INIS)

    1993-12-01

    The Department of Energy, Richland Operations Office (RL) Manual Environmental Restoration Program Quality System Requirements (QSR) for the Hanford Site, defines all quality requirements governing Hanford Environmental Restoration (ER) Program activities. The QSR requires that ER Program participants develop Quality Management Plans (QMPs) that describe how the QSR requirements will be implemented for their assigned scopes of work. This standard review plan (SRP) describes the ER program participant responsibilities for submittal of QMPs to the RL Environmental Restoration Division for review and the RL methodology for performing the reviews of participant QMPS. The SRP serves the following functions: acts as a guide in the development or revision of QMPs to assure that the content is complete and adequate; acts as a checklist to be used by the RL staff in their review of participant QMPs; acts as an index or matrix between the requirements of the QSR and implementing methodologies described in the QMPs; decreases the time and subjectivity of document reviews; and provides a formal, documented method for describing exceptions, modifications, or waivers to established ER Program quality requirements

  16. The NUREG-1150 probabilistic risk assessment for the Sequoyah nuclear plant

    International Nuclear Information System (INIS)

    Gregory, J.J.; Breeding, R.J.; Higgins, S.J.; Shiver, A.W.; Helton, J.C.; Murfin, W.B.

    1992-01-01

    This paper summarizes the findings of the probabilistic risk assessment (PRA) for Unit 1 of the Sequoyah Nuclear Plant performed in support of NUREG-1150. The emphasis is on the 'back-end' analyses, the accident progression, source term, and consequence analyses, and the risk results obtained when the results of these analyses are combined with the accident frequency analysis. The results of this PRA indicate that the offsite risk from internal initiating events at Sequoyah are quite low with respect to the safety goals. The containment appears likely to withstand the loads that might be placed upon it if the reactor vessel fails. A good portion of the risk, in this analysis, comes from initiating events which bypass the containment. These events are estimated to have a relatively low frequency of occurrence, but their consequences are quite large. Other events that contribute to offsite risk involve early containment failures that occur during degradation of the core or near the time of vessel breach. Considerable uncertainty is associated with the risk estimates produced in this analysis. Offsite risk from external initiating events was not included in this analysis. (orig.)

  17. 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)

    1992-12-01

    This report is to provide a comprehensive description of the implementation and verification status of Three Mile Island (TMI) Action Plan requirements, safety issues designated as Unresolved Safety Issues (USIs), Generic Safety Issues(GSIs), and other Multiplant Actions (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. 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

  18. Overview of the Nuclear Regulatory Commission's safety research program

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1989-01-01

    Accomplishments during 1988 of the Office of Nuclear Regulatory Research and the program of safety research are highlighted, and plans, expections, and needs of the next year and beyond are discussed. Topics discussed include: ECCS Appendix K Revision; pressurized thermal shock; NUREG-1150, or the PRA method performance document; resolution of station blackout; severe accident integration plan; nuclear safety research review committee; and program management

  19. Checklist for Reviewing EPA Quality Management Plans

    Science.gov (United States)

    This checklist will be used to review the Quality Management Plans (QMPs) that are submitted to the Quality Staff of the Office of Environmental Information (OEI) for Agency review under EPA Order 5360.1 A2.

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

    International Nuclear Information System (INIS)

    Gill, C.F.

    1987-01-01

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

  1. Nationwide Plan Review Phase 1 Report

    National Research Council Canada - National Science Library

    2006-01-01

    ...] and the Secretary of Homeland Security, in coordination with Gulf Coast States and contiguous States, shall jointly review and assess Federal and State evacuation plans for catastrophic hurricanes...

  2. Book Review: CFP Board Financial Planning Competency Handbook

    Directory of Open Access Journals (Sweden)

    Jorge Ruiz-Menjivar

    2015-07-01

    Full Text Available The CFP Board Financial Planning Competency Handbook (2013 is reviewed as a resource that extends beyond financial planning to other helping professionals who work with money related issues.

  3. 12 CFR 563b.115 - How will OTS review my business plan?

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 5 2010-01-01 2010-01-01 false How will OTS review my business plan? 563b.115... business plan? (a) OTS will review your business plan to determine that it demonstrates a safe and sound... will be determinative. OTS will review every case on its merits. (b) You must file your business plan...

  4. Guidelines on the defense-in-depth and diversity planning and analysis in digital instrumentation and control systems

    International Nuclear Information System (INIS)

    Cheon, Se Woo; Park, Jong Kyun; Lee, Ki Young; Kwon, Ki Choon; Lee, Jang Soo; Kim, Jang Yeol

    2000-08-01

    Digital instrumentation and control (I and C) systems are becoming an ever-increasing part in I and C systems of nuclear power plants due to such features such as versatility, flexibility, and reduced sizes. The digital technology introduces a possibility that common-cause or common-mode failures (CCF or CMF) may cause redundant safety systems to fail in such a way that there is loss of safety function. A special form of CMF analysis called 'defense-in-depth and diversity' (D-in-D and D) analysis has been developed to identify possible common-mode failure vulnerabilities and to support a specific licensing action in digital systems. There are two main stages in D-in-D and D activities: both plan and analysis. The purposes of this technical report are i) to review background of D-in-D and D and some of important issues in digital D-in-D and D, ii) to provide guidelines for a vendor to prepare planning and/or analysis documents on D-in-D and D, and iii) to provide guidelines for an evaluator to review applicant's D-in-D and D planning and/or analysis documents, to ensure that the requirements of the D-in-D and D for digital I and C systems are followed. Most of guidelines suggested in this report were based on NUREG/CR-6303 which was published in 1994. The report will be helpful for a vendor to prepare and for an evaluator to review both D-in-D and D planning or analysis documents for digital I and C systems such as the KNGR project

  5. Guidelines on the defense-in-depth and diversity planning and analysis in digital instrumentation and control systems

    Energy Technology Data Exchange (ETDEWEB)

    Cheon, Se Woo; Park, Jong Kyun; Lee, Ki Young; Kwon, Ki Choon; Lee, Jang Soo; Kim, Jang Yeol

    2000-08-01

    Digital instrumentation and control (I and C) systems are becoming an ever-increasing part in I and C systems of nuclear power plants due to such features such as versatility, flexibility, and reduced sizes. The digital technology introduces a possibility that common-cause or common-mode failures (CCF or CMF) may cause redundant safety systems to fail in such a way that there is loss of safety function. A special form of CMF analysis called 'defense-in-depth and diversity' (D-in-D and D) analysis has been developed to identify possible common-mode failure vulnerabilities and to support a specific licensing action in digital systems. There are two main stages in D-in-D and D activities: both plan and analysis. The purposes of this technical report are (i) to review background of D-in-D and D and some of important issues in digital D-in-D and D, (ii) to provide guidelines for a vendor to prepare planning and/or analysis documents on D-in-D and D, and (iii) to provide guidelines for an evaluator to review applicant's D-in-D and D planning and/or analysis documents, to ensure that the requirements of the D-in-D and D for digital I and C systems are followed. Most of guidelines suggested in this report were based on NUREG/CR-6303 which was published in 1994. The report will be helpful for a vendor to prepare and for an evaluator to review both D-in-D and D planning or analysis documents for digital I and C systems such as the KNGR project.

  6. 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

  7. 49 CFR 659.25 - Annual review of system safety program plan and system security plan.

    Science.gov (United States)

    2010-10-01

    ... system security plan. 659.25 Section 659.25 Transportation Other Regulations Relating to Transportation... and system security plan. (a) The oversight agency shall require the rail transit agency to conduct an annual review of its system safety program plan and system security plan. (b) In the event the rail...

  8. Generic Overview of the Status of Characterization Surveys and Guidance for Decommissioning

    International Nuclear Information System (INIS)

    Abu Eid, Rateb Boby

    2012-01-01

    This paper presents an overview of several topical areas pertaining to characterization and survey for decommissioning, including: U.S. NRC regulatory requirements for decommissioning and survey; a description of the decommissioning processes particularly role of characterization and survey; characterization survey types and NRC categorization of decommissioning groups; status of U.S. characterization survey guidance; and overview of key characterization and survey Issues. The specific topical areas are briefly discussed below: - The paper addresses the U.S. NRC requirements under 10 CFR Part 20, Subpart E - 'Radiological Criteria for License Termination', and final status surveys requirements under 10 CFR 20.1501(a). Other requirements under 10CFR Parts 50.75, 50.82, 51.53, and 51.95) as well as, reporting and record keeping for decommissioning planning will be outlined. The paper also discusses NRC general decommissioning process for materials and fuel cycle facilities, as well as, for power reactor facilities. - Strategy and planning for decommissioning using the data quality objectives (DQO) approach and its seven step process will be presented in some detail. - The US NRC 'Surveys and Site Investigation Process' as described in NUREG 1757 and categorization of 'Decommissioning Groups' in the context of characterization and survey needs will be addressed. - The paper briefly outlines methodologies, approaches, and status of U.S. multi-agency key guidance documents such as MARSSIM (NUREG-1575), MARSAME (NUREG- 1575, Supp.1), and more recently, the NRC Subsurface Guidance NUREG/CR 7021. - Dose modeling and software development/update in support of radiological survey and characterization for derivation of derived concentration guideline levels. - Lessons Learned from Regulatory 'Reviews of Survey Plans' particularly attributes of survey plans, common survey issues, and key aspects for decommissioning success are discussed in the paper. (author)

  9. Review of the FAA 1982 National Airspace System plan

    Science.gov (United States)

    1982-08-01

    The National Airspace (NAS) Plan outlines the Federal Aviation Administration's most recent proposals for modernizing the facilities and equipment that make up the air traffic control (ATC) system. This review of the NAS Plan examines the Plan at two...

  10. Procedures for the external event core damage frequency analyses for NUREG-1150

    International Nuclear Information System (INIS)

    Bohn, M.P.; Lambright, J.A.

    1990-11-01

    This report presents methods which can be used to perform the assessment of risk due to external events at nuclear power plants. These methods were used to perform the external events risk assessments for the Surry and Peach Bottom nuclear power plants as part of the NRC-sponsored NUREG-1150 risk assessments. These methods apply to the full range of hazards such as earthquakes, fires, floods, etc. which are collectively known as external events. The methods described in this report have been developed under NRC sponsorship and represent, in many cases, both advancements and simplifications over techniques that have been used in past years. They also include the most up-to-date data bases on equipment seismic fragilities, fire occurrence frequencies and fire damageability thresholds. The methods described here are based on making full utilization of the power plant systems logic models developed in the internal events analyses. By making full use of the internal events models one obtains an external event analysis that is consistent both in nomenclature and in level of detail with the internal events analyses, and in addition, automatically includes all the appropriate random and tests/maintenance unavailabilities as appropriate. 50 refs., 9 figs., 11 tabs

  11. The effectiveness of pretreatment physics plan review for detecting errors in radiation therapy

    International Nuclear Information System (INIS)

    Gopan, Olga; Zeng, Jing; Novak, Avrey; Nyflot, Matthew; Ford, Eric

    2016-01-01

    Purpose: The pretreatment physics plan review is a standard tool for ensuring treatment quality. Studies have shown that the majority of errors in radiation oncology originate in treatment planning, which underscores the importance of the pretreatment physics plan review. This quality assurance measure is fundamentally important and central to the safety of patients and the quality of care that they receive. However, little is known about its effectiveness. The purpose of this study was to analyze reported incidents to quantify the effectiveness of the pretreatment physics plan review with the goal of improving it. Methods: This study analyzed 522 potentially severe or critical near-miss events within an institutional incident learning system collected over a three-year period. Of these 522 events, 356 originated at a workflow point that was prior to the pretreatment physics plan review. The remaining 166 events originated after the pretreatment physics plan review and were not considered in the study. The applicable 356 events were classified into one of the three categories: (1) events detected by the pretreatment physics plan review, (2) events not detected but “potentially detectable” by the physics review, and (3) events “not detectable” by the physics review. Potentially detectable events were further classified by which specific checks performed during the pretreatment physics plan review detected or could have detected the event. For these events, the associated specific check was also evaluated as to the possibility of automating that check given current data structures. For comparison, a similar analysis was carried out on 81 events from the international SAFRON radiation oncology incident learning system. Results: Of the 356 applicable events from the institutional database, 180/356 (51%) were detected or could have been detected by the pretreatment physics plan review. Of these events, 125 actually passed through the physics review; however

  12. The effectiveness of pretreatment physics plan review for detecting errors in radiation therapy

    Energy Technology Data Exchange (ETDEWEB)

    Gopan, Olga; Zeng, Jing; Novak, Avrey; Nyflot, Matthew; Ford, Eric, E-mail: eford@uw.edu [Department of Radiation Oncology, University of Washington Medical Center, 1959 NE Pacific Street, Box 356043, Seattle, Washington 98195 (United States)

    2016-09-15

    Purpose: The pretreatment physics plan review is a standard tool for ensuring treatment quality. Studies have shown that the majority of errors in radiation oncology originate in treatment planning, which underscores the importance of the pretreatment physics plan review. This quality assurance measure is fundamentally important and central to the safety of patients and the quality of care that they receive. However, little is known about its effectiveness. The purpose of this study was to analyze reported incidents to quantify the effectiveness of the pretreatment physics plan review with the goal of improving it. Methods: This study analyzed 522 potentially severe or critical near-miss events within an institutional incident learning system collected over a three-year period. Of these 522 events, 356 originated at a workflow point that was prior to the pretreatment physics plan review. The remaining 166 events originated after the pretreatment physics plan review and were not considered in the study. The applicable 356 events were classified into one of the three categories: (1) events detected by the pretreatment physics plan review, (2) events not detected but “potentially detectable” by the physics review, and (3) events “not detectable” by the physics review. Potentially detectable events were further classified by which specific checks performed during the pretreatment physics plan review detected or could have detected the event. For these events, the associated specific check was also evaluated as to the possibility of automating that check given current data structures. For comparison, a similar analysis was carried out on 81 events from the international SAFRON radiation oncology incident learning system. Results: Of the 356 applicable events from the institutional database, 180/356 (51%) were detected or could have been detected by the pretreatment physics plan review. Of these events, 125 actually passed through the physics review; however

  13. Guidelines for the review of state ITS/CVO business plans

    Science.gov (United States)

    1997-08-01

    This document provides guidelines for the review of state ITS/CVO business plans by the FHWA. The purpose of the review is to ensure that the state business plans have been developed in a manner consistent with the FHWAs intent in awarding ITS/CVO...

  14. Does Peer Review of Radiation Plans Affect Clinical Care? A Systematic Review of the Literature

    International Nuclear Information System (INIS)

    Brunskill, Kelsey; Nguyen, Timothy K.; Boldt, R. Gabriel; Louie, Alexander V.; Warner, Andrew; Marks, Lawrence B.; Palma, David A.

    2017-01-01

    Purpose: Peer review is a recommended component of quality assurance in radiation oncology; however, it is resource-intensive and its effect on patient care is not well understood. We conducted a systematic review of the published data to assess the reported clinical impact of peer review on radiation treatment plans. Methods and Materials: A systematic review of published English studies was performed in accordance with the PRISMA guidelines using the MEDLINE and EMBASE databases and abstracts published from major radiation oncology scientific meeting proceedings. For inclusion, the studies were required to report the effect of peer review on ≥1 element of treatment planning (eg, target volume or organ-at-risk delineation, dose prescription or dosimetry). Results: The initial search strategy identified 882 potentially eligible studies, with 11 meeting the inclusion criteria for full-text review and final analysis. Across a total of 11,491 patient cases, peer review programs led to modifications in a weighted mean of 10.8% of radiation treatment plans. Five studies differentiated between major and minor changes and reported weighted mean rates of change of 1.8% and 7.3%, respectively. The most common changes were related to target volume delineation (45.2% of changed plans), dose prescription or written directives (24.4%), and non-target volume delineation or normal tissue sparing (7.5%). Conclusions: Our findings suggest that peer review leads to changes in clinical care in approximately 1 of every 9 cases overall. This is similar to the reported rates of change in peer review studies from other oncology-related specialties, such as radiology and pathology.

  15. Baseline Evaluations to Support Control Room Modernization at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Boring, Ronald L.; Joe, Jeffrey C.

    2015-02-01

    For any major control room modernization activity at a commercial nuclear power plant (NPP) in the U.S., a utility should carefully follow the four phases prescribed by the U.S. Nuclear Regulatory Commission in NUREG-0711, Human Factors Engineering Program Review Model. These four phases include Planning and Analysis, Design, Verification and Validation, and Implementation and Operation. While NUREG-0711 is a useful guideline, it is written primarily from the perspective of regulatory review, and it therefore does not provide a nuanced account of many of the steps the utility might undertake as part of control room modernization. The guideline is largely summative—intended to catalog final products—rather than formative—intended to guide the overall modernization process. In this paper, we highlight two crucial formative sub-elements of the Planning and Analysis phase specific to control room modernization that are not covered in NUREG-0711. These two sub-elements are the usability and ergonomics baseline evaluations. A baseline evaluation entails evaluating the system as-built and currently in use. The usability baseline evaluation provides key insights into operator performance using the control system currently in place. The ergonomics baseline evaluation identifies possible deficiencies in the physical configuration of the control system. Both baseline evaluations feed into the design of the replacement system and subsequent summative benchmarking activities that help ensure that control room modernization represents a successful evolution of the control system.

  16. Baseline Evaluations to Support Control Room Modernization at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Boring, Ronald L.; Joe, Jeffrey C.

    2015-01-01

    For any major control room modernization activity at a commercial nuclear power plant (NPP) in the U.S., a utility should carefully follow the four phases prescribed by the U.S. Nuclear Regulatory Commission in NUREG-0711, Human Factors Engineering Program Review Model. These four phases include Planning and Analysis, Design, Verification and Validation, and Implementation and Operation. While NUREG-0711 is a useful guideline, it is written primarily from the perspective of regulatory review, and it therefore does not provide a nuanced account of many of the steps the utility might undertake as part of control room modernization. The guideline is largely summative–intended to catalog final products–rather than formative–intended to guide the overall modernization process. In this paper, we highlight two crucial formative sub-elements of the Planning and Analysis phase specific to control room modernization that are not covered in NUREG-0711. These two sub-elements are the usability and ergonomics baseline evaluations. A baseline evaluation entails evaluating the system as-built and currently in use. The usability baseline evaluation provides key insights into operator performance using the control system currently in place. The ergonomics baseline evaluation identifies possible deficiencies in the physical configuration of the control system. Both baseline evaluations feed into the design of the replacement system and subsequent summative benchmarking activities that help ensure that control room modernization represents a successful evolution of the control system.

  17. 12 CFR 563b.110 - Who must review my business plan?

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Who must review my business plan? 563b.110... business plan? (a) Your chief executive officer and members of the board of directors must review, and at least two-thirds of your board of directors must approve, the business plan. (b) Your chief executive...

  18. Evaluation of a main steam line break with induced, multiple tube ruptures: A comparison of NUREG 1477 (Draft) and transient methodologies Palo Verde Nuclear Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Parrish, K.R.

    1995-09-01

    This paper presents the approach taken to analyze the radiological consequences of a postulated main steam line break event, with one or more tube ruptures, for the Palo Verde Nuclear Generating Station. The analysis was required to support the restart of PVNGS Unit 2 following the steam generator tube rupture event on March 14, 1993 and to justify continued operation of Units 1 and 3. During the post-event evaluation, the NRC expressed concern that Unit 2 could have been operating with degraded tubes and that similar conditions could exist in Units 1 and 3. The NRC therefore directed that a safety assessment be performed to evaluate a worst case scenario in which a non-isolable main steam line break occurs inducing one or more tube failures in the faulted steam generator. This assessment was to use the generic approach described in NUREG 1477, Voltage-Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report. An analysis based on the NUREG approach was performed but produced unacceptable results for off-site and control room thyroid doses. The NUREG methodology, however, does not account for plant thermal-hydraulic transient effects, system performance, or operator actions which could be credited to mitigate dose consequences. To deal with these issues, a more detailed analysis methodology was developed using a modified version of the Combustion Engineering Plant Analysis Code, which examines the dose consequences for a main steam line break transient with induced tube failures for a spectrum equivalent to 1 to 4 double ended guillotine U-tube breaks. By incorporating transient plant system responses and operator actions, the analysis demonstrates that the off-site and control room does consequences for a MSLBGTR can be reduced to acceptable limits. This analysis, in combination with other corrective and recovery actions, provided sufficient justification for continued operation of PVNGS Units 1 and 3, and for the subsequent restart of Unit 2.

  19. Evaluation of a main steam line break with induced, multiple tube ruptures: A comparison of NUREG 1477 (Draft) and transient methodologies Palo Verde Nuclear Generating Station

    International Nuclear Information System (INIS)

    Parrish, K.R.

    1995-01-01

    This paper presents the approach taken to analyze the radiological consequences of a postulated main steam line break event, with one or more tube ruptures, for the Palo Verde Nuclear Generating Station. The analysis was required to support the restart of PVNGS Unit 2 following the steam generator tube rupture event on March 14, 1993 and to justify continued operation of Units 1 and 3. During the post-event evaluation, the NRC expressed concern that Unit 2 could have been operating with degraded tubes and that similar conditions could exist in Units 1 and 3. The NRC therefore directed that a safety assessment be performed to evaluate a worst case scenario in which a non-isolable main steam line break occurs inducing one or more tube failures in the faulted steam generator. This assessment was to use the generic approach described in NUREG 1477, Voltage-Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report. An analysis based on the NUREG approach was performed but produced unacceptable results for off-site and control room thyroid doses. The NUREG methodology, however, does not account for plant thermal-hydraulic transient effects, system performance, or operator actions which could be credited to mitigate dose consequences. To deal with these issues, a more detailed analysis methodology was developed using a modified version of the Combustion Engineering Plant Analysis Code, which examines the dose consequences for a main steam line break transient with induced tube failures for a spectrum equivalent to 1 to 4 double ended guillotine U-tube breaks. By incorporating transient plant system responses and operator actions, the analysis demonstrates that the off-site and control room does consequences for a MSLBGTR can be reduced to acceptable limits. This analysis, in combination with other corrective and recovery actions, provided sufficient justification for continued operation of PVNGS Units 1 and 3, and for the subsequent restart of Unit 2

  20. WE-H-BRC-09: Simulated Errors in Mock Radiotherapy Plans to Quantify the Effectiveness of the Physics Plan Review

    International Nuclear Information System (INIS)

    Gopan, O; Kalet, A; Smith, W; Hendrickson, K; Kim, M; Young, L; Nyflot, M; Chvetsov, A; Phillips, M; Ford, E

    2016-01-01

    Purpose: A standard tool for ensuring the quality of radiation therapy treatments is the initial physics plan review. However, little is known about its performance in practice. The goal of this study is to measure the effectiveness of physics plan review by introducing simulated errors into “mock” treatment plans and measuring the performance of plan review by physicists. Methods: We generated six mock treatment plans containing multiple errors. These errors were based on incident learning system data both within the department and internationally (SAFRON). These errors were scored for severity and frequency. Those with the highest scores were included in the simulations (13 errors total). Observer bias was minimized using a multiple co-correlated distractor approach. Eight physicists reviewed these plans for errors, with each physicist reviewing, on average, 3/6 plans. The confidence interval for the proportion of errors detected was computed using the Wilson score interval. Results: Simulated errors were detected in 65% of reviews [51–75%] (95% confidence interval [CI] in brackets). The following error scenarios had the highest detection rates: incorrect isocenter in DRRs/CBCT (91% [73–98%]) and a planned dose different from the prescribed dose (100% [61–100%]). Errors with low detection rates involved incorrect field parameters in record and verify system (38%, [18–61%]) and incorrect isocenter localization in planning system (29% [8–64%]). Though pre-treatment QA failure was reliably identified (100%), less than 20% of participants reported the error that caused the failure. Conclusion: This is one of the first quantitative studies of error detection. Although physics plan review is a key safety measure and can identify some errors with high fidelity, others errors are more challenging to detect. This data will guide future work on standardization and automation. Creating new checks or improving existing ones (i.e., via automation) will help in

  1. WE-H-BRC-09: Simulated Errors in Mock Radiotherapy Plans to Quantify the Effectiveness of the Physics Plan Review

    Energy Technology Data Exchange (ETDEWEB)

    Gopan, O; Kalet, A; Smith, W; Hendrickson, K; Kim, M; Young, L; Nyflot, M; Chvetsov, A; Phillips, M; Ford, E [University of Washington, Seattle, WA (United States)

    2016-06-15

    Purpose: A standard tool for ensuring the quality of radiation therapy treatments is the initial physics plan review. However, little is known about its performance in practice. The goal of this study is to measure the effectiveness of physics plan review by introducing simulated errors into “mock” treatment plans and measuring the performance of plan review by physicists. Methods: We generated six mock treatment plans containing multiple errors. These errors were based on incident learning system data both within the department and internationally (SAFRON). These errors were scored for severity and frequency. Those with the highest scores were included in the simulations (13 errors total). Observer bias was minimized using a multiple co-correlated distractor approach. Eight physicists reviewed these plans for errors, with each physicist reviewing, on average, 3/6 plans. The confidence interval for the proportion of errors detected was computed using the Wilson score interval. Results: Simulated errors were detected in 65% of reviews [51–75%] (95% confidence interval [CI] in brackets). The following error scenarios had the highest detection rates: incorrect isocenter in DRRs/CBCT (91% [73–98%]) and a planned dose different from the prescribed dose (100% [61–100%]). Errors with low detection rates involved incorrect field parameters in record and verify system (38%, [18–61%]) and incorrect isocenter localization in planning system (29% [8–64%]). Though pre-treatment QA failure was reliably identified (100%), less than 20% of participants reported the error that caused the failure. Conclusion: This is one of the first quantitative studies of error detection. Although physics plan review is a key safety measure and can identify some errors with high fidelity, others errors are more challenging to detect. This data will guide future work on standardization and automation. Creating new checks or improving existing ones (i.e., via automation) will help in

  2. Summary of public comments and NRC staff analysis relating to rulemaking on emergency planning for nuclear power plants

    International Nuclear Information System (INIS)

    1980-09-01

    This NUREG provides a summary and discussions of public comments received during the expedited rulemaking to upgrade emergency preparedness around nuclear power reactor sites. The final rule was published in the Federal Register (45 FR 55402) on August 19, 1980. The information in NUREG-0684 was excerpted in the main from internal paper SECY-80-275 (June 3, 1980) which forwarded the final rule to the Commission for consideration. This document, along with NUREG-0628, NUREG/CP-0011, and the materials cited in the Final Rules, should be considered a compendium of the major issues raised in this proceeding and acted upon by the Commission

  3. 77 FR 21592 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Science.gov (United States)

    2012-04-10

    ... Licensing of Non-Power Reactors: Format and Content,'' for the production of radioisotopes and NUREG-1537, Part 2, ``Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors... by searching on http://www.regulations.gov under Docket ID NRC-2011-0135. You may submit comments by...

  4. WOMEN’S EMPOWERMENT AND FAMILY PLANNING: A REVIEW OF THE LITERATURE

    Science.gov (United States)

    PRATA, NDOLA; FRASER, ASHLEY; HUCHKO, MEGAN J.; GIPSON, JESSICA D.; WITHERS, MELLISSA; LEWIS, SHAYNA; CIARALDI, ERICA J.; UPADHYAY, USHMA D.

    2017-01-01

    Summary This paper reviews the literature examining the relationship between women’s empowerment and contraceptive use, unmet need for contraception and related family planning topics in developing countries. Searches were conducted using PubMed, Popline and Web of Science search engines in May 2013 to examine literature published between January 1990 and December 2012. Among the 46 articles included in the review, the majority were conducted in South Asia (n = 24). Household decision-making (n = 21) and mobility (n = 17) were the most commonly examined domains of women’s empowerment. Findings show that the relationship between empowerment and family planning is complex, with mixed positive and null associations. Consistently positive associations between empowerment and family planning outcomes were found for most family planning outcomes but those investigations represented fewer than two-fifths of the analyses. Current use of contraception was the most commonly studied family planning outcome, examined in more than half the analyses, but reviewed articles showed inconsistent findings. This review provides the first critical synthesis of the literature and assesses existing evidence between women’s empowerment and family planning use. PMID:28069078

  5. Standard Review Plan Maintenance Program implementing procedures document

    International Nuclear Information System (INIS)

    1996-11-01

    The implementing Procedures Document (IPD) was developed by the Inspection Program Projects Branch, Office of Nuclear Reactor Regulation, with assistance from Pacific Northwest National Laboratory, for the Standard Review Plan Maintenance Program (SRP-MP). The SRP-MP was established to maintain the Standard Review Plan (SRP) on an on-going basis. The IPD provides guidance, including an overall approach and procedures, for SRP-MP tasks. The objective of the IPD is to ensure that modifications to SRP need to reflect current NRC requirements and guidance are identified and that a consistent methodology is used to develop and revise SRP sections

  6. Constellation Mission Operation Working Group: ESMO Maneuver Planning Process Review

    Science.gov (United States)

    Moyer, Eric

    2015-01-01

    The Earth Science Mission Operation (ESMO) Project created an Independent Review Board to review our Conjunction Risk evaluation process and Maneuver Planning Process to identify improvements that safely manages mission conjunction risks, maintains ground track science requirements, and minimizes overall hours expended on High Interest Events (HIE). The Review Board is evaluating the current maneuver process which requires support by multiple groups. In the past year, there have been several changes to the processes although many prior and new concerns exist. This presentation will discuss maneuver process reviews and Board comments, ESMO assessment and path foward, ESMO future plans, recent changes and concerns.

  7. Reducing the Cost and Time to Perform a Human Factors Engineering Evaluation

    International Nuclear Information System (INIS)

    Geary, L.C. Dr.

    2003-01-01

    The Westinghouse Savannah River Company, a contractor to the Department of Energy, has developed a new software tool for automating the Human Factors Engineering design review, analysis, and evaluation processes. The set of design guidelines, used in the tool, was obtained from the United States Nuclear Regulatory Commission Nuclear Regulatory Guide, NUREG- 0700 - Human System Interface Design Review Guideline. This tool has been described at a previous IEEE Conference on Human Factors and Power Plants. The original software tool in NUREG- 0700 was used to evaluate a facility and a separate independent evaluation was performed using the new tool for the same facility. A comparison was made between the two different tools; both in results obtained and cost and time to complete the evaluation. The results demonstrate a five to ten fold reduction in time and cost to complete the evaluation using the newly developed tool while maintaining consistent evaluation results. The time to per form the review was measured in weeks using the new software tool rather than months using the existing NUREG-0700 tool. The new tool has been so successful that it was applied to two additional facilities with the same reduced time and cost savings. Plans have been made to use the new tool at other facilities in order to provide the same savings

  8. Nuclear emergency planning in Spain. The PLABEN review project

    International Nuclear Information System (INIS)

    Lentijo Lentijo, J. C.; Vila Pena, M.

    2002-01-01

    The international rules and recommendations for nuclear emergency planning and the Spanish experience gained in the management of event with radiological risk have noticed that is necessary to review the planning radiological bases for emergencies in nuclear power plants and to define the planning radiological bases for radiological emergencies that could happen in radioactive facilities or in activities out of the regulatory framework. The paper focuses on CSN actions concerning the Plaben review project related to define the new radiological principles taking into account the current international recommendations for interventions, make a proposal about the organisation and operation of the provincial radiological action group and the national support level for radiological emergency response. (Author) 7 refs

  9. Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components

    International Nuclear Information System (INIS)

    Ware, A.G.; Morton, D.K.; Nitzel, M.E.

    1995-03-01

    Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four U.S. nuclear steam supply system vendors. For each facility, six locations were studied, including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This report discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants

  10. Differing professional opinions: 1987 special review panel

    International Nuclear Information System (INIS)

    1988-01-01

    In November 1987, the five-member Differing Professional Opinions Special Review Panel established by the Executive Director for Operations of the US Nuclear Regulatory Commission to review agency policies and procedures for handling differing professional opinions (DPOs) presented its findings and recommendations in NUREG-1290. The issuance of that report completed the first task of the panel's charter. In accordance with Manual chapter 4125, Section L, and the charter of the Special Review Panel, the panel's second task was to ''...review...the DPOs submitted subsequent to the previous Panel's review, in order to identify any employee whose DPO made a significant contribution to the Agency or to the public safety but who has not yet been recognized for such contribution.'' This Addendum provides the findings of that review

  11. Review: Freshwater conservation planning in South Africa ...

    African Journals Online (AJOL)

    Review: Freshwater conservation planning in South Africa: Milestones to ... Water SA. Journal Home · ABOUT THIS JOURNAL · Advanced Search ... Since the 1970s, at approximately 10-year intervals, 4 national-scale freshwater conservation ...

  12. Reassessment of the technical bases for estimating source terms. Draft report for comment

    International Nuclear Information System (INIS)

    Silberberg, M.; Mitchell, J.A.; Meyer, R.O.; Pasedag, W.F.; Ryder, C.P.; Peabody, C.A.; Jankowski, M.W.

    1985-07-01

    NUREG-0956 describes the NRC staff and contractor efforts to reassess and update the agency's analytical procedures for estimating accident source terms for nuclear power plants. The effort included development of a new source term analytical procedure - a set of computer codes - that is intended to replace the methodology of the Reactor Safety Study (WASH-1400) and to be used in reassessing the use of TID-14844 assumptions (10 CFR 100). NUREG-0956 describes the development of these codes, the demonstration of the codes to calculate source terms for specific cases, the peer review of this work, some perspectives on the overall impact of new source terms on plant risks, the plans for related research projects, and the conclusions and recommendations resulting from the effort

  13. Russian MINATOM nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    1999-03-01

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

  14. On the peer review process and its implications for future PRAs

    International Nuclear Information System (INIS)

    Kastenberg, W.E.

    1989-01-01

    A Probabilistic Risk Assessment (PRA) is an effort to quantify nuclear power plant safety in terms of the frequency and consequences of severe accidents. Even though risk analysis can be considered a mature field, the results of recent PRA's are not as robust as they should be because of uncertainty. Some of the major contributors to the uncertainty regarding our current state of knowledge with respect to PRA are: System behavior is subjected to human intervention (and behavior) which is difficult to quantify. Phenomena encountered during severe accidents are difficult to model because they involve multi-component, multi-phase physico-chemical effects in ill-defined geometries. System behavior due to severe external events (e.g., earthquakes, fires) is difficult to model and quantify. Various aspects of plant design and operation are omitted from consideration such as design errors, plant aging and partial operation of engineered safety features. NUREG-1150, have been subject to peer review. The objective of this paper is to discuss the Peer Review of the Draft Reactor Risk Reference Document, and its implications of the future. We begin with a discussion of the objectives of a peer review, peer review committees, and the comments of a peer review committee. We then discuss a major aspect of the NUREG-1150 Peer Review dealing with uncertainty and expert opinion. Given these discussions, some implications for future PRA's will be presented. The goal is to initiate dialogue so that the PRA process as well as its bottom line results achieve credibility in the technical community

  15. PARTITION: A program for defining the source term/consequence analysis interface in the NUREG--1150 probabilistic risk assessments

    International Nuclear Information System (INIS)

    Iman, R.L.; Helton, J.C.; Johnson, J.D.

    1990-05-01

    The individual plant analyses in the US Nuclear Regulatory Commission's reassessment of the risk from commercial nuclear power plants (NUREG-1150) consist of four parts: systems analysis, accident progression analysis, source term analysis, and consequence analysis. Careful definition of the interfaces between these parts is necessary for both information flow and computational efficiency. This document has been designed for users of the PARTITION computer program developed by the authors at Sandia National Laboratories for defining the interface between the source term analysis (performed with the XXSOR programs) and the consequence analysis (performed with the MACCS program). This report provides a tutorial that details how the interactive partitioning is performed, along with detailed information on the partitioning process. The PARTITION program was written in ANSI standard FORTRAN 77 to make the code as machine-independent (i.e., portable) as possible. 9 refs., 4 figs

  16. Review of the current understanding of the potential for containment failure from in-vessel steam explosions

    International Nuclear Information System (INIS)

    1985-06-01

    A group of experts was convened to review the current understanding of the potential for containment failure from in-vessel steam explosions during core meltdown accidents in LWRs. The Steam Explosion Review Group (SERG) was requested to provide assessments of: (1) the conditional probability of containment failure due to a steam explosion, (2) a Sandia National Laboratory (SNL) report entitled ''An Uncertainty Study of PWR Steam Explosions,'' NUREG/CR-3369, (3) a SNL proposed steam explosion research program. This report summarizes the results of the deliberations of the review group. It also presents the detailed response of each individual member to each of the issues. The consensus of the SERG is that the occurrence of a steam explosion of sufficient energetics which could lead to alpha-mode containment failure has a low probability. The SERG members disagreed with the methodology used in NUREG/CR-3369 for the purpose of establishing the uncertainty in the probability of containment failure by a steam explosion. A consensus was reached among SERG members on the need for a continuing steam explosion research program which would improve our understanding of certain aspects of steam explosion phenomenology

  17. Practical education in family planning: integrative review

    Directory of Open Access Journals (Sweden)

    Creusa Ferreira da Silva

    2017-07-01

    Full Text Available Objectives: To identify educational practices in family planning, facilitating factors, difficulties and resulting impacts. Method: This is an integrative literature review, using the three descriptors: "family planning", "health education" and "contraception"; In the databases of the Scientific Electronic Library Online (SciELO, Latin American and Caribbean Literature in Health Sciences (LILACS and Nursing Database (BDENF, were searched in January and February 2016. Results: Regarding the accomplishment of educational practices, most of the studies pointed out its accomplishment. The difficulties and facilitators aspects were related to the management of the health service, professional competence and users. Guarantee of family rights and autonomy were the impacts pointed out. Conclusion: The study showed that educational practices in family planning are tools to be encouraged as a guarantee and respect for sexual and reproductive rights. Descriptors: family planning; education in health; contraception.

  18. Management implementation plan for a safety analysis and review system

    International Nuclear Information System (INIS)

    Hulburt, D.A.; Berkey, B.D.

    1981-04-01

    The US Department of Energy has issued an Order, DOE 5481.1, which establishes uniform requirements for the preparation and review of Safety Analysis for DOE Operations. The Management Implementation Plan specified herein establishes the administrative procedures and technical requirements for implementing DOE 5481.1 to Operations under the cognizance of the Pittsburgh Energy Technology Center. This Implementation Plan is applicable to all present and future Operations under the cognizance of PETC. The Plan identifies those Operations for which DOE 5481.1 is applicable and those Operations for which no further analysis is required because the initial determination and review has concluded that DOE 5481.1 does not apply

  19. The evaluation of equipment and Instrumentation Reliability Factors on Power Reactor

    International Nuclear Information System (INIS)

    Supriatna, Piping; Karlina, Itjeu; Widagdo, Suharyo; Santosa, Kussigit; Darlis; Sudiyono, Bambang; Yuniyanta, Sasongko; Sudarmin

    1999-01-01

    Equipment and instrumentation reliability on type power reactor control room was determined by its pattern and design. the principle of ergonomy applied on equipment and instrumentation layout in this ABWR type reactor are geometric pattern appropriate with economic body motion, average anthropometry data of operator especially operator hand-reach, range of vision, angle of vision, lighting, color arrangement and harmony as will as operator case in operating the equipment system. Limitation criteria of the parameter mentioned above are based on EPRI NP-3659, NURG 0700, and NUREG/CR-3331 documents. Besides that, the (working) physical environment parameter factor of the control room must be designed in order to fulfil the standard criteria of ergonomic condition based on NUREG-0800. The reliability evaluation of equipment and instrumentation system also occurs observed from man machine interaction side which happen between operator and equipment and instrumentation in the ABWR type power reactor control room. From the MMI analysis can be known the working failure possibility which is caused by the operator. The evaluation result of equipment and instrumentation reliability on ABWR type power reactor control room showed that the design of this ABWR control room is good and fulfils the ergonomy standard criteria have been determined

  20. Multi-Objective Planning Techniques in Distribution Networks: A Composite Review

    Directory of Open Access Journals (Sweden)

    Syed Ali Abbas Kazmi

    2017-02-01

    Full Text Available Distribution networks (DNWs are facing numerous challenges, notably growing load demands, environmental concerns, operational constraints and expansion limitations with the current infrastructure. These challenges serve as a motivation factor for various distribution network planning (DP strategies, such as timely addressing load growth aiming at prominent objectives such as reliability, power quality, economic viability, system stability and deferring costly reinforcements. The continuous transformation of passive to active distribution networks (ADN needs to consider choices, primarily distributed generation (DG, network topology change, installation of new protection devices and key enablers as planning options in addition to traditional grid reinforcements. Since modern DP (MDP in deregulated market environments includes multiple stakeholders, primarily owners, regulators, operators and consumers, one solution fit for all planning scenarios may not satisfy all these stakeholders. Hence, this paper presents a review of several planning techniques (PTs based on mult-objective optimizations (MOOs in DNWs, aiming at better trade-off solutions among conflicting objectives and satisfying multiple stakeholders. The PTs in the paper spread across four distinct planning classifications including DG units as an alternative to costly reinforcements, capacitors and power electronic devices for ensuring power quality aspects, grid reinforcements, expansions, and upgrades as a separate category and network topology alteration and reconfiguration as a viable planning option. Several research works associated with multi-objective planning techniques (MOPT have been reviewed with relevant models, methods and achieved objectives, abiding with system constraints. The paper also provides a composite review of current research accounts and interdependence of associated components in the respective classifications. The potential future planning areas, aiming at

  1. Care Plan Improvement in Nursing Homes: An Integrative Review.

    Science.gov (United States)

    Mariani, Elena; Chattat, Rabih; Vernooij-Dassen, Myrra; Koopmans, Raymond; Engels, Yvonne

    2017-01-01

    Care planning nowadays is a key activity in the provision of services to nursing home residents. A care plan describes the residents' needs and the actions to address them, providing both individualized and standardized interventions and should be updated as changes in the residents' conditions occur. The aim of this review was to identify the core elements of the implementation of changes in nursing homes' care plans, by providing an overview of the type of stakeholders involved, describing the implementation strategies used, and exploring how care plans changed. An integrative literature review was used to evaluate intervention studies taking place in nursing homes. Data were collected from PubMed, CINHAL-EBSCO, and PsycINFO. English language articles published between 1995 and April 2015 were included. Data analysis followed the strategy of Knafl and Whittemore. Twenty-six articles were included. The stakeholders involved were professionals, family caregivers, and patients. Only a few studies directly involved residents and family caregivers in the quality improvement process. The implementation strategies used were technology implementation, audit, training, feedback, and supervision. The majority of interventions changed the residents' care plans in terms of developing a more standardized care documentation that primarily focuses on its quality. Only some interventions developed more tailored care plans that focus on individualized needs. Care plans generally failed in providing both standardized and personalized interventions. Efforts should be made to directly involve residents in care planning and provide professionals with efficient tools to report care goals and actions in care plans.

  2. Government Performance and Results Act: Performance plan FY 1999, U.S. Nuclear Regulatory Commission. Volume 1

    International Nuclear Information System (INIS)

    Fuches, J.L.

    1998-02-01

    The Nuclear Regulatory Commission's (NRC) strategic plan [NUREG-1614, Vol. 1, September 1997] establishes a strategic framework that will guide future decision-making and will help the NRC continue to meet its responsibility for protecting public health and safety, promoting the common defense and security, and protecting the environment. This performance plan complements the agency's strategic plan by setting annual goals with measurable target levels of performance for FY 1999, as required by the Government Performance and Results Act. No significant contribution was made to the preparation of the performance plan by any non-Federal entity. However, a contractor was used to help facilitate discussions and resolution of issues. Within six months after the close of FY 1999, the NRC will submit to the President and the Congress a report on program performance for FY 1999. This performance report will review the success of the agency in achieving the performance goals established for FY 1999. Where those goals have been achieved, the underlying assumptions and strategies will be examined to ensure that continued applicability is warranted in the future. If any of the FY 1999 performance goals are not met, the agency will conduct a thorough analysis of why it did not meet the goal and the actions necessary to meet-the goal in the future. One result of this analysis will be the documentation of plans and schedules for achieving the established performance goal. If the analysis should indicate that the performance goal is impractical or infeasible, the performance report will document why that is the case and what action is recommended

  3. Organizational downsizing: a review of literature for planning and research.

    Science.gov (United States)

    Davis, Jullet A; Savage, Grant; Stewart, R Thomas

    2003-01-01

    The use of downsizing as management's strategic response to environmental and institutional changes is prevalent in all U.S. industries, including healthcare. The popular and research literature is inundated with reports on companies undergoing various stages of restructuring, which often include one or more staff reductions. This article provides a review of downsizing literature published from 1985 to 2002. Although the findings and conclusions of these articles are generally inconsistent, the prevailing opinion is that for downsizing to be successful, effective planning must occur long before, during, and after downsizing. Additionally, a downsizing plan should be included in the strategic management plan of all organizations, regardless of whether they plan to downsize or not. By including such a plan, the organization will be better prepared to begin the staff-reduction process should it be forced to do so in response to environmental changes. Finally, providing ample support and protection for staff is key to the organization's recovery and growth. The lessons provided in this literature review should assist healthcare managers in deciding how to plan and structure potential staff reductions.

  4. Russian Minatom nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    Royen, J.

    1999-01-01

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

  5. Agency procedures for the NRC incident response plan. Final report

    International Nuclear Information System (INIS)

    1983-02-01

    The NRC Incident Response Plan, NUREG-0728/MC 0502 describes the functions of the NRC during an incident and the kinds of actions that comprise an NRC response. The NRC response plan will be activated in accordance with threshold criteria described in the plan for incidents occurring at nuclear reactors and fuel facilities involving materials licensees; during transportation of licensed material, and for threats against facilities or licensed material. In contrast to the general overview provided by the Plan, the purpose of these agency procedures is to delineate the manner in which each planned response function is performed; the criteria for making those response decisions which can be preplanned; and the information and other resources needed during a response. An inexperienced but qualified person should be able to perform functions assigned by the Plan and make necessary decisions, given the specified information, by becoming familiar with these procedures. This rule of thumb has been used to determine the amount of detail in which the agency procedures are described. These procedures form a foundation for the training of response personnel both in their normal working environment and during planned emergency exercises. These procedures also form a ready reference or reminder checklist for technical team members and managers during a response

  6. Development and verification for review plan of emergency action level (EAL)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Emergency action levels (EALs) are used as the trigger in order to implement the precautionary protective actions at the nuclear emergency. In this study the framework for applying the EAL in Japan and the process for developing the review plan, such as procedures to review the basis of EAL submitted by the licensee, have been investigated based on the survey for EAL review executed in the United States. In addition, issues to reflect the EAL framework in enhancement of the local government emergency planning and emergency response support system have been investigated. (author)

  7. Engineering and planning for decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Gans, G.M. Jr.

    1982-01-01

    With the publication of NUREG-0586, ''Draft Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities'' in January, 1981 the Nuclear Regulatory Commission staff has put the industry on notice that the termination of operating licenses and the final disposal of physical facilities will require the early consideration of several options and approaches and the preparation of comprehensive engineering and planning documents for the selected option at the end of useful life. This paper opens with a discussion of the options available and the principal aspects of decommissioning. The major emphasis of the composition is the nature of documents, the general approach to be followed, and special considerations to be taken into account when performing the detailed engineering and planning for decommissioning, as the end of life approaches and actual physical disposal is imminent. The author's main point of reference is on-going work by Burns and Roe, with Nuclear Energy Services, under contract to the Department of Energy's Richland Office, to perform the engineering and planning for the decommissioning of the Shippingport Atomic Power Station in Pennsylvania

  8. Site-specific issues related to structural/seismic design of an underground independent spent fuel storage installation (ISFSI)

    International Nuclear Information System (INIS)

    Tripathi, B.P.

    2005-01-01

    Utilities owning and operating commercial nuclear power plants (NPP) in USA may choose to build an underground Independent Spent Fuel Storage Installation (ISFSI) to store the spent nuclear fuels. The regulatory requirements and other guidance are based on 10 CFR Part 72, Regulatory Guide RG 3.73, Standard Review Plans NUREG-1536 and NUREG-1567, and Interim staff Guidance (ISG) documents as applicable. Structures, Systems, and Components (SSCs) classified as important to safety are designed to withstand the effects of site-specific environmental conditions and natural phenomena such as earthquake, tornado, flood, etc. An underground ISFSI for storage of spent nuclear fuel, presents some unique analysis and design challenges. This paper will briefly address some of these challenges and discuss site-specific loads, including seismic for the ISFSI design. (authors)

  9. Review of P-scan computer-based ultrasonic inservice inspection system. Supplement 1

    International Nuclear Information System (INIS)

    Harris, R.V. Jr.; Angel, L.J.

    1995-12-01

    This Supplement reviews the P-scan system, a computer-based ultrasonic system used for inservice inspection of piping and other components in nuclear power plants. The Supplement was prepared using the methodology described in detail in Appendix A of NUREG/CR-5985, and is based on one month of using the system in a laboratory. This Supplement describes and characterizes: computer system, ultrasonic components, and mechanical components; scanning, detection, digitizing, imaging, data interpretation, operator interaction, data handling, and record-keeping. It includes a general description, a review checklist, and detailed results of all tests performed

  10. A Literature Review On Multimodal Freight Transportation Planning Under Disruptions

    Science.gov (United States)

    Rosyida, E. E.; Santosa, B.; Pujawan, I. N.

    2018-04-01

    This paper reviews publication that focuses on multimodal freight transportation planning under disruptions. In this paper, disruptions are specified by the level of the disruptions occurs and the scope of its effect. This becomes an important distinction since the cause and effect that may occur at different levels. The failure to make this distinction has implications for how we understand and manage. The reviewed papers include those that develop framework, model, and technical procedure for freight transportation. Finally, we provide an outlook of future research directions on the domain of transportation planning.

  11. Discussion of comments from a peer review of a technique for human event analysis (ATHEANA)

    International Nuclear Information System (INIS)

    Forester, J.A.; Ramey-Smith, A.; Bley, D.C.; Kolaczkowski, A.M.; Cooper, S.E.; Wreathall, J.

    1998-01-01

    In May of 1998, a technical basis and implementation guidelines document for A Technique for Human Event Analysis (ATHEANA) was issued as a draft report for public comment (NUREG-1624). In conjunction with the release of the draft NUREG, a paper review of the method, its documentation, and the results of an initial test of the method was held over a two-day period in Seattle, Washington, in June of 1998. Four internationally-known and respected experts in human reliability analysis (HRA) were selected to serve as the peer reviewers and were paid for their services. In addition, approximately 20 other individuals with an interest in HRA and ATHEANA also attended the peer review meeting and were invited to provide comments. The peer review team was asked to comment on any aspect of the method or the report in which improvements could be made and to discuss its strengths and weaknesses. All of the reviewers thought the ATEANA method had made significant contributions to the field of PRA/HRA, in particular by addressing the most important open questions and issues in HRA, by attempting to develop an integrated approach, and by developing a framework capable of identifying types of unsafe actions that generally have not been considered using existing methods. The reviewers had many concerns about specific aspects of the methodology and made many recommendations for ways to improve and extend the method, and to make its application more cost effective and useful to PRA in general. Details of the reviewers' comments and the ATHEANA team's responses to specific criticisms will be discussed

  12. 48 CFR 2019.705-4 - Reviewing the subcontracting plan.

    Science.gov (United States)

    2010-10-01

    ... COMMISSION SOCIOECONOMIC PROGRAMS SMALL BUSINESS PROGRAMS Subcontracting With Small Business, Small Disadvantaged Business, and Women-Owned Small Business Concerns 2019.705-4 Reviewing the subcontracting plan...

  13. Decontamination and dismantlement plan for international reviewing

    International Nuclear Information System (INIS)

    Wells, P.B.; Earle, O.K.; Klepikov, A.Kh.

    2000-01-01

    When developing a decommissioning plan, several factors need to be included. First and foremost is the issue of outline and scope. Specific to the BN-350, are issues related to short term tasks required to support the safe storage of the reactor for the next 50 years, and long term tasks required to dismantle the reactor, leaving some sort of final state, (brown field, green field, etc.) In addition, issues such as personnel and physical safety as well as environmental concerns must be addressed to ensure the shut down and dismantlement of the reactor is done in a safe manner, both for personnel and the environment. In addition to being the base document in which to support work, a D and D plan can also be utilized to obtain financial resources necessary to complete the plan, as is the case for the BN-350 Reactor located in Aktau, Kazakhstan. By providing a clear and complete D and D plan, which includes costs and schedules for each item, it is anticipated that donor countries will have the ability to review, approve, and provide financial support to complete the work described in the plan

  14. Standard Review Plan for the review of safety analysis reports for nuclear power plants, updates. Irregular repts

    International Nuclear Information System (INIS)

    1980-01-01

    The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews, and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. It is also a purpose of the SRP to make information about regulatory matters widely available and to improve communication and understanding of the staff review process by interested members of the public and the nuclear power industry. The Standard Review Plan is written so as to cover a variety of site conditions and plant designs. Each section is written to provide the complete procedure and all acceptance criteria for all of the areas of review pertinent to that section. However, for any given application, the staff reviewers may select and emphasize particular aspects of each SRP section as is appropriate for the application

  15. Government Performance and Results Act: Performance plan FY 1999, U.S. Nuclear Regulatory Commission. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Fuches, J.L.

    1998-02-01

    The Nuclear Regulatory Commission`s (NRC) strategic plan [NUREG-1614, Vol. 1, September 1997] establishes a strategic framework that will guide future decision-making and will help the NRC continue to meet its responsibility for protecting public health and safety, promoting the common defense and security, and protecting the environment. This performance plan complements the agency`s strategic plan by setting annual goals with measurable target levels of performance for FY 1999, as required by the Government Performance and Results Act. No significant contribution was made to the preparation of the performance plan by any non-Federal entity. However, a contractor was used to help facilitate discussions and resolution of issues. Within six months after the close of FY 1999, the NRC will submit to the President and the Congress a report on program performance for FY 1999. This performance report will review the success of the agency in achieving the performance goals established for FY 1999. Where those goals have been achieved, the underlying assumptions and strategies will be examined to ensure that continued applicability is warranted in the future. If any of the FY 1999 performance goals are not met, the agency will conduct a thorough analysis of why it did not meet the goal and the actions necessary to meet-the goal in the future. One result of this analysis will be the documentation of plans and schedules for achieving the established performance goal. If the analysis should indicate that the performance goal is impractical or infeasible, the performance report will document why that is the case and what action is recommended.

  16. Social workers' involvement in advance care planning: a systematic narrative review.

    Science.gov (United States)

    Wang, Chong-Wen; Chan, Cecilia L W; Chow, Amy Y M

    2017-07-10

    Advance care planning is a process of discussion that enables competent adults to express their wishes about end-of-life care through periods of decisional incapacity. Although a number of studies have documented social workers' attitudes toward, knowledge about, and involvement in advance care planning, the information is fragmented. The purpose of this review was to provide a narrative synthesis of evidence on social workers' perspectives and experiences regarding implementation of advance care planning. Six databases were searched for peer-reviewed research papers from their respective inception through December 2016. All of the resulting studies relevant to both advance care planning and social worker were examined. The findings of relevant studies were synthesized thematically. Thirty-one articles met the eligibility criteria. Six research themes were identified: social workers' attitudes toward advance care planning; social workers' knowledge, education and training regarding advance care planning; social workers' involvement in advance care planning; social workers' perceptions of their roles; ethical issues relevant to advance care planning; and the effect of social work intervention on advance care planning engagement. The findings suggest that there is a consensus among social workers that advance care planning is their duty and responsibility and that social workers play an important role in promoting and implementing advance care planning through an array of activities. This study provides useful knowledge for implementing advance care planning through illustrating social workers' perspectives and experiences. Further studies are warranted to understand the complexity inherent in social workers' involvement in advance care planning for different life-limiting illnesses or within different socio-cultural contexts.

  17. Transportation Management Area Planning Certification Review Primer: Revised January 18, 2018

    Science.gov (United States)

    2018-01-18

    This primer outlines key concepts and expectations of a Transportation Management Area (TMA) Planning Certification Review. Reflecting on the collective experiences of past Certification Reviews, this includes references to relevant laws and regulati...

  18. Environmental Standard Review Plan for the review of license renewal applications for nuclear power plants

    International Nuclear Information System (INIS)

    O'Brien, J.; Kim, T.J.; Reynolds, S.

    1991-08-01

    The Environmental Standard Review Plan for the Review of License Applications for Nuclear Power Plants (ESRP-LR) is to be used by the NRC staff when performing environmental reviews of applications for the renewal of power reactor licenses. The use of the ESRP-LR provides a framework for the staff to determine whether or not environmental issues important to license renewal have been identified and the impacts evaluated and provides acceptance standards to help the reviewers comply with the National Environmental Policy Act

  19. 77 FR 37614 - Tariffs (Other Than Tariff Review Plan); Connect America Fund; A National Broadband Plan for Our...

    Science.gov (United States)

    2012-06-22

    ... (Other Than Tariff Review Plan); Connect America Fund; A National Broadband Plan for Our Future; Establishing Just and Reasonable Rates for Local Exchange Carriers; High-Cost Universal Service Support AGENCY... with the Commission's Connect America Fund, Report and Order (Order). The Commission submitted...

  20. C-Division annual review and operating plan, August 1990

    Energy Technology Data Exchange (ETDEWEB)

    Morse, N.R.

    1990-11-01

    The Computing and Communications Division is responsible for the Laboratory's Integrated Computing Network as well as Laboratory-wide communications. Our computing network, used by 8000 people distributed throughout the nation, constitutes one of the most powerful scientific computing facilities in the world. The purpose of this publication is to inform our clients of our strategic and operating plans. We review major accomplishments since early 1989 and describe our strategic planning goals and specific projects that will guide our operations over the next couple of years. Our mission statement, planning considerations, and management policies and practices are also included.

  1. Operational readiness review implementation plan for K Basin sludge water system

    International Nuclear Information System (INIS)

    IRWIN, R.M.

    2003-01-01

    This Implementation Plan (IP) has been prepared consistent with the requirements of U.S. Department of Energy (DOE) Order 425.1B, ''Startup and Restart of Nuclear Facilities'', and DOE-STD-3006-2000, ''Planning and Conduct of Operational Readiness Reviews'' (ORR) (DOE 2002). The scope of the DOE ORR is described in the RL ''Plan of Action, K Basin Sludge Water System'' (Veitenheimer 2003), prepared by DOE project line management and approved by the RL Manager, the designated Approval Authority, on March 20, 2003. The scope of the contractor ORR is described in the contractor ''Plan of Action for the K Basins Sludge Water System Operational Readiness Review'' (FH 2002a) which was prepared by Spent Nuclear Fuel (SNF) Project line management and approved by the DOE Richland Operations Office (RL) Manager on December 19, 2002. DOE Order 425.1B indicates that the Secretarial Officer is the Authorization Authority when substantial modifications are made to a Hazard Category 2 nuclear facility. This Authorization Authority has been delegated to the RL Manager by memorandum from Jessie Hill Roberson, dated February 5, 2003 (Roberson 2003). This IP provides the overall approach and guidelines for performance of the DOE ORR. Appendix A contains the Criteria and Review Approach Documents (CRAD), which define the review objectives and criteria as well as the approach for assessing each objective. ORR results will be published in a final report, as discussed in Section 9.4

  2. Requirement analysis and architecture of data communication system for integral reactor

    International Nuclear Information System (INIS)

    Jeong, K. I.; Kwon, H. J.; Park, J. H.; Park, H. Y.; Koo, I. S.

    2005-05-01

    When digitalizing the Instrumentation and Control(I and C) systems in Nuclear Power Plants(NPP), a communication network is required for exchanging the digitalized data between I and C equipments in a NPP. A requirements analysis and an analysis of design elements and techniques are required for the design of a communication network. Through the requirements analysis of the code and regulation documents such as NUREG/CR-6082, section 7.9 of NUREG 0800 , IEEE Standard 7-4.3.2 and IEEE Standard 603, the extracted requirements can be used as a design basis and design concept for a detailed design of a communication network in the I and C system of an integral reactor. Design elements and techniques such as a physical topology, protocol transmission media and interconnection device should be considered for designing a communication network. Each design element and technique should be analyzed and evaluated as a portion of the integrated communication network design. In this report, the basic design requirements related to the design of communication network are investigated by using the code and regulation documents and an analysis of the design elements and techniques is performed. Based on these investigation and analysis, the overall architecture including the safety communication network and the non-safety communication network is proposed for an integral reactor

  3. Clinical trials radiotherapy treatment plan review software : is this the first quantified assessment

    International Nuclear Information System (INIS)

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

    2011-01-01

    Full text: Clinical trials require robust quality assurance (QA) procedures to ensure commonality of all treatments, with independent reviews to assess compliance with trial protocols. All clinical trials tools, including QA software, require testing for validity and reliability. enabling inter- and intra-trial comparison. Unlike clinical radiotherapy treatment planning (RTP) systems, review software has no published guidelines. This study describes the design and development of a test suite to quantify the performance of review software in TROG clinical trials. Test areas are image handling and reconstruction; geometric accuracy; dosimetric accuracy; dose-volume histogram (DVH) calculation; display of plan parameters. TROG have developed tests for commissioning plan review software, assessed with SWAN 2.3, and CMS Elekta FocalPro. While image handling tests were based on published guidelines for RTP systems, dosimetric tests used the TROG QA case review requirements. Treatment plans represented systems of all manufacturers (Pinnacle, Eclipse, Xio and Oncentra) used in Australasian centres. The test suite identified areas for SW A software development, including the DVH algorithm, changed to reduce calculation time. Results, in Fig. I, for known volumes of varying shapes and sizes, demonstrate differences between SWAN 2.1 and 2.3 when compared with Eclipse. Liaison with SWAN programmers enabled re-instatement of 2.1 algorithm. The test suite has quantified the RTP review software, prioritised areas for development with the programmers, and improved the user experience.

  4. Nuclear power reactor security personnel training and qualification plan reviewer workbook

    International Nuclear Information System (INIS)

    1979-06-01

    The Training and Qualification Plan Reviewer Workbook has been developed to provide the information required for evaluating the adequacy of the Training and Qualification (T and Q) Plans developed to meet the requirements of 10 CFR 73.55(b)(4) and 10 CFR 73, Appendix B

  5. PLANNED HOME BIRTH: A REVIEW

    Directory of Open Access Journals (Sweden)

    Tamara Serdinšek

    2016-05-01

    Full Text Available Background: Home birth is as old as humanity, but still most middle- and high-income countries consider hospitals as the safest birth settings, as complications regarding birth are highly unpredictable. Despite this there are a few countries in which home birth in integrated into official healthcare system (the Netherlands, United Kingdom, Canada etc.. Home births can be divided into unplanned and planned, and the latter can be further categorized by the presence of the birth attendants. This review focuses on planned home births, which are differently represented throughout the world. In the United States 0.6-1.0% of all children are born at home, in the United Kingdom 2-3%, in Canada 1.6% and in the Netherlands 20-30%. For Slovenia, the number of planned home births is unknown; however, in 2010 0.1% of children were born outside medical facilities.Conclusions: The safety of home birth in still under the debate. While research confirms smaller number of obstetric interventions and some complications in mothers who give birth at home, the data regarding the neonatal and perinatal mortality and morbidity is still conflicting. This confirms the need for large multicentric trials in this field. Current home birth guidelines emphasize that women should be well informed regarding the possible advantages and disadvantages of home births. In addition, the emphasis is on definition of selection criteria for home birth, indications for intrapartal transfer to the hospital and appropriate education of birth attendants. 

  6. Human-factors engineering-control-room design review: Shoreham Nuclear Power Station. Draft audit report

    International Nuclear Information System (INIS)

    Peterson, L.R.; Preston-Smith, J.; Savage, J.W.; Rousseau, W.F.

    1981-01-01

    A human factors engineering preliminary design review of the Shoreham control room was performed at the site on March 30 through April 3, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was prepared on the basis of the HFEB's review of the applicant's Preliminary Design Assessment and the human factors engineering design review/audit performed at the site. The presented sections are numbered to conform to the guidelines of the draft version of NUREG-0700. They summarize the teams's observations of the control room design and layout, and of the control room operators' interface with the control room environment

  7. Development of Safety Review Guidance for Research and Training Reactors

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  8. Peer Review Plan for OPPT Work Plan Risk Assessment of 1 - Bromopropane (“1 - BP”)

    Science.gov (United States)

    This document outlines the peer review plan for a risk assessment which addresses occupational uses of 1-BP in dry-cleaning and foam gluing operations, consumer uses in aerosol solvent cleaners and spray adhesives, and its effects on human health.

  9. Case mix planning in hospitals: a review and future agenda.

    Science.gov (United States)

    Hof, Sebastian; Fügener, Andreas; Schoenfelder, Jan; Brunner, Jens O

    2017-06-01

    The case mix planning problem deals with choosing the ideal composition and volume of patients in a hospital. With many countries having recently changed to systems where hospitals are reimbursed for patients according to their diagnosis, case mix planning has become an important tool in strategic and tactical hospital planning. Selecting patients in such a payment system can have a significant impact on a hospital's revenue. The contribution of this article is to provide the first literature review focusing on the case mix planning problem. We describe the problem, distinguish it from similar planning problems, and evaluate the existing literature with regard to problem structure and managerial impact. Further, we identify gaps in the literature. We hope to foster research in the field of case mix planning, which only lately has received growing attention despite its fundamental economic impact on hospitals.

  10. Review and summary of Solar Thermal Conversion Program planning assistance

    Energy Technology Data Exchange (ETDEWEB)

    1975-06-01

    The Solar Thermal Conversion Program comprises a major part of the national solar energy program which must be continuously reviewed and modified where necessary. Modifications are typically required to reflect technical achievements and uncertainties which arise from within the program or from other technical programs, changes in budgets available for supporting the program as well as internal program funding priorities, changing goals such as through acceleration or stretch-out of the program schedule, significant organizational changes involving responsible governmental agencies, the introduction of new project management support contractors, and required budget or schedule changes occurring within individual projects that make up the Solar Thermal Conversion Program. The Aerospace Corporation has provided data to assist in planning, review, coordination, and documentation of the overall Solar Thermal Conversion Program. The Solar Thermal Conversion Program Plan is described in detail. Sections 2.0 through 5.0 cover the discussion and detail planning covering the objectives, justification, basic and alternative plans, budgets, and schedules for the Solar Thermal sub-unit portion of the Solar Electric Applications effort. Appendices B1, B2, and B3 include the March 21, March 28, and April 5, 1975, Program Plan submissions of the complete Solar Electric Applications effort. In Appendix B the Solar Thermal, Solar Photovoltaic, Wind Energy, and Ocean Thermal sub-unit texts have been condensed and formatted for integration in the overall ERDA budget package. (WHK)

  11. The non-ordinary Regge behavior of the K{sup *}{sub 0}(800) or κ-meson versus the ordinary K{sup *}{sub 0}(1430)

    Energy Technology Data Exchange (ETDEWEB)

    Pelaez, J.R.; Rodas, A. [Universidad Complutense de Madrid, Departamento de Fisica Teorica II and UPARCOS, Madrid (Spain)

    2017-06-15

    The Regge trajectory of an elastic resonance can be calculated from dispersion theory, instead of fitted phenomenologically, using only its pole parameters as input. This also provides a correct treatment of resonance widths in Regge trajectories, essential for very wide resonances. In this work we first calculate the K{sup *}{sub 0}(1430) Regge trajectory, finding the ordinary almost real and linear behavior, typical of q anti q resonances. In contrast, for the K{sup *}{sub 0}(800) meson, the resulting Regge trajectory is non-linear and has a much smaller slope than ordinary resonances, being remarkably similar to that of the f{sub 0}(500) or σ meson. The slope of these unusual Regge trajectories seems to scale with the meson masses rather than with scales typical of quark degrees of freedom. We also calculate the range of the interaction responsible for the formation of these resonances. Our results strongly support a non-ordinary, predominantly meson-meson-like, interpretation for the lightest strange and non-strange resonances. (orig.)

  12. Integrated Care Planning for Cancer Patients: A Scoping Review

    Directory of Open Access Journals (Sweden)

    Anum Irfan Khan

    2017-11-01

    Full Text Available Introduction: There has been a growing emphasis on the use of integrated care plans to deliver cancer care. However little is known about how integrated care plans for cancer patients are developed including featured core activities, facilitators for uptake and indicators for assessing impact. Methods: Given limited consensus around what constitutes an integrated care plan for cancer patients, a scoping review was conducted to explore the components of integrated care plans and contextual factors that influence design and uptake. Results: Five types of integrated care plans based on the stage of cancer care: surgical, systemic, survivorship, palliative and comprehensive (involving a transition between stages are described in current literature. Breast, esophageal and colorectal cancers were common disease sites. Multi-disciplinary teams, patient needs assessment and transitional planning emerged as key features. Provider buy-in and training alongside informational technology support served as important facilitators for plan uptake. Provider-level measurement was considerably less robust compared to patient and system-level indicators. Conclusions: Similarities in design features, components and facilitators across the various types of integrated care plans indicates opportunities to leverage shared features and enable a management lens that spans the trajectory of a patient’s journey rather than a phase-specific silo approach to care.

  13. 75 FR 69709 - Office of New Reactors; Notice of Availability of the Final Staff Guidance; Standard Review Plan...

    Science.gov (United States)

    2010-11-15

    ... the Final Staff Guidance; Standard Review Plan, Section 13.6.6, Revision 0 on Cyber Security Plan... Reports for Nuclear Power Plants,'' Section 13.6.6, Revision 0 on ``Cyber Security Plan'' (Agencywide... reviews to amendments to licenses for operating reactors or for activities associated with review of...

  14. Review. Assessing uncertainty and risk in forest planning and decision support systems: review of classical methods and introduction of innovative approaches

    Energy Technology Data Exchange (ETDEWEB)

    Pasalodos-Tato, M.; Makinen, A.; Garcia-Gonzalez, J.; Borges, J. G.; Lamas, T.; Eriksson, L. O.

    2013-09-01

    Aim: Since forest planning is characterized by long time horizon and it typically involves large areas of land and numerous stake holders, uncertainty and risk should play an important role when developing forest management plans. The aim of this study is to review different methods to deal with risk and uncertainty in forest planning, listing problems that forest managers may face during the preparation of management plans and trying to give recommendations in regard to the application of each method according to the problem case. The inclusion of risk and uncertainty in decision support systems is also analyzed. Area: It covers the temporal and spatial scale of forest planning, the spatial context, the participation process, the objectives dimensions and the good and services addressed. Material and methods: Several hundreds of articles dealing with uncertainty and risk were identified regarding different forestry-related topics and approaches. Form them, around 170 articles were further reviewed, categorized and evaluated. Main results: The study presents a thorough review and classification of methods and approaches to consider risk and uncertainty in forest planning. Moreover, new approaches are introduced, showing the opportunities that their application presents in forest planning. Research highlights: The study can aid forest managers in the decision making process when designing a forest management plan considering risk and uncertainty. (Author)

  15. Review. Assessing uncertainty and risk in forest planning and decision support systems: review of classical methods and introduction of new approaches

    Directory of Open Access Journals (Sweden)

    M. Pasalodos-Tato

    2013-07-01

    Full Text Available Aim: Since forest planning is characterized by long time horizon and it typically involves large areas of land and numerous stakeholders, uncertainty and risk should play an important role when developing forest management plans. The aim of this study is to review different methods to deal with risk and uncertainty in forest planning, listing problems that forest managers may face during the preparation of management plans and trying to give recommendations in regard to the application of each method according to the problem case. The inclusion of risk and uncertainty in decision support systems is also analyzed.Area: It covers the temporal and spatial scale of forest planning, the spatial context, the participation process, the objectives dimensions and the good and services addressed.Material and methods: Several hundreds of articles dealing with uncertainty and risk were identified regarding different forestry-related topics and approaches. Form them, around 170 articles were further reviewed, categorized and evaluated.Main results: The study presents a thorough review and classification of methods and approaches to consider risk and uncertainty in forest planning. Moreover, new approaches are introduced, showing the opportunities that their application present in forest planning.Research highlights: The study can aid forest managers in the decision making process when designing a forest management plan considering risk and uncertainty.Keywords: operations research; optimal alternative; stochastic risk; endogenous risk; stand level; forest level.

  16. The implementation of the Plan Esperanza and response to the imPACT Review.

    Science.gov (United States)

    Vidaurre, Tatiana; Santos, Carlos; Gómez, Henry; Sarria, Gustavo; Amorin, Edgar; López, Marga; Regalado, Roxana; Manrique, Javier; Tarco, Duniska; Ayestas, Carlos; Calderón, Mónica; Mas, Luis; Neciosup, Silvia; Salazar, Miriam; Chávez, Juan Carlos; Ubillus, Milward; Limache, Abel; Ubillus, José Carlos; Navarro, Jeannie; Sarwal, Kavita; Sutcliffe, Simon; Gutiérrez-Aguado, Alfonso; Silva, Marianela; Mena, Amalia; Guillén, María Eugenia; Castañeda, Carlos; Abugattas, Julio

    2017-10-01

    Following the implementation of the National Cancer Prevention and Control Results-based Budget Programme (PpR Cancer-024) in 2011, the Peruvian Government approved the Plan Esperanza-a population-based national cancer control plan-in 2012. Legislation that ensured full government-supported funding for people who were otherwise unable to access or afford care and treatment accompanied the Plan. In 2013, the Ministry of Health requested an integrated mission of the Programme of Action for Cancer Therapy (imPACT) report to strengthen cancer control in Peru. The imPACT Review, which was executed in 2014, assessed Peru's achievements in cancer control, and areas for improvement, including cancer control planning, further development of population-based cancer registration, increased prevention, early diagnosis, treatment and palliative care, and the engagement and participation of civil society in the health-care system. This Series paper gives a brief history of the development of the Plan Esperanza, describes the innovative funding model that supports it, and summarises how funds are disseminated on the basis of disease, geography, and demographics. An overview of the imPACT Review, and the government's response in the context of the Plan Esperanza, is provided. The development and execution of the Plan Esperanza and the execution of and response to the imPACT Review demonstrates the Peruvian Government's commitment to fighting cancer across the country, including in remote and urban areas. Copyright © 2017 Elsevier Ltd. All rights reserved.

  17. Safety evaluation report related to the license renewal and power increase for the National Bureau of Standards reactor (Docket No. 50-184)

    International Nuclear Information System (INIS)

    Bernard, H.

    1984-03-01

    Supplement 1 to the Safety Evaluation Report (SER) related to the renewal of the operating license and for a power increase (10 MWt to 20 MWt) for the research reactor at the National Bureau of Standards (NBS) facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports on the review of the licensee's emergency plan, which had not been reviewed at the time the Safety Evaluation Report (NUREG-1007) was published, and the review of the NBS application by the Advisory Committee on Reactor Safeguards, which was completed subsequent to the publication of the SER

  18. HUMAN FACTORS GUIDANCE FOR CONTROL ROOM EVALUATION

    International Nuclear Information System (INIS)

    OHARA, J.; BROWN, W.; STUBLER, W.; HIGGINS, J.; WACHTEL, J.; PERSENSKY, J.J.

    2000-01-01

    The Human-System Interface Design Review Guideline (NUREG-0700, Revision 1) was developed by the US Nuclear Regulatory Commission (NRC) to provide human factors guidance as a basis for the review of advanced human-system interface technologies. The guidance consists of three components: design review procedures, human factors engineering guidelines, and a software application to provide design review support called the ''Design Review Guideline.'' Since it was published in June 1996, Rev. 1 to NUREG-0700 has been used successfully by NRC staff, contractors and nuclear industry organizations, as well as by interested organizations outside the nuclear industry. The NRC has committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool in the face of emerging and rapidly changing technology. This paper addresses the current research to update of NUREG-0700 based on the substantial work that has taken place since the publication of Revision 1

  19. 11 CFR 116.7 - Debt settlement plans filed by terminating committees; Commission review.

    Science.gov (United States)

    2010-01-01

    ... description of the terms under which the creditor has extended credit to nonpolitical debtors of similar risk... settlement plan after the creditors included in the debt settlement plan have agreed to the settlement or... payments to the creditors included in the debt settlement plan until completion of Commission review. The...

  20. 6 CFR 27.245 - Review and approval of site security plans.

    Science.gov (United States)

    2010-01-01

    ... 6 Domestic Security 1 2010-01-01 2010-01-01 false Review and approval of site security plans. 27.245 Section 27.245 Domestic Security DEPARTMENT OF HOMELAND SECURITY, OFFICE OF THE SECRETARY CHEMICAL FACILITY ANTI-TERRORISM STANDARDS Chemical Facility Security Program § 27.245 Review and approval of site...

  1. 76 FR 78183 - Preliminary Plan for Retrospective Review Under E.O. 13579

    Science.gov (United States)

    2011-12-16

    ... DEPARTMENT OF JUSTICE Parole Commission 28 CFR Part 2 [Docket No. USPC-2011-01] Preliminary Plan for Retrospective Review Under E.O. 13579 AGENCY: United States Parole Commission, Justice. ACTION: Request for comments. SUMMARY: The U.S. Parole Commission is asking for comments on its preliminary plan...

  2. 31 CFR 206.6 - Cash management planning and review.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Cash management planning and review. 206.6 Section 206.6 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) FISCAL SERVICE, DEPARTMENT OF THE TREASURY FINANCIAL MANAGEMENT SERVICE MANAGEMENT OF FEDERAL AGENCY...

  3. Attention demands of spoken word planning: A review

    Directory of Open Access Journals (Sweden)

    Ardi eRoelofs

    2011-11-01

    Full Text Available Attention and language are among the most intensively researched abilities in the cognitive neurosciences, but the relation between these abilities has largely been neglected. There is increasing evidence, however, that linguistic processes, such as those underlying the planning of words, cannot proceed without paying some form of attention. Here, we review evidence that word planning requires some but not full attention. The evidence comes from chronometric studies of word planning in picture naming and word reading under divided attention conditions. It is generally assumed that the central attention demands of a process are indexed by the extent that the process delays the performance of a concurrent unrelated task. The studies measured the speed and accuracy of linguistic and nonlinguistic responding as well as eye gaze durations reflecting the allocation of attention. First, empirical evidence indicates that in several task situations, processes up to and including phonological encoding in word planning delay, or are delayed by, the performance of concurrent unrelated nonlinguistic tasks. These findings suggest that word planning requires central attention. Second, empirical evidence indicates that conflicts in word planning may be resolved while concurrently performing an unrelated nonlinguistic task, making a task decision, or making a go/no-go decision. These findings suggest that word planning does not require full central attention. We outline a computationally implemented theory of attention and word planning, and describe at various points the outcomes of computer simulations that demonstrate the utility of the theory in accounting for the key findings. Finally, we indicate how attention deficits may contribute to impaired language performance, such as in individuals with specific language impairment.

  4. Path Planning Methods in an Environment with Obstacles (A Review

    Directory of Open Access Journals (Sweden)

    W. Liu

    2018-01-01

    Full Text Available Planning the path is the most important task in the mobile robot navigation. This task involves basically three aspects. First, the planned path must run from a given starting point to a given endpoint. Secondly, it should ensure robot’s collision-free movement. Thirdly, among all the possible paths that meet the first two requirements it must be, in a certain sense, optimal.Methods of path planning can be classified according to different characteristics. In the context of using intelligent technologies, they can be divided into traditional methods and heuristic ones. By the nature of the environment, it is possible to divide planning methods into planning methods in a static environment and in a dynamic one (it should be noted, however, that a static environment is rare. Methods can also be divided according to the completeness of information about the environment, namely methods with complete information (in this case the issue is a global path planning and methods with incomplete information (usually, this refers to the situational awareness in the immediate vicinity of the robot, in this case it is a local path planning. Note that incomplete information about the environment can be a consequence of the changing environment, i.e. in a dynamic environment, there is, usually, a local path planning.Literature offers a great deal of methods for path planning where various heuristic techniques are used, which, as a rule, result from the denotative meaning of the problem being solved. This review discusses the main approaches to the problem solution. Here we can distinguish five classes of basic methods: graph-based methods, methods based on cell decomposition, use of potential fields, optimization methods, фтв methods based on intelligent technologies.Many methods of path planning, as a result, give a chain of reference points (waypoints connecting the beginning and end of the path. This should be seen as an intermediate result. The problem

  5. Lessons learned from Three Mile Island (TMI), USNRC long-term trends, industry response

    International Nuclear Information System (INIS)

    Szalay, R.A.

    1981-01-01

    Studies resulting from Three Mile Island (TMI) showed that corrections were needed in information processing, operator training and procedures, and certain aspects of the safety review process. These have been undertaken by industry and NRC and the results are positive. New safety instructions have been set up. The Nuclear Safety Analysis Center (NSAC) is providing a focus for analysis of issues which have generic elements affecting a number of plants of similar or related design. The Institute of Nuclear Power Operations (INPO) is setting industry standards for training and certification of operators and supervisory personnel, and for training of the managerial chain which oversees safety practices. Changes in procedures and in some design features called for in the recommendations of the NRC Lessons Learned Task Force (NUREG-0578) have been simplemented by utilities. Other requirements included in the NRC Action Plan (NUREG-0660) and its companion document clarification of TMI Action Plan Requirements (NUREG-0737), are also being addressed. Improved operator training and emergency procedures provide a continuing opportunity to make safety gains. Problems remain to be faced in the regulatory and political arenas. The long-term licensing trend will be affected by the manner in which degraded core issues and the development of a safety goal proceed. The Industry Degraded Core Rulemaking (IDCOR) program has been undertaken to develop the nuclear industry's position in anticipation of an impending rulemaking. Both industry and NRC are working on the development of a safety goal and standard risk assessment methodology. (AF)

  6. Critical Review of Spatial Planning of CAT Watuputih, Rembang Zone, Central Java, Indonesia

    Science.gov (United States)

    Hadi, Sudharto P.

    2018-02-01

    The Act 26 of 2007 on spatial planning stipulates that spatial planning at national, provincial and local level must be based on environmental carrying capacity and environmental carrying capability. Provincial governments generally finished its spatial planning in 2010 and the city and regency's governments in 2011.This paper reviews the spatial planning of Central Java and Rembang Regency regarding the use of CAT (ground water basin) Watuputih, Rembang Zone. Both spatial planning determined that CAT Watuputih was allocated for conservation and for mining. The mixed use zoning stimulates conflict between private sector and government on one side and local people along with academician and NGOs on another side. The SEA (Strategic Environmental Assessment) studies initiated by central government found that CAT Watuputih has strong indication to be KBAK (natural landscape area of karst) need to be conserved while at the moment there have been 21 mining permit holders operating since 1998. The lesson learned from the review is that formulation of spatial planning must be conducted participatory by involving relevant stakeholder, objective and accountable.

  7. 77 FR 31869 - Iris Lacustris (Dwarf Lake Iris); Draft Recovery Plan for Review and Comment

    Science.gov (United States)

    2012-05-30

    ...-FF03E00000] Iris Lacustris (Dwarf Lake Iris); Draft Recovery Plan for Review and Comment AGENCY: Fish and... Service (Service) announces availability for public review of the draft recovery plan for the Iris lacustris (dwarf lake iris), a species that is federally listed as threatened under the Endangered Species...

  8. Staff supplement to the draft report on human engineering guide to control room evaluation: response to comments, sample checklist, draft systems review guidelines, and evaluation procedures

    International Nuclear Information System (INIS)

    1981-03-01

    This staff supplement to Draft Report NUREG/CR-1580, Human Engineering Guide to Control Room Evaluation, provides staff responses to comments on the draft report and supplemental material not provided in the draft report. The supplemental material includes new draft guidelines for the systems review of nuclear power plant control rooms and sample checklists and corresponding human engineering guidelines

  9. A Review on the Application of GIS in Land Use Planning

    OpenAIRE

    CHE, Wentao; ABE, Daishu; MASUDA, Noboru; SHIMOMURA, Yasuhiko; YAMAMOTO, Satoshi

    1995-01-01

    In the last decade, we have seen the rapid development of GIS methods that are capable of being applied to land use planning. This paper tries to give a general review on the past and the near future of GIS applications in this area by the following steps. Firstly, a brief definition of land use planning and GIS, and the reasons why GIS are so widely used in land use planning are presented. Secondly, the history of GIS development in the past three decades is briefly considered. Thirdly, some...

  10. Standard Review Plan Update and Development Program

    International Nuclear Information System (INIS)

    1992-05-01

    This implementing procedures document (IPD) was prepared for use in implementing tasks under the standard review plan update and development program (SRP-UDP). The IPD provides comprehensive guidance and detailed procedures for SRP-UDP tasks. The IPD is mandatory for contractors performing work for the SRP-UDP. It is guidance for the staff. At the completion of the SRP-UDP, the IPD will be revised (to remove the UDP aspects) and will replace NRR Office Letter No. 800 as long-term maintenance procedures

  11. Standard Review Plan Update and Development Program

    Energy Technology Data Exchange (ETDEWEB)

    1992-05-01

    This implementing procedures document (IPD) was prepared for use in implementing tasks under the standard review plan update and development program (SRP-UDP). The IPD provides comprehensive guidance and detailed procedures for SRP-UDP tasks. The IPD is mandatory for contractors performing work for the SRP-UDP. It is guidance for the staff. At the completion of the SRP-UDP, the IPD will be revised (to remove the UDP aspects) and will replace NRR Office Letter No. 800 as long-term maintenance procedures.

  12. Planning and the Public Interest. A Critical Review

    Directory of Open Access Journals (Sweden)

    JÚLIA A. NAGY

    2015-12-01

    Full Text Available From an ethical perspective, the biggest difficulty for planners is to take the best approach in responding to the decision makers and in acting in the public interest because it always becomes subject of pressures arising with the governmental change, on the one hand, and the societal change on the other hand. Even though many debates arise regarding its existence, for planners, as well as for the planning profession, the public interest has always been legitimizing principles as a norm of practice (Alexander, 2002. The paper critically analyses the planning activity in relation to the public interest and highlights the importance of reciprocity between the two. In order to analyse this issue, the article starts with the presentation of different perspectives regarding the public interest, touching upon its conceptual meaning which is followed by a historical review of its origins and transformation. The third section presents its contextual meaning, its representatives, and the change of its content starting from the 19th century until nowadays and discusses the planners’ ability to represent it. The final part comprises the conclusions that indicate that the planning activity should serve the public interest and, by that, it would serve also the interest of planning as a profession. It emphasises two important issues of the present days: the definition of the public interest and the rational decision making within the planning process.

  13. A review of national gas emergency plans in the European Union

    International Nuclear Information System (INIS)

    Zeniewski, Peter; Bolado-Lavin, Ricardo

    2012-01-01

    The purpose of this paper is to document and review existing national gas emergency plans in the European Union, following the guidelines and requirements set out by the EU's Regulation 994/2010 concerning measures to safeguard security of gas supply. Despite the great deal of attention paid to questions of natural gas security in an increasingly import-dependent European Union, the contingency plans of most of its member states have not been widely published or scrutinized. By reviewing TSO network codes and national legal and regulatory acts, this paper teases out the key similarities and differences between member states' emergency planning frameworks, tools and methods. A gas emergency operational template is subsequently proposed that conforms to EU legislation. This is followed by a discussion of emergency planning in the context of regional cooperation and the liberalizing European gas market. The paper concludes by advocating gas emergency measures which are proportionate to the crisis level, sensitive to the gas demand profile, aware of the regional context, inconsequential to normal market operation, transparent and non-discriminatory during implementation and verifiable during emergencies as well as under normal conditions. - Highlights: ► National gas emergency plans in the EU comprehensively assessed. ► Template for gas emergencies is created to measure conformity to Regulation 994/2010. ► Gas emergency measures are related to regional cooperation and liberal markets.

  14. NPP License Renewal and Aging Management: Revised Guidance

    International Nuclear Information System (INIS)

    Hull, A.B.; Hiser, A.L.; Lindo-Talin, S.E.

    2012-01-01

    Based on the Atomic Energy Act, the NRC issues licenses for commercial power reactors to operate for up to 40 years and allows these licenses to be renewed for up to another 20 years. NRC has approved license renewal for well over 50% of U.S. located reactors originally licensed to operate for 40 years. Of these 104 reactors (69 PWRs, 35 BWRs), the NRC has issued renewed licenses for 71 units and is currently reviewing applications for another 15 units. As of May 1, 2012, ten plants at nine sites had entered their 41st year of operation and thus are in their first period of extended operation (PEO). Five more plants will enter the PEO by the end of 2012. One foundation of the license renewal process has been license renewal guidance documents (LRGDs). The U.S. Nuclear Regulatory Commission (NRC) revised key guidance documents used for nuclear power license renewal in 2010 and 2011. These include NUREG-1800, 'Standard Review Plan for Review of License Renewal Applications,' revision 2 (SRP-LR), and NUREG-1801, 'Generic Aging Lessons Learned (GALL) Report,' revision 2 (GALL Report). The guidance documents were updated to reflect lessons learned and operating experience gained since the guidance documents were last issued in 2005. (author)

  15. Operational Readiness Review Implementation Plan for the K Basin Fuel Transfer System

    International Nuclear Information System (INIS)

    DAVIES, T.H.

    2002-01-01

    This implementation plan has been prepared to comply with the requirements of U.S. Department of Energy (DOE) Order 425.1A, Startup and Restart of Nuclear Facilities, and DOE-STD-3006-2000, Planning and Conduct of Operational Readiness Reviews (ORR) (DOE 2002). The scope of the ORR is described in the contractor K Basin Fuel Transfer System (FTS) Plan of Action (POA), which was prepared by Spent Nuclear Fuel (SNF) Project line management and approved by the DOE Richland Operations Office (RL) Manager on April 4, 2002 (FH 2002a). While the Project Hanford Management Contractor has been revised to include DOE Order 425.1B, the contractor implementing procedure, ''F-PRO-055, Startup Readiness (Revision 9) has not yet been approved by RL for contractor use. Appendix A provides a crosswalk between the requirements of DOE Order 425.1A and DOE Order 425.1B to show that all requirements of DOE 425.1B are covered by this implementation plan. DOE Order 425.1B indicates that the Secretarial Officer is the Authorization Authority when substantial modifications are made to a Hazard Category 2 nuclear facility. This Authorization Authority has been delegated to the RL Manager by memorandum from Jessie Hill Roberson, dated November 20, 2001 (Roberson 2001). The scope of the ORR is described in the RL Plan of Action, K Basin Fuel Transfer System, prepared by DOE project line management and approved by the RL Manager, the designated approval authority, on September 12, 2002 (Schlender 2002). This implementation plan provides the overall approach and guidelines for performance of the DOE ORR. Appendix B contains the Criteria and Review Approach Documents (CRAD), which define the review objectives and criteria as well as the approach for assessing each objective. ORR results will be published in a final report, as discussed in Section 9.4

  16. Task Action Plans for generic activities: Category A

    International Nuclear Information System (INIS)

    1978-10-01

    The document contains listings of generic technical activities as identified and placed in priority categories by the Office of Nuclear Reactor Regulation (NRR). In addition, it contains definitions of Priority Categories A, B, C, and D and copies of forty approved Task Action Plans for Category A activites. Problem Descriptions for the Category B, C and D tasks are contained in NUREG--0471. This material was developed within the context of NRR's Program for the Resolution of Generic Issues Related to Nuclear Power Plants. As part of this program, the assignment of identified issues to priority categories and the approval of Task Action Plans were made by NRR's Technical Activities Steering Committee, chaired by the Deputy Director, NRR. The original document was published in November 1977. In December 1977 it was updated to add the Task Action Plan for Task No. A-17, Systems Interactions in Nuclear Power Plants. This update adds Task Action Plans for Tasks A-13, A-18, A-21, A-22, A-32, A-37, A-38 and A-40. Task A-41 has been included in Task A-40. In addition, as part of this update, the following changes were made to each Task Action Plan (with the exception of the Task Action Plan for Task A-9): (1) a title page was added that includes information such as Lead NRR Organization, Lead Supervisor, Task Manager, Applicability, and Projected Completion Date; (2) detailed schedule information was deleted; and (3) a new Section 3 entitled Basis for Continued Plant Operation and Licensing Pending Completion of Task was added. These changes represent general reformatting and the addition or deletion of certain general types of information. Some substantive revisions were made to several of the plans, however, a general revision of all of the plans was not undertaken at this time

  17. Low Impact Development Intensive Rural Construction Planning in Xu Fu Village Ningbo, China: Planning Review through Rural Resilience Perspective

    Directory of Open Access Journals (Sweden)

    Roosmayri Lovina Hermaputi

    2017-08-01

    Full Text Available Xu Fu Village Ningbo LID Intensive Rural Construction Planning is a cooperation project between Zhejiang University and Ningbo Institute of Technology which named "12th Five-Year National Science and Technology support program-the comprehensive demonstration of the key technology of the beautiful rural construction in the rapid urbanization area of the Yangtze River Delta". This plan focuses on intensive rural construction as part of rural development and construction project that applies the principles of low impact development. Xu Fu Village located in the Yangtze River Delta Region. Currently, the rural growth brings the high impact of development, as a result of rapid urbanization growth arising several issues, such as low land use efficiency, dispersed rural residence, homestead occupies more, rural roads covering over, etc. Meanwhile, Xu Fu village wishes to develop its tourism potential. Thus, the intensive rural construction should be done to avoid the severe effect. The project result hopefully can improve the quality and level of rural residential planning, design, and construction; improve their living environment; save construction land and water use; and improve energy efficiency. The aim of this study is to review the Low Impact Development (LID Intensive Rural Construction in Xu Fu Village, Ningbo City through the rural resilience perspective. This paper will describe the project plan first, then review it through rural resilience perspective. This paper will elaborate the rural resilience theory and then review the rural resiliency through two parts; the first part is identifying rural resilience in rural infrastructure development based on the criteria created by Ayyob S. and Yoshiki Y. (2014, about urban resiliency criteria, and then the second part is reviewing Xu Fu Village resilience through Arup Resilience Qualities (2012, considering three rural resilience domain (economy, ecology, and cultural.

  18. A review of plan library approaches in adaptive radiotherapy of bladder cancer.

    Science.gov (United States)

    Collins, Shane D; Leech, Michelle M

    2018-05-01

    Large variations in the shape and size of the bladder volume are commonly observed in bladder cancer radiotherapy (RT). The clinical target volume (CTV) is therefore frequently inadequately treated and large isotropic margins are inappropriate in terms of dose to organs at risk (OAR); thereby making adaptive radiotherapy (ART) attractive for this tumour site. There are various methods of ART delivery, however, for bladder cancer, plan libraries are frequently used. A review of published studies on plan libraries for bladder cancer using four databases (Pubmed, Science Direct, Embase and Cochrane Library) was conducted. The endpoints selected were accuracy and feasibility of initiation of a plan library strategy into a RT department. Twenty-four articles were included in this review. The majority of studies reported improvement in accuracy with 10 studies showing an improvement in planning target volume (PTV) and CTV coverage with plan libraries, some by up to 24%. Seventeen studies showed a dose reduction to OARs, particularly the small bowel V45Gy, V40Gy, V30Gy and V10Gy, and the rectal V30Gy. However, the occurrence of no suitable plan was reported in six studies, with three studies showing no significant difference between adaptive and non-adaptive strategies in terms of target coverage. In addition, inter-observer variability in plan selection appears to remain problematic. The additional resources, education and technology required for the initiation of plan library selection for bladder cancer may hinder its routine clinical implementation, with eight studies illustrating increased treatment time required. While there is a growing body of evidence in support of plan libraries for bladder RT, many studies differed in their delivery approach. The advent of the clinical use of the MRI-linear accelerator will provide RT departments with the opportunity to consider daily online adaption for bladder cancer as an alternate to plan library approaches.

  19. Review and Analysis of the Colombian Foreign Language Bilingualism Policies and Plans

    Science.gov (United States)

    Gómez Sará, Mary Mily

    2017-01-01

    This article reviews the background of the foreign language bilingualism in Colombia, as well as the Colombian bilingualism plans and the policy launched between 2004 and 2016. Then, these plans and policy are analyzed taking into account the most common criticisms from the academic community. In this sense, aspects such as the lack of continuity,…

  20. Standard review plan for applications for sealed source and device evaluations and registrations

    International Nuclear Information System (INIS)

    1996-11-01

    The purpose of this document is to provide the reviewer of a request for a sealed source or device safety evaluation with the information and materials necessary to make a determination that the product is acceptable for licensing purposes. It provides the reviewer with a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, certain administrative procedures to be followed, and information on how to perform the evaluation and write the registration certificate. Standard review plans are prepared for the guidance of the Office of Nuclear Material Safety and Safeguards staff responsible for the review of a sealed source or device application. This document is made available to the public as part of the Commission's policy to inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required

  1. Standard review plan for applications for sealed source and device evaluations and registrations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    The purpose of this document is to provide the reviewer of a request for a sealed source or device safety evaluation with the information and materials necessary to make a determination that the product is acceptable for licensing purposes. It provides the reviewer with a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, certain administrative procedures to be followed, and information on how to perform the evaluation and write the registration certificate. Standard review plans are prepared for the guidance of the Office of Nuclear Material Safety and Safeguards staff responsible for the review of a sealed source or device application. This document is made available to the public as part of the Commission`s policy to inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission`s regulations and compliance with them is not required.

  2. Physical fitness training reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

    International Nuclear Information System (INIS)

    Arzino, P.A.; Caplan, C.S.; Goold, R.E.

    1991-09-01

    The recommendations contained throughout this NUREG are being provided to the Nuclear Regulatory Commission (NRC) as a reference manual which can be used by licensee management as they develop a program plan for the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The recommendations in this NUREG are similar in part to those contained within the Department of Energy (DOE) Medical and Fitness Implementation Guide which was published in March 1991. The guidelines contained in this NUREG are not requirements, and compliance is not required. 25 refs

  3. Physical fitness training reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Arzino, P.A.; Caplan, C.S.; Goold, R.E. (California State Univ., Hayward, CA (United States). Foundation)

    1991-09-01

    The recommendations contained throughout this NUREG are being provided to the Nuclear Regulatory Commission (NRC) as a reference manual which can be used by licensee management as they develop a program plan for the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The recommendations in this NUREG are similar in part to those contained within the Department of Energy (DOE) Medical and Fitness Implementation Guide which was published in March 1991. The guidelines contained in this NUREG are not requirements, and compliance is not required. 25 refs.

  4. Ongoing development of digital radiotherapy plan review tools

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  5. 78 FR 48159 - Preliminary 2012 Effluent Guidelines Program Plan and 2011 Annual Effluent Guidelines Review Report

    Science.gov (United States)

    2013-08-07

    ... publish a preliminary plan in the odd numbered years and a final plan in the even numbered years. The... necessary before concluding the review of the three remaining point source categories: Pulp, Paper and... standards for the 2012 reviews. These methodologies included: Identifying pass-through pollutants in sewage...

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

    International Nuclear Information System (INIS)

    1994-10-01

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

  7. Predicting actual weight loss: A review of the determinants according to the theory of planned behaviour.

    Science.gov (United States)

    Chung, Louisa Ming Yan; Fong, Shirley Siu Ming

    2015-01-01

    Weight reduction that corresponds with lifestyle modification is difficult to foster. The theory of planned behaviour has been actively cited in explaining health-related behaviour. This review evaluated the application of the theory of planned behaviour to weight-loss behaviour. Among the three reviewed papers, cross-sectional survey designs and subjective outcome measurements were commonly applied. All of the studies recruited obese female adults as participants, limiting the generalisability of the studies' findings. The theory of planned behaviour can be effectively applied in weight-reduction programmes targeting female obese patients. This review confirmed critiques citing the limitations of experimental studies, the subjective measurement of behaviour and short follow-up periods.

  8. Systematic Reviews of Mechanisms for Financing Family Planning: Findings, Implications, and Future Agenda.

    Science.gov (United States)

    Lissner, Craig L; Ali, Moazzam

    2016-12-01

    The article describes an international collaboration that systematically reviewed the evidence on financing mechanisms for family planning/contraception, assessed the strength of and summarized the evidence, identified research gaps, and proposed a new research agenda to address the gaps. The review found that the evidence base is weak owing to the paucity of studies, diversity in findings, and variations in intervention, study design, and outcome measures. Of more than 17,000 papers reviewed only 38 met the eligibility criteria. A number of general recommendations on the directions and areas of future research can be drawn. There is a strong need for more robust study designs on the effectiveness of financial incentives in family planning. © 2016 The Population Council, Inc.

  9. Standard Review Plan for a petition for rulemaking on radioactive waste streams below regulatory concern: Expedited review in accordance with Appendix B to 10 CFR, Part 2

    International Nuclear Information System (INIS)

    Larkins, P.M.

    1989-10-01

    The Standard Review Plan (SRP) provides guidance to staff reviewers acting on rulemaking petitions in an expeditious manner to exempt from regulation radioactive waste determined to be Below Regulatory Concern (BRC), as called for in the Low-Level Radioactive Waste Policy Amendments Act of 1985. The review plan is designed to ensure the quality and uniformity of staff reviews and to present a well-defined basis for the staff's evaluation of BRC petitions. The plan serves to improve the understanding of the staff's review by interested members of the public and the industry. It also provides information about the BRC rulemaking process to a wider audience. 6 refs., 7 figs

  10. The Olympic and Paralympic Games 2012: literature review of the logistical planning and operational challenges for public health.

    Science.gov (United States)

    Enock, K E; Jacobs, J

    2008-11-01

    To undertake a review of the literature relating to public health planning and interventions at previous summer Olympic and Paralympic Games and other relevant major summer sporting events or mass gatherings, with a focus on official publications and peer-reviewed articles. Literature review. A literature review was undertaken using all biomedical databases and a freetext search using Google to widen the search beyond peer-reviewed publications. Search terms used were: Olympics; Paralympics; mass gatherings; mass gathering medicine; sporting events; weather; planning; and organisation. Citations within articles were searched to identify additional references that would inform this review. This literature review concentrates on the public health aspects of population care at mass gatherings, particularly the Olympic and Paralympic Games which are set over several weeks, focusing on surveillance, prevention and health service quality. The literature identified 10 areas of public health planning: public health command centre and communication; surveillance, assessment and control; environmental health and safety; infectious disease outbreaks; implications of weather conditions; health promotion; travel information; economic assessments; public transport and reduction of asthma events; and preparing athletes for potential allergies. The following themes emerged as crucial factors for the success of any public health interventions at Olympic and Paralympic Games: detailed planning of deliverables; pre-identification of critical success factors; management of risk; detailed contingency planning; and full testing of all plans prior to the event. The 2012 Olympic Games will provide an exciting challenge for public health providers and systems. Preparation requires early detailed planning of policies, procedures and on-site health promotion events, in addition to helping to set up the surveillance and monitoring systems that will capture public health activity alongside

  11. Real-time meteorological data flow in support of TVA's radiological emergency plan

    International Nuclear Information System (INIS)

    Hunter, C.H.; Pittman, D.E.; Malo, J.E.

    1985-01-01

    The Tennessee Valley Authority (TVA) presently operates two nuclear power plants - Browns Ferry (3 units) and Sequoyah (2 units). Two additional plants are under construction. These are Watts Bar scheduled for commercial operation later this year, and Bellefonte (2 units), scheduled for operation near the end of the decade. Under regulations promulgated under 10 CFR Part 50, TVA has developed a Radiological Emergency Plan (REP) to facilitate assessment of the effects of a radiological accident at any of the operational plants. As part of the REP, TVA has developed a system for collecting, displaying, and reviewing, and disseminating real-time meteorological information collected at the nuclear plant sites. The flow of this information must be reliable and continuous so that prompt, informed decisions are possible. This system has been designed using guidance provided in applicable Nuclear Regulatory Commission (NRC) documents, most notably Supplement 1 to NUREG-0737 and Regularoty Guide (R.G.) 1.23. This paper presents a brief description of the REP meteorological support. Meteorological support for nuclear plant emergency preparedness at TVA nuclear plants has been provided for several years. The system has undergone numerous changes during this time, reflecting changes in regulatory guidance and experience gained in implementing the system through numerous drills and exercises. A brief discussion of some of this experience is also presented

  12. Disentangling self-management goal setting and action planning: A scoping review.

    Directory of Open Access Journals (Sweden)

    Stephanie Anna Lenzen

    Full Text Available The ongoing rise in the numbers of chronically ill people necessitates efforts for effective self-management. Goal setting and action planning are frequently used, as they are thought to support patients in changing their behavior. However, it remains unclear how goal setting and action planning in the context of self-management are defined in the scientific literature. This study aimed to achieve a better understanding of the various definitions used.A scoping review was conducted, searching PubMed, Cinahl, PsychINFO and Cochrane. Inclusion and exclusion criteria were formulated to ensure the focus on goal setting/action planning and self-management. The literature was updated to December 2015; data selection and charting was done by two reviewers. A qualitative content analysis approach was used.Out of 9115 retrieved articles, 58 met the inclusion criteria. We created an overview of goal setting phases that were applied (preparation, formulation of goals, formulation of action plan, coping planning and follow-up. Although the phases we found are in accordance with commonly known frameworks for goal setting, it was striking that the majority of studies (n = 39, 67% did not include all phases. We also prepared an overview of components and strategies for each goal setting phase. Interestingly, few strategies were found for the communication between patients and professionals about goals/action plans. Most studies (n = 35, 60% focused goal setting on one single disease and on a predefined lifestyle behavior; nearly half of the articles (n = 27, 47% reported a theoretical framework.The results might provide practical support for developers of interventions. Moreover, our results might encourage professionals to become more aware of the phases of the goal setting process and of strategies emphasizing on patient reflection. However, more research might be useful to examine strategies to facilitate communication about goals/action plans. It might

  13. 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

  14. Multicriteria Decisions in Urban Energy System Planning: A Review

    Energy Technology Data Exchange (ETDEWEB)

    Cajot, Sébastien, E-mail: sebastien.cajot@alumni.epfl.ch [European Institute for Energy Research, Karlsruhe (Germany); Industrial Process and Energy Systems Engineering Group, École Polytechnique Fédérale de Lausanne, Lausanne (Switzerland); Mirakyan, Atom [Energy Economics and Planning Department, Lahmeyer International, Bad Vilbel (Germany); Koch, Andreas [European Institute for Energy Research, Karlsruhe (Germany); Maréchal, François [Industrial Process and Energy Systems Engineering Group, École Polytechnique Fédérale de Lausanne, Lausanne (Switzerland)

    2017-05-30

    Urban energy system planning (UESP) is a topic of growing concern for cities in deregulated energy markets, which plan to decrease energy demand, reduce their dependency on fossil fuels, and increase the share of renewable energy sources. UESP being a highly multisectoral and multi-actor task, multicriteria decision analysis (MCDA) methods are frequently used in the decision processes. These methods may provide support in organizing and identifying solutions to problems with conflicting objectives. However, knowing which method to use is generally not straightforward, as the appropriateness of a method or combination of methods depends on the decision problem’s context. Therefore, this article reviewed scientific papers to characterize and analyze MCDA problems and methods in the context of UESP. The review systematically explores issues such as the scope of the problems, the alternatives and criteria considered, the expected decision outcomes, the decision analysis methods and the rationales for selecting and combining them, and the role of values in driving the decision problems. The final outcome is a synthesis of the data and insights obtained, which may help potential users identify appropriate decision analysis methods based on given problem characteristics.

  15. Multicriteria Decisions in Urban Energy System Planning: A Review

    International Nuclear Information System (INIS)

    Cajot, Sébastien; Mirakyan, Atom; Koch, Andreas; Maréchal, François

    2017-01-01

    Urban energy system planning (UESP) is a topic of growing concern for cities in deregulated energy markets, which plan to decrease energy demand, reduce their dependency on fossil fuels, and increase the share of renewable energy sources. UESP being a highly multisectoral and multi-actor task, multicriteria decision analysis (MCDA) methods are frequently used in the decision processes. These methods may provide support in organizing and identifying solutions to problems with conflicting objectives. However, knowing which method to use is generally not straightforward, as the appropriateness of a method or combination of methods depends on the decision problem’s context. Therefore, this article reviewed scientific papers to characterize and analyze MCDA problems and methods in the context of UESP. The review systematically explores issues such as the scope of the problems, the alternatives and criteria considered, the expected decision outcomes, the decision analysis methods and the rationales for selecting and combining them, and the role of values in driving the decision problems. The final outcome is a synthesis of the data and insights obtained, which may help potential users identify appropriate decision analysis methods based on given problem characteristics.

  16. Records needed for orthodontic diagnosis and treatment planning: a systematic review.

    Directory of Open Access Journals (Sweden)

    Robine J Rischen

    Full Text Available BACKGROUND: Traditionally, dental models, facial and intra-oral photographs and a set of two-dimensional radiographs are used for orthodontic diagnosis and treatment planning. As evidence is lacking, the discussion is ongoing which specific records are needed for the process of making an orthodontic treatment plan. OBJECTIVE: To estimate the contribution and importance of different diagnostic records for making an orthodontic diagnosis and treatment plan. DATA SOURCES: An electronic search in PubMed (1948-July 2012, EMBASE Excerpta Medica (1980-July 2012, CINAHL (1982-July 2012, Web of Science (1945-July 2012, Scopus (1996-July 2012, and Cochrane Library (1993-July 2012 was performed. Additionally, a hand search of the reference lists of included studies was performed to identify potentially eligible studies. There was no language restriction. STUDY SELECTION: The patient, intervention, comparator, outcome (pico question formulated for this study was as follows: for patients who need orthodontic treatment (P, will the use of record set X (I compared with record set Y (C change the treatment plan (O? Only primary publications were included. DATA EXTRACTION: Independent extraction of data and quality assessment was performed by two observers. RESULTS: Of the 1041 publications retrieved, 17 met the inclusion criteria. Of these, 4 studies were of high quality. Because of the limited number of high quality studies and the differences in study designs, patient characteristics, and reference standard or index test, a meta-analysis was not possible. CONCLUSION: Cephalograms are not routinely needed for orthodontic treatment planning in Class II malocclusions, digital models can be used to replace plaster casts, and cone-beam computed tomography radiographs can be indicated for impacted canines. Based on the findings of this review, the minimum record set required for orthodontic diagnosis and treatment planning could not be defined. SYSTEMATIC REVIEW

  17. Potential human factors deficiencies in the design of local control stations and operator interfaces in nuclear power plants

    International Nuclear Information System (INIS)

    Hartley, C.S.; Levy, I.S.; Fecht, B.A.

    1984-04-01

    The Pacific Northwest Laboratory has completed a project to identify human factors deficiencies in safety-significant control stations outside the control room of a nuclear power plant and to determine whether NUREG-0700, Guidelines for Control Room Design Reviews, would be sufficient for reviewing those local control stations (LCSs). The project accomplished this task by first, reviewing existing data pertaining to human factors deficiencies in LCSs involved in significant safety actions; second, surveying LCSs environments and design features at several operating nuclear power plants; and third, assessing the results of that survey relative to the contents of NUREG-0700

  18. Identification of advanced human factors engineering analysis, design and evaluation methods

    International Nuclear Information System (INIS)

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

    2006-01-01

    NUREG-0711 Rev.2, 'Human Factors Engineering Program Review Model,' provides comprehensive guidance to the Nuclear Regulatory Commission (NRC) in assessing the human factors practices employed by license applicants for Nuclear Power Plant control room designs. As software based human-system interface (HSI) technologies supplant traditional hardware-based technologies, the NRC may encounter new HSI technologies or seemingly unconventional approaches to human factors design, analysis, and evaluation methods which NUREG-0711 does not anticipate. A comprehensive survey was performed to identify advanced human factors engineering analysis, design and evaluation methods, tools, and technologies that the NRC may encounter in near term future licensee applications. A review was conducted to identify human factors methods, tools, and technologies relevant to each review element of NUREG-0711. Additionally emerging trends in technology which have the potential to impact review elements, such as Augmented Cognition, and various wireless tools and technologies were identified. The purpose of this paper is to provide an overview of the survey results and to highlight issues that could be revised or adapted to meet with emerging trends. (authors)

  19. NRC antitrust licensing actions, 1978--1996

    International Nuclear Information System (INIS)

    Mayer, S.J.; Simpson, J.J.

    1997-09-01

    NUREG-0447, Antitrust Review of Nuclear Power Plants, was published in May 1978 and includes a compilation and discussion of U.S. Nuclear Regulatory Commission (NRC) proceedings and activity involving the NRC's competitive review program through February 1978, NUREG-0447 is an update of an earlier discussion of the NRC's antitrust review of nuclear power plants, NR-AIG-001, The US Nuclear Regulatory Commission's Antitrust Review of Nuclear Power Plants: The Conditioning of Licenses, which reviewed the Commission's antitrust review function from its inception in December 1970 through April 1976. This report summarizes the support provided to NRC staff in updating the compilation of the NRC's antitrust licensing review activities for commercial nuclear power plants that have occurred since February 1978. 4 refs., 4 tabs

  20. Standard Review Plan for the review of safety analysis reports for nuclear power plants, Revision No. 7 to Section 9

    International Nuclear Information System (INIS)

    1978-03-01

    Revision No. 1 to Section 9 of the Standard Review Plan incorporates changes that have been developed since the original issuance in September 1975, many of which are editorial in nature, to reflect current staff practice in the review of safety analysis reports for nuclear power plants

  1. Disaster Planning Guidelines for Fire Chiefs.

    Science.gov (United States)

    1980-07-01

    book Money Receipts e I pad white squared paper * I roll masking tape (8 X 13) (-" × 60yds) * 3 spring clips * 3 felt tip markers (red, e I pkg. freezer...Avenue COMMIT EE HaRm Washington. D.C. 20012 C.Holy Redeemer Rectory (202) 723-0800 C. Neil Molenaar 9705 Summit Avenue Director, Domestic Programs

  2. Regulatory guidance for license renewal

    International Nuclear Information System (INIS)

    Thoma, John A.

    1991-01-01

    The proposed 10 CFR Part 54 rule proceduralizes the process for license renewal by identifying both the administrative and technical requirements for a renewal application. To amplify and support this regulation, written guidance has been provided in the form of a draft Regulatory Guide (DG 1009) and a draft Standard Review Plan for License Renewal (NUREG 1299). This guidance is scheduled to be finalized in 1992. Similar guidance will be provided for the proposed revisions to 10 CFR Part 51 concerning the environmental aspects of license renewal. (author)

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

    International Nuclear Information System (INIS)

    1988-01-01

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

  4. Community Education for Family Planning in the U.S.: A Systematic Review.

    Science.gov (United States)

    Carter, Marion W; Tregear, Michelle L; Moskosky, Susan B

    2015-08-01

    Community education may involve activities that seek to raise awareness and promote behavior change, using mass media, social media, and other media or interpersonal methods in community settings. This systematic review evaluated the evidence of the effects of community education on select short- and medium-term family planning outcomes. Using an analytic approach drawn from the U.S. Preventive Services Task Force, multiple databases were searched for articles published from January 1985 through February 2011 describing studies of community education related to family planning in the U.S. Included articles were reviewed and assessed for potential bias using a standardized process in 2011. An updated, targeted review for the 2011-2014 period was conducted in early 2015. Seventeen papers were identified. Most (nine) related to mass media interventions; three involved targeted print media, two involved text messaging or e-mail, two described outcome workers conducting community education, and one involved community theater. Study designs, strength of evidence, and levels of possible bias varied widely. Twelve of 15 studies that addressed outcomes such as increased awareness found positive associations with those outcomes, with six also reporting null findings. Seven of eight studies that addressed use of services reported positive associations, with two also reporting null findings. The targeted, additional review identified two other studies. Evidence related to community education for family planning purposes is limited and highly variable. As goals of community education are usually limited to shorter-term outcomes, the evidence suggests that a range of approaches may be effective. Published by Elsevier Inc.

  5. Knee mechanics during planned and unplanned sidestepping: a systematic review and meta-analysis.

    Science.gov (United States)

    Brown, Scott R; Brughelli, Matt; Hume, Patria A

    2014-11-01

    Knee joint mechanics during sidestepping are associated with anterior cruciate ligament injury. Unplanned sidestepping more closely emulates game scenarios when compared with planned sidestepping by limiting decision time, increasing knee loading and challenging the integrity of soft-tissue structures in the knee. It is important to quantify the loads that may challenge the integrity of the knee during planned and unplanned sidestepping. Our objective was to review literature on knee mechanics during planned and unplanned phases of sidestepping. PubMed, CINAHL, MEDLINE (EBSCO), SPORTDiscus and Web of Science were searched using the terms knee mechanics OR knee kine*, AND plan*, unplan*, anticipat*, unanticipat*, side*, cut* or chang*. A systematic approach was used to evaluate 4,629 records. Records were excluded when not available in English, only available in abstract of conference proceedings, not involving a change-of-direction sidestep, not comparing planned and unplanned or maintaining a running velocity greater than 2 m s(−1). Included studies were evaluated independently by two authors using a custom-designed methodological quality assessment derived from the Physiotherapy Evidence Database (PEDro) scale and then confirmed by a third author. Only six studies met the inclusion criteria and were retained for meta-analysis. Magnitude-based inferences were used to assess the standardised effect of the differences between planned and unplanned sidestepping. Knee angles and knee moments were extracted and reported for flexion/extension, abduction/adduction and internal/external rotation for initial contact, weight acceptance, peak push-off and final push-off phases of sidestepping. For kinematic variables, unplanned sidestepping produced a wide range of small to large increases in knee extension angles, small and moderate increases in knee abduction angles and a small increase in internal rotation angle relative to planned sidestepping during the sidestepping

  6. Review of the Shearon Harris Unit 1 auxiliary feedwater system reliability analysis

    International Nuclear Information System (INIS)

    Fresco, A.; Youngblood, R.; Papazoglou, I.A.

    1986-02-01

    This report presents the results of a review of the Auxiliary Feedwater System Reliability Analysis for the Shearon Harris Nuclear Power Plant (SHNPP) Unit 1. The objective of this report is to estimate the probability that the Auxiliary Feedwater System will fail to perform its mission for each of three different initiators: (1) loss of main feedwater with offsite power available, (2) loss of offsite power, (3) loss of all ac power except vital instrumentation and control 125-V dc/120-V ac power. The scope, methodology, and failure data are prescribed by NUREG-0611 for other Westinghouse plants

  7. Reviewing the impact of advanced control room technology

    International Nuclear Information System (INIS)

    Wilhelmsen, C.A.; Gertman, D.I.; Ostrom, L.T.; Nelson, W.R.; Galyean, W.J.; Byers, J.C.

    1992-01-01

    Progress to date on assessing the nature of the expected changes in human performance and risk associated with the introduction of digital control, instrumentation, and display systems is presented. Expected changes include the shift toward more supervisory tasks, development of intervention strategies, and reallocation of function between human and machine. Results are reported in terms of the scope of new technology, human performance issues, and crews experience with digital control systems in a variety of industries petrochemical and aerospace. Plans to conduct a limited Probabilistic Risk Assessment/Human Reliability Assessment (PRA/HRA) comparison between a conventional NUREG-1150 series plant and that same plant retrofit with distributed control and advanced instrumentation and display are also presented. Changes needed to supplement existing HRA modeling methods and quantification techniques are discussed

  8. Review Pages: Planning For Smart Cities. Dealing With New Urban Challenges

    Directory of Open Access Journals (Sweden)

    Gennaro Angiello

    2014-12-01

    Full Text Available Starting from the relationship between urban planning and mobility management, TeMA has gradually expanded the view of the covered topics, always remaining in the groove of rigorous scientific in-depth analysis. During the last two years a particular attention has been paid on the Smart Cities theme and on the different meanings that come with it. The last section of the journal is formed by the Review Pages. They have different aims: to inform on the problems, trends and evolutionary processes; to investigate on the paths by highlighting the advanced relationships among apparently distant disciplinary fields; to explore the interaction’s areas, experiences and potential applications; to underline interactions, disciplinary developments but also, if present, defeats and setbacks. Inside the journal the Review Pages have the task of stimulating as much as possible the circulation of ideas and the discovery of new points of view. For this reason the section is founded on a series of basic’s references, required for the identification of new and more advanced interactions. These references are the research, the planning acts, the actions and the applications, analysed and investigated both for their ability to give a systematic response to questions concerning the urban and territorial planning, and for their attention to aspects such as the environmental sustainability and the innovation in the practices. For this purpose the Review Pages are formed by five sections (Web Resources; Books; Laws; Urban Practices; News and Events, each of which examines a specific aspect of the broader information storage of interest for TeMA.

  9. Evaluation and review of planning for greater-confinement disposal by the Independent Peer Review Committee, July 9-10, 1985. Final report

    International Nuclear Information System (INIS)

    1985-07-01

    This evaluation and review was performed under contract by Argonne National Laboratory in support of their role for developing the ''Planning for Greater Confinement Disposal'' Document for the Low-Level Waste Management Program Office for the Department of Energy, Office of Defense Waste and Byproducts Management. The Independent Peer Review Committee was composed of 13 well-qualified and recognized experts in their fields and pertinent disciplines, collectively representing considerable expertise and experience in waste disposal operations, waste management, environmental assessment and impact analysis, and other aspects of radioactive waste disposal. The members of the Peer Review Committee, their organizations, and thier area of expertise are given in Appendix 1. The general consensus of the Independent Review Committee was that the ''Planning for Greater-Confinement Disposal'' document was reasonably comprehensive, covering nearly all topics necessary to provide a good planning guide. There is, however, a definite need to reorganize the document into two volumes with appendices and the relationship of the GCD document to other LLWMP documents needs to be clarified in the introductory volume. Specific recommendations made by the committee on the DCD document are given in Section 3.2. Recommendations by the committee that have a somewhat broader scope than just the GCD document are given in Section 3.3

  10. Standard review plan for dry cask storage systems. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    The Standard Review Plan (SRP) For Dry Cask Storage Systems provides guidance to the Nuclear Regulatory Commission staff in the Spent Fuel Project Office for performing safety reviews of dry cask storage systems. The SRP is intended to ensure the quality and uniformity of the staff reviews, present a basis for the review scope, and clarification of the regulatory requirements. Part 72, Subpart B generally specifies the information needed in a license application for the independent storage of spent nuclear fuel and high level radioactive waste. Regulatory Guide 3.61 {open_quotes}Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Storage Cask{close_quotes} contains an outline of the specific information required by the staff. The SRP is divided into 14 sections which reflect the standard application format. Regulatory requirements, staff positions, industry codes and standards, acceptance criteria, and other information are discussed.

  11. Standard review plan for dry cask storage systems. Final report

    International Nuclear Information System (INIS)

    1997-01-01

    The Standard Review Plan (SRP) For Dry Cask Storage Systems provides guidance to the Nuclear Regulatory Commission staff in the Spent Fuel Project Office for performing safety reviews of dry cask storage systems. The SRP is intended to ensure the quality and uniformity of the staff reviews, present a basis for the review scope, and clarification of the regulatory requirements. Part 72, Subpart B generally specifies the information needed in a license application for the independent storage of spent nuclear fuel and high level radioactive waste. Regulatory Guide 3.61 open-quotes Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Storage Caskclose quotes contains an outline of the specific information required by the staff. The SRP is divided into 14 sections which reflect the standard application format. Regulatory requirements, staff positions, industry codes and standards, acceptance criteria, and other information are discussed

  12. 2013 Nutrition Risk Research Plan Review Final Report. Research Plan Review for: The Risk Factor of Inadequate Nutrition

    Science.gov (United States)

    2014-01-01

    The 2013 Nutrition Risk Standing Review Panel (from here on referred to as the SRP) was impressed by the degree of progress the nutrition discipline has made with the research plan presented since the 2012 Nutrition Risk SRP WebEx/teleconference. The scientists and staff associated with the nutrition discipline have, in addition, continued their impressive publication track record. Specifically the SRP found that the novel and important progress in the ocular health research area (Gap N7.3) represents an important advance in understanding the etiology and potential countermeasures for this condition and thinks that the work will not only be valuable for vision, but may have implications for cardiovascular health, as well. The SRP also considered the bone countermeasure data presented a potentially valuable tool for investigating bone metabolism under the unique conditions of space travel, specifically the innovation of variable use of stable Ca isotopes for bone synthesis and equal contribution for bone to investigate bone metabolism, as well as, the impact of the advanced resistive exercise device (ARED) on body composition during spaceflight. Finally, the SRP considers the planned Integrated Nutrition task to be an important and necessary strategic part of the research plan. The SRP is concerned that the risks observed in previous research on Low Earth Orbit (LEO) may not capture all the risks of longer duration flight beyond LEO. In particular, the SRP believes that there may be a much greater likelihood of an intensified chronic inflammatory response compared to the very minimal evidence seen to date and that modest effects seen in LEO, such as the reduction in appetite, may not predict an absence in longer duration flight out of LEO. The added complications of longer duration flight, greater bio-behavioral stress, radiation exposure, poorer communication, and inability to respond to unforeseen exigencies may create different risks. Thus, preparation for

  13. Predicting actual weight loss: A review of the determinants according to the theory of planned behaviour

    OpenAIRE

    Chung, Louisa Ming Yan; Fong, Shirley Siu Ming

    2015-01-01

    Weight reduction that corresponds with lifestyle modification is difficult to foster. The theory of planned behaviour has been actively cited in explaining health-related behaviour. This review evaluated the application of the theory of planned behaviour to weight-loss behaviour. Among the three reviewed papers, cross-sectional survey designs and subjective outcome measurements were commonly applied. All of the studies recruited obese female adults as participants, limiting the generalisabili...

  14. Information for consideration in reviewing groundwater protection plans for uranium mill tailings sites

    International Nuclear Information System (INIS)

    Thorne, P.D.

    1992-05-01

    Guidelines and acceptance criteria were developed for reviewing certain aspects of groundwater protection plans for uranium mill tailing sites. The aspects covered include: (1) leaching and long-term releases of hazardous and radioactive constituents from tailings and other contaminated materials, (2) attenuation of hazardous and radioactive constituents in groundwater under saturated and unsaturated conditions, (3) design and implementation of groundwater monitoring programs, (4) design and construction of groundwater protection barriers, and (5) efficiency and effectiveness of groundwater cleanup programs. The objective of these guidelines is to assist the US Nuclear Regulatory Commission staff in reviewing Remedial Action Plans for inactive waste sites and licensing application documents for active commercial uranium and thorium mills

  15. Review and evaluation of TDI diesel generator owner's group program plan

    International Nuclear Information System (INIS)

    1984-06-01

    This report documents a review, performed by the Pacific Northwest Laboratory (PNL), of the Transamerica Delaval, Inc. (TDI) Diesel Generator Owner's Group Program Plan. This report was prepared as part of the technical support PNL is providing to the US Nuclear Regulatory Commission (NRC), Division of Licensing, on matters pertaining to the reliability of TDI diesel generators as emergency power sources for safety-related nuclear systems. The report presents the comments and conclusions reached by PNL, with the advice and counsel of five diesel engine consultants, on the principal elements of the Owners' Group Plan: Generic Problem Resolution, Design Review/Quality Revalidation, and Engine Testing and Inspection. Also included are PNL's comments on the related issues of Surveillance and Maintenance, and Administrative Controls. The conclusions drawn from PNL's evaluation of these issues form the basis for two additional topics addressed in the report: Critical Elements Required to Establish Diesel Engine Operability and Reliability, and Considerations for Interim Licensing

  16. Transfer to hospital in planned home births: a systematic review.

    Science.gov (United States)

    Blix, Ellen; Kumle, Merethe; Kjærgaard, Hanne; Øian, Pål; Lindgren, Helena E

    2014-05-29

    There is concern about the safety of homebirths, especially in women transferred to hospital during or after labour. The scope of transfer in planned home births has not been assessed in a systematic review. This review aimed to describe the proportions and indications for transfer from home to hospital during or after labour in planned home births. The databases Pubmed, Embase, Cinahl, Svemed+, and the Cochrane Library were searched using the MeSH term "home childbirth". Inclusion criteria were as follows: the study population was women who chose planned home birth at the onset of labour; the studies were from Western countries; the birth attendant was an authorised midwife or medical doctor; the studies were published in 1985 or later, with data not older than from 1980; and data on transfer from home to hospital were described. Of the 3366 titles identified, 83 full text articles were screened, and 15 met the inclusion criteria. Two of the authors independently extracted the data. Because of the heterogeneity and lack of robustness across the studies, there were considerable risks for bias if performing meta-analyses. A descriptive presentation of the findings was chosen. Fifteen studies were eligible for inclusion, containing data from 215,257 women. The total proportion of transfer from home to hospital varied from 9.9% to 31.9% across the studies. The most common indication for transfer was labour dystocia, occurring in 5.1% to 9.8% of all women planning for home births. Transfer for indication for foetal distress varied from 1.0% to 3.6%, postpartum haemorrhage from 0% to 0.2% and respiratory problems in the infant from 0.3% to 1.4%. The proportion of emergency transfers varied from 0% to 5.4%. Future studies should report indications for transfer from home to hospital and provide clear definitions of emergency transfers.

  17. A comparative review of radiation-induced cancer risk models

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Hee; Kim, Ju Youl [FNC Technology Co., Ltd., Yongin (Korea, Republic of); Han, Seok Jung [Risk and Environmental Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2017-06-15

    With the need for a domestic level 3 probabilistic safety assessment (PSA), it is essential to develop a Korea-specific code. Health effect assessments study radiation-induced impacts; in particular, long-term health effects are evaluated in terms of cancer risk. The objective of this study was to analyze the latest cancer risk models developed by foreign organizations and to compare the methodology of how they were developed. This paper also provides suggestions regarding the development of Korean cancer risk models. A review of cancer risk models was carried out targeting the latest models: the NUREG model (1993), the BEIR VII model (2006), the UNSCEAR model (2006), the ICRP 103 model (2007), and the U.S. EPA model (2011). The methodology of how each model was developed is explained, and the cancer sites, dose and dose rate effectiveness factor (DDREF) and mathematical models are also described in the sections presenting differences among the models. The NUREG model was developed by assuming that the risk was proportional to the risk coefficient and dose, while the BEIR VII, UNSCEAR, ICRP, and U.S. EPA models were derived from epidemiological data, principally from Japanese atomic bomb survivors. The risk coefficient does not consider individual characteristics, as the values were calculated in terms of population-averaged cancer risk per unit dose. However, the models derived by epidemiological data are a function of sex, exposure age, and attained age of the exposed individual. Moreover, the methodologies can be used to apply the latest epidemiological data. Therefore, methodologies using epidemiological data should be considered first for developing a Korean cancer risk model, and the cancer sites and DDREF should also be determined based on Korea-specific studies. This review can be used as a basis for developing a Korean cancer risk model in the future.

  18. NRC antitrust licensing actions, 1978--1996

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, S.J.; Simpson, J.J.

    1997-09-01

    NUREG-0447, Antitrust Review of Nuclear Power Plants, was published in May 1978 and includes a compilation and discussion of U.S. Nuclear Regulatory Commission (NRC) proceedings and activity involving the NRC`s competitive review program through February 1978, NUREG-0447 is an update of an earlier discussion of the NRC`s antitrust review of nuclear power plants, NR-AIG-001, The US Nuclear Regulatory Commission`s Antitrust Review of Nuclear Power Plants: The Conditioning of Licenses, which reviewed the Commission`s antitrust review function from its inception in December 1970 through April 1976. This report summarizes the support provided to NRC staff in updating the compilation of the NRC`s antitrust licensing review activities for commercial nuclear power plants that have occurred since February 1978. 4 refs., 4 tabs.

  19. Advance care planning within survivorship care plans for older cancer survivors: A systematic review.

    Science.gov (United States)

    O'Caoimh, Rónán; Cornally, Nicola; O'Sullivan, Ronan; Hally, Ruth; Weathers, Elizabeth; Lavan, Amanda H; Kearns, Tara; Coffey, Alice; McGlade, Ciara; Molloy, D William

    2017-11-01

    Advances in the medical treatment of cancer have increased the number of survivors, particularly among older adults, who now represent the majority of these. Survivorship care plans (SCPs) are documents that cancer patients receive summarising their care, usually at the end of treatment but preferably from initial diagnosis. These may increase patient satisfaction and represent an opportunity to initiate preventative strategies and address future care needs. Advance care planning (ACP), incorporating advance healthcare decision-making, including formal written directives, increases satisfaction and end-of-life care. This paper systematically reviews evaluations of ACP within SCPs among older (≥65 years) cancer survivors. No studies meeting the inclusion criteria were identified by search strategies conducted in PubMed/MEDLINE and the Cochrane databases. One paper examined cancer survivors' mainly positive views of ACP. Another discussed the use of a SCP supported by a 'distress inventory' that included an advance care directive (living will) as an issue, though no formal evaluation was reported. Although ACP is important for older adults, no study was found that evaluated its role within survivorship care planning. Despite the risk of recurrence and the potential for morbidity and mortality, especially among older cancer survivors, ACP is not yet a feature of SCPs. Copyright © 2017 Elsevier B.V. All rights reserved.

  20. Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

  1. Medical Signbank as a Model for Sign Language Planning? A Review of Community Engagement

    Science.gov (United States)

    Napier, Jemina; Major, George; Ferrara, Lindsay; Johnston, Trevor

    2015-01-01

    This paper reviews a sign language planning project conducted in Australia with deaf Auslan users. The Medical Signbank project utilised a cooperative language planning process to engage with the Deaf community and sign language interpreters to develop an online interactive resource of health-related signs, in order to address a gap in the health…

  2. Regional Transmission Planning: A review of practices following FERC Order Nos. 890 and 1000

    Energy Technology Data Exchange (ETDEWEB)

    Eto, Joseph H. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Gallo, Guilia [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2017-11-15

    Federal Energy Regulatory Commission (FERC) Order Nos. 890 and 10001 established requirements that transmission planning regions must follow in regional transmission planning and allocating the costs of new transmission facilities. Order No. 890, issued in 2007, outlined general requirements for local as well as regional transmission planning practices and procedures. Order No. 1000, issued in 2011, laid out specific requirements for: (1) regional transmission planning; (2) consideration of transmission needs driven by public policy requirements; (3) non-incumbent transmission development; (4) interregional transmission coordination; and (5) cost allocation for transmission facilities that have been selected in a regional transmission plan for purposes of cost allocation. This report reviews how these FERC orders are being implemented by the 12 transmission planning regions recognized by FERC.

  3. Review, reaction, and projection: the role of the CFO in planning.

    Science.gov (United States)

    Nauert, R C

    1985-08-01

    In recent years, CFOs have become an integral part of the healthcare organization's strategic planning process. Although not the leader in the process, CFOs should assume a role of review, reaction, and projection. Furthermore, they should oppose any venture that would weaken the financial strength of the institution--whether or not they support the venture on social grounds. The CFO's responsibility in planning is to improve the financial strength of the organization, using support documentation, thorough preparation, and logic. The CEO's concern for community needs and desire to pursue a new business should be tempered by the CFO's financial and economic judgment.

  4. Standard Review Plan for the review of financial assurance mechanisms for decommissioning under 10 CFR Parts 30, 40, 70, and 72

    International Nuclear Information System (INIS)

    1989-08-01

    Standard Review Plan (SRP) for the Review of Financial Assurance Mechanisms for Decommissioning under 10 CFR Parts 30, 40, 70 and 72, is prepared for the guidance of Nuclear Regulatory Commission staff reviewers in performing reviews of applications from material licensees affected by the decommissioning regulations established June 27, 1988 (53FR24018). The principal purpose of the SRP is to assure the quality and uniformity of staff reviews and to present a base from which to evaluate the financial assurance aspects of the applications. The SRP identifies who performs the review, the matters that are reviewed, the basis for the review, how the review is performed, and the conclusions that are sought

  5. Economic Evaluation of Family Planning Interventions in Low and Middle Income Countries : A Systematic Review

    NARCIS (Netherlands)

    Zakiyah, Neily; van Asselt, Antoinette D. I.; Roijmans, Frank; Postma, Maarten J.

    2016-01-01

    Background A significant number of women in low and middle income countries (L-MICs) who need any family planning, experience a lack in access to modern effective methods. This study was conducted to review potential cost effectiveness of scaling up family planning interventions in these regions

  6. 77 FR 24148 - Revision to the Hawaii State Implementation Plan, Minor New Source Review Program

    Science.gov (United States)

    2012-04-23

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2012-0213; FRL-9661-6] Revision to the Hawaii State Implementation Plan, Minor New Source Review Program AGENCY: Environmental Protection Agency... final action to approve revisions to the Hawaii State Implementation Plan (SIP). These revisions would...

  7. TU-G-BRD-01: Quantifying the Effectiveness of the Physics Pre-Treatment Plan Review for Detecting Errors in Radiation Therapy

    International Nuclear Information System (INIS)

    Gopan, O; Novak, A; Zeng, J; Ford, E

    2015-01-01

    Purpose: Physics pre-treatment plan review is crucial to safe radiation oncology treatments. Studies show that most errors originate in treatment planning, which underscores the importance of physics plan review. As a QA measure the physics review is of fundamental importance and is central to the profession of medical physics. However, little is known about its effectiveness. More hard data are needed. The purpose of this study was to quantify the effectiveness of physics review with the goal of improving it. Methods: This study analyzed 315 “potentially serious” near-miss incidents within an institutional incident learning system collected over a two-year period. 139 of these originated prior to physics review and were found at the review or after. Incidents were classified as events that: 1)were detected by physics review, 2)could have been detected (but were not), and 3)could not have been detected. Category 1 and 2 events were classified by which specific check (within physics review) detected or could have detected the event. Results: Of the 139 analyzed events, 73/139 (53%) were detected or could have been detected by the physics review; although, 42/73 (58%) were not actually detected. 45/73 (62%) errors originated in treatment planning, making physics review the first step in the workflow that could detect the error. Two specific physics checks were particularly effective (combined effectiveness of >20%): verifying DRRs (8/73) and verifying isocenter (7/73). Software-based plan checking systems were evaluated and found to have potential effectiveness of 40%. Given current data structures, software implementations of some tests such as isocenter verification check would be challenging. Conclusion: Physics plan review is a key safety measure and can detect majority of reported events. However, a majority of events that potentially could have been detected were NOT detected in this study, indicating the need to improve the performance of physics review

  8. 76 FR 23630 - Office of New Reactors; Proposed Revision 2 to Standard Review Plan, Section 1.0 on Introduction...

    Science.gov (United States)

    2011-04-27

    ... Standard Review Plan, Section 1.0 on Introduction and Interfaces AGENCY: Nuclear Regulatory Commission (NRC... Revision 2 to Standard Review Plan (SRP), Section 1.0, ``Introduction and Interfaces'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110110573). The Office of New Reactors (NRO...

  9. Radioactive waste isolation in salt: peer review of the Office of Nuclear Waste Isolation's plans for repository performance assessment

    International Nuclear Information System (INIS)

    Harrison, W.

    1984-05-01

    In the peer review of the preliminary performance assessment plan, suggestions to improve the presentation are given, technical issues are addressed, a page-by-page commentary is included, and recommendations are summarized. In the peer review of the verification and validation plan, the following are addressed: suggestions to improve presentation; key activities that have been overlooked; improving the technical content of the plan; and degree to which code documents support the plan. Comments on other supporting code documents, page-by-page commentary, and summary of recommendations are included

  10. An analysis of operational experience during low power and shutdown and a plan for addressing human reliability assessment issues

    International Nuclear Information System (INIS)

    Barriere, M.; Luckas, W.; Whitehead, D.; Ramey-Smith, A.

    1994-06-01

    Recent nuclear power plant events (e.g. Chernobyl, Diablo Canyon, and Vogtle) and US Nuclear Regulatory Commission (NRC) reports (e.g. NUREG-1449) have led to concerns regarding human reliability during low power and shutdown (LP ampersand S) conditions and limitations of human reliability analysis (HRA) methodologies in adequately representing the LP ampersand S environment. As a result of these concerns, the NRC initiated two parallel research projects to assess the influence of LP ampersand S conditions on human reliability through an analysis of operational experience at pressurized water reactors (PWRs) an boiling water reactors (BWRs). These research projects, performed by Brookhaven National Laboratory for PWRS, and Sandia National Laboratories for BWRs, identified unique aspects of human performance during LP ampersand S conditions and provided a program plan for research and development necessary to improve existing HRA methodologies. This report documents the results of the analysis of LP ampersand S operating experience and describes the improved HRA program plan

  11. Review of 3D image data calibration for heterogeneity correction in proton therapy treatment planning

    International Nuclear Information System (INIS)

    Zhu, Jiahua; Penfold, Scott N.

    2016-01-01

    Correct modelling of the interaction parameters of patient tissues is of vital importance in proton therapy treatment planning because of the large dose gradients associated with the Bragg peak. Different 3D imaging techniques yield different information regarding these interaction parameters. Given the rapidly expanding interest in proton therapy, this review is written to make readers aware of the current challenges in accounting for tissue heterogeneities and the imaging systems that are proposed to tackle these challenges. A summary of the interaction parameters of interest in proton therapy and the current and developmental 3D imaging techniques used in proton therapy treatment planning is given. The different methods to translate the imaging data to the interaction parameters of interest are reviewed and a summary of the implementations in several commercial treatment planning systems is presented.

  12. Review of 3D image data calibration for heterogeneity correction in proton therapy treatment planning.

    Science.gov (United States)

    Zhu, Jiahua; Penfold, Scott N

    2016-06-01

    Correct modelling of the interaction parameters of patient tissues is of vital importance in proton therapy treatment planning because of the large dose gradients associated with the Bragg peak. Different 3D imaging techniques yield different information regarding these interaction parameters. Given the rapidly expanding interest in proton therapy, this review is written to make readers aware of the current challenges in accounting for tissue heterogeneities and the imaging systems that are proposed to tackle these challenges. A summary of the interaction parameters of interest in proton therapy and the current and developmental 3D imaging techniques used in proton therapy treatment planning is given. The different methods to translate the imaging data to the interaction parameters of interest are reviewed and a summary of the implementations in several commercial treatment planning systems is presented.

  13. 76 FR 31381 - Office Of New Reactors; Proposed Revision 4 to Standard Review Plan; Section 8.1 on Electric...

    Science.gov (United States)

    2011-05-31

    ... Standard Review Plan; Section 8.1 on Electric Power--Introduction AGENCY: U.S. Nuclear Regulatory...,'' on a proposed Revision 4 to Standard Review Plan (SRP), Section 8.1 on ``Electric Power--Introduction,'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML111180542). The previous version of...

  14. Scales, strategies and actions for effective energy planning: A review

    International Nuclear Information System (INIS)

    Pasimeni, Maria Rita; Petrosillo, Irene; Aretano, Roberta; Semeraro, Teodoro; De Marco, Antonella; Zaccarelli, Nicola; Zurlini, Giovanni

    2014-01-01

    This paper is a review of the most recent literature on the interaction between climate change, land-use and energy, based on the analysis of papers collected through the most relevant scientific literature databases. A total of 114 papers published between 2000 and 2011 were reviewed. The aims of this review are: in general (1) to identify the different research topics that have been developed related to the interaction between climate change, land-use and energy; more specifically, (2) to analyze what are the most suitable spatial and temporal scales of investigation to focus on for actions and strategies to reduce critical issues in the field of energy and environment; (3) to identify which actions and strategies are deemed as the most appropriate to mitigate critical issues in energy and environment; and given the research gaps found in the review, (4) to propose research recommendations in the context of effective climate-energy planning. We argue that there are certain gaps and needs for a “nested” environmental governance. It is necessary to understand how different environmental policies overlap and how they can be integrated in order to verify whether there are conflicting targets that may negate each other in the long term. - Highlights: • Energy production and consumption can directly or indirectly affect climate change. • Energy sector is influenced directly and indirectly by changes in climate conditions. • Energy sector and climate change affect and limit alternative uses of land, causing land-use changes. • The most suitable spatial scale for energy planning is the municipal level requiring short-term perspectives. • Several research recommendations to deal with the complexity of energy-land-use-climate change issue are proposed

  15. A Systematic Review to Uncover a Universal Protocol for Accuracy Assessment of 3-Dimensional Virtually Planned Orthognathic Surgery.

    Science.gov (United States)

    Gaber, Ramy M; Shaheen, Eman; Falter, Bart; Araya, Sebastian; Politis, Constantinus; Swennen, Gwen R J; Jacobs, Reinhilde

    2017-11-01

    The aim of this study was to systematically review methods used for assessing the accuracy of 3-dimensional virtually planned orthognathic surgery in an attempt to reach an objective assessment protocol that could be universally used. A systematic review of the currently available literature, published until September 12, 2016, was conducted using PubMed as the primary search engine. We performed secondary searches using the Cochrane Database, clinical trial registries, Google Scholar, and Embase, as well as a bibliography search. Included articles were required to have stated clearly that 3-dimensional virtual planning was used and accuracy assessment performed, along with validation of the planning and/or assessment method. Descriptive statistics and quality assessment of included articles were performed. The initial search yielded 1,461 studies. Only 7 studies were included in our review. An important variability was found regarding methods used for 1) accuracy assessment of virtually planned orthognathic surgery or 2) validation of the tools used. Included studies were of moderate quality; reviewers' agreement regarding quality was calculated to be 0.5 using the Cohen κ test. On the basis of the findings of this review, it is evident that the literature lacks consensus regarding accuracy assessment. Hence, a protocol is suggested for accuracy assessment of virtually planned orthognathic surgery with the lowest margin of error. Copyright © 2017 American Association of Oral and Maxillofacial Surgeons. Published by Elsevier Inc. All rights reserved.

  16. [Planned home versus planned hospital births: adverse outcomes comparison by reviewing the international literature].

    Science.gov (United States)

    Faucon, C; Brillac, T

    2013-06-01

    To assess the safety of planned home birth compared to hospital birth, in low-risk pregnancies. An international literature review was conducted. Mortality, adverse outcomes and medical interventions were compared. Home birth was not associated with higher mortality rates, but with lower maternal adverse outcomes. Perinatal adverse outcomes are not significantly different at home and in hospital. Medical interventions are more frequent in hospital births. Home birth attended by a well-trained midwife is not associated with increased mortality and morbidity rates, but with less medical interventions. Copyright © 2013 Elsevier Masson SAS. All rights reserved.

  17. Radiological Effluent Technical Specifications (RETS) implementation: Zion Generating Station Units 1 and 2

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.; Duce, S.W.; Mandler, J.W.; Simpson, F.B.; Young, T.E.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) of the Zion Generating Station Units 1 and 2 was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7 of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by both EG and G and the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual was reviewed and generally found to be consistent with the NRC review guidelines. 35 refs., 2 figs., 1 tab

  18. Seismic hazard review for the systematic evaluation program: a use of probability in decision making

    International Nuclear Information System (INIS)

    Reiter, L.; Jackson, R.E.

    1983-03-01

    This document presents the US Nuclear Regulatory Commission (NRC) Geosciences Branch review and recommendations with respect to earthquake ground motion considerations in the Systematic Evaluation Program (SEP) Phases I and II. It evaluates the probabilistic estimates presented in the 5-volume report entitled Seismic Hazard Analysis (NUREG/CR-1582) and compares and modifies them to take into account deterministic estimates. It presents the NRC's Geosciences Branch first approach to utilizing complex state-of-the-art probabilistic studies in an area where probabilistic criteria have not yet been set and where decisions for specific plants have been previously made in a non-probabilistic way

  19. A review of family health's latest evaluation of the demographic impact of the Louisiana Family Planning Program.

    Science.gov (United States)

    Gettys, J O; Atkins, E H; Mary, C C

    1974-03-01

    The report, "Recent Trends in Louisiana Fertility," released in January 1973 is reviewed. This report was distinguished from other Louisiana Family Planning Program evaluations of demographic impact by several features: 1) Louisiana crude birth rates are compared with those of the United States and Mississippi; 2) differences in age-specific nonwhite fertility rates in Louisiana between 1965 and 1971 are compared with corresponding differences in Mississippi; and 3) the concepts of "parity components of age-specific rates" and "excess births" are introduced into the discussion of Louisiana fertility trends. According to the reviewers, no scientific or even psudoscientific analysis of the Louisiana Family Planning Program has ever been published or made available by the Family Health Foundation to any state agency. They contend that the so-called evaluations of the demographic impact of the Louisiana Family Planning Program are textbook examples of customized statistics. It is suggested that the family planning program services may contribute to increased natality and that the family planning program workers are more highly motivated to retain their jobs than to bring down the brith rate. The reviewers are not convinced that the statisticians on the Family Health Foundation are responsible for all of the narrative that accompanies their charts and tables.

  20. Readiness review plan for the in situ vitrification demonstration of Seepage Pit 1 in Waste Area Grouping 7

    International Nuclear Information System (INIS)

    1995-05-01

    A treatability study is planned that encompasses the application of in situ vitrification (ISV) to at least two segments of the Oak Ridge National Laboratory Seepage Pit I during the third quarter of fiscal year 1995. Before the treatability study can be initiated, the proposed activity must be subjected to an Operational Readiness Review (ORR). ORR is a structured methodology of determining readiness to proceed as outlined in Martin Marietta Energy Systems, Inc. (Energy Systems), Environmental Restoration Waste Management Procedure ER/C-P1610, which provides Energy Systems organizations assurance that the work to be performed is consistent with management's expectations and that the subject activity is ready to proceed safely. The readiness review plan provides details of the review plan overview and the scope of work to be performed. The plan also identifies individuals and position responsibilities for implementing the activity. The management appointed Readiness Review Board (RRB) has been identified. A Field Readiness Review Team (FRT), a management appointed multidisciplinary group, has been established (1) to evaluate the ISV treatability study, (2) to identify and assemble supporting objective evidences of the readiness to proceed, and (3) to assist the team leader in presenting the evidences to the RRB. A major component of RRB is the formulation of readiness review criteria months before the operation. A comprehensive readiness review tree (a positive logic tree) is included, which identifies the activities required for the development of the readiness criteria. The readiness review tree serves as a tool to prevent the omission of an item that could affect system performance. All deficiencies identified in the review will be determined as prestart findings and must be resolved before the project is permitted to proceed. The final approval of the readiness to proceed will be the decision of RRB

  1. Literature Review of Advantages and Disadvantages of Pre-planned Construction Projects 2013 PhD Conference

    DEFF Research Database (Denmark)

    Larsen, Jesper Kranker; Ussing, Lene Faber; Brunø, Thomas Ditlev

    2013-01-01

    The construction industry’s focus on pre-planning, with its advantages and disadvantages, has not been investigated in a literature review which gives a state of art understanding of the topic. The aim of the paper is to review related papers, to fulfill gaps in the literature which could...

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

    International Nuclear Information System (INIS)

    1987-06-01

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

  3. Where is the evidence for emergency planning: a scoping review.

    Science.gov (United States)

    Challen, Kirsty; Lee, Andrew C K; Booth, Andrew; Gardois, Paolo; Woods, Helen Buckley; Goodacre, Steve W

    2012-07-23

    Recent terrorist attacks and natural disasters have led to an increased awareness of the importance of emergency planning. However, the extent to which emergency planners can access or use evidence remains unclear. The aim of this study was to identify, analyse and assess the location, source and quality of emergency planning publications in the academic and UK grey literature. We conducted a scoping review, using as data sources for academic literature Embase, Medline, Medline in Process, Psychinfo, Biosis, Science Citation Index, Cinahl, Cochrane library and Clinicaltrials.gov. For grey literature identification we used databases at the Health Protection Agency, NHS Evidence, British Association of Immediate Care Schemes, Emergency Planning College and the Health and Safety Executive, and the websites of UK Department of Health Emergency Planning Division and UK Resilience.Aggregative synthesis was used to analyse papers and documents against a framework based on a modified FEMA Emergency Planning cycle. Of 2736 titles identified from the academic literature, 1603 were relevant. 45% were from North America, 27% were commentaries or editorials and 22% were event reports.Of 192 documents from the grey literature, 97 were relevant. 76% of these were event reports.The majority of documents addressed emergency planning and response. Very few documents related to hazard analysis, mitigation or capability assessment. Although a large body of literature exists, its validity and generalisability is unclear There is little evidence that this potential evidence base has been exploited through synthesis to inform policy and practice. The type and structure of evidence that would be of most value of emergency planners and policymakers has yet to be identified.

  4. Where is the evidence for emergency planning: a scoping review

    Directory of Open Access Journals (Sweden)

    Challen Kirsty

    2012-07-01

    Full Text Available Abstract Background Recent terrorist attacks and natural disasters have led to an increased awareness of the importance of emergency planning. However, the extent to which emergency planners can access or use evidence remains unclear. The aim of this study was to identify, analyse and assess the location, source and quality of emergency planning publications in the academic and UK grey literature. Methods We conducted a scoping review, using as data sources for academic literature Embase, Medline, Medline in Process, Psychinfo, Biosis, Science Citation Index, Cinahl, Cochrane library and Clinicaltrials.gov. For grey literature identification we used databases at the Health Protection Agency, NHS Evidence, British Association of Immediate Care Schemes, Emergency Planning College and the Health and Safety Executive, and the websites of UK Department of Health Emergency Planning Division and UK Resilience. Aggregative synthesis was used to analyse papers and documents against a framework based on a modified FEMA Emergency Planning cycle. Results Of 2736 titles identified from the academic literature, 1603 were relevant. 45% were from North America, 27% were commentaries or editorials and 22% were event reports. Of 192 documents from the grey literature, 97 were relevant. 76% of these were event reports. The majority of documents addressed emergency planning and response. Very few documents related to hazard analysis, mitigation or capability assessment. Conclusions Although a large body of literature exists, its validity and generalisability is unclear There is little evidence that this potential evidence base has been exploited through synthesis to inform policy and practice. The type and structure of evidence that would be of most value of emergency planners and policymakers has yet to be identified.

  5. "I sleep better at night:" How peer review of radiation treatment plans indirectly improves quality of care across radiation treatment programs.

    Science.gov (United States)

    Brundage, Michael D; Hart, Margaret; O'Donnell, Jennifer; Reddeman, Lindsay; Gutierrez, Eric; Foxcroft, Sophie; Warde, Padraig

    Peer review of radiation oncology treatment plans is increasingly recognized as an important component of quality assurance in radiation treatment planning and delivery. Peer review of treatment plans can directly improve the quality of those plans and can also have indirect effects on radiation treatment programs. We undertook a systematic, qualitative approach to describing the indirect benefits of peer review, factors that were seen to facilitate or act as barriers to the implementation of peer review, and strategies to address these barriers across a provincial jurisdiction of radiation oncology programs (ROPs). Semistructured qualitative interviews were held with radiation oncology department heads and radiation therapy managers (or delegates) in all 14 ROPs in Ontario, Canada. We used a theoretically guided phenomenological qualitative approach to design and analyze the interview content. Themes were recorded by 2 independent reviewers, and any discordance was resolved by consensus. A total of 28 interviews were completed with 32 interviewees. Twenty-two unique themes addressed perceived benefits of peer review, relating to either peer review structure (n = 3), process (n = 9), or outcome (n = 10). Of these 22 themes, 19 related to indirect benefits to ROPs. In addition, 18 themes related to factors that facilitated peer review activities and 30 themes related to key barriers to implementing peer review were identified. Findings were consistent with, and enhanced the understanding of, previous survey-based assessments of the benefits and challenges of implementing peer review programs. Although challenges and concerns regarding the implementation of peer review were evident, the indirect benefits to radiation programs are numerous, far outweigh the implementation challenges, and strongly complement the direct individual-patient benefits that result from peer review quality assurance of radiation treatment plans. Copyright © 2016. Published by Elsevier Inc.

  6. Guidelines for the review of advanced controls and displays

    International Nuclear Information System (INIS)

    Wachtel, J.; O'Hara, J.M.

    1991-01-01

    Advanced control room (ACR) concepts are being developed and refined in the commercial nuclear industry as part of future reactor designs. These ACRs will utilize advanced human-system interface (HSI) technologies which may have significant implications for plant safety in that they may affect: (1) the operators' overall role (function) in the system; (2) the methods by which operators receive information about system status; (3) the ways in which the operators interact with the system; and (4) the requirements on operators to understand and supervise an increasingly complex system. The Nuclear Regulatory Commission (NRC) reviews control room designs to ensure that they incorporate good human factors engineering principles so as to support operator performance and reliability necessary to protect public health and safety. The principal guidance available to the NRC (NUREG-0700) was developed more than ten years ago and does not address new technologies. Accordingly, the guidance must be updated. This paper discusses the development of an NRC Advanced Control Room Design Review Guideline

  7. NPP License Renewal and Aging Management: Revised Guidance

    International Nuclear Information System (INIS)

    Hull, A.B.; Hiser, A.L.; Lindo-Talin, S.E.

    2012-01-01

    Based on the Atomic Energy Act, the NRC issues licenses for commercial power reactors to operate for up to 40 years and allows these licenses to be renewed for up to another 20 years. NRC has approved license renewal (LR) for well over 50% of U.S. located reactors originally licensed to operate for 40 years. Of these 104 reactors (69 PWRs, 35 BWRs), the NRC has issued renewed licenses for 71 units and is currently reviewing applications for another 15 units. As of May 1, 2012, ten plants at nine sites had entered their 41st year of operation and thus are in their first period of extended operation (PEO). Five more plants will enter the PEO by the end of 2012. One foundation of the license renewal process has been license renewal guidance documents (LRGDs). The U.S. Nuclear Regulatory Commission (NRC) revised key guidance documents used for nuclear power LR in 2010 and 2011. These include NUREG-1800, 'Standard Review Plan for Review of License Renewal Applications,' revision 2 (SRP-LR), and NUREG-1801, 'Generic Aging Lessons Learned (GALL) Report,' revision 2 (GALL Report). The guidance documents were updated to reflect lessons learned and operating experience gained since the guidance documents were last issued in 2005. The reactor LRGDs referenced in this poster can all be accessed at http://www.nrc.gov/reactors/operating/licensing/renewal/guidance.html (author)

  8. The Sump Screen Clogging Issue in Belgium from the Standpoint of the Authorized Inspection Organisation (AIO) (AVN)

    International Nuclear Information System (INIS)

    Tombuyses, B.; Gelder, P. de; Vandewalle, A.

    2004-01-01

    All Belgian NPPs are PWRs. These PWRs have different containment designs and different sump designs. The four most recent units took RG 1.82 rev. 0 into account for the recirculation sump design. Several improvements were made in the framework of the first Periodic Safety Review to the oldest units such as enlargement of the sumps strainer in 1985, taking into account the requirements of RG 1.82 rev. 0. The problem of recirculation sump screen clogging due to the accumulation of insulation debris after an accident was also identified as a safety issue in the first Periodic Safety Review for Doel 3 and Tihange 2 and the second Periodic Safety Review for Doel 1 and 2 and Tihange 1, that started in the nineties. One of the purposes of the Periodic Safety Review being the justification of the safety level of the power plants with regard to the most recent safety rules and practices, the licensee was asked to review the characteristics of the sump strainers according to the revision 1 of the RG 1.82 (which referred to Nureg 0897 rev. 1). Later on, the Barsebaeck incident and the events leading to the NRC IN 93-34 showed that the conclusions of Nureg 0897 could underestimate the potential for loss of NPSH of the ECCS- and CSS-pumps. The issue was further examined and the AIO asked the licensee to continue efforts to recollect information. After issuance of the results from the parametric evaluation for pressurised water reactor recirculation sump performance (GSI-191) performed by LANL under NRC contract, the AIO asked the Belgian licensee in August 2002 to increase its efforts to investigate and to solve this issue. The requirements to the Licensee and the corresponding action plan as approved by the AIO are presented. Some significant lessons learned from the implementation of this action plan are discussed. (authors)

  9. Proceedings of the workshop on review of dose modeling methods for demonstration of compliance with the radiological criteria for license termination

    International Nuclear Information System (INIS)

    Nicholson, T.J.; Parrott, J.D.

    1998-05-01

    The workshop was one in a series to support NRC staff development of guidance for implementing the final rule on ''Radiological Criteria for License Termination.'' The workshop topics included discussion of: dose models used for decommissioning reviews; identification of criteria for evaluating the acceptability of dose models; and selection of parameter values for demonstrating compliance with the final rule. The 2-day public workshop was jointly organized by RES and NMSS staff responsible for reviewing dose modeling methods used in decommissioning reviews. The workshop was noticed in the Federal Register (62 FR 51706). The workshop presenters included: NMSS and RES staff, who discussed both dose modeling needs for licensing reviews, and development of guidance related to dose modeling and parameter selection needs; DOE national laboratory scientists, who provided responses to earlier NRC staff-developed questions and discussed their various Federally-sponsored dose models (i.e., DandD, RESRAD, and MEPAS codes); and an EPA scientist, who presented details on the EPA dose assessment model (i.e., PRESTO code). The workshop was formatted to provide opportunities for the attendees to observe computer demonstrations of the dose codes presented. More than 120 workshop attendees from NRC Headquarters and the Regions, Agreement States; as well as industry representatives and consultants; scientists from EPA, DOD, DNFSB, DOE, and the national laboratories; and interested members of the public participated. A complete transcript of the workshop, including viewgraphs and attendance lists, is available in the NRC Public Document Room. This NUREG/CP documents the formal presentations made during the workshop, and provides a preface outlining the workshop's focus, objectives, background, topics and questions provided to the invited speakers, and those raised during the panel discussion. NUREG/CP-0163 also provides technical bases supporting the development of decommissioning

  10. Return of IEEE Std 627 and its Value to Equipment Qualification Programs

    International Nuclear Information System (INIS)

    Horvath, D.A.

    2012-01-01

    IEEE Std 627 ''Design Qualification of Safety Systems Equipment Used in Nuclear Power Generating Stations'' was issued to more generically establish qualification requirements in the form of a high level umbrella document. Efforts on this standard began in late 1975 at the request of the IEEE Nuclear Standards Management Board. In 1977 a joint ASME/IEEE agreement established responsibility for qualification and quality assurance standards preparation. ASME accepted responsibility for Quality Assurance and IEEE for qualification. In accordance with that agreement, IEEE completed the generic qualification standard in 1980. This document provided high level approaches, criteria, guidance, and principles for qualification of both electrical and mechanical equipment that at that time appeared in no other industry standard. IEEE Std 627-1980 was later reaffirmed in 1996. In 1986, ASME's Board on Nuclear Codes and Standards directed its Committee on Qualification of Mechanical Equipment (QME) to develop a standard for qualifying mechanical equipment. This task was completed in several parts during the time frame from 1992 to 1994. Partly in response to this activity, IEEE Std 627 was withdrawn in 2002. Later although withdrawn, it was found that IEEE Std 627 was continuing to be used and referenced by many entities both in the US and other countries including in ASME's QME-1-2002 ''Qualification of Active Mechanical Equipment Used in Nuclear Power Plants'', US NRC's NUREG-0800 Standard Review Plan Section 3.11, at least one reactor vendor's Design Certification Document (DCD), several international licensing documents, and elsewhere. As a result, in 2007, the IEEE Standards Board authorized Working Group 2.10 of Subcommittee 2 (Qualification) of the Power and Energy Society's Nuclear Power Engineering Committee to resurrect and update IEEE Std 627-1980 (Reaff 1996). The result was the culmination IEEE Std 627 in 2010. This paper will report on the eight improvements made

  11. Economic Evaluation of Family Planning Interventions in Low and Middle Income Countries; A Systematic Review.

    Science.gov (United States)

    Zakiyah, Neily; van Asselt, Antoinette D I; Roijmans, Frank; Postma, Maarten J

    2016-01-01

    A significant number of women in low and middle income countries (L-MICs) who need any family planning, experience a lack in access to modern effective methods. This study was conducted to review potential cost effectiveness of scaling up family planning interventions in these regions from the published literatures and assess their implication for policy and future research. A systematic review was performed in several electronic databases i.e Medline (Pubmed), Embase, Popline, The National Bureau of Economic Research (NBER), EBSCOHost, and The Cochrane Library. Articles reporting full economic evaluations of strategies to improve family planning interventions in one or more L-MICs, published between 1995 until 2015 were eligible for inclusion. Data was synthesized and analyzed using a narrative approach and the reporting quality of the included studies was assessed using the Consolidated Health Economic Evaluation Reporting Standards (CHEERS) statement. From 920 references screened, 9 studies were eligible for inclusion. Six references assessed cost effectiveness of improving family planning interventions in one or more L-MICs, while the rest assessed costs and consequences of integrating family planning and HIV services, concerning sub-Saharan Africa. Assembled evidence suggested that improving family planning interventions is cost effective in a variety of L-MICs as measured against accepted international cost effectiveness benchmarks. In areas with high HIV prevalence, integrating family planning and HIV services can be efficient and cost effective; however the evidence is only supported by a very limited number of studies. The major drivers of cost effectiveness were cost of increasing coverage, effectiveness of the interventions and country-specific factors. Improving family planning interventions in low and middle income countries appears to be cost-effective. Additional economic evaluation studies with improved reporting quality are necessary to generate

  12. Economic Evaluation of Family Planning Interventions in Low and Middle Income Countries; A Systematic Review.

    Directory of Open Access Journals (Sweden)

    Neily Zakiyah

    Full Text Available A significant number of women in low and middle income countries (L-MICs who need any family planning, experience a lack in access to modern effective methods. This study was conducted to review potential cost effectiveness of scaling up family planning interventions in these regions from the published literatures and assess their implication for policy and future research.A systematic review was performed in several electronic databases i.e Medline (Pubmed, Embase, Popline, The National Bureau of Economic Research (NBER, EBSCOHost, and The Cochrane Library. Articles reporting full economic evaluations of strategies to improve family planning interventions in one or more L-MICs, published between 1995 until 2015 were eligible for inclusion. Data was synthesized and analyzed using a narrative approach and the reporting quality of the included studies was assessed using the Consolidated Health Economic Evaluation Reporting Standards (CHEERS statement.From 920 references screened, 9 studies were eligible for inclusion. Six references assessed cost effectiveness of improving family planning interventions in one or more L-MICs, while the rest assessed costs and consequences of integrating family planning and HIV services, concerning sub-Saharan Africa. Assembled evidence suggested that improving family planning interventions is cost effective in a variety of L-MICs as measured against accepted international cost effectiveness benchmarks. In areas with high HIV prevalence, integrating family planning and HIV services can be efficient and cost effective; however the evidence is only supported by a very limited number of studies. The major drivers of cost effectiveness were cost of increasing coverage, effectiveness of the interventions and country-specific factors.Improving family planning interventions in low and middle income countries appears to be cost-effective. Additional economic evaluation studies with improved reporting quality are necessary

  13. Review of the proposed Strategic National Plan for Civilian Nuclear Reactor Development: Volume 1

    International Nuclear Information System (INIS)

    1986-10-01

    On August 9, 1985, the Secretary of Energy requested that the Chairman of the Energy Research Advisory Board establish an ad-hoc Panel to review a draft ''Strategic National Plan for Civilian Nuclear Reactor Development.'' The resulting report, approved by the Board, contains suggestions for improving the draft plan and also contains major recommendations for alleviating the several institutional barriers that appear to preclude the construction of any new nuclear power plants in this country

  14. Evaluation of severe accident risks: Quantification of major input parameters: MAACS [MELCOR Accident Consequence Code System] input

    International Nuclear Information System (INIS)

    Sprung, J.L.; Jow, H-N; Rollstin, J.A.; Helton, J.C.

    1990-12-01

    Estimation of offsite accident consequences is the customary final step in a probabilistic assessment of the risks of severe nuclear reactor accidents. Recently, the Nuclear Regulatory Commission reassessed the risks of severe accidents at five US power reactors (NUREG-1150). Offsite accident consequences for NUREG-1150 source terms were estimated using the MELCOR Accident Consequence Code System (MACCS). Before these calculations were performed, most MACCS input parameters were reviewed, and for each parameter reviewed, a best-estimate value was recommended. This report presents the results of these reviews. Specifically, recommended values and the basis for their selection are presented for MACCS atmospheric and biospheric transport, emergency response, food pathway, and economic input parameters. Dose conversion factors and health effect parameters are not reviewed in this report. 134 refs., 15 figs., 110 tabs

  15. Factors Determining Quality of Care in Family Planning Services in Africa: A Systematic Review of Mixed Evidence.

    Science.gov (United States)

    Tessema, Gizachew Assefa; Streak Gomersall, Judith; Mahmood, Mohammad Afzal; Laurence, Caroline O

    2016-01-01

    Improving use of family planning services is key to improving maternal health in Africa, and provision of quality of care in family planning services is critical to support higher levels of contraceptive uptake. The objective of this systematic review was to synthesize the available evidence on factors determining the quality of care in family planning services in Africa. Quantitative and qualitative studies undertaken in Africa, published in English, in grey and commercial literature, between 1990 and 2015 were considered. Methodological quality of included studies was assessed using standardized tools. Findings from the quantitative studies were summarized using narrative and tables. Client satisfaction was used to assess the quality of care in family planning services in the quantitative component of the review. Meta-aggregation was used to synthesize the qualitative study findings. From 4334 records, 11 studies (eight quantitative, three qualitative) met the review eligibility criteria. The review found that quality of care was influenced by client, provider and facility factors, and structural and process aspects of the facilities. Client's waiting time, provider competency, provision/prescription of injectable methods, maintaining privacy and confidentiality were the most commonly identified process factors. The quality of stock inventory was the most commonly identified structural factor. The quality of care was also positively associated with privately-owned facilities. The qualitative synthesis revealed additional factors including access related factors such as 'pre-requisites to be fulfilled by the clients and cost of services, provider workload, and providers' behaviour. There is limited evidence on factors determining quality of care in family planning services in Africa that shows quality of care is influenced by multiple factors. The evidence suggests that lowering access barriers and avoiding unnecessary pre-requisites for taking contraceptive

  16. Factors Determining Quality of Care in Family Planning Services in Africa: A Systematic Review of Mixed Evidence.

    Directory of Open Access Journals (Sweden)

    Gizachew Assefa Tessema

    Full Text Available Improving use of family planning services is key to improving maternal health in Africa, and provision of quality of care in family planning services is critical to support higher levels of contraceptive uptake. The objective of this systematic review was to synthesize the available evidence on factors determining the quality of care in family planning services in Africa.Quantitative and qualitative studies undertaken in Africa, published in English, in grey and commercial literature, between 1990 and 2015 were considered. Methodological quality of included studies was assessed using standardized tools. Findings from the quantitative studies were summarized using narrative and tables. Client satisfaction was used to assess the quality of care in family planning services in the quantitative component of the review. Meta-aggregation was used to synthesize the qualitative study findings.From 4334 records, 11 studies (eight quantitative, three qualitative met the review eligibility criteria. The review found that quality of care was influenced by client, provider and facility factors, and structural and process aspects of the facilities. Client's waiting time, provider competency, provision/prescription of injectable methods, maintaining privacy and confidentiality were the most commonly identified process factors. The quality of stock inventory was the most commonly identified structural factor. The quality of care was also positively associated with privately-owned facilities. The qualitative synthesis revealed additional factors including access related factors such as 'pre-requisites to be fulfilled by the clients and cost of services, provider workload, and providers' behaviour.There is limited evidence on factors determining quality of care in family planning services in Africa that shows quality of care is influenced by multiple factors. The evidence suggests that lowering access barriers and avoiding unnecessary pre-requisites for taking

  17. 76 FR 58509 - Release of Risk and Exposure Assessment Planning Document for the Review of the National Ambient...

    Science.gov (United States)

    2011-09-21

    ... Assessment Planning Document for the Review of the National Ambient Air Quality Standards for Lead AGENCY... available for public review the Review of the National Ambient Air Quality Standards for Lead: Risk and... and/or welfare effects in this review of the national ambient air quality standards (NAAQS) for lead...

  18. Ethical Decision Making in Academic Dishonesty with Application of Modified Theory of Planned Behavior: A Review

    Science.gov (United States)

    Meng, Chan Ling; Othman, Jamilah; D'Silva, Jeffrey Lawrence; Omar, Zoharah

    2014-01-01

    This conceptual paper studies the application of the Theory of Planned Behavior (TBP) in academic dishonesty with the mediating variable of ethical ideologies. The study reviews literature on the Theory of Planned Behavior and past studies pertaining to academic dishonesty. The paper analyses the relationship of the variables of TPB on academic…

  19. Barriers to family planning and contraception uptake in sub-Saharan Africa: a systematic review.

    Science.gov (United States)

    Haider, Taj L; Sharma, Manoj

    This review assessed barriers to uptake of family planning and contraceptive services among women in sub-Saharan Africa. Included were studies: (1) published in the English; (2) between the years January 2010 and July 2012; (3) that measure barriers to family planning/contraceptive methods; and (4) that use any quantitative or qualitative study design. Eleven studies fitting the inclusion criteria were reviewed. The major barriers found to prevent uptake of services included cultural and societal pressure on women, socioeconomic status, financial barriers, and regional barriers associated with lack of access to services. Due to the diversity of the populations in sub-Saharan Africa, it is clear that a one-size-fits-all approach will not be efficacious; rather, a strategy that takes into account cultural and societal norms for the population of interest is better.

  20. Studies in Family Planning, Volume 5 Number 5. East Asia Review, 1973.

    Science.gov (United States)

    Keeny, S. M., Ed.

    An annual review, third in a series, covers developments in the field of population and family planning in East Asia. For each of the 10 countries involved (Hong Kong, Indonesia, South Korea, Laos, Malaysia, Phillipines, Singapore, Taiwan, Thailand, and South Vietnam) there is an article written by the agent responsible for the family planning…

  1. Standard Review Plan Update and Development Program. Implementing Procedures Document

    Energy Technology Data Exchange (ETDEWEB)

    1992-05-01

    This implementing procedures document (IPD) was prepared for use in implementing tasks under the standard review plan update and development program (SRP-UDP). The IPD provides comprehensive guidance and detailed procedures for SRP-UDP tasks. The IPD is mandatory for contractors performing work for the SRP-UDP. It is guidance for the staff. At the completion of the SRP-UDP, the IPD will be revised (to remove the UDP aspects) and will replace NRR Office Letter No. 800 as long-term maintenance procedures.

  2. Smart Distribution Networks: A Review of Modern Distribution Concepts from a Planning Perspective

    Directory of Open Access Journals (Sweden)

    Syed Ali Abbas Kazmi

    2017-04-01

    Full Text Available Smart grids (SGs, as an emerging grid modernization concept, is spreading across diverse research areas for revolutionizing power systems. SGs realize new key concepts with intelligent technologies, maximizing achieved objectives and addressing critical issues that are limited in conventional grids. The SG modernization is more noticeable at the distribution grid level. Thus, the transformation of the traditional distribution network (DN into an intelligent one, is a vital dimension of SG research. Since future DNs are expected to be interconnected in nature and operation, hence traditional planning methods and tools may no longer be applicable. In this paper, the smart distribution network (SDN concept under the SG paradigm, has presented and reviewed from the planning perspective. Also, developments in the SDN planning process have been surveyed on the basis of SG package (SGP. The package presents a SDN planning foundation via major SG-enabling technologies (SGTF, anticipated functionalities (SGAF, new consumption models (MDC as potential SDN candidates, associated policies and pilot projects and multi-objective planning (MOP as a real-world optimization problem. In addition, the need for an aggregated SDN planning model has also been highlighted. The paper discusses recent notable related works, implementation activities, various issues/challenges and potential future research directions; all aiming at SDN planning.

  3. Electrochemical Metal Deposition on Carbon Nanotubes

    Czech Academy of Sciences Publication Activity Database

    Dunsch, L.; Janda, Pavel; Mukhopadhyay, K.; Shinohara, H.

    2001-01-01

    Roč. 11, č. 6 (2001), s. 427-435 ISSN 1344-9931 Institutional research plan: CEZ:AV0Z4040901 Keywords : carbon nanotubes * electrodeposition * cyclic voltammetry Subject RIV: CG - Electrochemistry Impact factor: 0.800, year: 2001

  4. Detection of pinworm eggs in the dust of laboratory animals breeding facility, in the cages and on the hands of the technicians

    Czech Academy of Sciences Publication Activity Database

    Lytvynets, Andrej; Langrová, I.; Lachout, Josef; Vadlejch, J.

    2013-01-01

    Roč. 47, č. 1 (2013), s. 71-73 ISSN 0023-6772 Institutional research plan: CEZ:AV0Z50110509 Keywords : laboratory animal * pinworm * breeding facility Subject RIV: EG - Zoology Impact factor: 0.800, year: 2013

  5. Review and action plan for oral health improvement in Sheffield special schools.

    Science.gov (United States)

    Worsley, D J; Jones, K; Harris, J C; Charlesworth, J; Marshman, Z

    2018-03-01

    A description of the process of a review of oral health improvement in special schools in Sheffield and the implementation of an action plan for these activities. Public health competencies encompassed: assessing the evidence on oral health and dental interventions, programmes and services; strategic leadership and collaborative working for health; oral health improvement. Copyright© 2018 Dennis Barber Ltd.

  6. Safety evaluation report related to the construction permit and operating license for the research reactor at the University of Texas (Docket No. 50-602)

    International Nuclear Information System (INIS)

    1992-01-01

    The Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to NUREG-1135, ''Safety Evaluation Report Related to the Construction Permit and Operating License for the Research Reactor at the University of Texas'' (SER) May 1985. The reactor facility is owned by The University of Texas at Austin (UT, the applicant) and is located at the University's Balcones Research Center in Austin, Texas. This supplement to the SER (SSER) describes the changes to the reactor facility design from the description in the SER. The SER and SSER together reflect the facility as built. The SSER also documents the reviews that the NRC has completed regarding the applicant's emergency plan, security plan, and technical specifications that were identified as open in the SER

  7. Study on safety subsidiary objective of nuclear power plant in USA

    International Nuclear Information System (INIS)

    Chen Yan; Zhang Chunming; Fu Zhiwei; Song Wei; Li Chaojun; Wang Zhe; Zuo Jiaxu

    2013-01-01

    This paper reviewed the development of the quantitative safety objective and subsidiary objective in USA. The expressions of CDF and LERF were obtained according to NUREG-1150. The relationship between the subsidiary objective and the quantitative safety objective was derived. The method was compared with that used in NUREG-1860. The requirements of safety objective for the future nuclear power plant and the development of probabilistic safety analysis (PSA) technology in USA were studied and can be used as reference in China. (authors)

  8. The Impact of Colleague Peer Review on the Radiotherapy Treatment Planning Process in the Radical Treatment of Lung Cancer.

    Science.gov (United States)

    Rooney, K P; McAleese, J; Crockett, C; Harney, J; Eakin, R L; Young, V A L; Dunn, M A; Johnston, R E; Hanna, G G

    2015-09-01

    Modern radiotherapy uses techniques to reliably identify tumour and reduce target volume margins. However, this can potentially lead to an increased risk of geographic miss. One source of error is the accuracy of target volume delineation (TVD). Colleague peer review (CPR) of all curative-intent lung cancer plans has been mandatory in our institution since May 2013. At least two clinical oncologists review plans, checking treatment paradigm, TVD, prescription dose tumour and critical organ tolerances. We report the impact of CPR in our institution. Radiotherapy treatment plans of all patients receiving radical radiotherapy were presented at weekly CPR meetings after their target volumes were reviewed and signed off by the treating consultant. All cases and any resultant change to TVD (including organs at risk) or treatment intent were recorded in our prospective CPR database. The impact of CPR over a 13 month period from May 2013 to June 2014 is reported. One hundred and twenty-two patients (63% non-small cell lung carcinoma, 17% small cell lung carcinoma and 20% 'clinical diagnosis') were analysed. On average, 3.2 cases were discussed per meeting (range 1-8). CPR resulted in a change in treatment paradigm in 3% (one patient proceeded to induction chemotherapy, two patients had high-dose palliative radiotherapy). Twenty-one (17%) had a change in TVD and one (1%) patient had a change in dose prescription. In total, 6% of patients had plan adjustment after review of dose volume histogram. The introduction of CPR in our centre has resulted in a change in a component of the treatment plan for 27% of patients receiving curative-intent lung radiotherapy. We recommend CPR as a mandatory quality assurance step in the planning process of all radical lung plans. Copyright © 2015 The Royal College of Radiologists. Published by Elsevier Ltd. All rights reserved.

  9. River Protection Project Integrated safety management system phase II verification review plan - 7/29/99

    International Nuclear Information System (INIS)

    SHOOP, D.S.

    1999-01-01

    The purpose of this review is to verify the implementation status of the Integrated Safety Management System (ISMS) for the River Protection Project (RPP) facilities managed by Fluor Daniel Hanford, Inc. (FDH) and operated by Lockheed Martin Hanford Company (LMHC). This review will also ascertain whether within RPP facilities and operations the work planning and execution processes are in place and functioning to effectively protect the health and safety of the workers, public, environment, and federal property over the RPP life cycle. The RPP ISMS should support the Hanford Strategic Plan (DOERL-96-92) to safely clean up and manage the site's legacy waste and deploy science and technology while incorporating the ISMS central theme to ''Do work safely'' and protect human health and the environment

  10. 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

  11. TU-D-201-02: Medical Physics Practices for Plan and Chart Review: Results of AAPM Task Group 275 Survey

    Energy Technology Data Exchange (ETDEWEB)

    Fong de los Santos, L [Mayo Clinic, Rochester, MN (United States); Dong, L [Scripps Proton Therapy Center, San Diego, CA (United States); Greener, A [VA Medical Center, East Orange, NJ (United States); Johnson, J [UT MD Anderson Cancer Center, Houston, TX (United States); Johnson, P [University of Miami, Miami, FL (United States); Kim, G [University of California, San Diego, La Jolla, CA (United States); Mechalakos, J; Yorke, E [Memorial Sloan-Kettering Cancer Center, New York, NY (United States); Napolitano, B [Massachusetts General Hospital, Boston, MA (United States); Parker, S [Novant Health, Winston Salem, NC (United States); Schofield, D [Saint Vincent Hospital, Acton, MA (United States); Wells, M [Piedmont Hospital, Atlanta, GA (United States); Ford, E [Mayo Clinic, Rochester, MN (United States); Scripps Proton Therapy Center, San Diego, CA (United States)

    2016-06-15

    Purpose: AAPM Task Group (TG) 275 is charged with developing riskbased guidelines for plan and chart review clinical processes. As part of this work an AAPM-wide survey was conducted to gauge current practices. Methods: The survey consisted of 103 multiple-choice questions covering the following review processes for external beam including protons: 1) Initial Plan Check, 2) On-Treatment and 3) End-of-Treatment Chart Check. The survey was designed and validated by TG members with the goal of providing an efficient and easy response process. The survey, developed and deployed with the support of AAPM headquarters, was released to all AAPM members who have self-reported as working in the radiation oncology field and it was kept open for 7 weeks. Results: There are an estimated 4700 eligible participants. At the time of writing, 962 completed surveys have been collected with an average completion time of 24 minutes. Participants are mainly from community hospitals (40%), academicaffiliated hospitals (31%) and free-standing clinics (18%). Among many other metrics covered on the survey, results so far indicate that manual review is an important component on the plan and chart review process (>90%) and that written procedures and checklists are widely used (>60%). However, the details of what is reviewed or checked are fairly heterogeneous among the sampled medical physics community. Conclusion: The data gathered from the survey gauging current practices will be used by TG 275 to develop benchmarks and recommendations for the type and extent of checks to perform effective physics plan and chart review processes.

  12. Design review plan for Multi-Function Waste Tank Facility (Project W-236A)

    International Nuclear Information System (INIS)

    Renfro, G.G.

    1994-01-01

    This plan describes how the Multi-Function Waste Tank Facility (MWTF) Project conducts reviews of design media; describes actions required by Project participants; and provides the methodology to ensure that the design is complete, meets the technical baseline of the Project, is operable and maintainable, and is constructable. Project W-236A is an integrated project wherein the relationship between the operating contractor and architect-engineer is somewhat different than that of a conventional project. Working together, Westinghouse Hanford Company (WHC) and ICF Karser Hanford (ICF KH) have developed a relationship whereby ICF KH performs extensive design reviews and design verification. WHC actively participates in over-the-shoulder reviews during design development, performs a final review of the completed design, and conducts a formal design review of the Safety Class I, ASME boiler and Pressure Vessel Code items in accordance with WHC-CM-6-1, Standard Engineering Practices

  13. Peer review of HEDR uncertainty and sensitivity analyses plan

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, F.O.

    1993-06-01

    This report consists of a detailed documentation of the writings and deliberations of the peer review panel that met on May 24--25, 1993 in Richland, Washington to evaluate your draft report ``Uncertainty/Sensitivity Analysis Plan`` (PNWD-2124 HEDR). The fact that uncertainties are being considered in temporally and spatially varying parameters through the use of alternative time histories and spatial patterns deserves special commendation. It is important to identify early those model components and parameters that will have the most influence on the magnitude and uncertainty of the dose estimates. These are the items that should be investigated most intensively prior to committing to a final set of results.

  14. Application of objective provision tree to development of standard review plan for sodium-cooled fast reactor nuclear design

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Moo-Hoon; Suh, Namduk; Choi, Yongwon; Shin, Andong [Korea Institute of Nuclear Safety, Daejon (Korea, Republic of)

    2016-06-15

    A systematic methodology was developed for the standard review plan for sodium-cooled fast reactor nuclear design. The process is first to develop an objective provision tree of sodium-cooled fast reactor for the reactivity control safety function. The provision tree is generally developed by designer to confirm whether the design satisfies the defense-in-depth concept. Then applicability of the current standard review plan of nuclear design for light water reactor to sodium-cooled fast reactor was evaluated and complemented by the developed objective provision tree.

  15. Understanding what helps or hinders asthma action plan use: a systematic review and synthesis of the qualitative literature.

    Science.gov (United States)

    Ring, Nicola; Jepson, Ruth; Hoskins, Gaylor; Wilson, Caroline; Pinnock, Hilary; Sheikh, Aziz; Wyke, Sally

    2011-11-01

    To understand better what helps and/or hinders asthma action plan use from the professionals and patients/carers perspective. Systematic review and qualitative synthesis (using meta-ethnography). Nineteen studies (20 papers) were included in an analysis of patients/carers' and professionals' views. Seven main influences on action plan implementation were identified including perceived un-helpfulness and irrelevance of the plans. Translation and synthesis of the original authors' interpretations suggested that action plan promotion and use was influenced by professional and patient/carers' asthma beliefs and attitudes and patient/carer experiences of managing asthma. Action plan use is hindered because professionals and patients/carers have different explanatory models of asthma, its management and their respective roles in the management process. Patients/carers, based on their experiential knowledge of their condition, perceive themselves as capable, effective in managing their asthma, but health professionals do not always share this view. Professionally provided medically focused action plans that do not 'fit' with and incorporate the patients'/carers' views of asthma, and their management strategies, will continue to be under-utilised. Professionals need to develop a more patient-centred, partnership-based, approach to the joint development and review of action plans, recognising the experiential asthma knowledge of patients/carers. Copyright © 2011 Elsevier Ireland Ltd. All rights reserved.

  16. Analysis and evaluation of operational data. Annual report, 1996

    International Nuclear Information System (INIS)

    1997-12-01

    The United States Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) has published reports of its activities since 1984. The first report covered January through June of 1984, and the second report covered July through December of 1984. After those first two semiannual reports, AEOD published annual reports of its activities from 1985 through 1993. Beginning with report for 1986, AEOD Annual Reports have been published as NUREG-1272. Beginning with the report for 1987, NUREG-1272 has been published in two parts, No. 1 covering power reactors and No. 2 covering nonreactors (changed to 'nuclear materials' with the 1993 report). AEOD changed its annual report from a calendar year (CY) to a fiscal year report, and added part No. 3 covering technical training, beginning with the combined Annual Report for CY 1994 and fiscal year 1995, NUREG-1272, Vol. 9, Nos. 1-3. This report, NUREG-1272, Vol. 10, No. 2, covers nuclear materials and presents a review of the events and concerns associated with the use of licensed material in applications other than power reactores. NUREG-1272, Vol. 10, No. 1, covers power reactors and presents an overview of the fiscal year 1996 operating experience of the nuclear power industry from the NRC perspective. NUREG-1272, Vol. 10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC's mission. Throughout these reports, whenever information is presented for a calendar year, it is so designated. Fiscal year information is designated by the four digits of the fiscal year

  17. Planning and Reviewing for Success. Training Guides for the Head Start Learning Community.

    Science.gov (United States)

    Aspen Systems Corp., Rockville, MD.

    This guide offers Head Start staff a blueprint for developing the skills and methods necessary for a Head Start program's planning and review process. The guide stresses the need for Head Start administrative and managerial leadership to maintain a holistic, integrated approach; use the strength and resources of Head Start team members; identify…

  18. Planning Document for an NBSR Conversion Safety Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Diamond D. J.; Baek J.; Hanson, A.L.; Cheng, L-Y.; Brown, N.; Cuadra, A.

    2013-09-25

    The NIST Center for Neutron Research (NCNR) is a reactor-laboratory complex providing the National Institute of Standards and Technology (NIST) and the nation with a world-class facility for the performance of neutron-based research. The heart of this facility is the National Bureau of Standards Reactor (NBSR). The NBSR is a heavy water moderated and cooled reactor operating at 20 MW. It is fueled with high-enriched uranium (HEU) fuel elements. A Global Threat Reduction Initiative (GTRI) program is underway to convert the reactor to low-enriched uranium (LEU) fuel. This program includes the qualification of the proposed fuel, uranium and molybdenum alloy foil clad in an aluminum alloy, and the development of the fabrication techniques. This report is a planning document for the conversion Safety Analysis Report (SAR) that would be submitted to, and approved by, the Nuclear Regulatory Commission (NRC) before the reactor could be converted.This report follows the recommended format and content from the NRC codified in NUREG-1537, “Guidelines for Preparing and Reviewing Applications for the Licensing of Non-power Reactors,” Chapter 18, “Highly Enriched to Low-Enriched Uranium Conversions.” The emphasis herein is on the SAR chapters that require significant changes as a result of conversion, primarily Chapter 4, Reactor Description, and Chapter 13, Safety Analysis. The document provides information on the proposed design for the LEU fuel elements and identifies what information is still missing. This document is intended to assist ongoing fuel development efforts, and to provide a platform for the development of the final conversion SAR. This report contributes directly to the reactor conversion pillar of the GTRI program, but also acts as a boundary condition for the fuel development and fuel fabrication pillars.

  19. A pilot application of risk-informed methods to establish inservice inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station. Revision 1

    International Nuclear Information System (INIS)

    Vo, T.V.; Phan, H.K.; Gore, B.F.; Simonen, F.A.; Doctor, S.R.

    1997-02-01

    As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory Commission, the Pacific Northwest National Laboratory has developed risk-informed approaches for inservice inspection plans of nuclear power plants. This method uses probabilistic risk assessment (PRA) results to identify and prioritize the most risk-important components for inspection. The Surry Nuclear Power Station Unit 1 was selected for pilot application of this methodology. This report, which incorporates more recent plant-specific information and improved risk-informed methodology and tools, is Revision 1 of the earlier report (NUREG/CR-6181). The methodology discussed in the original report is no longer current and a preferred methodology is presented in this Revision. This report, NUREG/CR-6181, Rev. 1, therefore supersedes the earlier NUREG/CR-6181 published in August 1994. The specific systems addressed in this report are the auxiliary feedwater, the low-pressure injection, and the reactor coolant systems. The results provide a risk-informed ranking of components within these systems

  20. Review Pages: Planning for Livable and Safe Cities: Socio-economic Changes in Advanced Societies

    Directory of Open Access Journals (Sweden)

    Gennaro Angiello

    2016-12-01

    Full Text Available Starting from the relationship between urban planning and mobility management, TeMA has gradually expanded the view of the covered topics, always remaining in the groove of rigorous scientific in-depth analysis. During the last two years a particular attention has been paid on the Smart Cities theme and on the different meanings that come with it. The last section of the journal is formed by the Review Pages. They have different aims: to inform on the problems, trends and evolutionary processes; to investigate on the paths by highlighting the advanced relationships among apparently distant disciplinary fields; to explore the interaction’s areas, experiences and potential applications; to underline interactions, disciplinary developments but also, if present, defeats and setbacks. Inside the journal the Review Pages have the task of stimulating as much as possible the circulation of ideas and the discovery of new points of view. For this reason the section is founded on a series of basic’s references, required for the identification of new and more advanced interactions. These references are the research, the planning acts, the actions and the applications, analysed and investigated both for their ability to give a systematic response to questions concerning the urban and territorial planning, and for their attention to aspects such as the environmental sustainability and the innovation in the practices. For this purpose the Review Pages are formed by five sections (Web Resources; Books; Laws; Urban Practices; News and Events, each of which examines a specific aspect of the broader information storage of interest for TeMA.

  1. A Retrospective Review of Resuscitation Planning at a Children’s Hospital

    Directory of Open Access Journals (Sweden)

    Jean Kelly

    2018-01-01

    Full Text Available Resuscitation plans (RP are an important clinical indicator relating to care at the end of life in paediatrics. A retrospective review of the medical records of children who had been referred to the Royal Children’s Hospital, Brisbane, Australia who died in the calendar year 2011 was performed. Of 62 records available, 40 patients (65% had a life limiting condition and 43 medical records (69% contained a documented RP. This study demonstrated that both the underlying condition (life-limiting or life-threatening and the setting of care (Pediatric Intensive Care Unit or home influenced the development of resuscitation plans. Patients referred to the paediatric palliative care (PPC service had a significantly longer time interval from documentation of a resuscitation plan to death and were more likely to die at home. All of the patients who died in the paediatric intensive care unit (PICU had a RP that was documented within the last 48 h of life. Most RPs were not easy to locate. Documentation of discussions related to resuscitation planning should accommodate patient and family centered care based on individual needs. With varied diagnoses and settings of care, it is important that there is inter-professional collaboration, particularly involving PICU and PPC services, in developing protocols of how to manage this difficult but inevitable clinical scenario.

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

    International Nuclear Information System (INIS)

    1989-07-01

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

  3. Planned home versus planned hospital births in women at low-risk pregnancy: A systematic review with meta-analysis.

    Science.gov (United States)

    Rossi, A Cristina; Prefumo, Federico

    2018-03-01

    New interest in home birth have recently arisen in women at low risk pregnancy. Maternal and neonatal morbidity of women planning delivery at home has yet to be comprehensively quantified. We aimed to quantify pregnancy outcomes following planned home (PHB) versus planned hospital birth (PHos). We did a systematic review of maternal and neonatal morbidity following planned home (PHB) versus planned hospital birth (PHos). We included prospective, retrospective, cohort and case-control studies of low risk pregnancy outcomes according to planning place of birth, identified from January 2000 to June 2017. We excluded studies in which high-risk pregnancy and composite morbidity were included. Outcomes of interest were: maternal and neonatal morbidity/mortality, medical interventions, and delivery mode. We pooled estimates of the association between outcomes and planning place of birth using meta-analyses. The study protocol is registered with PROSPERO, protocol number CRD42017058016. We included 8 studies of the 4294 records identified, consisting in 14,637 (32.6%) in PHB and 30,177 (67.4%) in PHos group. Spontaneous delivery was significantly higher in PHB than PHos group (OR: 2.075; 95%CI:1.654-2.063) group. Women in PHB group were less likely to undergo cesarean section compared with women in PHos (OR:0.607; 95%CI:0.553-0.667) group. PHB group was less likely to receive medical interventions than PHos group. The risk of fetal dystocia was lower in PHB than PHos group (OR:0.287; 95%CI:0.133-0.618). The risk of post-partum hemorrhage was lower in PHB than PHos group (OR:0.692; 95% CI.0.634-0.755). The two groups were similar with regard to neonatal morbidity and mortality. Births assisted at hospital are more likely to receive medical interventions, fetal monitoring and prompt delivery in case of obstetrical complications. Further studies are needed in order to clarify whether home births are as safe as hospital births. Copyright © 2018 Elsevier B.V. All rights

  4. Review. Supporting problem structuring with computer-based tools in participatory forest planning

    Energy Technology Data Exchange (ETDEWEB)

    Hujala, T.; Khadka, C.; Wolfslehner, B.; Vacik, H.

    2013-09-01

    Aim of study: This review presents the state-of-art of using computerized techniques for problem structuring (PS) in participatory forest planning. Frequency and modes of using different computerized tool types and their contribution for planning processes as well as critical observations are described, followed by recommendations on how to better integrate PS with the use of forest decision support systems. Area of study: The reviewed research cases are from Asia, Europe, North-America, Africa and Australia. Material and methods: Via Scopus search and screening of abstracts, 32 research articles from years 2002-2011 were selected for review. Explicit and implicit evidence of using computerized tools for PS was recorded and assessed with content-driven qualitative analysis. Main results: GIS and forest-specific simulation tools were the most prevalent software types whereas cognitive modelling software and spreadsheet and calculation tools were less frequently used, followed by multi-criteria and interactive tools. The typical use type was to provide outputs of simulation–optimization or spatial analysis to negotiation situations or to compile summaries or illustrations afterwards; using software during group negotiation to foster interaction was observed only in a few cases. Research highlights: Expertise in both decision support systems and group learning is needed to better integrate PS and computerized decision analysis. From the knowledge management perspective, it is recommended to consider how the results of PS —e.g. conceptual models— could be stored into a problem perception database, and how PS and decision making could be streamlined by retrievals from such systems. (Author)

  5. Volumetric image-guidance: Does routine usage prompt adaptive re-planning? An institutional review

    International Nuclear Information System (INIS)

    Tanyi, James A.; Fuss, Martin H.

    2008-01-01

    Purpose. To investigate how the use of volumetric image-guidance using an on-board cone-beam computed tomography (CBCT) system impacts on the frequency of adaptive re-planning. Material and methods. Treatment courses of 146 patients who have undergone a course of external beam radiation therapy (EBRT) using volumetric CBCT image-guidance were analyzed. Target locations included the brain, head and neck, chest, abdomen, as well as prostate and non-prostate pelvis. The majority of patients (57.5%) were treated with hypo-fractionated treatment regimens (three to 15 fraction courses). The frequency of image-guidance ranged from daily (87.7%) to weekly or twice weekly. The underlying medical necessity for adaptive re-planning as well as frequency and consequences of plan adaptation to dose-volume parameters was assessed. Results. Radiation plans of 34 patients (23.3%) were adapted at least once (up to six time) during their course of EBRT as a result of image-guidance CBCT review. Most common causes for adaptive planning were: tumor change (mostly shrinkage: 10 patients; four patients more than one re-plan), change in abdominal girth (systematic change in hollow organ filling; n=7, two patients more than one re-plan), weight loss (n=5), and systematic target setup deviation from simulation (n=5). Adaptive re-plan was required mostly for conventionally fractionated courses; only 5 patient plans undergoing hypo-fractionated treatment were adjusted. In over 91% of adapted plans, the dose-volume parameters did deviate from the prescribed plan parameters by more than 5% for at least 10% of the target volume, or organs-at-risk in close proximity to the target volume. Discussion. Routine use of volumetric image-guidance has in our practice increased the demand for adaptive re-planning. Volumetric CBCT image-guidance provides sufficient imaging information to reliably predict the need for dose adjustment. In the vast majority of cases evaluated, the initial and adapted dose

  6. 77 FR 12086 - Final Staff Guidance, Revision 4 to Standard Review Plan; Section 8.1 on Electric Power-Introduction

    Science.gov (United States)

    2012-02-28

    ... Plan; Section 8.1 on Electric Power--Introduction AGENCY: Nuclear Regulatory Commission. [[Page 12087... Nuclear Power Plants,'' Standard Review Plan (SRP) Section 8.1 on ``Electric Power--Introduction,'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113640121), and the Branch...

  7. 78 FR 44981 - Agency Information Collection Activities; Submission for OMB Review; Comment Request; Plan Asset...

    Science.gov (United States)

    2013-07-25

    ... technological collection techniques or other forms of information technology, e.g., permitting electronic... DEPARTMENT OF LABOR Office of the Secretary Agency Information Collection Activities; Submission for OMB Review; Comment Request; Plan Asset Transactions Determined by In-House Asset Managers Under...

  8. Detailed review and analysis of complex radiotherapy clinical trial planning data: Evaluation and initial experience with the SWAN software system

    International Nuclear Information System (INIS)

    Ebert, Martin A.; Haworth, Annette; Kearvell, Rachel; Hooton, Ben; Coleman, Rhonda; Spry, Nigel; Bydder, Sean; Joseph, David

    2008-01-01

    Aim: Contemporary radiotherapy clinical trials typically require complex three-dimensional (3D) treatment planning. This produces large amounts of data relating technique and dose delivery for correlation with patient outcomes. Assessment of the quality of this information is required to ensure protocol compliance, to quantify the variation in treatments given to patients and to enhance the power of studies to determine correlates of patient outcomes. Materials and methods: A software system ('SWAN') was developed to facilitate the objective analysis, quality-assurance and review of digital treatment planning data from multi-centre radiotherapy trials. The utility of this system was assessed on the basis of its functionality and our experience of its use in the context of multi-centre clinical trials and trials-support activities. Results: The SWAN system has been shown to have the functionality required for use in several multi-centre trials, including automated review and archive processes. Approximately 800 treatment plans from over 30 participating institutions have so far been assessed with the system for several treatment planning scenarios. To illustrate this we include a description of the use of the system for a large-recruitment prostate radiotherapy trial being undertaken in Australasia, including examples of how the review process has changed clinical practice. Conclusion: The successful implementation of SWAN has been demonstrated in a number of clinical trials. The software provides an opportunity for comprehensive review of treatment parameters that could impact on clinical outcomes and trial results. Such quality-assurance (QA) has previously been difficult or impossible to achieve, particularly for a clinical trial involving large numbers of patients. Such reviews have highlighted inconsistencies in clinical practice that have since been addressed through feedback from the review process. The process of data collection and review should be

  9. Research Planning Process

    Science.gov (United States)

    Lofton, Rodney

    2010-01-01

    This presentation describes the process used to collect, review, integrate, and assess research requirements desired to be a part of research and payload activities conducted on the ISS. The presentation provides a description of: where the requirements originate, to whom they are submitted, how they are integrated into a requirements plan, and how that integrated plan is formulated and approved. It is hoped that from completing the review of this presentation, one will get an understanding of the planning process that formulates payload requirements into an integrated plan used for specifying research activities to take place on the ISS.

  10. Analysis and evaluation of operational data. Annual report, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The United States Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) has published reports of its activities since 1984. The first report covered January through June of 1984, and the second report covered July through December of 1984. After those first two semiannual reports, AEOD published annual reports of its activities from 1985 through 1993. Beginning with report for 1986, AEOD Annual Reports have been published as NUREG-1272. Beginning with the report for 1987, NUREG-1272 has been published in two parts, No. 1 covering power reactors and No. 2 covering nonreactors (changed to `nuclear materials` with the 1993 report). AEOD changed its annual report from a calendar year (CY) to a fiscal year report, and added part No. 3 covering technical training, beginning with the combined Annual Report for CY 1994 and fiscal year 1995, NUREG-1272, Vol. 9, Nos. 1-3. This report, NUREG-1272, Vol. 10, No. 2, covers nuclear materials and presents a review of the events and concerns associated with the use of licensed material in applications other than power reactores. NUREG-1272, Vol. 10, No. 1, covers power reactors and presents an overview of the fiscal year 1996 operating experience of the nuclear power industry from the NRC perspective. NUREG-1272, Vol. 10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC`s mission. Throughout these reports, whenever information is presented for a calendar year, it is so designated. Fiscal year information is designated by the four digits of the fiscal year.

  11. Planned hospital birth versus planned home birth

    DEFF Research Database (Denmark)

    Olsen, O.; Clausen, J.A.

    2012-01-01

    Observational studies of increasingly better quality and in different settings suggest that planned home birth in many places can be as safe as planned hospital birth and with less intervention and fewer complications. This is an update of a Cochrane review first published in 1998....

  12. Serving English as a Second Language Communities: A Literary Review and an In-Service Plan To Assist Administrators.

    Science.gov (United States)

    Westendorf, David; Karr-Kidwell, PJ

    This paper presents a literature review and describes an inservice plan for aspiring and current elementary administrators in schools serving English-as-a-Second-Language (ESL) communities. The literature review examines habits and guidelines for effective leaders to use in educational settings, discusses laws regarding bilingual/ESL education,…

  13. Generic implications of ATWS events at the Salem Nuclear Power Plant. Licensee and staff actions

    International Nuclear Information System (INIS)

    1983-08-01

    This report, Volume 2 of two volumes of NUREG-1000, describes the intermediate term actions to be taken by licensees and applicants of the US Nuclear Regulatory Commission (NRC), on the one hand, and by NRC staff, on the other, to address the generic issues raised by two anticipated transients without scram (ATWS) at the Salem Nuclear Generating Station, Unit 1, on February 22 and 25, 1983. These actions came about as a result of the findings of NUREG-1000, Volume 1, and of reviews by the NRC Committee to Review Generic Requirements, the NRC Program Offices, and the Commission. The actions to be taken by licensees and applicants have been detailed in a letter pursuant to 10 CFR 50.54(f)

  14. Radioactive waste isolation in salt: Peer review of the Golder Associates draft test plan for in situ testing in an exploratory shaft in salt

    International Nuclear Information System (INIS)

    Hambley, D.F.; Mraz, D.Z.; Unterberter, R.R.

    1987-01-01

    This report documents the peer review conducted by Argonne National Laboratory of a document entitled ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared for Battelle Memorial Institute's Office of Nuclear Waste Isolation by Golder Associates, Inc. In general, the peer review panelists found the test plan to be technically sound, although some deficiencies were identified. Recommendations for improving the test plan are presented in this review report. A microfiche copy of the following unpublished report is attached to the inside back cover of this report: ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared by Golder Associates, Inc., for Office of Nuclear Waste Isolation, Battelle Memorial Institute, Columbus, Ohio (March 1985)

  15. Review Pages: Planning for Livable and Safe Cities: Extreme Weather Events Caused by Climate Change

    Directory of Open Access Journals (Sweden)

    Gennaro Angiello

    2016-03-01

    Full Text Available Starting from the relationship between urban planning and mobility management, TeMA has gradually expanded the view of the covered topics, always remaining in the groove of rigorous scientific in-depth analysis. During the last two years a particular attention has been paid on the Smart Cities theme and on the different meanings that come with it. The last section of the journal is formed by the Review Pages. They have different aims: to inform on the problems, trends and evolutionary processes; to investigate on the paths by highlighting the advanced relationships among apparently distant disciplinary fields; to explore the interaction’s areas, experiences and potential applications; to underline interactions, disciplinary developments but also, if present, defeats and setbacks. Inside the journal the Review Pages have the task of stimulating as much as possible the circulation of ideas and the discovery of new points of view. For this reason the section is founded on a series of basic’s references, required for the identification of new and more advanced interactions. These references are the research, the planning acts, the actions and the applications, analysed and investigated both for their ability to give a systematic response to questions concerning the urban and territorial planning, and for their attention to aspects such as the environmental sustainability and the innovation in the practices. For this purpose the Review Pages are formed by five sections (Web Resources; Books; Laws; Urban Practices; News and Events, each of which examines a specific aspect of the broader information storage of interest for TeMA

  16. Radiation Planning Assistant - A Streamlined, Fully Automated Radiotherapy Treatment Planning System

    Science.gov (United States)

    Court, Laurence E.; Kisling, Kelly; McCarroll, Rachel; Zhang, Lifei; Yang, Jinzhong; Simonds, Hannah; du Toit, Monique; Trauernicht, Chris; Burger, Hester; Parkes, Jeannette; Mejia, Mike; Bojador, Maureen; Balter, Peter; Branco, Daniela; Steinmann, Angela; Baltz, Garrett; Gay, Skylar; Anderson, Brian; Cardenas, Carlos; Jhingran, Anuja; Shaitelman, Simona; Bogler, Oliver; Schmeller, Kathleen; Followill, David; Howell, Rebecca; Nelson, Christopher; Peterson, Christine; Beadle, Beth

    2018-01-01

    The Radiation Planning Assistant (RPA) is a system developed for the fully automated creation of radiotherapy treatment plans, including volume-modulated arc therapy (VMAT) plans for patients with head/neck cancer and 4-field box plans for patients with cervical cancer. It is a combination of specially developed in-house software that uses an application programming interface to communicate with a commercial radiotherapy treatment planning system. It also interfaces with a commercial secondary dose verification software. The necessary inputs to the system are a Treatment Plan Order, approved by the radiation oncologist, and a simulation computed tomography (CT) image, approved by the radiographer. The RPA then generates a complete radiotherapy treatment plan. For the cervical cancer treatment plans, no additional user intervention is necessary until the plan is complete. For head/neck treatment plans, after the normal tissue and some of the target structures are automatically delineated on the CT image, the radiation oncologist must review the contours, making edits if necessary. They also delineate the gross tumor volume. The RPA then completes the treatment planning process, creating a VMAT plan. Finally, the completed plan must be reviewed by qualified clinical staff. PMID:29708544

  17. Accident source terms for pressurized water reactors with high-burnup cores calculated using MELCOR 1.8.5.

    Energy Technology Data Exchange (ETDEWEB)

    Gauntt, Randall O.; Powers, Dana Auburn; Ashbaugh, Scott G.; Leonard, Mark Thomas; Longmire, Pamela

    2010-04-01

    analyses. Additionally, current analyses suggest that the NUREG-1465 release fractions are conservative by about a factor of 2 in terms of release fractions and that release durations for in-vessel and late in-vessel release periods are in fact longer than the NUREG-1465 durations. It is currently planned that a subsequent report will further characterize these results using more refined statistical methods, permitting a more precise reformulation of the NUREG-1465 alternative source term for both LBU and HBU fuels, with the most important finding being that the NUREG-1465 formula appears to embody significant conservatism compared to current best-estimate analyses.

  18. Review. Supporting problem structuring with computer-based tools in participatory forest planning

    Directory of Open Access Journals (Sweden)

    T. Hujala

    2013-07-01

    Full Text Available Aim of study: This review presents the state-of-art of using computerized techniques for problem structuring (PS in participatory forest planning. Frequency and modes of using different computerized tool types and their contribution for planning processes as well as critical observations are described, followed by recommendations on how to better integrate PS with the use of forest decision support systems.Area of study: The reviewed research cases are from Asia, Europe, North-America, Africa and Australia.Materials and methods: Via Scopus search and screening of abstracts, 32 research articles from years 2002–2011 were selected for review. Explicit and implicit evidence of using computerized tools for PS was recorded and assessed with content-driven qualitative analysis.Main results: GIS and forest-specific simulation tools were the most prevalent software types whereas cognitive modelling software and spreadsheet and calculation tools were less frequently used, followed by multi-criteria and interactive tools. The typical use type was to provide outputs of simulation–optimization or spatial analysis to negotiation situations or to compile summaries or illustrations afterwards; using software during group negotiation to foster interaction was observed only in a few cases.Research highlights: Expertise in both decision support systems and group learning is needed to better integrate PS and computerized decision analysis. From the knowledge management perspective, it is recommended to consider how the results of PS – e.g. conceptual models – could be stored into a problem perception database, and how PS and decision making could be streamlined by retrievals from such systems.Keywords: facilitated modeling; group negotiation; knowledge management; natural resource management; PSM; soft OR; stakeholders.

  19. 77 FR 65700 - Notice of Request for Comments on the Scope of Future Revisions to “Criteria for Preparation and...

    Science.gov (United States)

    2012-10-30

    ...: The Federal Emergency Management Agency (FEMA) is soliciting comments from stakeholders and interested... Regulatory Commission (NRC), is soliciting comments from stakeholders and interested members of the public on... revising NUREG-0654/ FEMA-REP-1, Rev.1 to address stakeholder interest and the various emergency planning...

  20. 78 FR 67177 - Center for Scientific Review; Amended Notice of Meeting

    Science.gov (United States)

    2013-11-08

    ... Technology A Study Section, October 07, 2013, 08:00 a.m. to October 08, 2013, 05:00 p.m., Hilton Alexandria... September 10, 2013, 78 FR 175 Pgs. 55268-55270. The meeting will be held at the Hilton Rockville, 1750...

  1. 78 FR 66372 - Center for Scientific Review; Amended Notice of Meeting

    Science.gov (United States)

    2013-11-05

    ... September 05, 2013, 78 FR 54664-54665. The meeting will be held at the Hotel Monaco Baltimore, 2 North Charles Street, Baltimore, MD 21201 on November 22, 2013, starting at 08:00 a.m. and ending at 07:00 p.m...

  2. K nízké sňatečnosti v České republice

    Czech Academy of Sciences Publication Activity Database

    Hašková, Hana; Rabušic, L.

    2008-01-01

    Roč. 5, č. 2 (2008), s. 9-33 ISSN 1214-813X. [European Sociological Association Conference. Glasgow, 03.09.2007-06.09.2007] R&D Projects: GA MPS 1J034/05-DP2 Grant - others:GA ČR(CZ) GA403/05/0800 Institutional research plan: CEZ:AV0Z70280505 Keywords : marriage rate * cohabitation * family planning Subject RIV: AO - Sociology, Demography

  3. Geotechnical engineering considerations in the NRC's review of uranium mill tailings remedial action plans

    International Nuclear Information System (INIS)

    Gillen, D.M.

    1985-01-01

    To reduce potential health hazards associated with inactive uranium mill tailings sites, the Department of Energy (DOE) is presently investigating and implementing remedial actions at 24 sites in the Uranium Mill Tailings Remedial Action Program (UMTRAP). All remedial actions must be selected and performed with the concurrence of the Nuclear Regulatory Commission (NRC). This paper provides a discussion of geotechnical engineering considerations during the NRC's preconcurrence review of proposed remedial action plans. In order for the NRC staff to perform an adequate geotechnical engineering review, DOE documents must contain a presentation of the properties and stability of all in-situ and engineered soil and rock which may affect the ability of the remedial action plans to meet EPA standards for long-term stability and control. Site investigations, laboratory testing, and remedial action designs must be adequate in scope and technique to provide sufficient data for the NRC staff to independently evaluate static and dynamic stability, settlement, radon attenuation through the soil cover, durability of rock for erosion protection, and other geotechnical engineering factors

  4. DOE financial assurance presentation

    International Nuclear Information System (INIS)

    Huck, R.

    1990-01-01

    The presentation topic is California's approach to license application review in meeting financial assurances for the proposed Ward Valley site. The purpose of the presentation is to provide information on specific financial assurance provisions contained in 10 CFR Part 61 and how California intends to satisfy those requirements. Also, as rate setter, California intends to demonstrate how it will assure allowable costs to the rate base though a financial prudency review. The key provisions of financial assurance are: 10 CFR Section 61.61 - This provision requires an applicant to demonstrate its ability to finance licensed activities; 10 CFR Section 61.62 - This provision requires an applicant to provide assurance that sufficient funds will be available for site closure and stabilization; and 10 CFR Section 61.63 - This provision requires an applicant to provide 'a copy of a binding arrangement, such as a lease, between the applicant and the disposal site owner, so that sufficient funds will be available to cover the costs of the institutional control period.' To assist California in its determination of financial assurance compliance to be demonstrated by the applicant for Part 61 requirements, is NUREG guidance document 1199 'Standard Format and Content of a License Application for a Low-Level Radioactive Waste (LLRW) Disposal Facility.' The detailed financial assurance provisions of NUREG 1199 are then embodied in NUREG 1200, 'Standard Review Plant for the Review of a License Application for a LLRW Disposal Facility.'

  5. Anticipated transients without scram for light water reactors

    International Nuclear Information System (INIS)

    1978-12-01

    In the first two volumes of this report, Anticipated Transients without Scram for Light Water Reactors NUREG-0460, dated April 1978, the NRC staff reviewed the information on this subject that had been developed in the past and evaluated the susceptibility of current nuclear plants to ATWS events using fault tree/event tree analysis techniques. Based on that evaluation, the staff concluded that some corrective measures were required to reduce the risk of severe consequences arising from possible ATWS events. Since the issuance of NUREG-0460, new safety and cost information has become available on ATWS. Also, new insights have been developed on the general subject of quantitative risk assessment. The purpose of this supplement to NUREG-0460 is to summarize the important additions to the information base and to propose a course of action from among a variety of alternatives for resolving the ATWS concern

  6. Temporal logic motion planning

    CSIR Research Space (South Africa)

    Seotsanyana, M

    2010-01-01

    Full Text Available In this paper, a critical review on temporal logic motion planning is presented. The review paper aims to address the following problems: (a) In a realistic situation, the motion planning problem is carried out in real-time, in a dynamic, uncertain...

  7. Provider Tools for Advance Care Planning and Goals of Care Discussions: A Systematic Review.

    Science.gov (United States)

    Myers, Jeff; Cosby, Roxanne; Gzik, Danusia; Harle, Ingrid; Harrold, Deb; Incardona, Nadia; Walton, Tara

    2018-01-01

    Advance care planning and goals of care discussions involve the exploration of what is most important to a person, including their values and beliefs in preparation for health-care decision-making. Advance care planning conversations focus on planning for future health care, ensuring that an incapable person's wishes are known and can guide the person's substitute decision maker for future decision-making. Goals of care discussions focus on preparing for current decision-making by ensuring the person's goals guide this process. To provide evidence regarding tools and/or practices available for use by health-care providers to effectively facilitate advance care planning conversations and/or goals of care discussions. A systematic review was conducted focusing on guidelines, randomized trials, comparative studies, and noncomparative studies. Databases searched included MEDLINE, EMBASE, and the proceedings of the International Advance Care Planning Conference and the American Society of Clinical Oncology Palliative Care Symposium. Although several studies report positive findings, there is a lack of consistent patient outcome evidence to support any one clinical tool for use in advance care planning or goals of care discussions. Effective advance care planning conversations at both the population and the individual level require provider education and communication skill development, standardized and accessible documentation, quality improvement initiatives, and system-wide coordination to impact the population level. There is a need for research focused on goals of care discussions, to clarify the purpose and expected outcomes of these discussions, and to clearly differentiate goals of care from advance care planning.

  8. Use of technology to support information needs for continuity of operations planning in public health: a systematic review.

    Science.gov (United States)

    Reeder, Blaine; Turner, Anne; Demiris, George

    2010-01-01

    Continuity of operations planning focuses on an organization's ability to deliver essential services before, during and after an emergency. Public health leaders must make decisions based on information from many sources and their information needs are often facilitated or hindered by technology. The aim of this study is to provide a systematic review of studies of technology projects that address public health continuity of operations planning information needs and to discuss patterns, themes, and challenges to inform the design of public health continuity of operations information systems. To return a comprehensive results set in an under-explored area, we searched broadly in the Medline and EBSCOHost bibliographic databases using terms from prior work in public health emergency management and continuity of operations planning in other domains. In addition, we manually searched the citation lists of publications included for review. A total of 320 publications were reviewed. Twenty studies were identified for inclusion (twelve risk assessment decision support tools, six network and communications-enabled decision support tools, one training tool and one dedicated video-conferencing tool). Levels of implementation for information systems in the included studies range from proposed frameworks to operational systems. There is a general lack of documented efforts in the scientific literature for technology projects about public health continuity of operations planning. Available information about operational information systems suggest inclusion of public health practitioners in the design process as a factor in system success.

  9. Office for Analysis and Evaluation of Operational Data. Annual report, 1994-FY 95

    Energy Technology Data Exchange (ETDEWEB)

    None

    1996-07-01

    The United States Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) has published reports of its activities since 1984. The first report covered January through June of 1984, and the second report covered July through December 1984. Since those first two semiannual reports, AEOD has published annual reports of its activities from 1985 through 1993. Beginning with the report for 1986, AEOD Annual Reports have been published as NUREG-1272. Beginning with the report for 1987, NUREG-1272 has been published in two parts, No. 1 covering power reactors and No. 2 covering nonreactors (changed to {open_quotes}nuclear materials{close_quotes} with the 1993 report). The 1993 AEOD Annual Report was NUREG-1272, Volume 8. AEOD has changed its annual report from a calendar year to a fiscal year report to be consistent with the NRC Annual Report and to conserve staff resources. NUREG-1272, Volume 9, No. 1 and No. 2, therefore, are combined calendar year 1994 (1994) and fiscal year 1995 (FY 95) reports which describe activities conducted between January 1, 1994, and September 30, 1995. Certain data which have historically been reported on a calendar year basis, however, are complete through calendar year 1995. Throughout this report, whenever information is presented for fiscal year 1995, it is designated as FY 95 data. Calendar year information is always designated by the four digits of the calendar year. This report, NUREG-1272, Volume 9, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective. NUREG-1272, Vol. 9, No. 2, covers nuclear materials and presents a review of the events and concerns associated with the use of licensed material in non-power reactor applications. A new part has been added, NUREG-1272, Volume 9, No. 3, which covers technical training and presents the activities of the Technical Training Center in FY 95 in support of the NRC`s mission.

  10. Health Workforce Planning

    Science.gov (United States)

    Al-Sawai, Abdulaziz; Al-Shishtawy, Moeness M.

    2015-01-01

    In most countries, the lack of explicit health workforce planning has resulted in imbalances that threaten the capacity of healthcare systems to attain their objectives. This has directed attention towards the prospect of developing healthcare systems that are more responsive to the needs and expectations of the population by providing health planners with a systematic method to effectively manage human resources in this sector. This review analyses various approaches to health workforce planning and presents the Six-Step Methodology to Integrated Workforce Planning which highlights essential elements in workforce planning to ensure the quality of services. The purpose, scope and ownership of the approach is defined. Furthermore, developing an action plan for managing a health workforce is emphasised and a reviewing and monitoring process to guide corrective actions is suggested. PMID:25685381

  11. DOE responses to Ecology review comments for ''Sampling and analysis plans for the 100-D Ponds voluntary remediation project''

    International Nuclear Information System (INIS)

    1996-01-01

    The Sampling and Analysis Plan describes the sampling and analytical activities which will be performed to support closure of the 100-D Ponds at the Hanford Reservation. This report contains responses by the US Department of Energy to Ecology review for ''Sampling and Analysis Plan for the 100-D Ponds Voluntary Remediation Project.''

  12. Web-Based Training on Reviewing Dose Modeling Aspects of NRC Decommissioning and License Termination Plans

    International Nuclear Information System (INIS)

    LePoire, D.; Cheng, J.J.; Kamboj, S.; Arnish, J.; Richmond, P.; Chen, S.Y.; Barr, C.; McKenney, C.

    2008-01-01

    NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course was developed in 2006 and 2007 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while the advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The objective of this course is to train NRC headquarters and regional office staff on how to review sections of a licensee's DP or LTP that pertain to dose modeling. The DP generally refers to the decommissioning of non-reactor facilities, while the LTP refers specifically to the decommissioning of reactors. This review is part of the NRC's licensing process, in which the NRC determines if a licensee has provided a suitable technical basis to support derived concentration guideline levels (DCGLs)1 or dose modeling analyses performed to demonstrate compliance with dose-based license termination rule criteria. This type of training is one component of an organizational management system. These systems 'use a range of practices to identify, create, represent, and distribute knowledge for reuse, awareness and learning'. This is especially important in an organization undergoing rapid change or staff turnover to retain organizational information and processes. NRC is committed to maintaining a dynamic program of training, development, and knowledge transfer to ensure that the NRC acquires and maintains the competencies needed to accomplish its mission. This paper discusses one specific project

  13. Life extension and life cycle management

    International Nuclear Information System (INIS)

    Hoang, H.

    2010-10-01

    To continue the effort of nuclear energy as the clean energy offsetting the increase in greenhouse gas emission that contributes to the increased global warming effect, the nuclear industry is focused on the optimization of their current nuclear generation assets. Plant life extension (Plex) and Plant life management (Plim), together with power up rate, are the key strategies for the optimization effort. Plex begins with the process to obtain the regulatory approval for an additional 20 years of operation, beyond the current 40-year limit. This highly standardized process consists of the following steps: 1) Scoping: identify the systems, structures and components for inclusion in the license renewal scope of work. 2) Screening: narrow down the selection of the in-scope systems, structures and components based on passive and long-lived characteristics. 3) Aging management review: demonstrate that aging effects will continue to be managed during the additional 20 years of operation. 4) Time limiting aging analyses: confirm the acceptability of design bases analyses that assume the 40-year plant life as a key input assumptions. To provide a consistent approach for the preparation of the license renewal application, the following are the key guidance documents: NUREG-1800: Standard review plan; NUREG-1801: Generic aging lessons learned; Nuclear Energy Institute NEI 95-10. The objectives of Plim are to focus on improving plant reliability/availability, and to plan for equipment upgrades for efficiency improvement as well as technological obsolescence. Plim is a technical evaluation combined with a risk assessment to produce a long-range business plant with a time horizon of 10 years or longer. Due to its long view nature, this plan will be reviewed on a yearly basis for any required adjustments. The technical evaluation consists of the following major steps: 1) Select systems, structures and components with performance deficiencies experience. 2) Collect operating data

  14. Nuclear control room modifications and the role of transfer of training principles: a review of issues and research

    International Nuclear Information System (INIS)

    Sawyer, C.R.; Pain, R.F.; Cott, H.V.; Banks, W.W.

    1982-08-01

    This report addresses issues and research related to the implementation of NUREG-0700 . . . specifically, transfer of training considerations associated with control room modifications, retrofits, and general upgrades. The ultimate purpose of this effort is to identify literature and data which would indicate any specific negative effects of instrumentation and control board changes on operator performance, especially under high stress conditions. An exhaustive search for these types of applied technical studies failed to reveal anything substantive due to the lack of definitive applied work in this area. However, a successful review of the theoretical and human performance literature was completed with emphasis placed upon the generalizability of transfer of training studies to control room modification scenarios

  15. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 3

    International Nuclear Information System (INIS)

    Andrews, W.B.; Bickford, W.E.; Counts, C.A.; Gallucci, R.H.V.; Heaberlin, S.W.; Powers, T.B.; Weakley, S.A.

    1985-09-01

    This supplemental report is the fourth in a series that document and use methods developed to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues. The initial report in this series was published by Andrews et al. in 1983 as NUREG/CR-2800. This supplement consists of two parts describing separate research efforts: (1) an alternative human factors methodology approach, and (2) a prioritization of the NRC's Human Factors Program Plan. The alternative human factors methodology approach may be used in specific future cases in which the methods identified in the initial report (NUREG/CR-2800) may not adequately assess the proper impact for resolution of new safety issues. The alternative methodology included in this supplement is entitled ''Methodology for Estimating the Public Risk Reduction Affected by Human Factors Improvement.'' The prioritization section of this report is entitled ''Prioritization of the US Nuclear Regulatory Commission Human Factors Program Plan.''

  16. Job analysis of the instrument and control technician position for the nuclear power plant maintenance personnel reliability model

    International Nuclear Information System (INIS)

    Siegel, A.I.; Bartter, W.D.; Federman, P.J.

    1983-08-01

    This report is one of a series that is planned to describe the results of a program undertaken by the Oak Ridge National Laboratory (ORNL) for the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, to define, develop, validate, and disseminate a methodology for the quantitative prediction of human reliability in the conduct of maintenance tasks in nuclear power plants (NPPs). ORNL has subcontracted portions of this effort to Applied Psychological Services, Inc. This report on the job analysis of the Instrument and Control technician (NUREG/CR-3274) and a report on the job analysis of the electrician position (NUREG/CR-3275) comprise a part of the initial efforts of the development phase of this program. With the publication of the job analysis of the electrician position, the series of job analyses reports addressing nuclear power plant maintenance personnel will be complete. Subsequent reports addressing model development and validation are planned

  17. 77 FR 20582 - Approval and Promulgation of Implementation Plans; State of Florida: New Source Review Prevention...

    Science.gov (United States)

    2012-04-05

    ... quality planning and air pollution control technology requirements. The CAA NSR program is comprised of... protection, Air pollution control, Intergovernmental relations, Ozone, Oxides of nitrogen, Recordkeeping and... preconstruction review program for the construction and modification of any stationary source of air pollution to...

  18. Educational program emergency planning.

    Science.gov (United States)

    Curtis, Tammy

    2009-01-01

    Tragic university shootings have prompted administrators of higher education institutions to re-evaluate their emergency preparedness plans and take appropriate measures for preventing and responding to emergencies. To review the literature and identify key components needed to prevent shootings at higher education institutions in the United States, and in particular, institutions housing radiologic science programs. Twenty-eight emergency preparedness plans were retrieved electronically and reviewed from a convenience sample of accredited radiologic science programs provided by the Joint Review Committee on Education in Radiologic Technology Web site. The review of the 28 emergency preparedness plans confirmed that most colleges are prepared for basic emergencies, but lack the key components needed to successfully address mass-casualty events. Only 5 (18%) of the 28 institutions addressed policies concerning school shootings.

  19. Emergency plan belgian experience

    International Nuclear Information System (INIS)

    Clymans, A.

    1989-01-01

    The Chernobyl disaster prompted authorities in Belgium to carry out a comprehensive review of all emergency plans and, in particular, those designed specifically for nuclear accidents. This review was aimed at determining what type of plans existed and to what extent such plans were operational. This paper sets out to present a broad overview of different aspects of this problem: organization of public emergency plans, co-ordination of operations, merits and demerits of centralization as opposed to decentralization, planning zones, obligation to release information to the public and relations with the media, and finally the international dimension to the problem. The author expresses the hope that the latter area will inspire practical suggestions [fr

  20. Reviewing the quality of strategic environmental assessment reports for English spatial plan core strategies

    International Nuclear Information System (INIS)

    Fischer, Thomas B.

    2010-01-01

    This paper summarises the results of a research project from early 2008, involving the author of this paper, as well as 18 post-graduate University of Liverpool students, in which the quality of European Directive based strategic environmental assessment (SEA) reports of English spatial plan core strategies (conducted within the context of the spatial planning sustainability appraisal-SA-regime) was reviewed. The project aimed at establishing the extensiveness of emerging spatial plan related SEA practice, as well as highlighting shortcomings and problems. Overall, it was found that whilst some aspects of assessment were done well, others were not of a satisfactory quality. Shortcomings were connected particularly with the practice of listing potentially relevant baseline documents and data without distinguishing sufficiently between those that are important in terms of significant impacts and those that are not. Problems were also found to exist with the evaluation of options and impacts, the consideration of substantive aspects, such as health, as well as regarding the formulation of final recommendations and monitoring.

  1. Hybrid MCDA Methods to Integrate Multiple Ecosystem Services in Forest Management Planning: A Critical Review.

    Science.gov (United States)

    Uhde, Britta; Hahn, W Andreas; Griess, Verena C; Knoke, Thomas

    2015-08-01

    Multi-criteria decision analysis (MCDA) is a decision aid frequently used in the field of forest management planning. It includes the evaluation of multiple criteria such as the production of timber and non-timber forest products and tangible as well as intangible values of ecosystem services (ES). Hence, it is beneficial compared to those methods that take a purely financial perspective. Accordingly, MCDA methods are increasingly popular in the wide field of sustainability assessment. Hybrid approaches allow aggregating MCDA and, potentially, other decision-making techniques to make use of their individual benefits and leading to a more holistic view of the actual consequences that come with certain decisions. This review is providing a comprehensive overview of hybrid approaches that are used in forest management planning. Today, the scientific world is facing increasing challenges regarding the evaluation of ES and the trade-offs between them, for example between provisioning and regulating services. As the preferences of multiple stakeholders are essential to improve the decision process in multi-purpose forestry, participatory and hybrid approaches turn out to be of particular importance. Accordingly, hybrid methods show great potential for becoming most relevant in future decision making. Based on the review presented here, the development of models for the use in planning processes should focus on participatory modeling and the consideration of uncertainty regarding available information.

  2. Hybrid MCDA Methods to Integrate Multiple Ecosystem Services in Forest Management Planning: A Critical Review

    Science.gov (United States)

    Uhde, Britta; Andreas Hahn, W.; Griess, Verena C.; Knoke, Thomas

    2015-08-01

    Multi-criteria decision analysis (MCDA) is a decision aid frequently used in the field of forest management planning. It includes the evaluation of multiple criteria such as the production of timber and non-timber forest products and tangible as well as intangible values of ecosystem services (ES). Hence, it is beneficial compared to those methods that take a purely financial perspective. Accordingly, MCDA methods are increasingly popular in the wide field of sustainability assessment. Hybrid approaches allow aggregating MCDA and, potentially, other decision-making techniques to make use of their individual benefits and leading to a more holistic view of the actual consequences that come with certain decisions. This review is providing a comprehensive overview of hybrid approaches that are used in forest management planning. Today, the scientific world is facing increasing challenges regarding the evaluation of ES and the trade-offs between them, for example between provisioning and regulating services. As the preferences of multiple stakeholders are essential to improve the decision process in multi-purpose forestry, participatory and hybrid approaches turn out to be of particular importance. Accordingly, hybrid methods show great potential for becoming most relevant in future decision making. Based on the review presented here, the development of models for the use in planning processes should focus on participatory modeling and the consideration of uncertainty regarding available information.

  3. Kinetics of ethanol decay in mouth- and nose-exhaled breath measured on-line by selected ion flow tube mass spectrometry following varying doses of alcohol

    Czech Academy of Sciences Publication Activity Database

    Smith, D.; Pysanenko, Andriy; Španěl, Patrik

    2010-01-01

    Roč. 24, č. 7 (2010), s. 1066-1074 ISSN 0951-4198 R&D Projects: GA ČR GA202/09/0800 Institutional research plan: CEZ:AV0Z40400503 Keywords : mass spectrometry * blood-alcohol * breath Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 2.846, year: 2010

  4. Making accessibility analyses accessible: A tool to facilitate the public review of the effects of regional transportation plans on accessibility

    OpenAIRE

    Golub, Aaron; Robinson, Glenn; Brendan Nee, Brendan Nee

    2013-01-01

    The regional transportation planning process in the United States has not been easily opened to public oversight even after strengthened requirements for public participation and civil rights considerations. In the effort to improve the public review of regional transportation plans, this paper describes the construction of a proof-of concept web-based tool designed to analyze the effects of regional transportation plans on accessibility to jobs and other essential destinations. The tool allo...

  5. Operational Readiness Review Plan for the Radioisotope Thermoelectric Generator Materials Production Tasks

    Science.gov (United States)

    Cooper, R. H.; Martin, M. M.; Riggs, C. R.; Beatty, R. L.; Ohriner, E. K.; Escher, R. N.

    1990-04-19

    In October 1989, a US shuttle lifted off from Cape Kennedy carrying the spacecraft Galileo on its mission to Jupiter. In November 1990, a second spacecraft, Ulysses, will be launched from Cape Kennedy with a mission to study the polar regions of the sun. The prime source of power for both spacecraft is a series of radioisotope thermoelectric generators (RTGs), which use plutonium oxide (plutonia) as a heat source. Several of the key components in this power system are required to ensure the safety of both the public and the environment and were manufactured at Oak Ridge National Laboratory (ORNL) in the 1980 to 1983 period. For these two missions, Martin Marietta Energy Systems, Inc. (Energy Systems), will provide an iridium alloy component used to contain the plutonia heat source and a carbon composite material that serves as a thermal insulator. ORNL alone will continue to fabricate the carbon composite material. Because of the importance to DOE that Energy Systems deliver these high quality components on time, performance of an Operational Readiness Review (ORR) of these manufacturing activities is necessary. Energy Systems Policy GP 24 entitled "Operational Readiness Process" describes the formal and comprehensive process by which appropriate Energy Systems activities are to be reviewed to ensure their readiness. This Energy System policy is aimed at reducing the risks associated with mission success and requires a management approved "readiness plan" to be issued. This document is the readiness plan for the RTG materials production tasks.

  6. Contribution of PET–CT in radiotherapy planning of oesophageal carcinoma: A review

    International Nuclear Information System (INIS)

    Cheung, Gabriel Sai Man

    2013-01-01

    Purpose: The aim of this study was to systematically review published data on the efficacy of positron emission tomography–computed tomography (PET–CT) in the radiotherapy planning process of patients with oesophageal carcinoma. Methods: A systematic search of the PubMed, CINAHL, Cochrane Library and ScienceDirect databases was performed. The quality of the included studies was appraised using validated assessment tool. Data of the studies were synthesized, compared and evaluated by constructing evidentiary tables. Results: The 37 included studies, comprising a total sample size of 1921 patients, had moderate methodological quality. Overall primary tumour detection rate was 92.7%, and pooling estimate of specificity was 88% (95%CI: 83–91%) for local lymph node metastasis. The pooled studies presented heterogeneity for sensitivity (p < 0.01). The introduction of PET–CT to the radiotherapy planning process has facilitated target volume delineation. A standardized uptake value (SUV) of 2.5 could be used in supplementation to visual assessment by a qualified practitioner. Conclusions: PET–CT has a high specificity but due to its variable sensitivity, information from other clinical investigations should still be sought. Discretion and sound clinical judgment must also be exercised before using the biologic information for radiotherapy planning

  7. Principles of treatment planning for compromised first permanent molars in mixed dentition period: A review article

    Directory of Open Access Journals (Sweden)

    Behrad Tanbakuchi

    2017-02-01

    Full Text Available Background and Aims: The first permanent molar is susceptible to caries, endodontic complications and developmental anomalies. Compromised teeth with poor prognosis could cause the clinician to face dilemmas. The aim of this review article was to assess recent guidelines on the treatment planning of compromised first permanent molars in mixed dentition period. Materials and Methods: The design of the study was based on review of literature by searching the MEDLINE, Web of science and Google scholar. Key words (permanent first molar, extraction, treatment plan were used. This search was limited to the English articles published after the year 2000. Conclusion: A number of factors influenced decision-making process regarding compromised first permanent molars including the restorative status of the tooth, dental age of the patient, degree of crowding and occlusal relationships were assessed. The ideal time for removal of these teeth was 8-9 years of age. However, the current evidence for managing compromised first permanent molars demands clinical trials.

  8. The use of air bags for mitigating grade crossing and trespass accidents : literature review and research plan.

    Science.gov (United States)

    2016-06-01

    This literature review will confirm prior work in the use of locomotive airbag technologies for vehicle or pedestrian collision : mitigation, and to focus planned activities and tasks for this research. The state of the art in relevant technologies h...

  9. Off-site shipment request development and review plan

    International Nuclear Information System (INIS)

    1992-05-01

    On May 17, 1991, Department of Energy Headquarters (DOE-HQ) imposed a moratorium on the shipment of all Resource Conservation and Recovery Act (RCRA) hazardous and Toxic Substances Control Act (TSCA) waste to commercial treatment, storage and disposal facilities. The moratorium was imposed after it was discovered that some shipments of RCRA and TSCA waste from Department of Energy (DOE) sites contained small quantities of radioactive and special nuclear material (SNM). The shipment of these wastes has been attributed to inconsistent and possibly erroneous interpretation of DOE Orders and guidance. In an effort to clarify existing DOE Orders and guidance and establish throughout the DOE complex, June 21, 1991, DOE-HQ issued in draft the Performance Objective for Certification of Non-Radioactive Hazardous Waste. This Performance Objective was subsequently approved on November 15, 1991. The Performance Objective contains specific requirements that must be net to allow the shipment of RCRA and TSCA waste for commercial treatment, storage and disposal. On July 16, 1991, based on the initial draft of the Performance Objective, Martin Marietta Energy Systems (MMES) issued a directive which applies the Performance Objective requirements to all wastes and materials. In addition, this MMES directive imposed the requirement for a review by a Central Waste Management (CWM) Readiness Review Board (RRB). Additional DOE and MMES guidance and directives have been issued since May 17, 1991. This plan applies to all waste destined for shipment from the Portsmouth Gaseous Diffusion Plant (PORTS) to off-site commercial treatment, storage and disposal facilities, and to all materials destined for recycle, surplus and salvage

  10. A study of plasma parameters in hollow cathode plasma jet in pulse regime

    Czech Academy of Sciences Publication Activity Database

    Kudrna, P.; Klusoň, J.; Leshkov, S.; Chichina, M.; Picková, I.; Hubička, Zdeněk; Tichý, M.

    2010-01-01

    Roč. 50, č. 9 (2010), s. 886-891 ISSN 0863-1042 R&D Projects: GA ČR GA202/09/0800 Institutional research plan: CEZ:AV0Z10100522 Keywords : thin-films * system * deposition * RF * nitride Subject RIV: BL - Plasma and Gas Discharge Physics Impact factor: 1.006, year: 2010

  11. ERG and GRG review of the draft of ''preliminary test plan for in situ testing from an exploratory shaft in salt - October 1983''

    International Nuclear Information System (INIS)

    Kalia, H.N.

    1986-03-01

    The Engineering Review Group (ERG) and Geologic Review Group (GRG) were established by the Office of Nuclear Waste Isolation (ONWI) to help evaluate engineering- and geologic-related issues in the US Department of Energy's nuclear waste repository program. The January 1984 meeting of the ERG and GRG reviewed the In Situ Test Plan (ISTP) titled ''Preliminary Test Plan for In Situ Testing From an Exploratory Shaft in Salt - October 1983.'' This report documents the ERG's and GRG's comments and recommendations on this subject and the ONWI responses to the specific points raised by the ERG and GRG. 6 refs., 2 figs., 1 tab

  12. EPA's Review of Concentrated Animal Feeding Operation (CAFO) Permits and Nutrient Management Plans in the Chesapeake Bay Watershed

    Science.gov (United States)

    Starting in 2013, EPA conducted reviews of Concentrated Animal Feeding Operations (CAFOs) permits and nutrient management plans (NMPs) in six of the Bay jurisdictions (Delaware, Maryland, New York, Pennsylvania, Virginia and West Virginia).

  13. Maternal and newborn outcomes in planned home birth vs planned hospital births: a metaanalysis.

    Science.gov (United States)

    Wax, Joseph R; Lucas, F Lee; Lamont, Maryanne; Pinette, Michael G; Cartin, Angelina; Blackstone, Jacquelyn

    2010-09-01

    We sought to systematically review the medical literature on the maternal and newborn safety of planned home vs planned hospital birth. We included English-language peer-reviewed publications from developed Western nations reporting maternal and newborn outcomes by planned delivery location. Outcomes' summary odds ratios with 95% confidence intervals were calculated. Planned home births were associated with fewer maternal interventions including epidural analgesia, electronic fetal heart rate monitoring, episiotomy, and operative delivery. These women were less likely to experience lacerations, hemorrhage, and infections. Neonatal outcomes of planned home births revealed less frequent prematurity, low birthweight, and assisted newborn ventilation. Although planned home and hospital births exhibited similar perinatal mortality rates, planned home births were associated with significantly elevated neonatal mortality rates. Less medical intervention during planned home birth is associated with a tripling of the neonatal mortality rate. Copyright 2010 Mosby, Inc. All rights reserved.

  14. Integrating Enterprise Resource Planning (SAP) in the Accounting Curriculum: A Systematic Literature Review and Case Study

    Science.gov (United States)

    Blount, Yvette; Abedin, Babak; Vatanasakdakul, Savanid; Erfani, Seyedezahra

    2016-01-01

    This study investigates how an enterprise resource planning (ERP) software package SAP was integrated into the curriculum of an accounting information systems (AIS) course in an Australian university. Furthermore, the paper provides a systematic literature review of articles published between 1990 and 2013 to understand how ERP systems were…

  15. Summary of the planning, management, and evaluation process for the Geothermal Program Review VI conference

    Energy Technology Data Exchange (ETDEWEB)

    1988-10-01

    The purpose of this document is to present an overview of the planning, facilitation, and evaluation process used to conduct the Geothermal Program Review VI (PR VI) conference. This document was also prepared to highlight lessons learned from PR VI and, by utilizing the evaluation summaries and recommendations, be used as a planning tool for PR VII. The conference, entitled Beyond Goals and Objectives,'' was sponsored by the US Department of Energy's (DOE) Geothermal Technology Division (GTD), PR VI was held in San Francisco, California on April 19--21, 1988 and was attended by 127 participants. PR VI was held in conjunction with the National Geothermal Association's (NGA) Industry Round Table. This document presents a brief summary of the activities, responsibilities, and resources for implementing the PR VI meeting and provides recommendations, checklists, and a proposed schedule for assisting in planning PR VII.

  16. Conversion of NEK standard technical specifications into improved technical specifications

    International Nuclear Information System (INIS)

    Glaser, B.

    2003-01-01

    Neck is currently using a standard format of operation's Technical Specifications - STS (based on NUREG-0452), which are planned to be converted into Improved Technical Specifications - ITS (based on NUREG-1431). To facilitate the development of individual ITS, each reactor vendor owners group (OG) and the NRC staff developed improved standard TS (ISTS). For Westinghouse plants, the ISTS are published as NUREG-1431, and this document is going to be the basis for the new NEK ITS. It has been recognized that nuclear safety in all plants would benefit from improvement and standardization of ITS, so this was also addressed and recognized by the NRC. There are several plants around Europe and US, which have replaced the format into ITS which brings a lot of improvements and practical value in operations. The main objective of conversion is to completely rewrite, reformat, and streamline the existing STS. Emphasis is placed on human factors principles to improve clarity and understanding. The Bases section will be significantly expanded to clarify and better explain the purpose and foundation of each specification. There might be some proposed changes to the existing STS that deviated from the ITS in NUREG-1431 and constitute a relaxation of the existing STS. Each of these additional proposed changes will be described and evaluated in amendment application and justified on a case-by-case basis. Since the NEK is going to operate for more than 20 year without considering life extension, such conversion will be beneficial for operation personnel as well as regulation, surveillance and focus on operation's safety. At the present, only preliminary plan of STS conversion exists, showing the time frame of approximately 2 years of conversion process and numerous tasks that need to be performed. The plan is to begin with process in year 2004 and finish project in 2006, which means use of new ITS in main control room in year 2007. Beside the main process of conversion, there are

  17. The Effect of Plan Type and Comprehensive Medication Reviews on High-Risk Medication Use.

    Science.gov (United States)

    Almodovar, Armando Silva; Axon, David Rhys; Coleman, Ashley M; Warholak, Terri; Nahata, Milap C

    2018-05-01

    In 2007, the Centers for Medicare & Medicaid Services (CMS) instituted a star rating system using performance outcome measures to assess Medicare Advantage Prescription Drug (MAPD) and Prescription Drug Plan (PDP) providers. To assess the relationship between 2 performance outcome measures for Medicare insurance providers, comprehensive medication reviews (CMRs), and high-risk medication use. This cross-sectional study included Medicare Part C and Part D performance data from the 2014 and 2015 calendar years. Performance data were downloaded per Medicare contract from the CMS. We matched Medicare insurance provider performance data with the enrollment data of each contract. Mann Whitney U and Spearman rho tests and a hierarchical linear regression model assessed the relationship between provider characteristics, high-risk medication use, and CMR completion rate outcome measures. In 2014, an inverse correlation between CMR completion rate and high-risk medication use was identified among MAPD plan providers. This relationship was further strengthened in 2015. No correlation was detected between the CMR completion rate and high-risk medication use among PDP plan providers in either year. A multivariate regression found an inverse association with high-risk medication use among MAPD plan providers in comparison with PDP plan providers in 2014 (beta = -0.358, P plan providers and higher CMR completion rates were associated with lower use of high-risk medications among beneficiaries. No outside funding supported this study. Silva Almodovar reports a fellowship funded by SinfoniaRx, Tucson, Arizona, during the time of this study. The other authors have nothing to disclose.

  18. An automated electronic system for managing radiation treatment plan peer review reduces missed reviews at a large, high-volume academic center.

    Science.gov (United States)

    Gabriel, Peter E; Woodhouse, Kristina D; Lin, Alexander; Finlay, Jarod C; Young, Richard B; Volz, Edna; Hahn, Stephen M; Metz, James M; Maity, Amit

    Assuring quality in cancer care through peer review has become increasingly important in radiation oncology. In 2012, our department implemented an automated electronic system for managing radiation treatment plan peer review. The purpose of this study was to compare the overall impact of this electronic system to our previous manual, paper-based system. In an effort to improve management, an automated electronic system for case finding and documentation of review was developed and implemented. The rates of missed initial reviews, late reviews, and missed re-reviews were compared for the pre- versus postelectronic system cohorts using Pearson χ 2 test and relative risk. Major and minor changes or recommendations were documented and shared with the assigned clinical provider. The overall rate of missed reviews was 7.6% (38/500) before system implementation versus 0.4% (28/6985) under the electronic system (P automated system. Missed re-reviews occurred in 23.1% (3/13) of courses in the preelectronic system cohort and 6.6% (10/152) of courses in the postelectronic system cohort (P = .034). Late reviews were more frequent during high travel or major holiday periods. Major changes were recommended in 2.2% and 2.8% in the pre- versus postelectronic systems, respectively. Minor changes were recommended in 5.3% of all postelectronic cases. The implementation of an automated electronic system for managing peer review in a large, complex department was effective in significantly reducing the number of missed reviews and missed re-reviews when compared to our previous manual system. Copyright © 2016 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

  19. A Literary Review and a Plan for Principals: Extracurricular Activities, Academic Achievement, and Secondary Students' Success.

    Science.gov (United States)

    Reynolds, Richard Kent; Karr-Kidwell, PJ

    Extracurricular activities have enhanced the lives of students through the years and continue to provide students with additional skills they need to succeed in school and life. This paper offers an extensive literature review of the effect of extracurricular activities on student development and offers a plan for extending successful…

  20. Review of off-site emergency preparedness and response plan of Indian NPPs based on experience of Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Singh, Hukum; Dash, M.; Shukla, Vikas; Vijayan, P.; Krishnamurthy, P.R.

    2012-01-01

    Nuclear power plants in India are designed, constructed and operated based on the principle of the highest priority to nuclear safety. To deal with any unlikely situation of radiological emergency, the emergency preparedness and response plans are ensured to be in place at all NPPs prior to their commissioning. These plans are periodically reviewed and tested by conducting emergency exercise with the participation of various agencies such as Nuclear Power Corporation of India Limited, NDMA, district authorities, regulatory body and general public. On March 11, 2011 an earthquake of magnitude 9.0 hit the Fukushima Dai-ichi and Dai-ni followed by tsunami waves of height 15 meters above reference sea level. This resulted in large scale release of radioactive material from Fukushima Dai-ichi NPS. This led to the evacuation of a large number of people from the areas surrounding the affected nuclear power plants. The event was rated as level 7 event in International Nuclear Event Scale (INES). The event also revealed the challenges in handling radiological emergency situation in adverse environmental conditions, The experience of managing radiological emergency situation during Fukushima nuclear accident provides opportunities to review and improve emergency preparedness and response programme. The present paper presents the chronology of the emergency situation, challenges faced and handled in Fukushima. Even though the possibility of a Fukushima type nuclear accident in India is very remote due to the low probability of a high intensity earthquake followed by tsunami at NPP sites, the efforts needs to be initiated from the regulatory point of view for an effective Nuclear and Radiological Emergency Preparedness and Response Plans. The Emergency Preparedness and Response Plans of NPP sites were reviewed in the light of unique challenges of accident at Fukushima. It is realized that multi unit events are the realities that must be addressed as part of Emergency

  1. Review of off-site emergency preparedness and response plan of Indian NPPs based on experience of Fukushima nuclear accident

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Hukum; Dash, M.; Shukla, Vikas; Vijayan, P.; Krishnamurthy, P.R., E-mail: vshukla@aerb.gov.in [Operating Plants Safety Division, Atomic Energy Regulatory Board, Mumbai (India)

    2012-07-01

    Nuclear power plants in India are designed, constructed and operated based on the principle of the highest priority to nuclear safety. To deal with any unlikely situation of radiological emergency, the emergency preparedness and response plans are ensured to be in place at all NPPs prior to their commissioning. These plans are periodically reviewed and tested by conducting emergency exercise with the participation of various agencies such as Nuclear Power Corporation of India Limited, NDMA, district authorities, regulatory body and general public. On March 11, 2011 an earthquake of magnitude 9.0 hit the Fukushima Dai-ichi and Dai-ni followed by tsunami waves of height 15 meters above reference sea level. This resulted in large scale release of radioactive material from Fukushima Dai-ichi NPS. This led to the evacuation of a large number of people from the areas surrounding the affected nuclear power plants. The event was rated as level 7 event in International Nuclear Event Scale (INES). The event also revealed the challenges in handling radiological emergency situation in adverse environmental conditions, The experience of managing radiological emergency situation during Fukushima nuclear accident provides opportunities to review and improve emergency preparedness and response programme. The present paper presents the chronology of the emergency situation, challenges faced and handled in Fukushima. Even though the possibility of a Fukushima type nuclear accident in India is very remote due to the low probability of a high intensity earthquake followed by tsunami at NPP sites, the efforts needs to be initiated from the regulatory point of view for an effective Nuclear and Radiological Emergency Preparedness and Response Plans. The Emergency Preparedness and Response Plans of NPP sites were reviewed in the light of unique challenges of accident at Fukushima. It is realized that multi unit events are the realities that must be addressed as part of Emergency

  2. USI A-43 resolution positions

    International Nuclear Information System (INIS)

    1983-04-01

    NUREG-0869 is comprised of the following documents: Proposed Regulatory Guide 1.82, Revision 1, Sump for Emergency Core Cooling and Containment Spray Systems; The Value-Impact Statement for USI A-43, Containment Emergency Sump Performance; and Background and Summary of Minutes of Meetings of the Committee to Review Generic Requirements Regarding Unresolved Safety Issue A-43 Resolution. The report has been assembled to facilitate obtaining for comment feedback on the position developed for resolution of USI A-43. There are no licensing requirements contained in NUREG-0869, and it should be clearly noted that this for comment report will not be used as interim requirements

  3. Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 Nuclear Island Design (Docket No. 50-447). Supplement No. 3

    International Nuclear Information System (INIS)

    1985-01-01

    Supplement 3 to the Safety Evaluation Report (SER) for the application filed by General Electric Company for the final design approval for the GE BWR/6 nuclear island design has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report supplements the GESSAR II SER (NUREG-0979), issued in April 1983, summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in draft NUREG-1070

  4. Systematic Review of Methods to Determine the Cost-Effectiveness of Monitoring Plans for Chemical and Biological Hazards in the Life Sciences

    NARCIS (Netherlands)

    Focker, M.; Fels-Klerx, van der H.J.; Oude Lansink, A.G.J.M.

    2018-01-01

    This study reviews the methods used to determine the cost-effectiveness of monitoring plans for hazards in animals (diseases), plants (pests), soil, water, food, and animal feed, and assesses their applicability to food safety hazards. The review describes the strengths and weaknesses of each

  5. Review Pages: Planning for Livable and Safe Cities: Energy, Pollution and the Degradation of the Urban Environment

    Directory of Open Access Journals (Sweden)

    Gennaro Angiello

    2016-08-01

    Full Text Available Starting from the relationship between urban planning and mobility management, TeMA has gradually expanded the view of the covered topics, always remaining in the groove of rigorous scientific in-depth analysis. During the last two years a particular attention has been paid on the Smart Cities theme and on the different meanings that come with it. The last section of the journal is formed by the Review Pages. They have different aims: to inform on the problems, trends and evolutionary processes; to investigate on the paths by highlighting the advanced relationships among apparently distant disciplinary fields; to explore the interaction’s areas, experiences and potential applications; to underline interactions, disciplinary developments but also, if present, defeats and setbacks. Inside the journal the Review Pages have the task of stimulating as much as possible the circulation of ideas and the discovery of new points of view. For this reason the section is founded on a series of basic’s references, required for the identification of new and more advanced interactions. These references are the research, the planning acts, the actions and the applications, analysed and investigated both for their ability to give a systematic response to questions concerning the urban and territorial planning, and for their attention to aspects such as the environmental sustainability and the innovation in the practices. For this purpose the Review Pages are formed by five sections (Web Resources; Books; Laws; Urban Practices; News and Events, each of which examines a specific aspect of the broader information storage of interest for TeMA

  6. Palaeoenvironments and palaeoceanography changes across the Jurassic/Cretaceous boundary in the Arctic realm: case study of the Nordvik section (north Siberia, Russia)

    Czech Academy of Sciences Publication Activity Database

    Zakharov, V. A.; Rogov, M. A.; Dzyuba, O. S.; Žák, Karel; Košťák, M.; Pruner, Petr; Skupien, P.; Chadima, Martin; Mazuch, M.; Nikitenko, B. L.

    2014-01-01

    Roč. 33, 25 March (2014) ISSN 0800-0395 R&D Projects: GA ČR GA205/07/1365 Institutional research plan: CEZ:AV0Z30130516 Institutional support: RVO:67985831 Keywords : biodiversity * stable isotopes * J/K boundary * Arctic Realm * palaeoceanography Subject RIV: DB - Geology ; Mineralogy Impact factor: 1.141, year: 2014

  7. Operations research for resource planning and -use in radiotherapy: a literature review.

    Science.gov (United States)

    Vieira, Bruno; Hans, Erwin W; van Vliet-Vroegindeweij, Corine; van de Kamer, Jeroen; van Harten, Wim

    2016-11-25

    The delivery of radiotherapy (RT) involves the use of rather expensive resources and multi-disciplinary staff. As the number of cancer patients receiving RT increases, timely delivery becomes increasingly difficult due to the complexities related to, among others, variable patient inflow, complex patient routing, and the joint planning of multiple resources. Operations research (OR) methods have been successfully applied to solve many logistics problems through the development of advanced analytical models for improved decision making. This paper presents the state of the art in the application of OR methods for logistics optimization in RT, at various managerial levels. A literature search was performed in six databases covering several disciplines, from the medical to the technical field. Papers included in the review were published in peer-reviewed journals from 2000 to 2015. Data extraction includes the subject of research, the OR methods used in the study, the extent of implementation according to a six-stage model and the (potential) impact of the results in practice. From the 33 papers included in the review, 18 addressed problems related to patient scheduling (of which 12 focus on scheduling patients on linear accelerators), 8 focus on strategic decision making, 5 on resource capacity planning, and 2 on patient prioritization. Although calculating promising results, none of the papers reported a full implementation of the model with at least a thorough pre-post performance evaluation, indicating that, apart from possible reporting bias, implementation rates of OR models in RT are probably low. The literature on OR applications in RT covers a wide range of approaches from strategic capacity management to operational scheduling levels, and shows that considerable benefits in terms of both waiting times and resource utilization are likely to be achieved. Various fields can be further developed, for instance optimizing the coordination between the available

  8. Electron beam treatment planning: A review of dose computation methods

    International Nuclear Information System (INIS)

    Mohan, R.; Riley, R.; Laughlin, J.S.

    1983-01-01

    Various methods of dose computations are reviewed. The equivalent path length methods used to account for body curvature and internal structure are not adequate because they ignore the lateral diffusion of electrons. The Monte Carlo method for the broad field three-dimensional situation in treatment planning is impractical because of the enormous computer time required. The pencil beam technique may represent a suitable compromise. The behavior of a pencil beam may be described by the multiple scattering theory or, alternatively, generated using the Monte Carlo method. Although nearly two orders of magnitude slower than the equivalent path length technique, the pencil beam method improves accuracy sufficiently to justify its use. It applies very well when accounting for the effect of surface irregularities; the formulation for handling inhomogeneous internal structure is yet to be developed

  9. Review of nuclear air treatment system related License Event Reports for the period 1985 - 1987

    International Nuclear Information System (INIS)

    Jacox, J.W.

    1989-01-01

    This paper will continue the review of HVAC/NATS related LERS presented at past Air Cleaning Conferences by Dr. D. W. Moeller and his associates. The general approach and format are similar. LER abstracts from mid 1985 through 1987 were reviewed and those related to HVAC/NATS classified and analyzed. The categories were jointly developed by Dr. Moeller, Dr. Casper Sun and myself. In appropriate cases both primary and secondary categories fora problem are given. A basic listing by category and brief statistical review are presented. Additionally a number of categories are discussed in some detail. The categories chosen for specific review are intended to highlight particular problem areas. NUREG/CR-2000 License Event Report (LER) Compilation is the basis for the initial review and coding. In essentially all cases where an LER is classified as of interest the complete LER was obtained and reviewed in full. The intent of this paper is to provide a basis for the industry to document and analyze problem areas that require additional attention. It appears that about 15% of all LERS in the subject period are HVAC/NATS related. This figure is generally consistent with those reported at the 17th DOE Nuclear Air Cleaning Conference. It is hoped that such attention will allow additional resources to be allocated to upgrade systems, procedures and training as well as in some cases government regulation

  10. Advance care planning with individuals experiencing homelessness: Literature review and recommendations for public health practice.

    Science.gov (United States)

    Hubbell, Sarah A

    2017-09-01

    Vulnerable populations in the United States experience disparities in access to advance care planning and may have significant unmet health care needs at the end of life, including unrelieved suffering. People who are homeless have increased morbidity and mortality risks, yet lack opportunities to communicate end-of-life preferences. This paper includes a narrative literature review of advance care planning interventions and qualitative investigations into end-of-life concerns among people experiencing homelessness. Trials of clinician-guided interventions with homeless individuals demonstrated effectiveness in achieving advance directive completion and surrogate decision-maker designation. End-of-life concerns among homeless persons included fears of dying alone, dying unnoticed, or remaining unidentified after death. Research participants also reported concerns regarding burial and notification of family members. Public health practitioners should facilitate advance care planning for people who are homeless by providing opportunities for education and discussion on care options and advance directives. © 2017 Wiley Periodicals, Inc.

  11. Development of the fire PSA methodology and the fire analysis computer code system

    International Nuclear Information System (INIS)

    Katsunori, Ogura; Tomomichi, Ito; Tsuyoshi, Uchida; Yusuke, Kasagawa

    2009-01-01

    Fire PSA methodology has been developed and was applied to NPPs in Japan for power operation and LPSD states. CDFs of preliminary fire PSA for power operation were the higher than that of internal events. Fire propagation analysis code system (CFAST/FDS Network) was being developed and verified thru OECD-PRISME Project. Extension of the scope for LPSD state is planned to figure out the risk level. In order to figure out the fire risk level precisely, the enhancement of the methodology is planned. Verification and validation of phenomenological fire propagation analysis code (CFAST/FDS Network) in the context of Fire PSA. Enhancement of the methodology such as an application of 'Electric Circuit Analysis' in NUREG/CR-6850 and related tests in order to quantify the hot-short effect precisely. Development of seismic-induced fire PSA method being integration of existing seismic PSA and fire PSA methods is ongoing. Fire PSA will be applied to review the validity of fire prevention and mitigation measures

  12. Nuclear waste shipping container response to severe accident conditions, A brief critique of the modal study

    International Nuclear Information System (INIS)

    Audin, L.

    1990-12-01

    The Modal Study (NUREG/CR-4829) attempts to upgrade the analysis of spent nuclear fuel transportation accidents, and to verify the validity of the present regulatory scheme of cask performance standards as a means to minimize risk. While an improvement over many prior efforts in this area (such as NUREG-0170), it unfortunately fails to create a realistic simulation either of a shipping cask, the severe conditions to which it could be subjected, or the potential damage to the spent fuel cargo during an accident. There are too many deficiencies in its analysis to allow acceptance of its results for the presumed cask design, and many pending changes in new containers, cargoes and shipping patterns will limit applicability of the Modal Study to future shipments. In essence, the Modal Study is a good start, but is too simplistic, incomplete, outdated and open to serious question to be used as the basis for any present-day environmental or risk assessment of spent fuel transportation. It needs to be redone, with peer review during its production and experimental verification of its assumptions, before it has any relevance to the shipments planned to Yucca Mountain. Finally, it must be expanded into a full risk assessment by inputing its radiological release fractions and probabilities into a valid dispersal simulation to properly determine the impact of its results. 51 refs

  13. The planning of decommissioning activities within nuclear facilities - Generating a Baseline Decommissioning Plan

    International Nuclear Information System (INIS)

    Meek, N.C.; Ingram, S.; Page, J.

    2003-01-01

    BNFL Environmental Services has developed planning tools to meet the emerging need for nuclear liabilities management and decommissioning engineering both in the UK and globally. It can provide a comprehensive baseline planning service primarily aimed at nuclear power stations and nuclear plant. The paper develops the following issues: Decommissioning planning; The baseline decommissioning plan;The process; Work package; Compiling the information; Deliverables summary; Customer Benefits; - Planning tool for nuclear liability life-cycle management; - Robust and reliable plans based upon 'real' experience; - Advanced financial planning; - Ascertaining risk; - Strategy and business planning. The following Deliverables are mentioned:1. Site Work Breakdown Structure; 2. Development of site implementation strategy from the high level decommissioning strategy; 3. An end point definition for the site; 4. Buildings, operational systems and plant surveys; 5. A schedule of condition for the site; 6. Development of technical approach for decommissioning for each work package; 7. Cost estimate to WBS level 5 for each work package; 8. Estimate of decommissioning waste arisings for each work package; 9. Preparation of complete decommissioning programme in planning software to suit client; 10. Risk modelling of work package and overall project levels; 11. Roll up of costs into an overall cost model; 12. Cash flow, waste profiling and resource profiling against the decommissioning programme; 13. Preparation and issue of Final Report. Finally The BDP process is represented by a flowchart listing the following stages: [Power Station project assigned] → [Review project and conduct Characterisation review of power station] → [Identify work packages] → [Set up WBS to level 3] → [Assign work packages] → [Update WBS to level 4] →[Develop cost model] → [Develop logic network] → [Develop risk management procedure] ] → [Develop project strategy document]→ [Work package

  14. Planning for strategic change? A participative planning approach for community hospitals.

    Science.gov (United States)

    MacDonald, S K; Beange, J E; Blachford, P C

    1992-01-01

    Strategic planning is becoming to hospitals what business case analysis is to private corporations. In fact, this type of planning is becoming essential for the professional management of Ontario hospitals. The participative strategic planning process at Toronto East General Hospital (TEGH) is an example of how a professionally structured and implemented strategic planning process can be successfully developed and implemented in a community hospital. In this article, the environmental factors driving planning are reviewed and the critical success factors for the development and implementation of a strategic plan are examined in the context of TEGH's experience.

  15. A study of the composition of the products of laser-induced breakdown of hexogen, octogen, pentrite and trinitrotoluene using selected ion flow tube mass spectrometry and UV-Vis spectrometry

    Czech Academy of Sciences Publication Activity Database

    Sovová, Kristýna; Dryahina, Kseniya; Španěl, Patrik; Kyncl, M.; Civiš, Svatopluk

    2010-01-01

    Roč. 135, č. 5 (2010), s. 1106-1114 ISSN 0003-2654 R&D Projects: GA AV ČR IAAX00100903; GA ČR GA202/09/0800 Institutional research plan: CEZ:AV0Z40400503 Keywords : hexogen * UV-vis spectrometry * mass spectrometry Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 3.913, year: 2010

  16. Quantification of acetaldehyde and carbon dioxide in the headspace of malignant and non-malignant lung cells in vitro by SIFT-MS

    Czech Academy of Sciences Publication Activity Database

    Sule-Suso, J.; Pysanenko, Andriy; Španěl, Patrik; Smith, D.

    2009-01-01

    Roč. 134, č. 12 (2009), s. 2419-2425 ISSN 0003-2654 R&D Projects: GA ČR GA202/09/0800; GA ČR GA203/09/0256 Institutional research plan: CEZ:AV0Z40400503 Keywords : acetaldehyde * SIFT-MS * carbon dioxide Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 3.272, year: 2009

  17. Volatile compounds in health and disease

    Czech Academy of Sciences Publication Activity Database

    Španěl, Patrik; Smith, D.

    2011-01-01

    Roč. 14, č. 5 (2011), s. 455-460 ISSN 1363-1950 R&D Projects: GA ČR GA202/09/0800; GA ČR GA203/09/0256 Institutional research plan: CEZ:AV0Z40400503 Keywords : acetone * breath analysis * hydrogen Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 4.378, year: 2011

  18. Spektroskopie tabákového kouře

    Czech Academy of Sciences Publication Activity Database

    Pazdera, V.; Fousek, M.; Ferus, Martin; Dryahina, Kseniya; Španěl, Patrik; Shestivska, Violetta; Civiš, Svatopluk

    2011-01-01

    Roč. 61, č. 2 (2011), s. 67-75 ISSN 0009-0700 R&D Projects: GA MŠk 2E08038; GA ČR GA202/09/0800; GA AV ČR IAA400400705 Institutional research plan: CEZ:AV0Z40400503 Keywords : Raman spectroscopy * tobacco smoke * SIFT-MS Subject RIV: CF - Physical ; Theoretical Chemistry

  19. Priorities for Addressing Severe Accident and L3PSA in Radiation Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Jang, M. S.; Kang, H. S.; Kim, S. R. [NESS, Daejeon (Korea, Republic of); Yang, Y. H.; Yoon, Y. I. [KHNP, Daejeon (Korea, Republic of)

    2016-05-15

    Domestic rules for the radiation environment impact assessment were enacted based on NUREG-0555, the guidance to the nuclear regulatory commission staff in implementing provisions of 10 CFR 51, 'environmental protection regulations for domestic licensing and related regulatory functions', related to NPPs. A revised document of NUREG-0555 was published in 2000 as NUREG-1555, Vol. 1 and 2. The related domestic rules would have made some revisions in accordance with NUREG-1555 in 2016. In this paper, we would introduce the new technical standards and review legal and technical issues on legislation. There are three legal and technical issues on revised legislation that includes severe accidents and L3PSA results in RER. First, it may need a regular and continuing education for the severe accident concept, probabilistic assessment method and conservative assumptions for severe accident, how to interpret the assessment results, the probability of a severe accident, SAMA and etc. to obtain the public understanding for severe accident. Second, it needs the development of strategy and technology not only to evaluate the risk of multi-unit accidents and failure case and the impacts of inter-unit shared systems and common events for the probabilistic assessment of severe accidents but also to solve many potential L3PSA challenges. Finally, the cost-beneficial SAMAs analysis would be added in radiation environmental impact and severe accident impact analysis.

  20. Accident Source Terms for Pressurized Water Reactors with High-Burnup Cores Calculated using MELCOR 1.8.5.

    Energy Technology Data Exchange (ETDEWEB)

    Gauntt, Randall O.; Goldmann, Andrew; Kalinich, Donald A.; Powers, Dana A.

    2016-12-01

    analyses. Additionally, current analyses suggest that the NUREG-1465 release fractions are conservative by about a factor of 2 in terms of release fractions and that release durations for in-vessel and late in-vessel release periods are in fact longer than the NUREG-1465 durations. It is currently planned that a subsequent report will further characterize these results using more refined statistical methods, permitting a more precise reformulation of the NUREG-1465 alternative source term for both LBU and HBU fuels, with the most important finding being that the NUREG-1465 formula appears to embody significant conservatism compared to current best-estimate analyses. ACKNOWLEDGEMENTS This work was supported by the United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The authors would like to thank Dr. Ian Gauld and Dr. Germina Ilas, of Oak Ridge National Laboratory, for their contributions to this work. In addition to development of core fission product inventory and decay heat information for use in MELCOR models, their insights related to fuel management practices and resulting effects on spatial distribution of fission products in the core was instrumental in completion of our work.

  1. Review: Improving the Impact of Plant Science on Urban Planning and Design

    Directory of Open Access Journals (Sweden)

    Peter C. Wootton-Beard

    2016-11-01

    Full Text Available Urban planning is a vital process in determining the functionality of future cities. It is predicted that at least two thirds of the world’s citizens will reside in towns and cities by the middle of this century, up from one third in the middle of the previous century. Not only is it essential to provide space for work and dwelling, but also for their well-being. Well-being is inextricably linked with the surrounding environment, and natural landscapes have a potent positive effect. For this reason, the inclusion and management of urban green infrastructure has become a topic of increasing scientific interest. Elements of this infrastructure, including green roofs and façades are of growing importance to operators in each stage of the planning, design and construction process in urban areas. Currently, there is a strong recognition that “green is good”. Despite the positive recognition of urban greenery, and the concerted efforts to include more of it in cities, greater scientific attention is needed to better understand its role in the urban environment. For example, many solutions are cleverly engineered without giving sufficient consideration to the biology of the vegetation that is used. This review contends that whilst “green is good” is a positive mantra to promote the inclusion of urban greenery, there is a significant opportunity to increase the contribution of plant science to the process of urban planning through both green infrastructure, and biomimicry.

  2. Quality Primary Care and Family Planning Services for LGBT Clients: A Comprehensive Review of Clinical Guidelines.

    Science.gov (United States)

    Klein, David A; Malcolm, Nikita M; Berry-Bibee, Erin N; Paradise, Scott L; Coulter, Jessica S; Keglovitz Baker, Kristin; Schvey, Natasha A; Rollison, Julia M; Frederiksen, Brittni N

    2018-04-01

    LGBT clients have unique healthcare needs but experience a wide range of quality in the care that they receive. This study provides a summary of clinical guideline recommendations related to the provision of primary care and family planning services for LGBT clients. In addition, we identify gaps in current guidelines, and inform future recommendations and guidance for clinical practice and research. PubMed, Cochrane, and Agency for Healthcare Research and Quality electronic bibliographic databases, and relevant professional organizations' websites, were searched to identify clinical guidelines related to the provision of primary care and family planning services for LGBT clients. Information obtained from a technical expert panel was used to inform the review. Clinical guidelines meeting the inclusion criteria were assessed to determine their alignment with Institute of Medicine (IOM) standards for the development of clinical practice guidelines and content relevant to the identified themes. The search parameters identified 2,006 clinical practice guidelines. Seventeen clinical guidelines met the inclusion criteria. Two of the guidelines met all eight IOM criteria. However, many recommendations were consistent regarding provision of services to LGBT clients within the following themes: clinic environment, provider cultural sensitivity and awareness, communication, confidentiality, coordination of care, general clinical principles, mental health considerations, and reproductive health. Guidelines for the primary and family planning care of LGBT clients are evolving. The themes identified in this review may guide professional organizations during guideline development, clinicians when providing care, and researchers conducting LGBT-related studies.

  3. Regulatory instrument review: Aging management of LWR cables, containment and basemat, reactor coolant pumps, and motor-operated valves

    International Nuclear Information System (INIS)

    Werry, E.V.; Somasundaram, S.

    1995-09-01

    The results of Stage 2 of the Regulatory Instrument Review are presented in this volume. Selected regulatory instruments, such as the Code of Federal Regulations (CFR), US Nuclear Regulatory Commission (NRC), Regulatory Guides, and ASME Codes, were investigated to determine the extent to which these regulations apply aging management to selected safety-related components in nuclear power plants. The Regulatory Instrument Review was funded by the NRC under the Nuclear Plant Aging Research (NPAR) program. Stage 2 of the review focused on four safety-related structures and components; namely, cables, containment and basemat, reactor coolant pumps, and motor-operated valves. The review suggests that the primary-emphasis of the regulatory instruments was on the design, construction, start-up, and operation of a nuclear power plant, and that aging issues were primarily addressed after an aging-related problem was recognized. This Stage 2 review confirms the results of the prior review; (see Regulatory Instrument Review: Management of Aging of LWR Major Safety-Related Components NUREG/CR-5490. The observations indicate that the regulations generally address management of age-related degradation indirectly. Specific age-related degradation phenomena frequently are dealt with in bulletins and notices or through generic issues, letters, etc. The major recommendation of this report, therefore, is that the regulatory instruments should more directly and explicitly address the aging phenomenon and the management of the age-related degradation process

  4. 77 FR 43405 - Final Standard Review Plan, Branch Technical Position 7-19 on Guidance for Evaluation of...

    Science.gov (United States)

    2012-07-24

    ... in the Standard Review Plan (SRP), Chapter 7, for those standard reactor designs that have not been... methods: Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2010... search, select ``ADAMS Public Documents'' and then select ``Begin Web- based ADAMS Search.'' For problems...

  5. Review and critique of the US Department of Energy environmental program plan for site characterization for a high-level waste repository at Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    1992-01-01

    This report provides a review and critique of the US Department of Energy (DOE) environmental program plan for site characterization activities at Yucca Mountain which principally addresses compliance with federal and state environmental regulation and to a lesser extent monitoring and mitigation of significant adverse impacts and reclamation of disturbed areas. There are 15 documents which comprise the plan and focus on complying with the environmental requirements of the Nuclear Waste Policy Act, as amended, (NWPA) and with single-media environmental statutes and their regulations. All elements of the plan follow from the 1986 statutory environmental assessment (EA) required by NWPA which concluded that no significant adverse impacts would result from characterization of the Yucca Mountain site. The lack of appropriate environmental planning and review for site characterization at Yucca Mountain points to the need for an oversight function by the State of Nevada. It cannot be assumed that on its own DOE will properly comply with environmental requirements, especially the substantive requirements that comprise the intent of NEPA. Thus, procedures must be established to assure that the environmental interests of the State are addressed in the course of the Yucca Mountain Project. Accordingly, steps will be taken by the State of Nevada to review the soundness and efficacy of the DOE field surveys, monitoring and mitigation activities, reclamation actions, and ecological impact studies that follow from the DOE environmental program plans addressed by this review

  6. Review and critique of the US Department of Energy environmental program plan for site characterization for a high-level waste repository at Yucca Mountain, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-31

    This report provides a review and critique of the US Department of Energy (DOE) environmental program plan for site characterization activities at Yucca Mountain which principally addresses compliance with federal and state environmental regulation and to a lesser extent monitoring and mitigation of significant adverse impacts and reclamation of disturbed areas. There are 15 documents which comprise the plan and focus on complying with the environmental requirements of the Nuclear Waste Policy Act, as amended, (NWPA) and with single-media environmental statutes and their regulations. All elements of the plan follow from the 1986 statutory environmental assessment (EA) required by NWPA which concluded that no significant adverse impacts would result from characterization of the Yucca Mountain site. The lack of appropriate environmental planning and review for site characterization at Yucca Mountain points to the need for an oversight function by the State of Nevada. It cannot be assumed that on its own DOE will properly comply with environmental requirements, especially the substantive requirements that comprise the intent of NEPA. Thus, procedures must be established to assure that the environmental interests of the State are addressed in the course of the Yucca Mountain Project. Accordingly, steps will be taken by the State of Nevada to review the soundness and efficacy of the DOE field surveys, monitoring and mitigation activities, reclamation actions, and ecological impact studies that follow from the DOE environmental program plans addressed by this review.

  7. Laser Ablation of FOX-7: Proposed Mechanism of Decomposition

    Czech Academy of Sciences Publication Activity Database

    Civiš, Martin; Civiš, Svatopluk; Sovová, Kristýna; Dryahina, Kseniya; Španěl, Patrik; Kyncl, M.

    2011-01-01

    Roč. 83, č. 3 (2011), s. 1069-1077 ISSN 0003-2700 R&D Projects: GA MPO FT-TA4/124; GA ČR GA202/09/0800 Institutional research plan: CEZ:AV0Z40400503 Keywords : induced breakdown spectroscopy * tube mass spectroscopy * trace gas analysis Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 5.856, year: 2011

  8. Selected ion flow tube, SIFT, studies of the reactions of H3O+, NO+ and O2 + with some biologically active isobaric compounds in preparation for SIFT-MS analyses

    Czech Academy of Sciences Publication Activity Database

    Smith, D.; Chippendale, T. W. E.; Španěl, Patrik

    2011-01-01

    Roč. 303, 2-3 (2011), s. 81-89 ISSN 1387-3806 R&D Projects: GA ČR GA202/09/0800; GA ČR GA203/09/0256 Institutional research plan: CEZ:AV0Z40400503 Keywords : SIFT-MS * ion-molecule reactions * proton transfers Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 2.549, year: 2011

  9. Selected ion flow tube (SIFT) studies of the reactions of H3O+, NO+ and O-2(+center dot) with six volatile phytogenic esters

    Czech Academy of Sciences Publication Activity Database

    Sovová, K.; Dryahina, Kseniya; Španěl, Patrik

    2011-01-01

    Roč. 300, č. 1 (2011), s. 31-38 ISSN 1387-3806 R&D Projects: GA ČR GA202/09/0800; GA ČR GA203/09/0256 Institutional research plan: CEZ:AV0Z40400503 Keywords : SIFT-MS * ion-molecule reactions * plant esters Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 2.549, year: 2011

  10. Analysis of the isobaric compounds propanol, acetic acid and methyl formate in humid air and breath by selected ion flow tube mass spectrometry, SIFT-MS

    Czech Academy of Sciences Publication Activity Database

    Pysanenko, A.; Španěl, Patrik; Smith, D.

    2009-01-01

    Roč. 285, 1-2 (2009), s. 42-48 ISSN 1387-3806 R&D Projects: GA ČR GA203/09/0256; GA ČR GA202/09/0800 Institutional research plan: CEZ:AV0Z40400503 Keywords : SIFT-MS * isobaric compound * propanol * acetic acid Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 2.117, year: 2009

  11. The quantification of carbon dioxide in humid air and exhaled breath by selected ion flow tube mass spectrometry

    Czech Academy of Sciences Publication Activity Database

    Smith, D.; Pysanenko, A.; Španěl, Patrik

    2009-01-01

    Roč. 23, č. 10 (2009), s. 1419-1425 ISSN 0951-4198 R&D Projects: GA ČR GA203/09/0256; GA ČR GA202/09/0800 Institutional research plan: CEZ:AV0Z40400503 Keywords : trace gras-analysis * quantitative analysis * SIFT-MS Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 2.695, year: 2009

  12. Quantification of methane in humid air and exhaled breath using selected ion flow tube mass spectrometry

    Czech Academy of Sciences Publication Activity Database

    Dryahina, Kseniya; Smith, D.; Španěl, Patrik

    2010-01-01

    Roč. 24, č. 9 (2010), s. 1296-1304 ISSN 0951-4198 R&D Projects: GA ČR GP203/09/P172; GA ČR GA202/09/0800 Institutional research plan: CEZ:AV0Z40400503 Keywords : mass spectrometry * SIFT-MS * breath Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 2.846, year: 2010

  13. Ambient analysis of trace compounds in gaseous media by SIFT-MS

    Czech Academy of Sciences Publication Activity Database

    Smith, D.; Španěl, Patrik

    2011-01-01

    Roč. 136, č. 10 (2011), s. 2009-2032 ISSN 0003-2654 R&D Projects: GA ČR GA202/09/0800; GA ČR GA203/09/0256 Institutional research plan: CEZ:AV0Z40400503 Keywords : ion-flow tube * mass spectrometry * SIFT-MS Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 4.230, year: 2011

  14. 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 control rooms as a result of several factors. These include: (1) incorporation of new systems such as safety parameter display systems, (2) backfitting of current control rooms with new technologies when existing hardware is no longer supported by equipment vendors, and (3) development of advanced control room concepts. Control rooms of the future will be developed almost exclusively with advanced instrumentation and controls based upon digital technology. In addition, the control room operator will be interfacing with more intelligent systems which will be capable of providing information processing support to the operator. These developments may have significant implications for plant safety in that they will greatly affect the operator's role in the system as well as the ways in which he interacts with it. At present, however, the only guidance available to the Nuclear Regulatory Commission (NRC) for the review of control room-operator interfaces is NUREG-0700. It is a document which was written prior to these technological changes and is, therefore, tailored to the technologies used in traditional control rooms. Thus, the present guidance needs to be updated since it is inadequate to serve as the basis for NRC staff review of such advanced or hybrid control room designs. The objective of the project reported in this paper is to develop an Advanced Control Room Design Review Guideline suitable for use in performing human factors reviews of advanced operator interfaces. This guideline will take the form of a portable, interactive, computer-based document that may be conveniently used by an inspector in the field, as well as a text-based document

  15. Requantification of the Zion risk profile

    International Nuclear Information System (INIS)

    Park, C.K.; Cazzoli, E.; Lee, M.; Grimshaw, C.; Pratt, W.T.; Unwin, S.D.

    1988-01-01

    In February 1987, a preliminary version of the Zion Study performed at the Brookhaven National Laboratory was published for comment. This analysis provided one of the technical bases for the draft NUREG-1150 document. Since the publication, various comments both upon general technical terms and specific calculational issues were received from industry, the public and various peer review panels. In the light of methodological and modelling deficiencies identified in the draft analysis by both internal and external reviews, extensive modifications to the preliminary Zion study were undertaken in support of the final version of NUREG-1150. The integrated analysis of Zion is a collaborative effort involving Brookhaven National Laboratory (BNL) and Idaho National Engineering Laboratories (INEL). The current paper discusses preliminary results of the requantification efforts in various stages of the Zion back-end analysis performed at BNL. 7 refs., 7 figs., 6 tabs

  16. Recent emergency planning trends in Canada

    International Nuclear Information System (INIS)

    Howieson, J.Q.; Ali, F.B.

    1988-01-01

    Two significant reviews have recently been completed which have affected the approach to emergency planning in Canada. The two reviews have occurred in the province of Ontario where 21 of Canada's 23 reactors are located. Both reviews (one dealing with safety in general, and the other specifically with emergency planning) were performed for the Government of Ontario and were primarily motivated by the severe consequences of the accident at Chernobyl. It was determined that two tiers of emergency planning are needed: (i) the first tier (termed the Maximum Planning Accident or MPA) provides for detailed planning for accidents which can be quantitatively determined to be as low as once in 10 5 station-years. (about once in 10 6 reactor-years for Ontario Hydro's multi-unit sites). For this tier, planning assures public exposure to radioactive doses is kept less than the Protective Action Levels. (ii) the second tier (termed the Worst Credible Radiation Emission or WCRE) provides for planning for accidents which are lower in frequency or whose frequency cannot be quantified (e.g., gross human error or hostile action). For this tier, planning protects against the onset of early morbidity (sickness) and the onset of early mortality (death) in a member of the public

  17. Family planning program: world review 1974. Introduction.

    Science.gov (United States)

    Watson, W B; Lapham, R J

    1975-08-01

    The 1974 Population Conference at Bucharest was marked with controversy between developed and developing countries, with the latter strongly critical of aid for population control but less for social and economic development. The Plan of Action which was finally approved emphasized the importance of social and economic factors in relation to population growth while recommending that couples in all nations should have access to family planning information. Different regions of the world, however, have widely divergent population policies and goals. The Asia-Pacific region of the developing world, which has 3/4 of the population of the developing world, has articulated a strong stance in favor of reducing birth rates at Post-Bucharest Consultation. Government-supported family planning programs are seen as a high priority item to reduce rapid population growth. Rapid population growth is not seen as a high-priority problem in most African, Arab, and Latin American countries. Population problems will be solved with economic and social advancement. There is more concern in Latin America for family planning as a "human right" issue than to promote demographic goals. Latin America was also concerned with migration/urbanization issues. All of the Regional Consultations after Bucharest favored a greater emphasis on population in development planning, concern for the problems caused by migration and urbanization, improvement in the status of women, and support for the reduction of mortality levels. Some 74 countries containing 93% of the population of the developing world, supported family planning, with only 4 populous countries -- Burma, Ethiopia, Peru, and North Korea not in support. More than 98% of the population of Asia lives in countries which support family planning; the figures are 94% for Latin America, 90% for the Middle East and North Africa and 64% for Sub-Saharan Africa. The governments of 39 countries with a combined population of 2.3 billion have stated that

  18. Incentives to promote family planning.

    Science.gov (United States)

    Heil, Sarah H; Gaalema, Diann E; Herrmann, Evan S

    2012-11-01

    Over the past 60 years, population control has become an increasingly urgent issue worldwide as a growing population strains already limited resources. The use of financial incentives to promote family planning is an innovative approach that has potential to make a contribution to efforts to better manage population growth. This report reviews eight studies that examined the effect of incentives on family planning. Published studies that tested the impact of incentives to promote some aspect of family planning and included an appropriate control or comparison condition were reviewed. Incentives have been used to promote attendance at contraceptive education sessions, adoption and continuation of contraceptive methods, sterilization, and to limit family size. All but one of the eight studies reviewed reported positive outcomes, but weaknesses in study design and execution limit the strength of the conclusions that can be drawn. Review of this literature suggests that family planning behaviors, like other behaviors, are sensitive to incentives. Given the tremendous need for efficacious interventions in global efforts to manage population growth, further research on this topic using more rigorous experimental methods is warranted. Copyright © 2012 Elsevier Inc. All rights reserved.

  19. Reanalysis of Zion risk

    International Nuclear Information System (INIS)

    Park, C.K.; Unwin, S.D.; Cazzoli, E.; Tingle, A.; Chun, M.

    1988-01-01

    As part of the NUREG-1150 effort, Brookhaven National Laboratory (BNL) has undertaken a risk analysis of Zion Unit 1 adopting the methodology developed at Sandia National Laboratories (SNL) under the Severe Accident Risk Rebaselining Program. Resulting of the preliminary version of that analysis are reported here. Completion plans for the Zion study are described also

  20. Safety evaluation report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499)

    International Nuclear Information System (INIS)

    1987-01-01

    In April 1986 staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0781) regarding the application of Houston Lighting and Power Company (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. The first supplement to NUREG-0781 was issued in September 1986. This second supplement reports on the status of unresolved items in the Safety Evaluation Report and identifies certain additional items that have since been reviewed by the staff

  1. Planning for land use and conservation: Assessing GIS-based conservation software for land use planning

    Science.gov (United States)

    Rob Baldwin; Ryan Scherzinger; Don Lipscomb; Miranda Mockrin; Susan Stein

    2014-01-01

    Recent advances in planning and ecological software make it possible to conduct highly technical analyses to prioritize conservation investments and inform local land use planning. We review these tools, termed conservation planning tools, and assess the knowledge of a key set of potential users: the land use planning community. We grouped several conservation software...

  2. An Automation Planning Primer.

    Science.gov (United States)

    Paynter, Marion

    1988-01-01

    This brief planning guide for library automation incorporates needs assessment and evaluation of options to meet those needs. A bibliography of materials on automation planning and software reviews, library software directories, and library automation journals is included. (CLB)

  3. Social Licensing in uranium mining: Experiences from the IAEA review of the planned Mukju River Uranium Project, Tanzania

    International Nuclear Information System (INIS)

    Schnell, H.; Hilton, J.; Saint-Pierre, S.; Baldry, K.; Fan, Z.; Tulsidas, H.

    2014-01-01

    The IAEA Uranium Production Site Appraisal Team (UPSAT) programme is designed to assist Member States to enhance the operational performance and the occupational, public and environmental health and safety of uranium mining and processing facilities across all phases of the uranium production cycle. The scope of the appraisal process includes exploration, resource assessment, planning, environmental and social impact assessment, mining, processing, waste management, site management, remediation, and final closure. An UPSAT review was requested in 2010 by the United Republic of Tanzania (URT) to address the challenges the country is currently facing in developing its uranium mining and processing capability for the first time. The review that was carried out from 27 May to 5 June, 2013 had the objective to to appraise URT’s preparedness for overseeing the Uranium Production Cycle in general, at the same time focusing on the planned Mkuju River Project (MRP) in the south of the country in particular. The UPSAT team was tasked to report its findings according to five primary areas: 1. Regulatory system; 2. Sustainable uranium production life cycle; 3. Health, Safety and Environment (HSE); 4. Social licensing; 5. Capacity building. The paper will discuss the key findings and suggestions that were provided to governmental stakeholders and the operater to improve the planned operations. (author)

  4. USNRC regulatory guidance for engineered safety feature air cleaning systems

    International Nuclear Information System (INIS)

    Bellamy, R.R.

    1991-01-01

    The need for clear, technically appropriate, and easily implementable guidance for the design, testing, and maintenance of nuclear air cleaning systems has long been recognized. Numerous industry consensus standards have been issued and revised over the last 30 years. Guidance has also been published by the US Nuclear Regulatory Commission in the form of regulations, regulatory guides, standard review plans, NUREG documents, and information notices. This paper will summarize the latest revisions to these documents and emphasize Regulatory Guide 1.52, Design, Testing, and Maintenance Criteria for Post-Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants, which was last revised in 1978. The USNRC has undertaken a project to revise this regulatory guide, and the status of that revision is highlighted

  5. The theory of planned behaviour and discrete food choices: a systematic review and meta-analysis

    OpenAIRE

    McDermott, M?irt?n S.; Oliver, Madalyn; Svenson, Alexander; Simnadis, Thomas; Beck, Eleanor J.; Coltman, Tim; Iverson, Don; Caputi, Peter; Sharma, Rajeev

    2015-01-01

    The combination of economic and social costs associated with non-communicable diseases provide a compelling argument for developing strategies that can influence modifiable risk factors, such as discrete food choices. Models of behaviour, such as the Theory of Planned Behaviour (TPB) provide conceptual order that allows program designers and policy makers to identify the substantive elements that drive behaviour and design effective interventions. The primary aim of the current review was to ...

  6. Theory of reasoned action and theory of planned behavior-based dietary interventions in adolescents and young adults: a systematic review

    OpenAIRE

    Hackman CL; Knowlden AP

    2014-01-01

    Christine L Hackman, Adam P KnowldenDepartment of Health Science, The University of Alabama, Tuscaloosa, AL, USABackground: Childhood obesity has reached epidemic proportions in many nations around the world. The theory of planned behavior (TPB) and the theory of reasoned action (TRA) have been used to successfully plan and evaluate numerous interventions for many different behaviors. The aim of this study was to systematically review and synthesize TPB and TRA-based dietary behavior interven...

  7. Nationwide Plan Review Phase 2 Report

    National Research Council Canada - National Science Library

    2006-01-01

    .... These events tested the Nation's ability to respond to catastrophic events and demonstrated the importance of ensuring the effectiveness of Federal, State, and local plans and the ability to quickly...

  8. JOINT OPTIMIZATION OF PRODUCTION PLANNING AND VEHICLE ROUTING PROBLEMS: A REVIEW OF EXISTING STRATEGIES

    Directory of Open Access Journals (Sweden)

    Marc Reimann

    2014-05-01

    Full Text Available Keen competition and increasingly demanding customers have forced companies to use their resources more efficiently and to integrate production and transportation planning. In the last few years more and more researchers have also focused on this challenging problem by trying to determine the complexity of the individual problems and then developing fast and robust algorithms to solve them. This paper reviews existing literature on integrated production and distribution decisions at the tactical and operational level, where the distribution part is modelled as some variation of the well-known Vehicle Routing Problem (VRP. The focus is thereby on problems that explicitly consider deliveries to multiple clients in a less-than-truckload fashion. In terms of the production decisions we distinguish in our review between tactical and operational production problems by considering lot-sizing/capacity allocation and scheduling models, respectively.

  9. A review of planning models for maintenance and production.

    NARCIS (Netherlands)

    G. Budai-Balke (Gabriella); R. Dekker (Rommert); R.P. Nicolai (Robin)

    2006-01-01

    textabstractIn this article we give an overview of the relation between planning of maintenance and production. On the one hand we consider production planning and scheduling models in which failures and maintenance aspects are taken into account. Next we discuss the planning of maintenance

  10. 42 CFR 460.132 - Quality assessment and performance improvement plan.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false Quality assessment and performance improvement plan... assessment and performance improvement plan. (a) Basic rule. A PACE organization must have a written quality assessment and performance improvement plan. (b) Annual review. The PACE governing body must review the plan...

  11. 42 CFR 137.365 - What is the procedure for the Secretary's review and approval of project planning and design...

    Science.gov (United States)

    2010-10-01

    ... SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES TRIBAL SELF-GOVERNANCE Construction Roles of the...-Governance Tribe? (a) The Secretary shall review and approve planning documents to ensure compliance with... design documents for general compliance with requirements of the construction project agreement. (b) The...

  12. Regulatory and technical reports. Compilation for second quarter 1982, April to June

    International Nuclear Information System (INIS)

    1982-08-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, and NUREG/CR-XXXX. A detailed explanation of the entries precedes each index

  13. Regulatory and technical reports (abstract index journal). Compilation for third quarter 1984, July-September. Volume 9, No. 3

    International Nuclear Information System (INIS)

    1984-11-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, and NUREG/CR-XXXX. These precede the following indexes: Contractor Report Number, Personal Author, Subject, NRC Originating Organization (Staff Reports), NRC Contract Sponsor (Contractor Reports), Contractor, and Licensed Facility

  14. 78 FR 66023 - National Institute on Alcohol Abuse and Alcoholism; Amended Notice of Meeting

    Science.gov (United States)

    2013-11-04

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health National Institute on Alcohol Abuse and Alcoholism; Amended Notice of Meeting Notice is hereby given of a change in the meeting of the Clinical, Treatment and Health Services Research Review Subcommittee, October 15, 2013, 08:00...

  15. 78 FR 64226 - National Institute on Deafness and Other Communication Disorders; Amended Notice of Meeting

    Science.gov (United States)

    2013-10-28

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health National Institute on Deafness and Other Communication Disorders; Amended Notice of Meeting Notice is hereby given of a change in the meeting of the Communication Disorders Review Committee, October 03, 2013, 08:00 a.m. to October...

  16. 42 CFR 456.523 - Revised UR plan.

    Science.gov (United States)

    2010-10-01

    ... control over the utilization of services; and (2) Conducts reviews in a way that improves the quality of...) MEDICAL ASSISTANCE PROGRAMS UTILIZATION CONTROL Utilization Review Plans: FFP, Waivers, and Variances for Hospitals and Mental Hospitals Ur Plan: Remote Facility Variances from Time Requirements § 456.523 Revised...

  17. 40 CFR 194.5 - Publications incorporated by reference.

    Science.gov (United States)

    2010-07-01

    .... Nuclear Regulatory Commission, NUREG-1297 “Peer Review for High-Level Nuclear Waste Repositories... Characterization of High-Level Nuclear Waste Repositories” (excluding section 2.1 (b) and (c)); IBR approved for... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Publications incorporated by reference...

  18. PROGRESS IN SIFT-MS: BREATH ANALYSIS AND OTHER APPLICATIONS

    Czech Academy of Sciences Publication Activity Database

    Španěl, Patrik; Smith, D.

    2011-01-01

    Roč. 30, č. 2 (2011), s. 236-267 ISSN 0277-7037 R&D Projects: GA MPO FT-TA4/124; GA ČR GA202/09/0800; GA ČR GA203/09/0256 Institutional research plan: CEZ:AV0Z40400503 Keywords : SIFT-MS * breath analysis * ion flow tube Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 10.461, year: 2011

  19. The exposed N-terminal tail of the D1 subunit is required for rapid D1 degradation during Photosystem II repair in Synechocystis sp

    Czech Academy of Sciences Publication Activity Database

    Komenda, Josef; Tichý, Martin; Prášil, Ondřej; Knoppová, Jana; Kuviková, Stanislava; de Vries, R.; Nixon, P. J.

    2007-01-01

    Roč. 19, - (2007), s. 2839-2854 ISSN 1040-4651 R&D Projects: GA MŠk LN00A141; GA ČR GA203/04/0800; GA ČR GA206/06/0322 Institutional research plan: CEZ:AV0Z50200510 Keywords : photosystem II * cyanobacterium * synechocystis sp. pcc 6803 Subject RIV: EE - Microbiology, Virology Impact factor: 9.653, year: 2007

  20. Technical architecture of ONC-approved plans for statewide health information exchange.

    Science.gov (United States)

    Barrows, Randolph C; Ezzard, John

    2011-01-01

    ONC-approved state plans for HIE were reviewed for descriptions and depictions of statewide HIE technical architecture. Review was complicated by non-standard organizational elements and technical terminology across state plans. Findings were mapped to industry standard, referenced, and defined HIE architecture descriptions and characteristics. Results are preliminary due to the initial subset of ONC-approved plans available, the rapid pace of new ONC-plan approvals, and continuing advancements in standards and technology of HIE, etc. Review of 28 state plans shows virtually all include a direct messaging component, but for participating entities at state-specific levels of granularity (RHIO, enterprise, organization/provider). About ½ of reviewed plans describe a federated architecture, and ¼ of plans utilize a single-vendor "hybrid-federated" architecture. About 1/3 of states plan to leverage new federal and open exchange technologies (DIRECT, CONNECT, etc.). Only one plan describes a centralized architecture for statewide HIE, but others combine central and federated architectural approaches.

  1. Improvements to Technical Specifications surveillance requirements

    International Nuclear Information System (INIS)

    Lobel, R.; Tjader, T.R.

    1992-12-01

    In August 1983 an NRC task group was formed to investigate problems with surveillance testing required by Technical Specifications, and to recommend approaches to effect improvements. NUREG-1024 (''Technical Specifications-Enhancing Safety Impact'') resulted, and it contained recommendations to review the basis for test frequencies; to ensure that the tests promote safety and do not degrade equipment; and to review surveillance tests so that they do not unnecessarily burden personnel. The Technical Specifications Improvement Program (TSIP) was established in December 1984 to provide the framework for rewriting and improving the Technical Specifications. As an element of the TSIP, all Technical Specifications surveillance requirements were comprehensively examined as recommended in NUREG-1024. The results of that effort are presented in this report. The study found that while some testing at power is essential to verify equipment and system operability, safety can be improved, equipment degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at power

  2. 23 CFR 1200.25 - Improvement plan.

    Science.gov (United States)

    2010-04-01

    ... 23 Highways 1 2010-04-01 2010-04-01 false Improvement plan. 1200.25 Section 1200.25 Highways... Implementation and Management of the Highway Safety Program § 1200.25 Improvement plan. If a review of the Annual... improvement plan. This plan will detail strategies, program activities, and funding targets to meet the...

  3. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    1991-06-01

    A comprehensive Nuclear Plant Aging Research (NPAR) Program was implemented by the US NRC office of Nuclear Regulatory Research in 1985 to identify and resolve technical safety issues related to the aging of systems, structures, and components in operating nuclear power plants. This is Revision 2 to the Nuclear Plant Aging Research Program Plant. This planes defines the goals of the program the current status of research, and summarizes utilization of the research results in the regulatory process. The plan also describes major milestones and schedules for coordinating research within the agency and with organizations and institutions outside the agency, both domestic and foreign. Currently the NPAR Program comprises seven major areas: (1) hardware-oriented engineering research involving components and structures; (2) system-oriented aging interaction studies; (3) development of technical bases for license renewal rulemaking; (4) determining risk significance of aging phenomena; (5) development of technical bases for resolving generic safety issues; (6) recommendations for field inspection and maintenance addressing aging concerns; (7) and residual lifetime evaluations of major LWR components and structures. The NPAR technical database comprises approximately 100 NUREG/CR reports by June 1991, plus numerous published papers and proceedings that offer regulators and industry important insights to aging characteristics and aging management of safety-related equipment. Regulatory applications include revisions to and development of regulatory guides and technical specifications; support to resolve generic safety issues; development of codes and standards; evaluation of diagnostic techniques; (e.g., for cables and valves); and technical support for development of the license renewal rule. 80 refs., 25 figs., 10 tabs

  4. ECP divisional training: plan 1996

    OpenAIRE

    Storr, Kenneth Mick

    1996-01-01

    The divisional training plan is produced each year at the request of the Joint Training Board (JTB) following a recommendation in the 1991 CERN Training Plan which states that divisions should produce a plan setting out training priorities. This plan presents a review of training activities. a report on ECP progress in implementing the recommendations of the 1995 CERN training plan, a discussion of divisional training objectives, and a summary of training requests generated by the 1996 period...

  5. Answers to frequently asked questions about cleanup activities at Three Mile Island, Unit 2. Public information report

    International Nuclear Information System (INIS)

    1980-09-01

    The document presents answers to frequently asked questions about plans for cleanup and decontamination activities at Three Mile Island, Unit 2. Answers to the questions asked are based on information in the NRC 'Draft Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident, Three Mile Island Nuclear Station, Unit 2' NUREG-0683

  6. Nuclear Regulatory Commission staff development of the license application review plan for a high-level radioactive waste repository

    International Nuclear Information System (INIS)

    Johnson, R.L.; Holonich, J.J.; Lee, M.P.; Delligatti, M.S.

    1993-01-01

    The Nuclear Regulatory Commission staff has recently started a new initiative to develop the License Application Review Plan (LARP) which the staff will use in its reviews of the U.S. Department of Energy's (DOE's) license application (LA) for a geologic repository for the disposal of high-level radioactive waste (HLW). This paper describes the staff's approach for developing the LARP, the development schedule and current status, the organization and content of the LARP, and the staff's LA review strategy. Therefore, it gives a preview of the draft LARP which will be made available in late 1993. It also describes how the LARP will be used as guidance to the staff in conducting reviews of regulatory and technical issues important to the licensing of a geologic repository. Finally, the benefits to the NRC staff, DOE, and other parties are discussed

  7. Digital Architecture Planning Model

    International Nuclear Information System (INIS)

    Oxstrand, Johanna Helene; Al Rashdan, Ahmad Yahya Mohammad; Bly, Aaron Douglas; Rice, Brandon Charles; Fitzgerald, Kirk; Wilson, Keith Leon

    2016-01-01

    As part of the U.S. Department of Energy's Light Water Reactor Sustainability Program, the Digital Architecture (DA) Project focuses on providing a model that nuclear utilities can refer to when planning deployment of advanced technologies. The digital architecture planning model (DAPM) is the methodology for mapping power plant operational and support activities into a DA that unifies all data sources needed by the utilities to operate their plants. The DA is defined as a collection of information technology capabilities needed to support and integrate a wide spectrum of real-time digital capabilities for performance improvements of nuclear power plants. DA can be thought of as integration of the separate instrumentation and control and information systems already in place in nuclear power plants, which are brought together for the purpose of creating new levels of automation in plant work activities. A major objective in DAPM development was to survey all key areas that needed to be reviewed in order for a utility to make knowledgeable decisions regarding needs and plans to implement a DA at the plant. The development was done in two steps. First, researchers surveyed the nuclear industry in order to learn their near-term plans for adopting new advanced capabilities and implementing a network (i.e., wireless and wire) infrastructure throughout the plant, including the power block. Secondly, a literature review covering regulatory documents, industry standards, and technical research reports and articles was conducted. The objective of the review was to identify key areas to be covered by the DAPM, which included the following: 1. The need for a DA and its benefits to the plant 2. Resources required to implement the DA 3. Challenges that need to be addressed and resolved to implement the DA 4. Roles and responsibilities of the DA implementation plan. The DAPM was developed based on results from the survey and the literature review. Model development

  8. Digital Architecture Planning Model

    Energy Technology Data Exchange (ETDEWEB)

    Oxstrand, Johanna Helene [Idaho National Lab. (INL), Idaho Falls, ID (United States). Light Water Reactor Sustainability Program (LWRS); Al Rashdan, Ahmad Yahya Mohammad [Idaho National Lab. (INL), Idaho Falls, ID (United States). Light Water Reactor Sustainability Program (LWRS); Bly, Aaron Douglas [Idaho National Lab. (INL), Idaho Falls, ID (United States). Light Water Reactor Sustainability Program (LWRS); Rice, Brandon Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States). Light Water Reactor Sustainability Program (LWRS); Fitzgerald, Kirk [Idaho National Lab. (INL), Idaho Falls, ID (United States). Light Water Reactor Sustainability Program (LWRS); Wilson, Keith Leon [Idaho National Lab. (INL), Idaho Falls, ID (United States). Light Water Reactor Sustainability Program (LWRS)

    2016-03-01

    As part of the U.S. Department of Energy’s Light Water Reactor Sustainability Program, the Digital Architecture (DA) Project focuses on providing a model that nuclear utilities can refer to when planning deployment of advanced technologies. The digital architecture planning model (DAPM) is the methodology for mapping power plant operational and support activities into a DA that unifies all data sources needed by the utilities to operate their plants. The DA is defined as a collection of information technology capabilities needed to support and integrate a wide spectrum of real-time digital capabilities for performance improvements of nuclear power plants. DA can be thought of as integration of the separate instrumentation and control and information systems already in place in nuclear power plants, which are brought together for the purpose of creating new levels of automation in plant work activities. A major objective in DAPM development was to survey all key areas that needed to be reviewed in order for a utility to make knowledgeable decisions regarding needs and plans to implement a DA at the plant. The development was done in two steps. First, researchers surveyed the nuclear industry in order to learn their near-term plans for adopting new advanced capabilities and implementing a network (i.e., wireless and wire) infrastructure throughout the plant, including the power block. Secondly, a literature review covering regulatory documents, industry standards, and technical research reports and articles was conducted. The objective of the review was to identify key areas to be covered by the DAPM, which included the following: 1. The need for a DA and its benefits to the plant 2. Resources required to implement the DA 3. Challenges that need to be addressed and resolved to implement the DA 4. Roles and responsibilities of the DA implementation plan. The DAPM was developed based on results from the survey and the literature review. Model development, including

  9. Sanitation health risk and safety planning in urban residential ...

    African Journals Online (AJOL)

    The aim of this review paper was to determine the best sanitation health risk and safety planning approach for sustainable management of urban environment. This was achieved by reviewing the concept of sanitation safety planning as a tool. The review adopted exploratory research approach and used secondary data ...

  10. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1996 July--September. Volume 21, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: secondary report number index; personal author index; subject index; NRC originating organization index (staff reports); NRC originating organization index (international agreements); NRC contract sponsor index (contractor reports); contractor index; international organization index; and licensed facility index. A detailed explanation of the entries precedes each index.

  11. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1994, July--September. Volume 19, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    None

    1994-12-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issues by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: Secondary Report Number Index, Personal Author Index, Subject Index, NRC Originating Organization Index (Staff Reports), NRC Originating Organization Index (International Agreements), NRC Contract Sponsor Index (Contractor Reports) Contractor Index, International Organization Index, Licensed Facility Index. A detailed explanation of the entries precedes each index.

  12. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1996 July--September. Volume 21, Number 3

    International Nuclear Information System (INIS)

    1997-02-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: secondary report number index; personal author index; subject index; NRC originating organization index (staff reports); NRC originating organization index (international agreements); NRC contract sponsor index (contractor reports); contractor index; international organization index; and licensed facility index. A detailed explanation of the entries precedes each index

  13. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1994, July--September. Volume 19, Number 3

    International Nuclear Information System (INIS)

    1994-12-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issues by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: Secondary Report Number Index, Personal Author Index, Subject Index, NRC Originating Organization Index (Staff Reports), NRC Originating Organization Index (International Agreements), NRC Contract Sponsor Index (Contractor Reports) Contractor Index, International Organization Index, Licensed Facility Index. A detailed explanation of the entries precedes each index

  14. Safety Evaluation report related to the operation of Braidwood Station, Units 1 and 2 (Docket Nos. STN 50-456 and STN 50-457)

    International Nuclear Information System (INIS)

    1987-07-01

    In November 1983, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-1002) regarding the application filed by the Commonwealth Edison Company, as applicant and owner, for a license to operate Braidwood Station, Units 1 and 2 (Docket Nos. 50-456 and 50-457). The first supplement to NUREG-1002 was issued in September 1986; the second supplement to NUREG-1002 was issued in October 1986; the third supplement to NUREG-1002 was issued in May 1987. This fourth supplement to NUREG-1002 reports the status of certain items that remained unresolved at the time Supplement 3 was published. The facility is located in Reed Township, Will County, Illinois

  15. Scrotal Irradiation in Primary Testicular Lymphoma: Review of the Literature and In Silico Planning Comparative Study

    International Nuclear Information System (INIS)

    Brouwer, Charlotte L.; Wiesendanger, Esther M.; Hulst, Peter C. van der; Imhoff, Gustaaf W. van; Langendijk, Johannes A.; Beijert, Max

    2013-01-01

    We examined adjuvant irradiation of the scrotum in primary testicular lymphoma (PTL) by means of a literature review in MEDLINE, a telephone survey among Dutch institutes, and an in silico planning comparative study on scrotal irradiation in PTL. We did not find any uniform adjuvant irradiation technique assuring a safe planning target volume (PTV) coverage in published reports, and the definition of the clinical target volume is unclear. Histopathologic studies of PTL show a high invasion rate of the tunica albuginea, the epididymis, and the spermatic cord. In retrospective studies, a prescribed dose of at least 30 Gy involving the scrotum is associated with best survival. The majority of Dutch institutes irradiate the whole scrotum without using a planning computed tomography scan, with a single electron beam and a total dose of 30 Gy. The in silico planning comparative study showed that all evaluated approaches met a D 95% scrotal dose of at least 85% of the prescription dose, without exceeding the dose limits of critical organs. Photon irradiation with 2 oblique beams using wedges resulted in the best PTV coverage, with a mean value of 95% of the prescribed dose, with lowest maximum dose. Adjuvant photon or electron irradiation of the whole scrotum including the contralateral testicle with a minimum dose of 30 Gy is recommended in PTL. Computed tomography-based radiation therapy treatment planning with proper patient positioning and position verification guarantees optimal dose coverage.

  16. Fitness for duty in the nuclear power industry: A review of technical issues

    International Nuclear Information System (INIS)

    Moore, C.; Barnes, V.; Hauth, J.

    1989-05-01

    This report presents information gathered and analyzed in support of the US Nuclear Regulatory Commission's (NRC's) efforts to develop a rule that will ensure that workers with unescorted access to protected areas of nuclear power plants are fit for duty. This report supplements information previously published in NUREG/CR-5227, Fitness for Duty in the Nuclear Power Industry: A Review of Technical Issues (Barnes et al., 1988). The primary potential fitness-for-duty concern addressed in both of these reports is impairment caused by substance abuse, although other fitness concerns are discussed. This report addresses issues pertaining to workers' use and misuse of alcohol, prescription drugs, and over-the-counter drugs as fitness-for-duty concerns; responds to several questions raised by NRC Commissioners; discusses subversion of the chemical testing process and methods of preventing such subversion; and examines concerns about the urinalysis cutoff levels used when testing for marijuana metabolites, amphetamines, and phencyclidine

  17. Frequently Asked Questions in Fire Probabilistic Safety Assessment

    International Nuclear Information System (INIS)

    Kang, Dae Il; Kim, Kil Yoo; Park, Gee Yong

    2010-05-01

    The FAQs(Frequently Asked Questions) in the Fire Probabilistic Safety Assessment(FPSA) are the issues occurred during performing the engineering evaluation based on NFPA-805. In this report, the background and resolutions are reviewed and described for 17 FAQs related to FPSA among 57 FAQs. The current FAQs related to FPSA are the issues concerning to NUREG/CR-6850, and are almost resolved but for the some FAQ, the current resolutions would be changed depending on the results of the future or on-going research. Among FAQs related to FPSA, best estimate approaches are suggested concerning to the conservative method of NUREG/CR-6850. If these best estimate solutions are used in the FPSA of nuclear power plants, realistic evaluation results of fire risk would be obtained

  18. Planning Development for a Family Planning Centre in Nursing Unit of the General Hospital of Argolida

    OpenAIRE

    Koukoufilippou J; Koinis A.

    2015-01-01

    Introduction: The family planning centres must be upgraded to a cornerstone of primary health care, and prevent, advise and protect the citizen's health while reducing hospitalization costs for hospitals. Aim: The purpose of this literature review is the family planning centre development in general hospital of Argolida that has a similar clinic. Material and Methods: Literature review was conducted of published English and Greek Articles from bibliographic databases Medline, Goog...

  19. Performance-based ratemaking for electric utilities: Review of plans and analysis of economic and resource-planning issues. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Comnes, G.A.; Stoft, S.; Greene, N. [Lawrence Berkeley Lab., CA (United States). Energy and Environment Div.; Hill, L.J. [Lawrence Berkeley Lab., CA (United States). Energy and Environment Div.]|[Oak Ridge National Lab., TN (United States). Energy Div.

    1995-11-01

    Performance-Based Ratemaking (PBR) is a form of utility regulation that strengthens the financial incentives to lower rates, lower costs, or improve nonprice performance relative traditional regulation, which the authors call cost-of-service, rate-of-return (COS/ROR) regulation. Although the electric utility industry has considerable experience with incentive mechanisms that target specific areas of performance, implementation of mechanisms that cover a comprehensive set of utility costs or services is relatively rare. In recent years, interest in PBR has increased as a result of growing dissatisfaction with COS/ROR and as a result of economic and technological trends that are leading to more competition in certain segments of the electricity industry. In addition, incentive regulation has been used with some success in other public utility industries, most notably telecommunications in the US and telecommunications, energy, and water in the United Kingdom. In this report, the authors analyze comprehensive PBR mechanisms for electric utilities in four ways: (1) they describe different types of PBR mechanisms, (2) they review a sample of actual PBR plans, (3) they consider the interaction of PBR and utility-funded energy efficiency programs, and (4) they examine how PBR interacts with electric utility resource planning and industry restructuring. The report should be of interest to technical staff of utilities and regulatory commissions that are actively considering or designing PBR mechanisms. 16 figs., 17 tabs.

  20. Web-based training related to NRC staff review of dose modeling aspects of license termination and decommissioning plans

    International Nuclear Information System (INIS)

    LePoire, D.; Arnish, J.; Cheng, J.J.; Kamboj, S.; Richmond, P.; Chen, S.Y.; Barr, C.; McKenney, C.

    2007-01-01

    NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course is being developed in 2006 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while the advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The training course consists of the core and advanced modules tailored to specific NRC job functions. Topics for individual modules include identifying the characteristics of simple and complex sites, identifying when outside expertise or consultation is needed, demonstrating how to conduct acceptance and technical reviews of dose modeling, and providing details regarding the level of justification needed for realistic scenarios for both dose modeling and derivation of DCGLs. Various methods of applying probabilistic uncertainty analysis to demonstrate compliance with dose-based requirements are presented. These approaches include: (1) modeling the pathways of radiological exposure and estimating doses to receptors from a combination of contaminated media and radionuclides, and (2) using probabilistic analysis to determine an appropriate set of input parameters to develop derived concentration guideline limits or DCGLs (DCGLs are media- and nuclide-specific concentration limits that will meet dose-based, license termination rule criteria found in 10 CFR Part 20, Subpart E). Calculation of operational (field) DCGL's from media- and nuclide-specific DCGLs and use of operational DCGLs in conducting