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Sample records for nrc staff review

  1. A review of NRC staff uses of probabilistic risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    The NRC staff uses probabilistic risk assessment (PRA) and risk management as important elements its licensing and regulatory processes. In October 1991, the NRC`s Executive Director for Operations established the PRA Working Group to address concerns identified by the Advisory Committee on Reactor Safeguards with respect to unevenness and inconsistency in the staff`s current uses of PRA. After surveying current staff uses of PRA and identifying needed improvements, the Working Group defined a set of basic principles for staff PRA use and identified three areas for improvements: guidance development, training enhancements, and PRA methods development. For each area of improvement, the Working Group took certain actions and recommended additional work. The Working Group recommended integrating its work with other recent PRA-related activities the staff completed and improving staff interactions with PRA users in the nuclear industry. The Working Group took two key actions by developing general guidance for two uses of PRA within the NRC (that is, screening or prioritizing reactor safety issues and analyzing such issues in detail) and developing guidance on basic terms and methods important to the staff`s uses of PRA.

  2. A review of NRC staff uses of probabilistic risk assessment

    International Nuclear Information System (INIS)

    1994-03-01

    The NRC staff uses probabilistic risk assessment (PRA) and risk management as important elements its licensing and regulatory processes. In October 1991, the NRC's Executive Director for Operations established the PRA Working Group to address concerns identified by the Advisory Committee on Reactor Safeguards with respect to unevenness and inconsistency in the staff's current uses of PRA. After surveying current staff uses of PRA and identifying needed improvements, the Working Group defined a set of basic principles for staff PRA use and identified three areas for improvements: guidance development, training enhancements, and PRA methods development. For each area of improvement, the Working Group took certain actions and recommended additional work. The Working Group recommended integrating its work with other recent PRA-related activities the staff completed and improving staff interactions with PRA users in the nuclear industry. The Working Group took two key actions by developing general guidance for two uses of PRA within the NRC (that is, screening or prioritizing reactor safety issues and analyzing such issues in detail) and developing guidance on basic terms and methods important to the staff's uses of PRA

  3. NRC staff review of licensee responses to pressure-locking and thermal-binding issue

    Energy Technology Data Exchange (ETDEWEB)

    Rathbun, H.J.

    1996-12-01

    Commercial nuclear power plant operating experience has indicated that pressure locking and thermal binding represent potential common mode failure mechanisms that can cause safety-related power-operated gate valves to fail in the closed position, thus rendering redundant safety-related systems incapable of performing their safety functions. In Generic Letter (GL) 95-07, {open_quotes}Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves,{close_quotes} the U.S. Nuclear Regulatory Commission (NRC) staff requested that nuclear power plant licensees take certain actions to ensure that valves susceptible to pressure locking or thermal binding are capable of performing their safety functions within the current licensing bases of the facility. The NRC staff has received summary information from licensees in response to GL 95-07 describing actions they have taken to prevent the occurrence of pressure locking and thermal binding. The NRC staff has developed a systematic process to help ensure uniform and consistent review of licensee submittals in response to GL 95-07.

  4. 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

  5. 10 CFR 2.709 - Discovery against NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Discovery against NRC staff. 2.709 Section 2.709 Energy... Rules for Formal Adjudications § 2.709 Discovery against NRC staff. (a)(1) In a proceeding in which the NRC staff is a party, the NRC staff will make available one or more witnesses, designated by the...

  6. 10 CFR 2.1505 - Role of the NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Role of the NRC staff. 2.1505 Section 2.1505 Energy... Legislative Hearings § 2.1505 Role of the NRC staff. The NRC staff shall be available to answer any Commission or presiding officer's questions on staff-prepared documents, provide additional information or...

  7. 10 CFR 51.40 - Consultation with NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Consultation with NRC staff. 51.40 Section 51.40 Energy....40 Consultation with NRC staff. (a) A prospective applicant or petitioner for rulemaking is encouraged to confer with NRC staff as early as possible in its planning process before submitting...

  8. Public comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Volume 1

    International Nuclear Information System (INIS)

    1996-05-01

    This report documents the Nuclear Regulatory Commission (NRC) staff review of public comments provided in response to the NRC's proposed amendments to 10 Code of Federal Regulations (CFR) Part 51, which establish new requirements for the environmental review of applications for the renewal of operating licenses of nuclear power plants. The public comments include those submitted in writing, as well as those provided at public meetings that were held with other Federal agencies, State agencies, nuclear industry representatives, public interest groups, and the general public. This report also contains the NRC staff response to the various concerns raised, and highlights the changes made to the final rule and the supporting documents in response to these concerns

  9. 10 CFR 2.1202 - Authority and role of NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Authority and role of NRC staff. 2.1202 Section 2.1202... ORDERS Informal Hearing Procedures for NRC Adjudications § 2.1202 Authority and role of NRC staff. (a) During the pendency of any hearing under this subpart, consistent with the NRC staff's findings in its...

  10. NRC staff site characterization analysis of the Department of Energy`s Site Characterization Plan, Yucca Mountain Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-08-01

    This Site Characterization Analysis (SCA) documents the NRC staff`s concerns resulting from its review of the US Department of Energy`s (DOE`s) Site Characterization Plan (SCP) for the Yucca Mountain site in southern Nevada, which is the candidate site selected for characterization as the nation`s first geologic repository for high-level radioactive waste. DOE`s SCP explains how DOE plans to obtain the information necessary to determine the suitability of the Yucca Mountain site for a repository. NRC`s specific objections related to the SCP, and major comments and recommendations on the various parts of DOE`s program, are presented in SCA Section 2, Director`s Comments and Recommendations. Section 3 contains summaries of the NRC staff`s concerns for each specific program, and Section 4 contains NRC staff point papers which set forth in greater detail particular staff concerns regarding DOE`s program. Appendix A presents NRC staff evaluations of those NRC staff Consultation Draft SCP concerns that NRC considers resolved on the basis of the SCP. This SCA fulfills NRC`s responsibilities with respect to DOE`s SCP as specified by the Nuclear Waste Policy Act (NWPA) and 10 CFR 60.18. 192 refs., 2 tabs.

  11. 10 CFR 2.1403 - Authority and role of the NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Authority and role of the NRC staff. 2.1403 Section 2.1403... ORDERS Expedited Proceedings with Oral Hearings § 2.1403 Authority and role of the NRC staff. (a) During the pendency of any hearing under this subpart, consistent with the NRC staff's findings in its own...

  12. 10 CFR 2.1316 - Authority and role of NRC staff.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Authority and role of NRC staff. 2.1316 Section 2.1316... ORDERS Procedures for Hearings on License Transfer Applications § 2.1316 Authority and role of NRC staff. (a) During the pendency of any hearing under this subpart, consistent with the NRC staff's findings...

  13. NRC staff site characterization analysis of the Department of Energy's Site Characterization Plan, Yucca Mountain Site, Nevada

    International Nuclear Information System (INIS)

    1989-08-01

    This Site Characterization Analysis (SCA) documents the NRC staff's concerns resulting from its review of the US Department of Energy's (DOE's) Site Characterization Plan (SCP) for the Yucca Mountain site in southern Nevada, which is the candidate site selected for characterization as the nation's first geologic repository for high-level radioactive waste. DOE's SCP explains how DOE plans to obtain the information necessary to determine the suitability of the Yucca Mountain site for a repository. NRC's specific objections related to the SCP, and major comments and recommendations on the various parts of DOE's program, are presented in SCA Section 2, Director's Comments and Recommendations. Section 3 contains summaries of the NRC staff's concerns for each specific program, and Section 4 contains NRC staff point papers which set forth in greater detail particular staff concerns regarding DOE's program. Appendix A presents NRC staff evaluations of those NRC staff Consultation Draft SCP concerns that NRC considers resolved on the basis of the SCP. This SCA fulfills NRC's responsibilities with respect to DOE's SCP as specified by the Nuclear Waste Policy Act (NWPA) and 10 CFR 60.18. 192 refs., 2 tabs

  14. NRC [Nuclear Regulatory Commission] staff evaluation of the General Electric Company Nuclear Reactor Study (''Reed Report'')

    International Nuclear Information System (INIS)

    1987-07-01

    In 1975, the General Electric Company (GE) published a Nuclear Reactor Study, also referred to as ''the Reed Report,'' an internal product-improvement study. GE considered the document ''proprietary'' and thus, under the regulations of the Nuclear Regulatory Commission (NRC), exempt from mandatory public disclosure. Nonetheless, members of the NRC staff reviewed the document in 1976 and determined that it did not raise any significant new safety issues. The staff also reached the same conclusion in subsequent reviews. However, in response to recent inquiries about the report, the staff reevaluated the Reed Report from a 1987 perspective. This re-evaluation, documented in this staff report, concluded that: (1) there are no issues raised in the Reed Report that support a need to curtail the operation of any GE boiling water reactor (BWR); (2) there are no new safety issues raised in the Reed Report of which the staff was unaware; and (3) although certain issues addressed by the Reed Report are still being studied by the NRC and the industry, there is no basis for suspending licensing and operation of GE BWR plants while these issues are being resolved

  15. NRC Enforcement Policy Review, July 1995-July 1997

    International Nuclear Information System (INIS)

    Lieberman, J.; Pedersen, R.M.

    1998-04-01

    On June 30, 1995, the Nuclear Regulatory Commission (NRC) issued a complete revision of its General Statement of Policy and Procedure for Enforcement Action (Enforcement Policy) (60 FR 34381). In approving the 1995 revision to the Enforcement Policy, the Commission directed the staff to perform a review of its implementation of the Policy after approximately 2 years of experience and to consider public comments. This report represents the results of that review

  16. 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)

  17. Review of NRC Regulatory processes and functions

    International Nuclear Information System (INIS)

    1980-01-01

    The Advisory Committee on Reactor Safeguards (ACRS) has spent much time over many years observing and examining the NRC licensing process. The Committee is, consequently, in a position to comment on the situation, and it believes this review will be helpful to those examining the regulatory process by discussing how it works, where it is weak, and the opportunities for improvement. The Committee's review may also help put current proposals and discussions in perspective

  18. NRC systematic evaluation program: seismic review

    International Nuclear Information System (INIS)

    Levin, H.A.

    1980-01-01

    The NRC Systematic Evaluation Program is currently making an assessment of the seismic design safety of 11 older nuclear power plant facilities. The general review philosophy and review criteria relative to seismic input, structural response, and equipment functionability are presented, including the rationale for the development of these guidelines considering the significant evolution of seismic design criteria since these plants were originally licensed. Technical approaches thought more realistic in light of current knowledge are utilized. Initial findings for plants designed to early seismic design procedures suggest that with minor exceptions, these plants possess adequate seismic design margins when evaluated against the intent of current criteria. However, seismic qualification of electrical equipment has been identified as a subject which requires more in-depth evaluation

  19. NRC staff preliminary analysis of public comments on advance notice of proposed rulemaking on emergency planning

    International Nuclear Information System (INIS)

    Peabody, C.A.; Hickey, J.W.N.

    1980-01-01

    The Nuclear Regulatory Commission (NRC) published an advance notice of proposed rulemaking on emergency planning on July 17, 1979 (44 FR 41483). In October and November 1979, the NRC staff submitted several papers to the Commission related to the emergency planning rulemaking. One of these papers was a preliminary analysis of public comments received on the advance notice (SECY-79-591B, November 13, 1979). This document consists of the preliminary analysis as it was submitted to the Commission, with minor editorial changes

  20. Public Comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Appendices

    International Nuclear Information System (INIS)

    1996-05-01

    This volume contains several appendices. Appendix A contains the list of individuals and organizations providing comments at various stages of the rulemaking process. The names of commenters at the public meetings are listed in the order that they spoke at the meeting; those who submitted written comments are listed by docket number. Appendix B contains the summaries of comments made. Each comment summary is identified by a unique comment number. Appendix C presents the concerns and NRC staff responses. Each concern embodies one or more comments on similar or related issues. The associated comment numbers are referenced for each concern. The concerns are organized by topic areas. A three-letter identifier for the topic, followed by a number, is assigned to each concern

  1. Public Comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    This volume contains several appendices. Appendix A contains the list of individuals and organizations providing comments at various stages of the rulemaking process. The names of commenters at the public meetings are listed in the order that they spoke at the meeting; those who submitted written comments are listed by docket number. Appendix B contains the summaries of comments made. Each comment summary is identified by a unique comment number. Appendix C presents the concerns and NRC staff responses. Each concern embodies one or more comments on similar or related issues. The associated comment numbers are referenced for each concern. The concerns are organized by topic areas. A three-letter identifier for the topic, followed by a number, is assigned to each concern.

  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. Amalgamation of performance indicators to support NRC senior management reviews

    International Nuclear Information System (INIS)

    Wreathall, J.; Schurman, D.; Modarres, M.; Mosleh, A.; Anderson, N.; Reason, J.

    1991-01-01

    The purpose of this project is to develop a methodology for amalgamating performance indicators to provide an overall perspective on plant safety, as one input to Nuclear Regulatory Commission's (NRC) senior management reviews of plant safety. These reviews are used to adjust the level of oversight by NRC. Work completed to date includes the development of frameworks for relating indicator measures to safety, a classification scheme for performance indicators, and a mapping process to portray indicators in the frameworks

  5. 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

  6. NRC Consultation and Monitoring at the Savannah River Site: Focusing Reviews of Two Different Disposal Actions - 12181

    Energy Technology Data Exchange (ETDEWEB)

    Ridge, A. Christianne; Barr, Cynthia S.; Pinkston, Karen E.; Parks, Leah S.; Grossman, Christopher J.; Alexander, George W. [U.S. Nuclear Regulatory Commission (United States)

    2012-07-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2011, the NRC staff reviewed DOE performance assessments for tank closure at the F-Tank Farm (FTF) Facility and salt waste disposal at the Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) as part of consultation and monitoring, respectively. Differences in inventories, waste forms, and key barriers led to different areas of focus in the NRC reviews of these two activities at the SRS. Because of the key role of chemically reducing grouts in both applications, the evaluation of chemical barriers was significant to both reviews. However, radionuclide solubility in precipitated metal oxides is expected to play a significant role in FTF performance whereas release of several key radionuclides from the SDF is controlled by sorption or precipitation within the cementitious wasteform itself. Similarly, both reviews included an evaluation of physical barriers to flow, but differences in the physical configurations of the waste led to differences in the reviews. For example, NRC's review of the FTF focused on the modeled degradation of carbon steel tank liners while the staff's review of the SDF performance included a detailed evaluation of the physical degradation of the saltstone wasteform and infiltration-limiting closure cap. Because of the long time periods considered (i.e., tens of thousands of years), the NRC reviews of both facilities included detailed evaluation of the engineered chemical and physical barriers. The NRC staff reviews of residual waste disposal in the FTF and salt waste disposal in the SDF focused on physical barriers to flow and chemical barriers to

  7. NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  8. 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

  9. Applying risk insights in US NRC reviews of integral pressurized water reactor designs

    International Nuclear Information System (INIS)

    Caruso, M.A.; Hilsmeier, T.; Kevern, T.A.

    2012-01-01

    In its Staff Requirements Memorandum (SRM) on COMGBJ-10-0004/COMGEA-10-0001, 'Use of Risk Insights to Enhance Safety Focus of Small Modular Reactor Reviews,' dated August 31, 2010 (ML102510405), the U.S. Nuclear Regulatory Commission (NRC) directed the NRC staff to more fully integrate the use of risk insights into pre-application activities and the review of small modular reactor (SMR) applications with near-term focus on integral pressurized water reactor (iPWR) designs. The Commission's objective is to align the review focus and resources with the risk-significant systems, structures, and components (SSCs) and other aspects of the design, that contribute most to safety in order to enhance the efficiency of the review process while still enabling a decision of reasonable assurance of the design's safety. The staff was directed to develop a design-specific, risk-informed review plan for each SMR to address pre-application and application review activities. The NRC staff submitted a response to the Commission which describes its approach for (1) using risk insights, consistent with current regulatory requirements, to assign SSCs to one of a limited set of graded categories, and (2) adjusting the scope and depth of current review plans--where possible--consistent with regulatory requirements and consistent with the applicable graded category. Because the staff's review constitutes an independent audit of the application, the staff may emphasize or de-emphasize particular aspects of its review guidance (i.e., Standard Review Plan), as appropriate and consistent with regulatory requirements, for the application being reviewed. The staff may propose justifications for not performing certain sections of the reviews called for by the applicable review plan. Examples of acceptable variations in the scope of a review can include reduced emphasis on SSC attributes such as reliability, availability, or functional performance when the SSC will be in the scope of a program

  10. Working draft regulatory guide on release criteria for decommissioning: NRC staff's draft for comment

    International Nuclear Information System (INIS)

    Daily, M.C.; Huffert, A.; Cardile, F.; Malaro, J.C.

    1994-08-01

    The Nuclear Regulatory Commission's (NRC) regulations in 10 CFR 20 are being amended to include radiological criteria for decommissioning of lands and structures at nuclear facilities. 10 CFR Part 20, Subpart E establishes criteria for the remediation of contaminated sites or facilities that will allow their release for future use with or without restrictions. The criteria include a Total Effective Dose Equivalent (TEDE) limit of 15 mrem/year (0.15 mSv/y) that should not be exceeded by an average individual among those who could potentially receive the greatest exposure from any residual activity within a facility or on a site. The criteria also require a licensee to reduce any residual radioactivity to as-low-as-reasonably-achievable (ALARA) levels. This staff draft guide describes acceptable procedures for determining the predicted dose level (PDL) from any residual radioactivity at the site. It describes the basic features of the calculational models and the associated default assumptions and parameter values the NRC staff would find acceptable in calculating PDLs. Appendices A, B, and C provide numerical values that can be used to estimate the dose from residual radioactivity remaining at a site. Since 10 CFR Part 20, Subpart E introduces several new concepts, definitions and discussions are included in a regulatory position concepts section of the guide to assist licensees in understanding some of the philosophy underlying the rule

  11. REVIEW OF NRC APPROVED DIGITAL CONTROL SYSTEMS ANALYSIS

    International Nuclear Information System (INIS)

    Markman, D.W.

    1999-01-01

    Preliminary design concepts for the proposed Subsurface Repository at Yucca Mountain indicate extensive reliance on modern, computer-based, digital control technologies. The purpose of this analysis is to investigate the degree to which the U. S. Nuclear Regulatory Commission (NRC) has accepted and approved the use of digital control technology for safety-related applications within the nuclear power industry. This analysis reviews cases of existing digitally-based control systems that have been approved by the NRC. These cases can serve as precedence for using similar types of digitally-based control technologies within the Subsurface Repository. While it is anticipated that the Yucca Mountain Project (YMP) will not contain control systems as complex as those required for a nuclear power plant, the review of these existing NRC approved applications will provide the YMP with valuable insight into the NRCs review process and design expectations for safety-related digital control systems. According to the YMP Compliance Program Guidance, portions of various NUREGS, Regulatory Guidelines, and nuclear IEEE standards the nuclear power plant safety related concept would be applied to some of the designs on a case-by-case basis. This analysis will consider key design methods, capabilities, successes, and important limitations or problems of selected control systems that have been approved for use in the Nuclear Power industry. An additional purpose of this analysis is to provide background information in support of further development of design criteria for the YMP. The scope and primary objectives of this analysis are to: (1) Identify and research the extent and precedence of digital control and remotely operated systems approved by the NRC for the nuclear power industry. Help provide a basis for using and relying on digital technologies for nuclear related safety critical applications. (2) Identify the basic control architecture and methods of key digital control

  12. 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

  13. Transition from Consultation to Monitoring-NRC's Increasingly Focused Review of Factors Important to F-Area Tank Farm Facility Performance - 13153

    Energy Technology Data Exchange (ETDEWEB)

    Barr, Cynthia; Grossman, Christopher; Alexander, George; Parks, Leah; Fuhrmann, Mark; Shaffner, James; McKenney, Christepher [U.S. NRC, Rockville, MD (United States); Pabalan, Roberto; Pickett, David [Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, San Antonio, TX (United States); Dinwiddie, Cynthia [Southwest Research Institute, San Antonio, TX (United States)

    2013-07-01

    In consultation with the NRC, DOE issued a waste determination for the F-Area Tank Farm (FTF) facility in March 2012. The FTF consists of 22 underground tanks, each 2.8 to 4.9 million liters in capacity, used to store liquid high-level waste generated as a result of spent fuel reprocessing. The waste determination concluded stabilized waste residuals and associated tanks and auxiliary components at the time of closure are not high-level and can be disposed of as LLW. Prior to issuance of the final waste determination, during the consultation phase, NRC staff reviewed and provided comments on DOE's revision 0 and revision 1 FTF PAs that supported the waste determination and produced a technical evaluation report documenting the results of its multi-year review in October 2011. Following issuance of the waste determination, NRC began to monitor DOE disposal actions to assess compliance with the performance objectives in 10 CFR Part 61, Subpart C. To facilitate its monitoring responsibilities, NRC developed a plan to monitor DOE disposal actions. NRC staff was challenged in developing a focused monitoring plan to ensure limited resources are spent in the most cost-effective manner practical. To address this challenge, NRC prioritized monitoring areas and factors in terms of risk significance and timing. This prioritization was informed by NRC staff's review of DOE's PA documentation, independent probabilistic modeling conducted by NRC staff, and NRC-sponsored research conducted by the Center for Nuclear Waste Regulatory Analyses in San Antonio, TX. (authors)

  14. 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...

  15. 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

  16. 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.

  17. NRC review of passive reactor design certification testing programs: Overview, progress, and regulatory perspective

    Energy Technology Data Exchange (ETDEWEB)

    Levin, A.E.

    1995-09-01

    New reactor designs, employing passive safety systems, are currently under development by reactor vendors for certification under the U.S. Nuclear Regulatory Commission`s (NRC`s) design certification rule. The vendors have established testing programs to support the certification of the passive designs, to meet regulatory requirements for demonstration of passive safety system performance. The NRC has, therefore, developed a process for the review of the vendors` testing programs and for incorporation of the results of those reviews into the safety evaluations for the passive plants. This paper discusses progress in the test program reviews, and also addresses unique regulatory aspects of those reviews.

  18. NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapter 1, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

  19. NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapters 2--13, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

  20. NRC overview: Repository QA

    International Nuclear Information System (INIS)

    Kennedy, J.E.

    1988-01-01

    The US Department of Energy (DOE) is on the threshold of an extensive program for characterizing Yucca Mountain in Nevada to determine if it is a suitable site for the permanent disposal of high-level nuclear waste. Earlier this year, the DOE published the Consultation Draft Site Characterization Plan for the Nevada site, which describes in some detail the studies that need to be performed to determine if the site is acceptable. In the near future, the final site characterization plan (SCP) is expected to be issued and large-scale site characterization activities to begin. The data and analyses that will result from the execution of that plan are expected to be the primary basis for the license application to the US Nuclear Regulatory Commission (NRC). Because of the importance of these data and analyses in the assessment of the suitability of the site and in the demonstration of that suitability in the NRC licensing process, the NRC requires in 10CFR60 that site characterization be performed under a quality assurance (QA) program. The QA program is designed to provide confidence that data are valid, retrievable, and reproducible. The documentation produced by the program will form an important part of the record on which the suitability of the site is judged in licensing. In addition, because the NRC staff can review only a selected portion of the data collected, the staff will need to rely on the system of controls in the DOE QA program

  1. Review and critique of April 10, 1985 exercise at the new NRC Operations Center

    International Nuclear Information System (INIS)

    Laats, E.T.; Charlton, T.R.; Bryan, G.R.; Beelman, R.J.; Bray, M.A.; Bethke, G.A.; King, M.A.

    1985-07-01

    An emergency preparedness training exercise was conducted. Objectives of the exercise addressed how well the new Operations Center was utilized when responding to an incident at a nuclear power plant. The simulated accident portrayed a small (approx.75 gpm) leak from the Turkey Point Unit 3 primary coolant system, that led to radionuclide release that exceeded EPA guidelines at the site boundary. The Operation Center response was led by NRC Chairman Nunzio J. Palladino and the roles of the simulated power plant and other outside organizations were jointly portrayed by EG and G Idaho, COMEX Corporation and the NRC's Office of Inspection and Enforcement. Overall, the exercise was successful. The new Operations Center facility provided capabilities and services never before available, which significantly aided the performance of the Operations Center staff. The various teams that manned the Center performed credibly. Substantial improvement in team performance was noted over the past several exercises

  2. 14 CFR 385.33 - Review by the staff.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Review by the staff. 385.33 Section 385.33...) ORGANIZATION STAFF ASSIGNMENTS AND REVIEW OF ACTION UNDER ASSIGNMENTS Procedure on Review of Staff Action § 385.33 Review by the staff. Where a petition for review is duly filed, the staff member may, upon...

  3. 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).

  4. Overview of NRC PRA research program

    International Nuclear Information System (INIS)

    Cunningham, M.A.; Drouin, M.T.; Ramey-Smith, A.M.; VanderMolen, M.T.

    1997-01-01

    The NRC's research program in probabilistic risk analysis includes a set of closely-related elements, from basic research to regulatory applications. The elements of this program are as follows: (1) Development and demonstration of methods and advanced models and tools for use by the NRC staff and others performing risk assessments; (2) Support to agency staff on risk analysis and statistics issues; (3) Reviews of risk assessments submitted by licensees in support of regulatory applications, including the IPEs and IPEEEs. Each of these elements is discussed in the paper, providing highlights of work within an element, and, where appropriate, describing important support and feedback mechanisms among elements

  5. Nuclear regulation. NRC's security clearance program can be strengthened

    International Nuclear Information System (INIS)

    Fultz, Keith O.; Kruslicky, Mary Ann; Bagnulo, John E.

    1988-12-01

    Because of the national security implications of its programs, the Nuclear Regulatory Commission (NRC) investigates the background of its employees and consultants as well as others to ensure that they are reliable and trustworthy. If the investigation indicates that an employee will not endanger national security, NRC grants a security clearance that allows access to classified information, material, and facilities. NRC also requires periodic checks for some clearance holders to ensure their continued clearance eligibility. The Chairman, Subcommittee on Environment, Energy, and Natural Resources, House Committee on Government Operations, asked GAO to review NRC's personnel security clearance program and assess the procedures that NRC uses to ensure that those who operate nuclear power plants do not pose a threat to the public. The Atomic Energy Act of 1954 requires NRC to conduct background investigations of its employees and consultants as well as others who have access to classified information, material, or facilities. To do this, NRC established a personnel security clearance program. Under NRC policies, a security clearance is granted after the Office of Personnel Management (OPM) or the Federal Bureau of Investigation checks the background of those applying for an NRC clearance. NRC also periodically reassesses the integrity of those holding the highest level clearance. NRC employees, consultants, contractors, and licensees as well as other federal employees hold approximately 10,600 NRC clearances. NRC does not grant clearances to commercial nuclear utility employees unless they require access to classified information or special nuclear material. However, the utilities have voluntarily established screening programs to ensure that their employees do not pose a threat to nuclear plants. NRC faces a dilemma when it hires new employees. Although its policy calls for new hires to be cleared before they start work, the security clearance process takes so long

  6. 76 FR 17160 - Office of New Reactors; Final Interim Staff Guidance on the Review of Nuclear Power Plant Designs...

    Science.gov (United States)

    2011-03-28

    ... design certification (DC) application for new nuclear power reactors under Title 10 of the Code of... NUCLEAR REGULATORY COMMISSION [NRC-2010-0033; DC/COL-ISG-021] Office of New Reactors; Final Interim Staff Guidance on the Review of Nuclear Power Plant Designs Using a Gas Turbine Driven Standby...

  7. NRC confirmatory safety system testing in support of AP600 design review

    International Nuclear Information System (INIS)

    Rhee, G.S.; Bessette, D.E.; Shotkin, L.M.

    1994-01-01

    Westinghouse Electric Corporation has submitted the Advanced Passive 600 MWe (AP600) nuclear power plant design to the NRC for design certification. The Office of Nuclear Regulatory Research is proceeding to conduct confirmatory testing to help the NRC staff evaluate the AP600 safety system design. For confirmatory testing, it was determined that the cost-effective route was to modify an existing full-height, full-pressure test facility rather than build a new one. Thus, all the existing integral effects test facilities, both in the US and abroad, were screened to select the best candidate. As a result, the ROSA-V (Rig of Safety Assessment-V) test facility located in the Japan Atomic Energy Research Institute (JAERI) was chosen. However, because of some differences in design between the existing ROSA-V facility and the AP600, the ROSA-V is being modified to conform to the AP600 safety system design. The modification work will be completed by the end of this year. A series of facility characterization tests will then be performed in January 1994 for the modified part of the facility before the main test series is initiated in February 1994. A total of 12 tests will be performed in 1994 under Phase I of this cooperative program with JAERI. Phase II testing is being considered to be conducted in 1995 mainly for beyond-design-basis accident evaluation

  8. 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

  9. NRC review of passive reactor design certification testing programs: Overview and regulatory perspective

    International Nuclear Information System (INIS)

    Levin, A.E.

    1993-01-01

    Reactor vendors are developing new designs for future deployment, including open-quotes passiveclose quotes light water reactors (LWRs), such as General Electric's (G.E.'s) simplified boiling water reactor (SBWR) and Westinghouse's AP600, which depend primarily on inherent processes, such as national convection and gravity feed, for safety injection and emergency core cooling. The U.S. Nuclear Regulatory Commission (NRC) has implemented a new process, certification of standardized reactor designs, for licensing these Plants. Part 52 of Title 10 of the Code of Federal Regulations (10CFR52) contains the requirements that vendors must meet for design certification. One important section, 10CFR52.47, reads open-quotes Certification of a standard design which . . . utilizes simplified, inherent, passive, or other innovative means to accomplish its safety functions will be granted only if: (1) The performance of each safety feature of the design has been demonstrated through either analysis, appropriate test programs, experience, or a combination thereof; (2) Interdependent effects among the safety features have been found acceptable by analysis, appropriate test programs, experience, or a combination thereof; and (3) Sufficient data exist on the safety features of the design to assess the analytical tools used for safety analyses. . . . The vendors have initiated programs to test innovative features of their designs and to develop data bases needed to validate their analytical codes, as required by the design certification rule. Accordingly, the NRC is reviewing and evaluating the vendors programs to ensure that they address adequately key issues concerning safety system performance. This paper provides an overview of the NRC's review process and regulatory perspective

  10. Review of NRC Commission Papers on Regulatory Basis for Licensing and Regulating Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Yeong; Shin, Hyeong Ki [KINS, Daejeon (Korea, Republic of)

    2016-05-15

    Spent nuclear fuel (SNF) accumulated in nuclear power plant has been a serious issue in most countries with operating nuclear power plants. Direct disposal of SNF could be a solution of the problem but many countries including the Republic of Korea have had a hard time selecting a site for high level waste repository because of low public acceptance. SNF recycling technologies consisting of reprocessing and transmutation have been developed so as to reduce the final volume of the disposed radioactive waste and to diminish the radiotoxicity of the waste. The Republic of Korea is now developing pyroprocessing and sodium-cooled fast reactor (SFR) technology to be used for the recycling of the wastes. KAERI has a plan to construct a pyroprocessing facility with a capacity of 30 tHM/y and a facility manufacturing TRU fuel for SFR by 2025. However, to license these facility and secure the safety, the current regulatory system related to SNF treatment needs to be improved and amended since the system has been developed focusing on facilities to examine irradiated nuclear materials. Status of reprocessing facility regulations developed by U.S.NRC was reviewed based on SECY papers. U.S.NRC has approved the development of a new rule referred to nationally as '10CFR Part 7x'. Existing 10CFR 50 and 70 has been evolved mainly for nuclear power plants and fuel cycle facilities whose radiological hazard is much lower than reprocessing plants respectively. U.S.NRC also derived many regulatory gaps including safety assessment methods, technical specification, general design criteria and waste classification and continue to develop the regulatory framework limited in scope to the resolution of Gap 5.

  11. NRC performance indicator program

    International Nuclear Information System (INIS)

    Singh, R.N.

    1987-01-01

    The performance indicator development work of the US Nuclear Regulatory Commission (NRC) interoffice task group involved several major activities that included selection of candidate indicators for a trial program, data collection and review, validation of the trial indicators, display method development, interactions with the industry, and selection of an optimum set of indicators for the program. After evaluating 27 potential indicators against certain ideal attributes, the task group selected 17 for the trial program. The pertinent data for these indicators were then collected from 50 plants at 30 sites. The validation of the indicators consisted of two primary processes: logical validity and statistical analysis. The six indicators currently in the program are scrams, safety system actuations, significant events, safety system failures, forced outage rate, and equipment forced outages per 100 critical hours. A report containing data on the six performance indicators and some supplemental information is issued on a quarterly basis. The NRC staff is also working on refinements of existing indicators and development of additional indicators as directed by the commission

  12. U.S. NRC training for research and training reactor inspectors

    International Nuclear Information System (INIS)

    Sandquist, G.M.; Kunze, J.F.

    2011-01-01

    Currently, a large number of license activities (Early Site Permits, Combined Operating License, reactor certifications, etc.), are pending for review before the United States Nuclear Regulatory Commission (US NRC). Much of the senior staff at the NRC is now committed to these review and licensing actions. To address this additional workload, the NRC has recruited a large number of new Regulatory Staff for dealing with these and other regulatory actions such as the US Fleet of Research and Test Reactors (RTRs). These reactors pose unusual demands on Regulatory Staff since the US Fleet of RTRs, although few (32 Licensed RTRs as of 2010), they represent a broad range of reactor types, operations, and research and training aspects that nuclear reactor power plants (such as the 104 LWRs) do not pose. The US NRC must inspect and regulate all these entities. This paper addresses selected training topics and regulatory activities provided US NRC Inspectors for US RTRs. (author)

  13. Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Environmental monitoring and surveillance programs

    International Nuclear Information System (INIS)

    Denham, D.H.; Stenner, R.D.; Eddy, P.A.; Jaquish, R.E.; Ramsdell, J.V. Jr.

    1988-07-01

    Licensing of a facility for low-level radioactive waste disposal requires the review of the environmental monitoring and surveillance programs. A set of review criteria is recommended for the US Nuclear Regulatory Commission (NRC) staff to use in each monitoring phase---preoperational, operational, and post operational---for evaluating radiological and selected nonradiological parameters in proposed environmental monitoring and surveillance programs at low-level waste disposal facilities. Applicable regulations, industry standards, and technical guidance on low-level radioactive waste are noted throughout the document. In the preoperational phase, the applicant must demonstrate that the environmental monitoring program identifies radiation levels and radionuclide concentrations at the site and also provides adequate basic data on the disposal site. Data recording and statistical analyses for this phase are addressed

  14. Impacts of NRC programs on state and local governments

    International Nuclear Information System (INIS)

    Nussbaumer, D.A.; Lubenau, J.O.

    1983-12-01

    This document reports the results of an NRC staff examination of the impacts of NRC regulatory programs on State and local governments. Twenty NRC programs are identified. For each, the source of the program (e.g., statutory requirement) and NRC funding availability are described and the impacts upon State and local governments are assessed. Recommendations for NRC monitoring and assessing impacts and for enhancing NRC staff awareness of the impacts are offered

  15. Review of utility staff training and certification

    International Nuclear Information System (INIS)

    1999-04-01

    The Advisory Committee on Nuclear Safety (ACNS) has reviewed the nuclear utility training programs in Canada and the Atomic Energy Control Board (AECB) certification program, to determine their effectiveness in meeting current and future needs. It has also looked briefly at the practices in other countries and in the aviation industry in Canada, by way of comparison. While a quantitative measure of effectiveness was beyond the scope of this review, on a purely qualitative basis the ACNS concludes that the current training and certification regime produces qualified operators, but not necessarily in the most effective way. The report makes five recommendations. The thrust of these recommendations is towards a more effective and streamlined training and certification regime based on strict adherence to the Systematic Approach to Training (SAT) methodology combined with independent verification through a peer review and accreditation process. The Committee believes that training and qualification of nuclear power plant operating staff is the complete responsibility of the utilities and that the role of the AECB is to audit the process to ensure that the utilities discharge their responsibility appropriately. In other words, the AECB should deal with operator training and certification in the same way that it deals with other aspects of nuclear power plant operation that are important to health, safety, security and the environment - by inspections and audits. The Committee believes that the proposed regulatory requirement for recertification of certain nuclear power plant operating staff, which would come into effect when the new Regulations are promulgated, is not consistent with the government's thrust and with how the AECB regulates other aspects of nuclear power plant operations. (author)

  16. NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669

    International Nuclear Information System (INIS)

    1994-08-01

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  17. NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669

    International Nuclear Information System (INIS)

    1994-08-01

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  18. COMPOSITION OF STAFF REVIEW ADVISORY BODIES - 2001

    CERN Multimedia

    Seamus Hegarty / HR; Tel. 74128

    2001-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows : Senior Staff Advancement Committee (SSAC) David O. Williams/it (Convener) Cristoforo Benvenuti/est David Plane/ep Technical Engineers & Administrative Careers Committee (TEACC) Sverre Jarp/it (Chairman) Flemming Pedersen/ps Robin Lauckner/sl Christian Roche/ett Lars Leistam/est Dietrich Schinzel/ep Long-term contract Boards (LTCBs) LTCB 1 (Categories 2 & 5a) Tiziano Camporesi/ep [Convener] - Florence Ranjard/ep [Alternate] Jacques Gruber/ps - Peter Sievers/lhc [Alternate] Thomas Pettersson/est - Michel Mayoud/est [Alternate] Sue Foffano/as - Thierry Lagrange/spl [Alternate] Werner Zapf/hr (Secretary) LTCB 2 (Categories 3, 4, 5b & 5c) Véronique Paris/sl [Convener] - Fabien Perriollat/ps [Alternate] Mats Wilhelmsson/st - Véronique Fassnacht/tis [Alternate] Lucie Linssen/ep - Alfredo Placci/ep [Alternate] Patrick Geeraert/fi - John Cuthb...

  19. Composition of Staff Review Advisory Bodies - 2003

    CERN Multimedia

    2003-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows : Senior Staff Advancement Committee (SSAC) David Plane/EP [Convener] Enrico Chiaveri/AB Peter Schmid/EP Technical Engineers & Administrative Careers Committee (TEACC) Robin Lauckner/AB [Chairman]Marcel Mottier/EST Michael Letheren/EP Louis Walckiers/AT Lucie Linssen/EP Mats Wilhelmsson/ST Long-term contract Boards (LTCBs) LTCB 1 (Categories 2 & 5a) Tiziano Camporesi/EP [Convener]Florence Ranjard/EP [Alternate] Roger Bailey/ABPeter Sievers/AT " " Doris Forkel-Wirth/TISPierre Ninin/ST " " Rob Rayson/HRMaarten Wilbers/DSU " " Seamus Hegarty/HR [Secretary] LTCB 2 (Categories 3, 4, 5b & 5c) Véronique Paris/AB [Convener]Fabien Perriollat/AB [Alternate] Christian Lasseur/ESTRamon Folch/EST " " Lucie Linssen/EP Alfredo Placci/EP " " Mats Møller/ASLaszlo Abel/SPL " " Seamus Hegarty/HR [Secretary] Human Resources Division Tel. 74128

  20. COMPOSITION OF STAFF REVIEW ADVISORY BODIES - 2002

    CERN Multimedia

    Human Resources Division

    2002-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows: Senior Staff Advancement Committee (SSAC) Cristoforo BENVENUTI/EST [Convener] David PLANE/EP Peter SCHMID/EP Technical Engineers & Administrative Careers Committee (TEACC) Robin LAUCKNER/SL [Chairman] Flemming PEDERSEN/PS Lucie LINSSEN/EP Dietrich SCHINZEL/EP Marcel MOTTIER/EST Louis WALCKIERS/LHC Long-term contract Boards (LTCBs) (Categories 2 & 5a) Tiziano CAMPORESI/EP [Convener] Florence RANJARD/EP [Alternate] Jacques GRUBER/PS [until 30.6.2002] Roger BAILEY/SL [from 1.7. 2002] Peter SIEVERS/LHC [Alternate] Doris FORKEL-WIRTH/TIS Pierre NININ/ST [Alternate] Sue FOFFANO/AS Maarten WILBERS/DSU [Alternate] Werner ZAPF/HR[Secretary] LTCB 2 Categories 3, 4, 5b & 5c) Véronique PARIS/SL [Convener] Fabien PERRIOLLAT/PS [Alternate] Mats WILHELMSSON/ST Charles NUTTALL/TIS [Alternate] Lucie LINSSEN/EP Alfredo PLACCI/EP [Alternate] Patrick GEERAER...

  1. NRC study of control room habitability

    International Nuclear Information System (INIS)

    Hayes, J.J. Jr.; Muller, D.R.; Gammill, W.P.

    1985-01-01

    Since 1980, the Advisory Committee on Reactor Safeguards (ACRS) has held several meetings with the NRC staff to discuss the subject of control room habitability. Several meetings between the ACRS and the staff have resulted in ACRS letters that express specific concerns, and the staff has provided responses in reports and meetings. In June of 1983, the NRC Executive Director for Operations directed the Offices of Nuclear Reactor Regulation and Inspection and Enforcement to develop a plan to handle the issues raised by the ACRS and to report to him specific proposed courses of action to respond to the ACRS's concerns. The NRC control room habitability working group has reviewed the subject in such areas as NRR review process, transformation of control room habitability designs to as-built systems, and determination of testing protocol. The group has determined that many of the ACRS concerns and recommendations are well founded, and has recommended actions to be taken to address these as well as other concerns which were raised independent of the ACRS. The review has revealed significant areas where the approach presently utilized in reviews should be altered

  2. Staff review of 'Radioecological assessment of the Wyhl nuclear power plant': Analysis of the report prepared by the University of Heidelberg, West Germany. Draft summary report

    International Nuclear Information System (INIS)

    Congel, F.J.; Cardile, F.P.; Zalcman, B.; Pasciak, W.J.; Chu, A.

    1980-06-01

    The Heidelberg Report presents an assessment of the environmental radiological impact of a proposed pressurized-water reactor to be built near Wyhl, West Germany. The assessment is based largely on mathematical models that are used to calculate doses to humans in the area surrounding a reactor site and describe the movement of radioactive materials in the environment. These are the same mathematical models that are used by the U.S. Nuclear Regulatory Commission (NRC) in licensing reactors in the United States. The NRC uses these models to make sure that any radiation exposure due to a reactor is far below national and international recommended 'safe' levels, as well as below natural radiation levels. The NRC staff reviewed certain parts of the Heidelberg Report because the report implied that the NRC may be substantially underestimating doses to individuals living near nuclear power plants by using incorrect values for parameters in the mathematical models. Although the Heidelberg Report assessment is based largely on environmental models described in four NRC Regulatory Guides, the NRC staff's review of the Heidelberg Report indicates that the Heidelberg authors used values for some model parameters that are too high

  3. NRC/UBC Node

    Energy Technology Data Exchange (ETDEWEB)

    Ellis-Perry, B. [Univ. of British Columbia, Vancouver, British Columbia (Canada); Yogendran, Y. [NRC Inst. for Fuel Cell Innovation, Vancouver, British Columbia (Canada)

    2004-07-01

    'Full text:' In the search for cleaner, more sustainable energy sources, many of the most promising breakthroughs have been in hydrogen technology. However, this promise will remain unfulfilled without public interest and enthusiasm, and without the infrastructure to support the technology. In order to get there, we have to test, perfect, and demonstrate technology that is safe and affordable, and we must do so in practical, familiar settings. Ideally, such settings should be easily accessible to the engineers, planners, and architects of tomorrow while providing a showcase for hydrogen technology that will attract the general public. This place is the NRC/UBC Hydrogen Node. The UBC campus in Point Grey is home to leading edge, internationally recognized researchers in a range of disciplines, both within the University and at the NRC Institute for Fuel Cell Innovation. On average, 40,000 students, faculty, and staff use the campus every day; UBC graduates go on to leadership positions in communities around the globe. Its spectacular setting makes UBC a popular destination for thousands of visitors from around the world. In 2006 UBC will host the World Urban Forum, and in 2010 it will be one of the sites for the Vancouver-Whistler Olympic Games. UBC and its South Campus neighbourhoods are developing as a model sustainable community, offering an excellent opportunity to develop and showcase hydrogen infrastructure and technology in a real-life, attractive setting that will be seen by thousands of people around the world. UBC's facilities, location, and Trek 2010 commitment to excellence in learning, research, and sustainability make it an ideal location for such a project. The H2 Village at UBC will be an integrated hydrogen demonstration project, linked to the hydrogen highway. This project is bringing together leading companies, researchers, and government agencies committed to making the refinement and early adoption of safe hydrogen technology a

  4. NRC/UBC Node

    International Nuclear Information System (INIS)

    Ellis-Perry, B.; Yogendran, Y.

    2004-01-01

    'Full text:' In the search for cleaner, more sustainable energy sources, many of the most promising breakthroughs have been in hydrogen technology. However, this promise will remain unfulfilled without public interest and enthusiasm, and without the infrastructure to support the technology. In order to get there, we have to test, perfect, and demonstrate technology that is safe and affordable, and we must do so in practical, familiar settings. Ideally, such settings should be easily accessible to the engineers, planners, and architects of tomorrow while providing a showcase for hydrogen technology that will attract the general public. This place is the NRC/UBC Hydrogen Node. The UBC campus in Point Grey is home to leading edge, internationally recognized researchers in a range of disciplines, both within the University and at the NRC Institute for Fuel Cell Innovation. On average, 40,000 students, faculty, and staff use the campus every day; UBC graduates go on to leadership positions in communities around the globe. Its spectacular setting makes UBC a popular destination for thousands of visitors from around the world. In 2006 UBC will host the World Urban Forum, and in 2010 it will be one of the sites for the Vancouver-Whistler Olympic Games. UBC and its South Campus neighbourhoods are developing as a model sustainable community, offering an excellent opportunity to develop and showcase hydrogen infrastructure and technology in a real-life, attractive setting that will be seen by thousands of people around the world. UBC's facilities, location, and Trek 2010 commitment to excellence in learning, research, and sustainability make it an ideal location for such a project. The H2 Village at UBC will be an integrated hydrogen demonstration project, linked to the hydrogen highway. This project is bringing together leading companies, researchers, and government agencies committed to making the refinement and early adoption of safe hydrogen technology a reality

  5. Presentation on NRC Regulatory Positions and guidelines

    International Nuclear Information System (INIS)

    Russell, W.T.

    1994-01-01

    The NRC staff recognizes the potential for enhanced safety and reliability that digital systems bring to the nuclear industry. The staff also recognizes the challenges to safety that are unique to digital systems implementation

  6. The impact of staff training on staff outcomes in dementia care: a systematic review.

    Science.gov (United States)

    Spector, Aimee; Revolta, Catherine; Orrell, Martin

    2016-11-01

    Caring for people with dementia can be emotionally challenging and is often linked to low job satisfaction and burnout in care staff. Staff training within care settings is potentially valuable in improving well-being and quality of care. This review aimed to (i) establish the impact of training on staff outcomes; (ii) compare the impact of different training approaches; (iii) explore the influence of training intensity; and (iv) explore potential barriers to success. A database search of staff training interventions revealed 207 papers, 188 of which were excluded based on prespecified criteria. Nineteen studies were included and appraised using a quality rating tool. Overall, the studies were found to be of variable quality; however, 16 studies found a significant change following training in at least one staff domain, with knowledge improving most frequently. Approaches focusing on managing challenging behaviours appeared to be the most effective. Training staff can be an effective method of improving well-being, and programmes helping staff to manage challenging behaviour appear to be the most beneficial. There is no clear relationship between training intensity and outcome. Most studies point to the importance of addressing organisational factors as a barrier to change. Copyright © 2016 John Wiley & Sons, Ltd. Copyright © 2016 John Wiley & Sons, Ltd.

  7. NRC performance assessment program

    International Nuclear Information System (INIS)

    Coplan, S.M.

    1986-01-01

    The U.S. Nuclear Regulatory Commission's (NRC) performance assessment program includes the development of guidance to the U.S. Department of Energy (DOE) on preparation of a license application and on conducting the studies to support a license application. The nature of the licensing requirements of 10 CFR Part 60 create a need for performance assessments by the DOE. The NRC and DOE staffs each have specific roles in assuring the adequacy of those assessments. Performance allocation is an approach for determining what testing and analysis will be needed during site characterization to assure that an adequate data base is available to support the necessary performance assessments. From the standpoint of establishing is implementable methodology, the most challenging performance assessment needed for licensing is the one that will be used to determine compliance with the U.S. Environmental Protection Agency's (EPA) containment requirement

  8. IRIS and the National Research Council (NRC)

    Science.gov (United States)

    Since the 2011 National Academies’ National Research Council (NRC) review of the IRIS Program's assessment of Formaldehyde, EPA and NRC have had an ongoing relationship into the improvements of developing the IRIS Assessments.

  9. Staff nurses as antimicrobial stewards: An integrative literature review.

    Science.gov (United States)

    Monsees, Elizabeth; Goldman, Jennifer; Popejoy, Lori

    2017-08-01

    Guidelines on antimicrobial stewardship emphasize the importance of an interdisciplinary team, but current practice focuses primarily on defining the role of infectious disease physicians and pharmacists; the role of inpatient staff nurses as antimicrobial stewards is largely unexplored. An updated integrative review method guided a systematic appraisal of 13 articles spanning January 2007-June 2016. Quantitative and qualitative peer-reviewed publications including staff nurses and antimicrobial knowledge or stewardship were incorporated into the analysis. Two predominant themes emerged from this review: (1) nursing knowledge, education, and information needs; and (2) patient safety and organizational factors influencing antibiotic management. Focused consideration to empower and educate staff nurses in antimicrobial management is needed to strengthen collaboration and build an interprofessional stewardship workforce. Further exploration on the integration and measurement of nursing participation is needed to accelerate this important patient safety initiative. Copyright © 2017 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Elsevier Inc. All rights reserved.

  10. Effects of patient death on nursing staff: a literature review.

    Science.gov (United States)

    Wilson, Janet; Kirshbaum, Marilyn

    There were 509090 deaths recorded in England and Wales for 2008 (Office for National Statistics, 2010); of these, over 56% (260000) occurred in NHS hospitals. The death of a patient is an event that most, if not all, nursing staff will encounter during their work. This experience can elicit physical, cognitive, behavioural, spiritual and emotional responses (Parkes, 1998). The aim of this literature review is to explore how the death of patients in a hospital setting impact on nursing staff. A review of the literature was undertaken using the online databases CINAHL, Medline and PsychInfo. The search was limited to articles in the English language and those from peer-reviewed journals. Themes arising from the literature review included: the theoretical context; the emotional impact; the culture of the healthcare setting; staff's previous life experiences; and support available for healthcare staff. The death of patients does have an impact on nurses. This can affect them both in their work environment and outside of work. Education around grief theory and support from others are helpful for staff in developing strategies for coping with patient deaths.

  11. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-03-01

    Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase future decommissioning needs, the NRC staff began an in-depth review and re-evaluation of NRC's regulatory approach to decommissioning in 1975. Major technical studies on decommissioning have been initiated at Battelle Pacific Northwest Laboratory in order to provide a firm information base on the engineering methodology, radiation risks, and estimated costs of decommissioning light water reactors and associated fuel cycle facilities. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. The report sets forth in detail the NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  12. NRC perspectives on fuel cycle and safeguards

    International Nuclear Information System (INIS)

    Chapman, K.R.

    1976-01-01

    This paper discusses NRC's mandate in the field of safeguards and the thoughts of NRC on other newly emerging policy considerations. The status of some of the current issues facing the nuclear community and the regulatory staff in particular is touched on

  13. NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147

    Energy Technology Data Exchange (ETDEWEB)

    Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D. [U.S. Nuclear Regulatory Commission (United States)

    2013-07-01

    As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in

  14. NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147

    International Nuclear Information System (INIS)

    Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D.

    2013-01-01

    As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in coordination with South

  15. Cost allocation review : staff discussion paper

    International Nuclear Information System (INIS)

    2005-09-01

    This report addressed the need for updated cost allocation studies filed by local electricity distribution companies because they ensure that distribution rates for each customer class remain just and reasonable. According to the 2001 Electricity Distribution Rate Handbook, the Ontario Energy Board requires new cost allocation studies before implementing any future incentive regulation plans. A review of cost allocations allows the Board to consider the need for adjustments to the current share of distribution costs paid by different classes of ratepayers. This report included 14 sections to facilitate consultations with stakeholders on financial information requirements for cost allocation; directly assignable costs; functionalization; categorization; allocation methods; allocation of other costs; load data requirements; cost allocation implementation issues; addition of new rate class and rate design for scattered unmetered loads; addition of new rate class for larger users; rates to charge embedded distributors; treatment of the rate sub-classification identified as time-of-use; and, rate design implementation issues. 1 fig., 7 appendices

  16. NRC regulatory information conference: Proceedings

    International Nuclear Information System (INIS)

    1989-09-01

    This volume of the report provides the proceedings from the Nuclear Regulatory Commission (NRC) Regulatory Information Conference that was held at the Mayflower Hotel, Washington, DC, on April 18, 19, and 20, 1989. This conference was held by the NRC and chaired by Dr. Thomas E. Mosley, Director, Office of Nuclear Reactor Regulations (NRR) and coordinated by S. Singh Bajwa, Chief, Technical Assistance Management Section, NRR. There were approximately 550 participants from nine countries at the conference. The countries represented were Canada, England, Italy, Japan, Mexico, Spain, Taiwan, Yugoslavia, and the United States. The NRC staff discussed with nuclear industry its regulatory philosophy and approach and the bases on which they have been established. Furthermore, the NRC staff discussed several initiatives that have been implemented recently and their bases as well as NRC's expectations for new initiatives to further improve safety. The figures contained in Appendix A to the volume correspond to the slides that were shown during the presentations. Volume 2 of this report contains the formal papers that were distributed at the beginning of the Regulatory Information Conference and other information about the conference

  17. NRC assessment of the high-level waste repository quality assurance program

    International Nuclear Information System (INIS)

    Kennedy, J.E.

    1987-01-01

    As part of its licensing responsibilities, the NRC is independently reviewing the DOE quality assurance program applied to the site characterization phase activities. Data collected and other information generated during this phase of the program will ultimately be used in a license application to demonstrate the suitability of one site for long-term isolation of waste. They must therefore fall under the quality assurance program to provide confidence in their adequacy. This NRC review consists of three main activities: development of staff guidance on quality assurance measures appropriate for site characterization activities; review of DOE QA plans and procedures; and audits and other reviews of the implementation of the program

  18. Staff assignment practices in nursing homes: review of the literature.

    Science.gov (United States)

    Rahman, Anna; Straker, Jane K; Manning, Lydia

    2009-01-01

    Consistent assignment, whereby nursing home staff members, particularly certified nurse aides, are assigned to the same residents on most shifts, is increasingly viewed as a cornerstone of culture change in nursing homes. It has been advocated as a best-care model that increases residents' quality of life while contributing to a more stable frontline staff. Given these potential benefits, consistent assignment is now widely viewed as superior to rotating assignment, an alternative staffing model that aims to distribute care burden more fairly among staff and ensure that workers are familiar with most residents. Despite favorable anecdotal reports about the benefits of consistent assignment, the research literature reports mixed and sometimes contradictory findings for this staffing practice. This article reviews the research pertaining to staff assignment practices in nursing homes. Reviewed here are 13 reports on experimental trials (6 reports), evaluation research (4 reports), and nursing home surveys (3 reports). The review reveals broad diversity in staffing practices and raises questions that challenge popular assumptions about consistent assignment. The article closes with a discussion of the research, policy, and practice implications of the research findings.

  19. 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...

  20. NRC regulatory agenda: Semiannual report, January--June 1997. Volume 16, Number 1

    International Nuclear Information System (INIS)

    1997-08-01

    The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition. The agenda consists of two sections that have been updated through June 30, 1997. Section 1, ''Rules,'' includes (A) rules on which final action has been taken since December 31, 1996, the closing date of the last NRC Regulatory Agenda; (B) rules published previously as proposed rules on which the Commission has not taken final action; (C) rules published as advance notices of proposed rulemaking for which neither a proposed nor final rule has been issued; and (D) unpublished rules on which the NRC expects to take action. Section 2, ''Petitions for Rulemaking,'' includes (A) petitions denied or incorporated into final rules since December 31, 1996; (B) petitions incorporated into proposed rules; and (C) petitions pending staff review

  1. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1990-10-01

    The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has recently completed action or has proposed, or is considering action and of all petitions for rulemaking that the NRC has received that are pending disposition

  2. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1990-04-01

    The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has recently completed action or has proposed, or is considering action and of all petitions for rulemaking that the NRC has received that are pending disposition

  3. Environmental assessment for decontamination of the Three Mile Island Unit 2 reactor building atmosphere. Draft NRC staff report for public comment

    International Nuclear Information System (INIS)

    1980-03-01

    The krypton-85 (Kr-85) released to the reactor building during the accident at TMI-2 must be removed from the reactor building in order to permit greater access to the building than is currently possible. The gases currently in the building emit sufficient radiation (1.2 rem/hr total body, 150 rad/hr skin dose) that occupation of the reactor building is severely limited even with protective clothing. Greater access is likely to be necessary to maintain instrumentation and equipment required to keep the reactor in a safe shutdown condition. In addition greater access would facilitate the gathering of data needed for planning the building decontamination program. An additional consideration is that prolonged enclosure of the Kr-85 within the building greatly increases the risk of its successive uncontrolled releases to the outside environment. The staff's evaluation of alternative methods for removing the krypton shows that each could be implemented with little risk to the health and safety of the public. The reactor building purge system, charcoal adsorption system, gas compression, selective absorption process system, and cryogenic processing system could each be operated to keep levels of airborne radioactive materials to unrestricted areas in compliance with the requirements of 10 CFR Part 20, and the design objectives of Appendix 1 to 10 CFR Part 50 of the Commission's regulations, and with the applicable requirements of 40 CFR Part 190.10

  4. Environmental assessment for decontamination of the Three Mile Island Unit 2 reactor building atmosphere. Draft NRC staff report for public comment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-03-01

    The krypton-85 (Kr-85) released to the reactor building during the accident at TMI-2 must be removed from the reactor building in order to permit greater access to the building than is currently possible. The gases currently in the building emit sufficient radiation (1.2 rem/hr total body, 150 rad/hr skin dose) that occupation of the reactor building is severely limited even with protective clothing. Greater access is likely to be necessary to maintain instrumentation and equipment required to keep the reactor in a safe shutdown condition. In addition greater access would facilitate the gathering of data needed for planning the building decontamination program. An additional consideration is that prolonged enclosure of the Kr-85 within the building greatly increases the risk of its successive uncontrolled releases to the outside environment. The staff's evaluation of alternative methods for removing the krypton shows that each could be implemented with little risk to the health and safety of the public. The reactor building purge system, charcoal adsorption system, gas compression, selective absorption process system, and cryogenic processing system could each be operated to keep levels of airborne radioactive materials to unrestricted areas in compliance with the requirements of 10 CFR Part 20, and the design objectives of Appendix 1 to 10 CFR Part 50 of the Commission's regulations, and with the applicable requirements of 40 CFR Part 190.10.

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

    Science.gov (United States)

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

    2016-01-01

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

  6. Report to Congress on NRC emergency communications

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-09-01

    The accident at Three Mile Island highlighted the need for improved communications among the NRC and other organizations which respond to such emergencies. This report summarizes the communication problems identified by several major review groups after the accident, the status of corrective actions, and NRC plans to improve communications still further. (author)

  7. Fluorine--a current literature review. An NRC and ATSDR based review of safety standards for exposure to fluorine and fluorides.

    Science.gov (United States)

    Prystupa, Jeff

    2011-02-01

    A review of the literature of the element fluorine and its bonded-form, fluoride, was undertaken. Generally regarded as safe, an expanding body of literature reveals that fluoride's toxicity has been unappreciated, un-scrutinized, and hidden for over 70 years. The context for the literature search and review was an environmental climate-change study, which demonstrated widespread fluoride contamination by smokestack emissions from coal-fired electricity-generating plants. The objective of this review is to educate and inform regarding the ubiquitous presence and harmful nature of this now ever-present corrosive and reactive toxin. Methods include examination of national health agency reviews, primarily the National Research Council (NRC), Agency for Toxic Substances & Disease Registry (ATSDR), standard medical toxicology references, text books, as well as reports and documents from both private and public research as well as consumer-based NGOs. Study criteria were chosen for relevancy to the subject of the toxicity of fluoride. Fluoride is the extreme electron scavenger, the most corrosive of all elements, as well as the most-reactive. Fluoride appears to attack living tissues, via several mechanisms. Fluoride renders strong evidence that it is a non-biological chemical, demonstrating no observed beneficial function or role in organic chemistry, beyond use as a pesticide or insecticide. Fluorine has a strong role to play in industry, having been utilized extensively in metals, plastics, paints, aluminium, steel, and uranium production. Due to its insatiable appetite for calcium, fluorine and fluorides likely represent a form of chemistry that is incompatible with biological tissues and organ system functions. Based on an analysis of the affects of fluoride demonstrated consistently in the literature, safe levels have not been determined nor standardized. Mounting evidence presents conflicting value to its presence in biological settings and applications. Evidence

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

    Directory of Open Access Journals (Sweden)

    Louise H Hall

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

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

    Science.gov (United States)

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

    2016-01-01

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

  10. NRC Regulatory Agenda. Quarterly report, July-September 1982

    International Nuclear Information System (INIS)

    1982-10-01

    The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received and are pending disposition by the Commission. The agenda consists of two sections. Section I, Rules, includes: (1) rules on which final action has been taken since June 30, the cutoff date of the last Regulatory Agenda; (2) rules published previously as proposed rules and on which the Commission has not taken final action; (3) rules published as advance notices of proposed rulemaking and for which neither a proposed nor final rule has been issued; and (4) unpublished rules on which the NRC expects to take action. Section II, Petitions for Rulemaking, includes: (1) Petitions incorporated into final rules or petitions denied since the cutoff date of the last Regulatory Agenda; (2) Petitions incorporated into proposed rules, (3) Petitions pending staff review; and (4) Petitions with deferred action

  11. Shift technical advisors: in the eyes of the NRC

    International Nuclear Information System (INIS)

    Crocker, L.P.

    1981-01-01

    Since January 1, 1980, the NRC has required that Shift Technical Advisors be on-shift at all operating nuclear power plants. The objective of the requirement is to assure that technical expertise is immediately available to each operating shift to assess off-normal events and to provide advice to control room personnel. Further, this advice and assistance is to be provided by an individual not responsible for control manipulations or for directing the activities of reactor operators. The long-term requirement for on-shift technical expertise is firm. However, the exact manner in which this expertise must be furnished has not been determined. Licensees have proposed various alternatives to meet this requirement. These proposals still are being reviewed by the NRC staff

  12. Recommendations for NEAMS Engagement with the NRC: Preliminary Report

    International Nuclear Information System (INIS)

    Bernholdt, David E.

    2012-01-01

    The vision of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program is to bring a new generation of analytic tools to the nuclear engineering community in order to facilitate students, faculty, industry and laboratory researchers in investigating advanced reactor and fuel cycle designs. Although primarily targeting at advance nuclear technologies, it is anticipated that these new capabilities will also become interesting and useful to the nuclear regulator Consequently, the NEAMS program needs to engage with the Nuclear Regulatory Commission as the software is being developed to ensure that they are familiar with and ready to respond to this novel approach when the need arises. Through discussions between key NEAMS and NRC staff members, we tentatively recommend annual briefings to the Division of Systems Analysis in the NRC's Office of Nuclear Regulatory Research. However the NEAC subcommittee review of the NEAMS program may yield recommendations that would need to be considered before finalizing this plan.

  13. Recommendations for NEAMS Engagement with the NRC: Preliminary Report

    Energy Technology Data Exchange (ETDEWEB)

    Bernholdt, David E [ORNL

    2012-06-01

    The vision of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program is to bring a new generation of analytic tools to the nuclear engineering community in order to facilitate students, faculty, industry and laboratory researchers in investigating advanced reactor and fuel cycle designs. Although primarily targeting at advance nuclear technologies, it is anticipated that these new capabilities will also become interesting and useful to the nuclear regulator Consequently, the NEAMS program needs to engage with the Nuclear Regulatory Commission as the software is being developed to ensure that they are familiar with and ready to respond to this novel approach when the need arises. Through discussions between key NEAMS and NRC staff members, we tentatively recommend annual briefings to the Division of Systems Analysis in the NRC's Office of Nuclear Regulatory Research. However the NEAC subcommittee review of the NEAMS program may yield recommendations that would need to be considered before finalizing this plan.

  14. Significant NRC Enforcement Actions

    Data.gov (United States)

    Nuclear Regulatory Commission — This dataset provides a list of Nuclear Regulartory Commission (NRC) issued significant enforcement actions. These actions, referred to as "escalated", are issued by...

  15. Review article: Staff perception of the emergency department working environment: Integrative review of the literature

    Science.gov (United States)

    Abraham, Louisa; Greenslade, Jaimi; Thom, Ogilvie; Carlstrom, Eric; Wallis, Marianne; Crilly, Julia

    2016-01-01

    Abstract Employees in EDs report increasing role overload because of critical staff shortages, budgetary cuts and increased patient numbers and acuity. Such overload could compromise staff satisfaction with their working environment. This integrative review identifies, synthesises and evaluates current research around staff perceptions of the working conditions in EDs. A systematic search of relevant databases, using MeSH descriptors ED/EDs, Emergency room/s, ER/s, or A&E coupled with (and) working environment, working condition/s, staff perception/s, as well as reference chaining was conducted. We identified 31 key studies that were evaluated using the mixed methods assessment tool (MMAT). These comprised 24 quantitative‐descriptive studies, four mixed descriptive/comparative (non‐randomised controlled trial) studies and three qualitative studies. Studies included varied widely in quality with MMAT scores ranging from 0% to 100%. A key finding was that perceptions of working environment varied across clinical staff and study location, but that high levels of autonomy and teamwork offset stress around high pressure and high volume workloads. The large range of tools used to assess staff perception of working environment limits the comparability of the studies. A dearth of intervention studies around enhancing working environments in EDs limits the capacity to recommend evidence‐based interventions to improve staff morale. © 2016 The Authors. Emergency Medicine Australasia published by John Wiley & Sons Australia, Ltd on behalf of Australasian College for Emergency Medicine and Australasian Society for Emergency Medicine PMID:26784282

  16. Topical report review status

    International Nuclear Information System (INIS)

    1982-08-01

    A Topical Report Review Status is scheduled to be published semi-annually. The primary purpose of this document is to provide periodic progress reports of on-going topical report reviews, to identify those topical reports for which the Nuclear Regulatory Commission (NRC) staff review has been completed and, to the extent practicable, to provide NRC management with sufficient information regarding the conduct of the topical report program to permit taking whatever actions deemed necessary or appropriate. This document is also intended to be a source of information to NRC Licensing Project Managers and other NRC personnel regarding the status of topical reports which may be referenced in applications for which they have responsibility. This status report is published primarily for internal NRC use in managing the topical report program, but is also used by NRC to advise the industry of report review status

  17. Topical report review status

    International Nuclear Information System (INIS)

    1983-01-01

    A Topical Report Review Status is scheduled to be published semi-annually. The primary purpose of this document is to provide periodic progress reports of on-going topical report reviews, to identify those topical reports for which the Nuclear Regulatory Commission (NRC) staff review has been completed and, to the extent practicable, to provide NRC management with sufficient information regarding the conduct of the topical report program to permit taking whatever actions deemed necessary or appropriate. This document is also intended to be a source of information to NRC Licensing Project Managers and other NRC personnel regarding the status of topical reports which may be referenced in applications for which they have responsibility. This status report is published primarily for internal NRC use in managing the topical report program, but is also used by NRC to advise the industry of report review status

  18. 75 FR 5632 - Office of New Reactors; Interim Staff Guidance on the Review of Nuclear Power Plant Designs Using...

    Science.gov (United States)

    2010-02-03

    ... Management System (ADAMS) Accession No. ML092640035). This ISG provides new guidance information for applicants submitting a combined license (COL) or design certification (DC) for construction and operation of... (SRP), Section 8.3.1 and Sections 9.5.4 through 9.5.8. The NRC staff issues DC/COL-ISGs to facilitate...

  19. NRC concerns about steam generator tube U-bend failures

    International Nuclear Information System (INIS)

    Dillon, R.L.

    1981-01-01

    This paper concerns itself with genralized NRC regulatory policy regarding SGT failures and staff reports and opinions which may tend to influence the developing policy specific to U-bend failures. The most significant analysis at hand in predicting NRC policy on SGT U-bend failures is Marsh's Evaluation of Steam Generator Tube Rupture Events. Marsh sets out to describe and analyze the five steam generator tube ruptures that are known to NRC. All have occurred in the period 1975 to 1980

  20. NRC comprehensive records disposition schedule

    International Nuclear Information System (INIS)

    1992-03-01

    Title 44 United States Code, ''Public Printing and Documents,'' regulations cited in the General Services Administration's (GSA) ''Federal Information Resources Management Regulations'' (FIRMR), Part 201-9, ''Creation, Maintenance, and Use of Records,'' and regulation issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter XII, Subchapter B, ''Records Management,'' require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA's General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 2, contains ''NRC's Comprehensive Records Disposition Schedule,'' and the original authorized approved citation numbers issued by NARA. Rev. 2 totally reorganizes the records schedules from a functional arrangement to an arrangement by the host office. A subject index and a conversion table have also been developed for the NRC schedules to allow staff to identify the new schedule numbers easily and to improve their ability to locate applicable schedules

  1. NRC Regulatory Agenda

    International Nuclear Information System (INIS)

    1991-10-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  2. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1993-04-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  3. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1990-01-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  4. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1991-04-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action or has proposed, or is considering action and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  5. NRC Regulatory Agenda

    International Nuclear Information System (INIS)

    1991-08-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action or has proposed, or is considering action and all petitions for rulemaking which have been received by the commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  6. 76 FR 48919 - NRC Enforcement Policy

    Science.gov (United States)

    2011-08-09

    .... In all such cases when a licensee determines that an unplanned change during construction associated..., States, members of the public, and the regulated industry (i.e., reactor and materials licensees, vendors, and contractors), on construction-related topics addressed in this notice that the NRC staff is...

  7. A review of radiology staff doses and dose monitoring requirements

    International Nuclear Information System (INIS)

    Martin, C. J.

    2009-01-01

    Studies of radiation doses received during X-ray procedures by radiology, cardiology and other clinical staff have been reviewed. Data for effective dose (E), and doses to the eyes, thyroid, hands and legs have been analysed. These data have been supplemented with local measurements to determine the most exposed part of the hand for monitoring purposes. There are ranges of 60-100 in doses to individual tissues reported in the literature for similar procedures at different centres. While ranges in the doses per unit dose-area product (DAP) are between 10 and 25, large variations in dose result from differences in the sensitivity of the X-ray equipment, the type of procedure and the operator technique, but protection factors are important in maintaining dose levels as low as possible. The influence of shielding devices is significant for determining the dose to the eyes and thyroid, and the position of the operator, which depends on the procedure, is the most significant factor determining doses to the hands. A second body dosemeter worn at the level of the collar is recommended for operators with high workloads for use in assessment of effective dose and the dose to the eye. It is proposed that the third quartile values from the distributions of dose per unit DAP identified in the review might be employed in predicting the orders of magnitude of doses to the eye, thyroid and hands, based on interventional operator workloads. Such dose estimates could be employed in risk assessments when reviewing protection and monitoring requirements. A dosemeter worn on the little finger of the hand nearest to the X-ray tube is recommended for monitoring the hand. (authors)

  8. A Preliminary Review of Fatigue Among Rail Staff

    Directory of Open Access Journals (Sweden)

    Jialin Fan

    2018-05-01

    Full Text Available Background: Fatigue is a severe problem in the rail industry, which may jeopardize train crew's health and safety. Nonetheless, a preliminary review of all empirical evidence for train crew fatigue is still lacking. The aim of the present paper is, therefore, to provide a preliminary description of occupational fatigue in the rail industry. This paper reviews the literature with the research question examining the risk factors associated with train crew fatigue, covering both papers published in refereed journals and reports from trade organizations and regulators. It assesses the progress of research on railway fatigue, including research on the main risk factors for railway fatigue, the association between fatigue and railway incidents, and how to better manage fatigue in the railway industry.Methods: Systematic searches were performed in both science and industry databases. The searches considered studies published before August 2017. The main exclusion criterion was fatigue not being directly measured through subjective or objective methods.Results: A total of 31 studies were included in the main review. The causes of fatigue included long working hours, heavy workload, early morning or night shifts, and insufficient sleep. Poor working environment, particular job roles, and individual differences also contributed to fatigue.Conclusion: Fatigue in the rail industry includes most of the features of occupational fatigue, and it is also subject to industry-specific factors. The effect of fatigue on well-being and the fatigued population in the railway industry are still not clear. Future studies can consider associations between occupational risk factors and perceived fatigue by examining the prevalence of fatigue and identifying the potential risk factors in staff within the railway industry.

  9. Performance testing of dosimetry processors, status of NRC rulemaking for improved personnel dosimetry processing, and some beta dosimetry and instrumentation problems observed by NRC regional inspectors

    International Nuclear Information System (INIS)

    Dennis, N.A.; Kinneman, J.D.; Costello, F.M.; White, J.R.; Nimitz, R.L.

    1983-01-01

    Early dosimetry processor performance studies conducted between 1967 and 1979 by several different investigators indicated that a significant percentage of personnel dosimetry processors may not be performing with a reasonable degree of accuracy. Results of voluntary performance testing of US personnel dosimetry processors against the final Health Physics Society Standard, Criteria for Testing Personnel Dosimetry Performance by the University of Michigan for the Nuclear Regulatory Commission (NRC) will be summarized with emphasis on processor performance in radiation categories involving beta particles and beta particles and photon mixtures. The current status of the NRC's regulatory program for improved personnel dosimetry processing will be reviewed. The NRC is proposing amendments to its regulations, 10 CFR Part 20, that would require its licensees to utilize specified personnel dosimetry services from processors accredited by the National Voluntary Laboratory Accreditation Program of the National Bureau of Standards. Details of the development and schedule for implementation of the program will be highlighted. Finally, selected beta dosimetry and beta instrumentation problems observed by NRC Regional Staff during inspections of NRC licensed facilities will be discussed

  10. 78 FR 13686 - Draft Guidance for Industry and Review Staff on Pediatric Information Incorporated Into Human...

    Science.gov (United States)

    2013-02-28

    ... FDA review staff in making decisions about the placement and content of pediatric information in human... assist that office in processing your requests. See the SUPPLEMENTARY INFORMATION section for electronic...] Draft Guidance for Industry and Review Staff on Pediatric Information Incorporated Into Human...

  11. Assessment of the NRC Enforcement Program

    International Nuclear Information System (INIS)

    Lieberman, J.; Coblentz, L.

    1995-04-01

    On May 12, 1994, the Executive Director for Operations (EDO) established a Review Team composed of senior NRC managers to re-examine the NRC enforcement program. A copy of the Review Team's charter is enclosed as Appendix A. This report presents the Team's assessment. The purpose of this review effort are: (1) to perform an assessment of the NRC's enforcement program to determine whether the defined purposes of the enforcement program are appropriate; (2) to determine whether the NRC's enforcement practices and procedures for issuing enforcement actions are consistent with those purposes; and (3) to provide recommendations on any changes the Review Team believes advisable. In accordance with its charter, the Review Team considered the following principal issues in conducting its assessment of the enforcement program: the balance between providing deterrence and incentives (both positive and negative) for the identification and correction of violations; the appropriateness of NRC sanctions; whether the commission should seek statutory authority to increase the amount of civil penalties; whether the NRC should use different enforcement policies and practices for different licensees (e.g., materials licensees in contrast to power reactors or large fuel facilities); and whether the commission should establish open enforcement conferences as the normal practice

  12. Status of U. S. NRC Actions for the Events of Fukushima Dacha NPP

    International Nuclear Information System (INIS)

    Kim, Donghak; Lee, Jaeyong; Kim, Myungki

    2013-01-01

    In this study, status of U. S. NRC actions for the events of Fukushima is studied by reviewing commission papers, orders, request for information (RFI), Interim Staff Guidance (ISG) issued by NRC, etc. In order to acquire design certification of the APR1400, status of U. S. NRC actions for the events of Fukushima Dacha NTT is reviewed. The NRC has determined and conducted the 38 recommendations for action including 31 NTTF recommendations and seven additional recommendations. The recommendations are divided into Tier 1, Tier 2 and Tier 3. Tier 1 and Tier 2 recommendations are implemented by three Orders, one request for information and two rule makings. To comply with three orders and one request for information, the NRC issued six ISGs and NEI issued three technical reports. The final rule on strengthening and integrating onsite emergency response capabilities will be issued in February 2016. Station blackout mitigating strategies rulemaking on SBO mitigation capability and on spent fuel pool instrumentation and makeup capability will proceed

  13. NRC methods for evaluation of industry training

    International Nuclear Information System (INIS)

    Morisseau, D.S.; Koontz, J.L.; Persensky, J.J.

    1987-01-01

    On March 20, 1985, the Nuclear Regulatory Commission published the Policy Statement on Training and Qualification. The Policy Statement endorsed the INPO-managed Training Accreditation Program because it encompasses the five elements of performance-based training. This paper described the multiple methods that the NRC is using to monitor industry efforts to improve training and implement the NRC Policy Statement on Training and Qualification. The results of the evaluation of industry training improvement programs will be reviewed by the Commissioners in April 1987 to determine the nature of continuing NRC policy and programs for ensuring effective training for the US nuclear industry

  14. Public citizen slams NRC on nuclear inspections

    International Nuclear Information System (INIS)

    Newman, P.

    1993-01-01

    Charging the Nuclear Regulatory Commission with open-quotes abandoning tough regulation of the nuclear power industry,close quotes Public Citizen's Critical Mass Energy Project on Wednesday released a report asserting that NRC is shielding sensitive internal nuclear industry self-evaluations from public scrutiny. Based on their review of 56 Institute of Nuclear Power Operations reports and evaluations and comparing these to the NRC's Systematic Assessment of Licensee Performance reports for the same plants, it was concluded that the NRC failed to address issues raised in all eight areas evaluated by the INPO reports

  15. NRC perspective on alternative disposal methods

    International Nuclear Information System (INIS)

    Pittiglio, C.L.; Tokar, M.

    1987-01-01

    In this paper is discussed an NRC staff strategy for the development of technical criteria and procedures for the licensing of various alternatives for disposal of low-level radioactive waste. Steps taken by the staff to identify viable alternative disposal methods and to comply with the requirements of the Low-Level Radioactive Waste Policy Amendments Act (LLRWPAA) of 1985 are also discussed. The strategy proposed by the NRC staff is to focus efforts in FY 87 on alternative concepts that incorporate concrete materials with soil or rock cover (e.g., below ground vaults and earth-mounded concrete bunkers), which several State and State Compacts have identified as preferred disposal options. While the NRC staff believes that other options, such as above ground vaults and mined cavities, are workable and licensable, the staff also believes, for reasons addressed in the paper, that it is in the best interest of the industry and the public to encourage standardization and to focus limited resources on a manageable number of alternative options. Therefore, guidance on above ground vaults, which are susceptible to long-term materials degradation due to climatological effects, and mined cavities, which represent a significant departure from the current experience base for low-level radioactive waste disposal, will receive minimal attention. 6 references

  16. NRC regulatory uses of PSA

    International Nuclear Information System (INIS)

    Murley, T.E.

    1991-01-01

    The publication in 1975 of WASH-1400, with its new probabilistic safety assessment (PSA) methodology, had the effect of presenting a pair of eyeglasses to a man with poor eyesight. Suddenly, it gave us a view of nuclear safety with a new clarity, and it allowed us to sort out the important safety issues from the unimportant. In the intervening years, PSA insights have permeated the fabric of nearly all our safety judgments. This acceptance can be seen from the following list of broad areas where the Nuclear Regulatory Commission (NRC) staff uses PSA insights and methodology: evaluating the safety significance of operating events and recommending safety improvements where warranted; requesting licensees to systematically look for design vulnerabilities in each operating reactor; evaluating the safety significance of design weaknesses or non-compliances when judging the time frame for necessary improvements; conducting sensitivity analyses to judge where safety improvements are most effective; assessing the relative safety benefits of design features for future reactors. In judging where PSA methodology can be improved to give better safety insights, it is believed that the following areas need more attention: better modeling of cognitive errors; more comprehensive modeling of accident sequences initiated from conditions other than full power; more comprehensive modeling of inter-system loss of coolant accident (ISLOCA) sequences. Although PSA is widely used in the staff's regulatory activities, the NRC deliberately chooses not to include probabilistic prescriptions in regulations or guidance documents. The staff finds the bottom line risk estimates to be one of the least reliable products of a PSA. The reason for this view is that PSA cannot adequately address cognitive errors nor assess the effects of a pervasive poor safety attitude

  17. The NRC perspective on low-level radioactive waste disposal

    International Nuclear Information System (INIS)

    Thompson, H.L. Jr.; Knapp, M.R.

    1987-01-01

    This paper describes the Nuclear Regulatory Commission's (NRC) actions in response to the Low-Level Radioactive Waste Policy Amendments Act (the Act) and NRC's assistance to States and Compacts working to discharge their responsibilities under the Act. Three of NRC's accomplishments which respond explicitly to direction in the Act are highlighted. These are: development of the capability of expedited handling of petitions addressing wastes below regulatory concern (BRC); development of capability to review and process an application within fifteen months; and development of guidance on alternatives to shallow land burial. Certain NRC efforts concerning special topics related to the Act as well as NRC efforts to assist States and Compacts are summarized

  18. NRC inspections of licensee activities to improve the performance of motor-operated valves

    International Nuclear Information System (INIS)

    Scarbrough, T.G.

    1992-01-01

    The NRC regulations require that components important to the safe operation of a nuclear power plant be treated in a manner that provides assurance of their proper performance. Despite these regulatory requirements, operating experience and research programs have raised concerns regarding the performance of motor-operated valves (MOVs) in nuclear power plants. In June 1990, the staff issued NUREG-1352, Action Plans for Motor-Operated Valves and Check Valves, which contains planned actions to organize the activities aimed at resolving the concerns about MOV performance. A significant task of the MOV action plan is the staff's review of the implementation of Generic Letter (GL) 89-10 (June 28, 1989), 'Safety-Related Motor-Operated Valve Testing and Surveillance,' and its supplements, by nuclear power plant licensees. The NRC staff has issued several supplements to GL 89-10 to provide additional guidance for use by licensees in responding to the generic letter. The NRC staff has conducted initial inspections of the GL 89-10 programs at most licensee facilities. This paper outlines some of the more significant findings of those inspections. For example, licensees who have begun differential pressure and flow testing have found some MOVs to require more thrust to operate than predicted by the standard industry equation with typical valve factors assumed in the past. The NRC staff has found weaknesses in licensee procedures for conducting the differential pressure and flow tests, the acceptance criteria for the tests in evaluating the capability of the MOV to perform its safety function under design basis conditions, and feedback of the test results into the methodology used by the licensee in predicting the thrust requirements for other MOVs. Some licensees have not made adequate progress toward resolving the MOV issue for their facilities within the recommended schedule of GL 89-10

  19. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-12-01

    The present decommissioning regulations contained in Sections 50.33(f) and 50.82 of 10 CFR part 50 require applicants for power reactor operating licenses to demonstrate that they can obtain the funds needed to meet both operating costs and estimated costs of shutdown and decommissioning. The development of detailed, specific decommissioning plans for nuclear power plants is not currently required until the licensee seeks to terminate his operating license. Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase the need for future decommissionings, the NRC staff began an in-depth review and reevaluation of NRC's regulatory approach to decommissioning in 1975. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. In response to comments from the public and states, and to information gained during the initial stage of execution of the plan, several modifications of the plan are now required. The revised overall report sets forth in detail the current NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  20. 76 FR 17649 - Science Advisory Board Staff Office; Request for Nominations; SAB Mercury Review Panel

    Science.gov (United States)

    2011-03-30

    ... nominations of women and men of all racial and ethnic groups. The EPA SAB Staff Office will acknowledge... factors); (b) availability and willingness to serve; (c) absence of financial conflicts of interest; (d... Staff Office's evaluation of an absence of financial conflicts of interest will include a review of the...

  1. Burnout in University Teaching Staff: A Systematic Literature Review

    Science.gov (United States)

    Watts, J.; Robertson, N.

    2011-01-01

    Background: Teacher stress potentially impairs personal and professional competence and compromises productivity. Aversive emotional experience has been most comprehensively encapsulated by the phenomenon of burnout, which is particularly prominent for staff in human service sectors. Burnout reactions have been characterised as tripartite: the…

  2. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1993-07-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter. The rules on which final action has been taken since March 31, 1993 are: Repeal of NRC standards of conduct; Fitness-for-duty requirements for licensees who possess, use, or transport Category I material; Training and qualification of nuclear power plant personnel; Monitoring the effectiveness of maintenance at nuclear power plants; Licensing requirements for land disposal of radioactive wastes; and Licensees' announcements of safeguards inspections

  3. Initial demonstration of the NRC`s capability to conduct a performance assessment for a High-Level Waste Repository

    Energy Technology Data Exchange (ETDEWEB)

    Codell, R.; Eisenberg, N.; Fehringer, D.; Ford, W.; Margulies, T.; McCartin, T.; Park, J.; Randall, J.

    1992-05-01

    In order to better review licensing submittals for a High-Level Waste Repository, the US Nuclear Regulatory Commission staff has expanded and improved its capability to conduct performance assessments. This report documents an initial demonstration of this capability. The demonstration made use of the limited data from Yucca Mountain, Nevada to investigate a small set of scenario classes. Models of release and transport of radionuclides from a repository via the groundwater and direct release pathways provided preliminary estimates of releases to the accessible environment for a 10,000 year simulation time. Latin hypercube sampling of input parameters was used to express results as distributions and to investigate model sensitivities. This methodology demonstration should not be interpreted as an estimate of performance of the proposed repository at Yucca Mountain, Nevada. By expanding and developing the NRC staff capability to conduct such analyses, NRC would be better able to conduct an independent technical review of the US Department of Energy (DOE) licensing submittals for a high-level waste (HLW) repository. These activities were divided initially into Phase 1 and Phase 2 activities. Additional phases may follow as part of a program of iterative performance assessment at the NRC. The NRC staff conducted Phase 1 activities primarily in CY 1989 with minimal participation from NRC contractors. The Phase 2 activities were to involve NRC contractors actively and to provide for the transfer of technology. The Phase 2 activities are scheduled to start in CY 1990, to allow Sandia National Laboratories to complete development and transfer of computer codes and the Center for Nuclear Waste Regulatory Analyses (CNWRA) to be in a position to assist in the acquisition of the codes.

  4. Clinical Nurse Specialists Guide Staff Nurses to Promote Practice Accountability Through Peer Review.

    Science.gov (United States)

    Semper, Julie; Halvorson, Betty; Hersh, Mary; Torres, Clare; Lillington, Linda

    2016-01-01

    The aim of the study was to describe the clinical nurse specialist role in developing and implementing a staff nurse education program to promote practice accountability using peer review principles. Peer review is essential for professional nursing practice demanding a significant culture change. Clinical nurse specialists in a Magnet-designated community hospital were charged with developing a staff nurse peer review education program. Peer review is a recognized mechanism of professional self-regulation to ensure delivery of quality care. The American Nurses Association strongly urges incorporating peer review in professional nursing practice models. Clinical nurse specialists play a critical role in educating staff nurses about practice accountability. Clinical nurse specialists developed an education program guided by the American Nurses Association's principles of peer review. A baseline needs assessment identified potential barriers and learning needs. Content incorporated tools and strategies to build communication skills, collaboration, practice change, and peer accountability. The education program resulted in increased staff nurse knowledge about peer review and application of peer review principles in practice. Clinical nurse specialists played a critical role in helping staff nurses understand peer review and its application to practice. The clinical nurse specialist role will continue to be important in sustaining the application of peer review principles in practice.

  5. Systematic evaluation program review of NRC Safety Topic VI-7.3 associated with the electrical, instrumentation and control portions of the ECCS actuation system for the Dresden II Nuclear Power Plant

    International Nuclear Information System (INIS)

    St Leger-Barter, G.

    1980-11-01

    This report documents the technical evaluation and review of NRC Safety Topic VI-7.A.3, associated with the electrical, instrumentation, and control portions of the classification of the ECCS actuation system for the Dresden II nuclear power plant, using current licensing criteria

  6. Systematic evaluation program review of NRC safety topic VII-2 associated with the electrical, instrumentation and control portions of the ESF system control logic and design for the Dresden Station, Unit II nuclear power plant

    International Nuclear Information System (INIS)

    St Leger-Barter, G.

    1980-11-01

    This report documents the technical evaluation and review of NRC Safety Topic VII-2, associated with the electrical, instrumentation, and control portions of the ESF system control logic and design for the Dresden Station Unit II nuclear power plant, using current licensing criteria

  7. NRC Regulatory Agenda

    International Nuclear Information System (INIS)

    1992-07-01

    This document compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rule making which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  8. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1993-02-01

    This document is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considered action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  9. NRC Regulatory Agenda

    International Nuclear Information System (INIS)

    1989-07-01

    This document is a compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  10. NRC regulatory agenda

    International Nuclear Information System (INIS)

    1992-11-01

    This document provides a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  11. NRC closing remarks

    International Nuclear Information System (INIS)

    Coffman, F.

    1994-01-01

    This section contains the edited transcript of the NRC closing remarks made by Mr. Franklin Coffman (Chief, Human Factors Branch, Office of Nuclear Regulatory Research) and Dr. Cecil Thomas (Deputy Director, Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation). This editing consisted of minimal editing to correct grammar and remove extraneous references to microphone volume, etc

  12. NRC inventory of dams

    International Nuclear Information System (INIS)

    Lear, G.E.; Thompson, O.O.

    1983-01-01

    The NRC Inventory of Dams has been prepared as required by the charter of the NRC Dam Safety Officer. The inventory lists 51 dams associated with nuclear power plant sites and 14 uranium mill tailings dams (licensed by NRC) in the US as of February 1, 1982. Of the 85 listed nuclear power plants (148 units), 26 plants obtain cooling water from impoundments formed by dams. The 51 dams associated with the plants are: located on a plant site (29 dams at 15 plant sites); located off site but provide plant cooling water (18 dams at 11 additional plant sites); and located upstream from a plant (4 dams) - they have been identified as dams whose failure, and ensuing plant flooding, could result in a radiological risk to the public health and safety. The dams that might be considered NRC's responsibility in terms of the federal dam safety program are identified. This group of dams (20 on nuclear power plant sites and 14 uranium mill tailings dams) was obtained by eliminating dams that do not pose a flooding hazard (e.g., submerged dams) and dams that are regulated by another federal agency. The report includes the principal design features of all dams and related useful information

  13. Nuclear Regulatory Commission staff approaches to improving the integration of regulatory guidance documents and prelicensing reviews

    International Nuclear Information System (INIS)

    Johnson, R.L.

    1994-01-01

    The Nuclear Regulatory Commission staff is conducting numerous activities to improve the integration of its regulatory guidance documents (i.e., License Application Review Plan (LARP) and open-quotes Format and Content for the License Application for the High-Level Waste repositoryclose quotes (FCRG)) and pre-license application (LA) reviews. Those activities related to the regulatory guidance documents consist of: (1) developing an hierarchy of example evaluation findings for LARP; (2) identifying LARP review plan interfaces; (3) conducting an integration review of LARP review strategies; (4) correlating LARP to the ongoing technical program; and (5) revising the FCRG. Some of the more important strategies the staff is using to improve the integration of pre-LA reviews with the LA review include: (1) use of the draft LARP to guide the staff's pre-LA reviews; (2) focus detailed pre-LA reviews on key technical uncertainties; (3) identify and track concerns with DOE's program; and (4) use results of pre-LA reviews in LA reviews. The purpose of this paper is to describe these ongoing activities and strategies and discuss some of the new work that is planned to be included in LARP Revision 1 and the final FCRG, which are scheduled to be issued in late 1994. These activities reflect both the importance the staff has placed on integration and the staff's approach to improving integration in these areas. The staff anticipates that the results of these activities, when incorporated in the FCRG, LARP, and pre-LA reviews, will improve its guidance for DOE's ongoing site characterization program and LA annotated outline development

  14. Topical report review status. Volume 7, No. 2

    International Nuclear Information System (INIS)

    1984-11-01

    Purpose of this document is to provide periodic progress reports of on-going topical report reviews, to identify those topical reports for which the NRC staff review has been completed and those which are under review and to provide NRC management with sufficient information regarding the conduct of the topical report program to permit taking whatever actions are deemed necessary or appropriate. This document is also intended to be a source of information to NRC Licensing Project Managers and other NRC personnel regarding the status of topical reports which may be referenced in applications for which they have responsibility

  15. Five-Yearly Review: the Staff Association keeps you informed!

    CERN Multimedia

    Staff Association

    2016-01-01

    The Staff Association (SA) has already published several articles on this topic, especially at the beginning of the year and at the end of June (Echo No. 248). In these articles, we discussed the implementation of the decisions taken by the CERN Council in December 2015, covering the deadlines and progress, but also the SA’s concerns. First milestone reached On 18 August, all staff members received an individual notification letter indicating: their placement within the new salary scale, i.e. their grade and salary position expressed as a percentage of the midpoint of the grade; the provisional benchmark job they are assigned to. An information sheet was also enclosed in the email from HR Office. Soon after, the SA was contacted by a significant number of colleagues seeking further information on the content of the documents or wishing to share their disappointment and fears regarding the impact that these changes will have on their career. It seems therefore that the information provide...

  16. Reassessment of the NRC's program for protecting allegers against retaliation

    International Nuclear Information System (INIS)

    1994-01-01

    On July 6, 1993, the Nuclear Regulatory Commission's (NRC's) Executive Director for Operations established a review team to reassess the NRC's program for protecting allegers against retaliation. The team evaluated the current system, and solicited comments from various NRC offices, other Federal agencies, licensees, former allegers, and the public. This report is subject to agency review. The report summarizes current processes and gives an overview of current problems. It discusses: (1) ways in which licensees can promote a quality-conscious work environment, in which all employees feel free to raise concerns without fear of retaliation; (2) ways to improve the NRC's overall handling of allegations; (3) the NRC's involvement in the Department of Labor process; (4) related NRC enforcement practices; and (5) methods other than investigation and enforcement that may be useful in treating allegations of potential or actual discrimination. Recommendations are given in each area

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

    International Nuclear Information System (INIS)

    Lo, R.; Snyder, B.J.

    1980-07-01

    The NRC plan defines the functional role of the NRC in cleanup operations at Three Mile Island Unit 2 to assure that agency regulatory responsibilities and objectives will be fulfilled. The plan outlines NRC functions in TMI-2 cleanup operations in the following areas: (1) the functional relationship of NRC to other government agencies, the public, and the licensee to coordinate activities, (2) the functional roles of these organizations in cleanup operations, (3) the NRC review and decision-making procedure for the licensee's proposed cleanup operation, (4) the NRC/licensee estimated schedule of major actions, and (5) NRC's functional role in overseeing implementation of approved licensee activities

  18. Critical review of conservation equations for two-phase flow in the U.S. NRC TRACE code

    International Nuclear Information System (INIS)

    Wulff, Wolfgang

    2011-01-01

    Research highlights: → Field equations as implemented in TRACE are incorrect. → Boundary conditions needed for cooling of nuclear fuel elements are wrong. → The two-fluid model in TRACE is not closed. → Three-dimensional flow modeling in TRACE has no basis. - Abstract: The field equations for two-phase flow in the computer code TRAC/RELAP Advanced Computational Engine or TRACE are examined to determine their validity, their capabilities and limitations in resolving nuclear reactor safety issues. TRACE was developed for the NRC to predict thermohydraulic phenomena in nuclear power plants during operational transients and postulated accidents. TRACE is based on the rigorously derived and well-established two-fluid field equations for 1-D and 3-D two-phase flow. It is shown that: (1)The two-fluid field equations for mass conservation as implemented in TRACE are wrong because local mass balances in TRACE are in conflict with mass conservation for the whole reactor system, as shown in Section . (2)Wrong equations of motion are used in TRACE in place of momentum balances, compromising at branch points the prediction of momentum transfer between, and the coupling of, loops in hydraulic networks by impedance (form loss and wall shear) and by inertia and thereby the simulation of reactor component interactions. (3)Most seriously, TRACE calculation of heat transfer from fuel elements is incorrect for single and two-phase flows, because Eq. of the TRACE Manual is wrong (see Section ). (4)Boundary conditions for momentum and energy balances in TRACE are restricted to flow regimes with single-phase wall contact because TRACE lacks constitutive relations for solid-fluid exchange of momentum and heat in prevailing flow regimes. Without a quantified assessment of consequences from (3) to (4), predictions of phasic fluid velocities, fuel temperatures and important safety parameters, e.g., peak clad temperature, are questionable. Moreover, TRACE cannot predict 3-D single- or

  19. Reassessment of NRC's dollar per person-rem conversion factor policy

    International Nuclear Information System (INIS)

    1995-12-01

    The US Nuclear Regulatory Commission (NRC) has completed a review and analysis of its dollar per person-rem conversion factor policy. As a result of this review, the NRC has decided to adopt a $2000 per person-rem conversion factor, subject it to present worth considerations, and limit its scope solely to health effects. This is in contrast to the previous policy and staff practice of using an undiscounted $1000 per person-rem conversion factor that served as a surrogate for all offsite consequences (health and offsite property). The policy shift has been incorporated in ''Regulatory Analysis Guidelines of the US Nuclear Regulatory Commission,'' NUREG/BR-0058, Revision 2, November 1995

  20. AECB staff review of Pickering NGS operations for the year 1988

    International Nuclear Information System (INIS)

    1989-05-01

    The operation of Pickering NGS-A Units 1-4 and Pickering NGS-B Units 5-8 are monitored to ensure compliance with licensing requirements by the AECB Pickering project office staff. This report presents AECB staff's review of major licensing issues and of the operational performance of Pickering NGS during 1988. The report is limited to those aspects that AECB staff considers to have particular safety significance. More detailed information on routine performance is contained in Ontario Hydro's 1988 Quarterly Technical Reports for Pickering NGS-A and Pickering NGS-B

  1. EPA Response to the National Research Council (NRC) Report - A Review of the Technical Basis of the Chemical and Pathogen Regulations for Biosolids

    Science.gov (United States)

    The NRC published two reports over a twenty year span. They concluded that there is no documented scientific evidence that sewage sludge regulations have failed to protect public health, but identified areas of research.

  2. A Preliminary Review of Fatigue Among Rail Staff

    OpenAIRE

    Jialin Fan; Andrew P. Smith

    2018-01-01

    Background: Fatigue is a severe problem in the rail industry, which may jeopardize train crew's health and safety. Nonetheless, a preliminary review of all empirical evidence for train crew fatigue is still lacking. The aim of the present paper is, therefore, to provide a preliminary description of occupational fatigue in the rail industry. This paper reviews the literature with the research question examining the risk factors associated with train crew fatigue, covering both papers published...

  3. Professional Development for Sessional Staff in Higher Education: A Review of Current Evidence

    Science.gov (United States)

    Hitch, Danielle; Mahoney, Paige; Macfarlane, Susie

    2018-01-01

    The aim of this study was to provide an integrated review of evidence published in the past decade around professional development for sessional staff in higher education. Using the Integrating Theory, Evidence and Action method, the review analysed recent evidence using the three principles of the Benchmarking Leadership and Advancement of…

  4. 78 FR 40199 - Draft Spent Fuel Storage and Transportation Interim Staff Guidance

    Science.gov (United States)

    2013-07-03

    .... ML13056A516. NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21... current or future applicants The NRC staff has no intention to impose the draft ISG positions on existing... of the effective date of this guidance The NRC staff has no intention to impose the draft ISG...

  5. Workplace Harassment among Staff in Higher Education: A Systematic Review

    Science.gov (United States)

    Henning, Marcus A.; Zhou, Chen; Adams, Peter; Moir, Fiona; Hobson, Jennifer; Hallett, Charlene; Webster, Craig S.

    2017-01-01

    Workplace harassment in higher education adversely impacts workforce productivity and has deleterious health effects on victims. The aim of this study was to review the literature pertaining to workplace harassment in higher education. This systematic literature search was conducted in December 2013 and completed in January 2014. Refereed journal…

  6. NRC regulatory agenda: Semiannual report, January--June 1995. Volume 14, Number 1

    International Nuclear Information System (INIS)

    1995-09-01

    The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition. The agenda consists of two sections that have been updated through June 30, 1995. Section 1, ''Rules,'' includes (A) rules on which final action has been taken since December 30, 1994, the closing date of the last NRC Regulatory Agenda; (B) rules published previously as proposed rules on which the Commission has not taken final action; (C) rules published as advance notices of proposed rulemaking for which neither a proposed nor final rule has been issued; and (D) unpublished rules on which the NRC expects to take action. Section 2, ''Petitions for Rulemaking,'' includes (A) petitions denied or incorporated into final rules since December 30, 1994; (B) petitions incorporated into proposed rules; (C) petitions pending staff review, and (D) petitions with deferred action

  7. NRC licensing criteria for portable radwaste systems

    International Nuclear Information System (INIS)

    Hayes, J.J. Jr.

    1983-01-01

    The shortcomings of various components of the liquid and solid radwaste systems at nuclear power reactors has resulted in the contracting of the functions performed by these systems to various contractors who utilize portable equipment. In addition, some streams, for which treatment was not originally anticipated, have been processed by portable equipment. The NRC criteria applicable to portable liquid and solid radwaste systems is presented along with discussion on what is required to provide an adequate 10 CFR Part 50.59 review for those situations where changes are made to an existing system. The criteria the NRC is considering for facilities which may intend to utilize portable incinerators is also presented

  8. Leadership practices and staff nurses' intent to stay: a systematic review.

    Science.gov (United States)

    Cowden, Tracy; Cummings, Greta; Profetto-McGrath, Joanne

    2011-05-01

    The aim of the present study was to describe the findings of a systematic review of the literature that examined the relationship between managers' leadership practices and staff nurses' intent to stay in their current position. The nursing shortage demands that managers focus on the retention of staff nurses. Understanding the relationship between leadership practices and nurses' intent to stay is fundamental to retaining nurses in the workforce. Published English language articles on leadership practices and staff nurses' intent to stay were retrieved from computerized databases and a manual search. Data extraction and quality assessments were completed for the final 23 research articles. Relational leadership practices influence staff nurses' intentions to remain in their current position. This study supports a positive relationship between transformational leadership, supportive work environments and staff nurses' intentions to remain in their current positions. Incorporating relational leadership theory into management practices will influence nurse retention. Advancing current conceptual models will increase knowledge of intent to stay. Clarifying the distinction between the concepts intent to stay and intent to leave is needed to establish a clear theoretical foundation for further intent to stay research. Nurse managers and leaders who practice relational leadership and ensure quality workplace environments are more likely to retain their staff. The findings of the present study support the claim that leadership practices influence staff nurse retention and builds on intent to stay knowledge. © 2011 The Authors. Journal compilation © 2011 Blackwell Publishing Ltd.

  9. Improving the health of mental health staff through exercise interventions: a systematic review.

    Science.gov (United States)

    Fibbins, Hamish; Ward, Philip B; Watkins, Andrew; Curtis, Jackie; Rosenbaum, Simon

    2018-04-01

    Exercise interventions are efficacious in reducing cardiometabolic risk and improving symptoms in people with severe mental illness, yet evidence guiding the implementation and scalability of such efforts is lacking. Given increasing efforts to address the disparity in physical health outcomes facing people with a mental illness, novel approaches to increasing adoption of effective interventions are required. Exercise interventions targeting mental health staff may improve staff health while also creating more positive attitudes towards the role of lifestyle interventions for people experiencing mental illness. We aimed to determine the feasibility, acceptability and effectiveness of exercise interventions delivered to staff working in mental health services. A systematic review was conducted from database inception, until November 2017. Studies recruiting staff participants to receive an exercise intervention were eligible for inclusion. Five studies met the inclusion criteria. Physical health interventions for mental health staff were feasible and acceptable with low dropout rates. Reductions in anthropometric measures and work-related stress were reported. Limited evidence suggests that exercise interventions targeting mental health staff are feasible and acceptable. Further research is required to determine the efficacy of such interventions and the impact such strategies may have on staff culture and patient outcomes.

  10. NRC Task Force report on review of the federal/state program for regulation of commercial low-level radioactive waste burial grounds

    International Nuclear Information System (INIS)

    1977-01-01

    The underlying issue explored in this report is that of Federal vs State regulation of commercial radioactive waste burial grounds. The need for research and development, a comprehensive set of standards and criteria, a national plan for low-level waste management, and perpetual care funding are closely related to the central issue and are also discussed. Five of the six commercial burial grounds are regulated by Agreement States; the sixth is regulated solely by the NRC (NRC also regulates Special Nuclear Material at the sites). The sites are operated commercially. The operators contribute to the perpetual care funds for the sites at varying rates. The States have commitments for the perpetual care of the decommissioned sites except for one site, located on Federally owned land. Three conclusions are reached. Federal control over the disposal of low-level waste should be increased by requiring joint Federal/State site approval, NRC licensing, Federal ownership of the land, and a Federally administered perpetual care program. The NRC should accelerate the development of its regulatory program for the disposal of low-level waste. The undisciplined proliferation of low-level burial sites must be avoided. NRC should evaluate alternative disposal methods, conduct necessary studies, and develop a comprehensive low-level waste regulatory program (i.e., accomplish the above recommendations) prior to the licensing of new disposal sites

  11. 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)

  12. NRC perspective and experience on valve testing

    International Nuclear Information System (INIS)

    Eapen, P.K.

    1990-01-01

    Testing of safety related valves is one of the major activities at commercial nuclear power plants. In addition to Technical Specification, valve testing is required in 10 CFR 50.55a and 10 CFR 50 Appendix J. NRC inspectors (both resident and specialists) spend a considerable amount of time in following the valve test activities as part of their routine business. In the past, depending on a licensee's organizational structure, a valve could be tested more than three times to verify conformance with Technical Specifications, 10 CFR 50.55a, and 10 CFR 50 Appendix J. The regulatory reviewers were isolated from each other. Licensee test personnel were also not communicating among themselves. As a result, NRC inspectors found that certain valves in the IST program were inadequately tested. The typical licensee response was to say that this valve is exempted from testing under Appendix J. Others would say that the technical specification does not require fast closure of a valve in question. In addition to the above, the inspectors had to deal with exemption requests that were not dispositioned by the NRC. In the seventies there was a gentlemen's agreement to allow the licensee to do the testing in accordance with the exception, without waiting for the NRC approval. Needless to say when the new NRC inspection procedure was issued in March 1989 for implementation, the Regional inspectors had extremely difficult time to cope with the gray areas of valve testing. In August 1987, NRC Region I was reorganized and the special test program section was established to perform inspections in the IST area. This section was chartered to optimize resources and develop a meaningful inspection plan. The perspectives and insights used in the development of a detailed inspection plan is discussed below

  13. The Impact on Staff of Working with Personality Disordered Offenders: A Systematic Review.

    Directory of Open Access Journals (Sweden)

    Mark C Freestone

    Full Text Available Personality disordered offenders (PDOs are generally considered difficult to manage and to have a negative impact on staff working with them.This study aimed to provide an overview of studies examining the impact on staff of working with PDOs, identify impact areas associated with working with PDOs, identify gaps in existing research,and direct future research efforts.The authors conducted a systematic review of the English-language literature from 1964-2014 across 20 databases in the medical and social sciences.27 papers were included in the review. Studies identified negative impacts upon staff including: negative attitudes, burnout, stress, negative counter-transferential experiences; two studies found positive impacts of job excitement and satisfaction, and the evidence related to perceived risk of violence from PDOs was equivocal. Studies demonstrated considerable heterogeneity and meta-analysis was not possible. The overall level of identified evidence was low: 23 studies (85% were descriptive only, and only one adequately powered cohort study was found.The review identified a significant amount of descriptive literature, but only one cohort study and no trials or previous systematic reviews of literatures. Clinicians and managers working with PDOs should be aware of the potential impacts identified, but there is an urgent need for further research focusing on the robust evaluation of interventions to minimise harm to staff working with offenders who suffer from personality disorder.

  14. Burnout intervention studies for inpatient elderly care nursing staff: systematic literature review.

    Science.gov (United States)

    Westermann, Claudia; Kozak, Agnessa; Harling, Melanie; Nienhaus, Albert

    2014-01-01

    Staff providing inpatient elderly and geriatric long-term care are exposed to a large number of factors that can lead to the development of burnout syndrome. Burnout is associated with an increased risk of absence from work, low work satisfaction, and an increased intention to leave. Due to the fact that the number of geriatric nursing staff is already insufficient, research on interventions aimed at reducing work-related stress in inpatient elderly care is needed. The aim of this systematic review was to identify and analyse burnout intervention studies among nursing staff in the inpatient elderly and geriatric long-term care sector. A systematic search of burnout intervention studies was conducted in the databases Embase, Medline and PsycNet published from 2000 to January 2012. We identified 16 intervention studies. Interventions were grouped into work-directed (n=2), person-directed (n=9) and combined approaches (work- and person-directed, n=5). Seven out of 16 studies observed a reduction in staff burnout. Among them are two studies with a work-directed, two with a person-directed and three with a combined approach. Person-directed interventions reduced burnout in the short term (up to 1 month), while work-directed interventions and those with a combined approach were able to reduce burnout over a longer term (from 1 month to more than 1 year). In addition to staff burnout, three studies observed positive effects relating to the client outcomes. Only three out of ten Randomised Control Trials (RCT) found that interventions had a positive effect on staff burnout. Work-directed and combined interventions are able to achieve beneficial longer-term effects on staff burnout. Person-directed interventions achieve short-term results in reducing staff burnout. However, the evidence is limited. Copyright © 2012 Elsevier Ltd. All rights reserved.

  15. NRC's license renewal regulations

    International Nuclear Information System (INIS)

    Akstulewicz, Francis

    1991-01-01

    In order to provide for the continuity of the current generation of nuclear power plant operating licenses and at the same time ensure the health and safety of the public, and the quality of the environment, the US Nuclear Regulatory Commission (NRC) established a goal of developing and issuing regulations and regulatory guidance for license renewal in the early 1990s. This paper will discuss some of those activities underway to achieve this goal. More specifically, this paper will discuss the Commission's regulatory philosophy for license renewal and the two major license renewal rule makings currently underway. The first is the development of a new Part 54 to address procedural and technical requirements for license renewal; the second is a revision to existing Part 51 to exclude environmental issues and impacts from consideration during the license renewal process. (author)

  16. NRC quarterly [status] report

    International Nuclear Information System (INIS)

    1987-01-01

    This report covers the third quarter of calendar year 1987. The NRC licensing activity during the period of this report included the issuance of a full-power license for Beaver Valley 2 on August 14, 1987, and operating license restricted to five percent power for South Texas Unit 1 on August 21, 1987. Additional licensing delay for Shoreham is projected due to complex litigation. Also, licensing delay may occur for Comanche Peak Unit 1, because the duration of the hearing is uncertain. Although a license authorizing fuel loading and precriticality testing for Seabrook Unit 1 has been issued, there is a projected delay for low-power licensing. Full-power licensing for Seabrook Unit 1 will be delayed due to offsite emergency preparedness issues. The length of the delay is not known at this time. With the exception of Seabrook and Shoreham, regulatory delays in this report are not impacted by the schedules for resolving off-site emergency preparedness issues

  17. NRC Perspectives on Waste Incidental to Reprocessing Consultations and Monitoring - 13398

    Energy Technology Data Exchange (ETDEWEB)

    McKenney, Christepher A.; Suber, Gregory F.; Felsher, Harry D.; Mohseni, Aby [U.S. Nuclear Regulatory Commission, Mail Stop T8F5, 11545 Rockville Pike, Rockville, MD 20852 (United States)

    2013-07-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste (HLW) determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations to assess compliance with NRC regulations in 10 CFR Part 61, Subpart C. The NDAA applies to DOE activities that will remain within the States of South Carolina and Idaho. DOE has chosen to, under DOE Order 435.1, engage in consultation with NRC for similar activities in the State of Washington and New York, however, the NRC has no monitoring responsibilities. In 2007, the NRC developed a draft Final Report for Interim Use entitled, NUREG-1854: NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations. Since the law was enacted, the DOE and NRC have consulted on three waste determinations within the affected States: (1) the Saltstone Disposal Facility at the Savannah River Site (SRS) within the State of South Carolina in 2005, (2) the INTEC Tank Farm at the Idaho National Laboratory within the State of Idaho in 2006, and (3) the F Tank Farm at SRS in 2011. After the end of consultation and issuance by DOE of the final waste determination, monitoring began at each of these sites, including the development of monitoring plans. In addition to the NDAA sites, DOE has requested NRC consultation support on both individual tanks and the entire C Tank Farm at the Hanford Nuclear Reservation in the State of Washington. DOE also requested consultation of waste determinations performed on the melter and related feed tanks at the West Valley site in New York that would be disposed offsite. In the next few years, NRC and DOE will consult on the last of the NDAA waste determinations for a while, the H Tank Farm waste determination at SRS. DOE may identify other activities in the future but

  18. NRC Perspectives on Waste Incidental to Reprocessing Consultations and Monitoring - 13398

    International Nuclear Information System (INIS)

    McKenney, Christepher A.; Suber, Gregory F.; Felsher, Harry D.; Mohseni, Aby

    2013-01-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste (HLW) determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations to assess compliance with NRC regulations in 10 CFR Part 61, Subpart C. The NDAA applies to DOE activities that will remain within the States of South Carolina and Idaho. DOE has chosen to, under DOE Order 435.1, engage in consultation with NRC for similar activities in the State of Washington and New York, however, the NRC has no monitoring responsibilities. In 2007, the NRC developed a draft Final Report for Interim Use entitled, NUREG-1854: NRC Staff Guidance for Activities Related to U.S. Department of Energy Waste Determinations. Since the law was enacted, the DOE and NRC have consulted on three waste determinations within the affected States: (1) the Saltstone Disposal Facility at the Savannah River Site (SRS) within the State of South Carolina in 2005, (2) the INTEC Tank Farm at the Idaho National Laboratory within the State of Idaho in 2006, and (3) the F Tank Farm at SRS in 2011. After the end of consultation and issuance by DOE of the final waste determination, monitoring began at each of these sites, including the development of monitoring plans. In addition to the NDAA sites, DOE has requested NRC consultation support on both individual tanks and the entire C Tank Farm at the Hanford Nuclear Reservation in the State of Washington. DOE also requested consultation of waste determinations performed on the melter and related feed tanks at the West Valley site in New York that would be disposed offsite. In the next few years, NRC and DOE will consult on the last of the NDAA waste determinations for a while, the H Tank Farm waste determination at SRS. DOE may identify other activities in the future but largely

  19. NRC regulation of DOE facilities

    International Nuclear Information System (INIS)

    Buhl, A.R.; Edgar, G.; Silverman, D.; Murley, T.

    1997-01-01

    The US Department of Energy (DOE), its contractors, and the Nuclear Regulatory Commission (NRC) are in for major changes if the DOE follows through on its intentions announced December 20, 1996. The DOE is seeking legislation to establish the NRC as the regulatory agency with jurisdiction over nuclear health, safety, and security at a wide range of DOE facilities. At this stage, it appears that as many as 200 (though not all) DOE facilities would be affected. On March 28, 1997, the NRC officially endorsed taking over the responsibility for regulatory oversight of DOE nuclear facilities as the DOE had proposed, contingent upon adequate funding, staffing resources, and a clear delineation of NRC authority. This article first contrasts the ways in which the NRC and the DOE carry out their basic regulatory functions. Next, it describes the NRC's current authority over DOE facilities and the status of the DOE's initiative to expand that authority. Then, it discusses the basic changes and impacts that can be expected in the regulation of DOE facilities. The article next describes key lessons learned from the recent transition of the GDPs from DOE oversight to NRC regulation and the major regulatory issues that arose in that transition. Finally, some general strategies are suggested for resolving issues likely to arise as the NRC assumes regulatory authority over DOE facilities

  20. NRC influences on nuclear training

    International Nuclear Information System (INIS)

    Hannon, J.N.

    1987-01-01

    NRC influences on utility training programs through prescriptive requirements and evaluation of industry self-initiatives are discussed. NRC regulation and industry initiatives are complimentary and in some instances industry initiatives are replacing NRC requirements. Controls and feedback mechanisms designed to enhance positive NRC influences and minimize or eliminate negative influences are discussed. Industry and NRC efforts to reach an acceptable mix between regulator oversight and self-initiatives by the industry are recognized. Problem areas for continued cooperation to enhance training and minimize conflicting signals to industry are discussed. These areas include: requalification examination scope and content, depth of training and examination on emergency procedures; improved learning objectives as the basis for training and examination, and severe accident training

  1. AECB staff review of Bruce NGS'A' operation for the year 1987

    International Nuclear Information System (INIS)

    1988-06-01

    This report presents AECB project staff's review of major licensing issues and of the operational performance of the station during 1987. Ontario Hydro reports and official correspondence and observations on AECB staff at site have been taken into consideration. The report is limited to aspects of the station performance that AECB staff considers to have a safety significance. Where significant developments associated with issues addressed in the report occurred in the early part of 1988 (up to the time of writing), these are mentioned where appropriate. Ontario Hydro's Quarterly Reports for 1987 contain detailed technical information on the performance of the station, individual units and unit systems. It is the opinion of AECB project staff that despite a number of commendable actions and achievements which are identified in this report, the performance of the station in 1987 was only marginally satisfactory and less satisfactory than in 1986. This assessment is supported by key performance indicators such as the number of reportable significant events, the number of events caused by or influenced by human error and the reactor trip frequency, all of which exceeded 1986 levels, and also by the lack of satisfactory progress made during the year on actions to address the findings of the Fall '86 AECB Assessment of Operating Practices. AECB staff considers that the outstanding operations and maintenance problems that were identified in the 1986 Assessment are due, in part, to an ineffective quality assurance program, and in part to a shortage of resources

  2. 10 CFR 51.104 - NRC proceeding using public hearings; consideration of environmental impact statement.

    Science.gov (United States)

    2010-01-01

    ... environmental impact statement. 51.104 Section 51.104 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED....104 NRC proceeding using public hearings; consideration of environmental impact statement. (a)(1) In... scope of NEPA and this subpart are in issue, the NRC staff may not offer the final environmental impact...

  3. Disaster Preparedness among Health Professionals and Support Staff: What is Effective? An Integrative Literature Review.

    Science.gov (United States)

    Gowing, Jeremy R; Walker, Kim N; Elmer, Shandell L; Cummings, Elizabeth A

    2017-06-01

    Introduction It is important that health professionals and support staff are prepared for disasters to safeguard themselves and the community during disasters. There has been a significantly heightened focus on disasters since the terrorist attacks of September 11, 2001 in New York (USA); however, despite this, it is evident that health professionals and support staff may not be adequately prepared for disasters. Report An integrative literature review was performed based on a keyword search of the major health databases for primary research evaluating preparedness of health professionals and support staff. The literature was quality appraised using a mixed-methods appraisal tool (MMAT), and a thematic analysis was completed to identify current knowledge and gaps. Discussion The main themes identified were: health professionals and support staff may not be fully prepared for disasters; the most effective content and methods for disaster preparedness is unknown; and the willingness of health professionals and support staff to attend work and perform during disasters needs further evaluation. Gaps were identified to guide further research and the creation of new knowledge to best prepare for disasters. These included the need for: high-quality research to evaluate the best content and methods of disaster preparedness; inclusion of the multi-disciplinary health care team as participants; preparation for internal disasters; the development of validated competencies for preparedness; validated tools for measurement; and the importance of performance in actual disasters to evaluate preparation. The literature identified that all types of disaster preparedness activities lead to improvements in knowledge, skills, or attitude preparedness for disasters. Most studies focused on external disasters and the preparedness of medical, nursing, public health, or paramedic professionals. There needs to be a greater focus on the whole health care team, including allied health

  4. AECB staff review of Bruce NGS 'A' operation for the year 1988

    International Nuclear Information System (INIS)

    1989-05-01

    AECB project staff believes that overall performance of the station in 1988 was generally satisfactory and better than in 1987. However, this assessment is not supported by some of the key performance indicators, although the indicators in areas where AECB staff had specific concerns do support it. For example, the percentage of reported significant events attributable to human error, the number of operating memos beyond the review date, scheduled emergency drills completed, the number of completed reactor trips all show a significant improvement over the 1987 value. In addition, AECB staff has been encouraged by the licensee's implementation of effective review processes for operator and maintenance call-ups, routines and deficiencies, and the establishment of supervisor inspection tours and operator rounds programs. Nevertheless, it is the opinion of AECB staff that to achieve standards of operation which would be considered fully satisfactory, the backlog of maintenance work must be reduced, the quality of work performed in the plant improved, and assurance provided that the required quality standards are being consistently achieved and maintained

  5. Arts-based palliative care training, education and staff development: A scoping review.

    Science.gov (United States)

    Turton, Benjamin Mark; Williams, Sion; Burton, Christopher R; Williams, Lynne

    2018-02-01

    The experience of art offers an emerging field in healthcare staff development, much of which is appropriate to the practice of palliative care. The workings of aesthetic learning interventions such as interactive theatre in relation to palliative and end-of-life care staff development programmes are widely uncharted. To investigate the use of aesthetic learning interventions used in palliative and end-of-life care staff development programmes. Scoping review. Published literature from 1997 to 2015, MEDLINE, CINAHL and Applied Social Sciences Index and Abstracts, key journals and citation tracking. The review included 138 studies containing 60 types of art. Studies explored palliative care scenarios from a safe distance. Learning from art as experience involved the amalgamation of action, emotion and meaning. Art forms were used to transport healthcare professionals into an aesthetic learning experience that could be reflected in the lived experience of healthcare practice. The proposed learning included the development of practical and technical skills; empathy and compassion; awareness of self; awareness of others and the wider narrative of illness; and personal development. Aesthetic learning interventions might be helpful in the delivery of palliative care staff development programmes by offering another dimension to the learning experience. As researchers continue to find solutions to understanding the efficacy of such interventions, we argue that evaluating the contextual factors, including the interplay between the experience of the programme and its impact on the healthcare professional, will help identify how the programmes work and thus how they can contribute to improvements in palliative care.

  6. Dementia training programmes for staff working in general hospital settings - a systematic review of the literature.

    Science.gov (United States)

    Scerri, Anthony; Innes, Anthea; Scerri, Charles

    2017-08-01

    Although literature describing and evaluating training programmes in hospital settings increased in recent years, there are no reviews that summarise these programmes. This review sought to address this, by collecting the current evidence on dementia training programmes directed to staff working in general hospitals. Literature from five databases were searched, based on a number of inclusion criteria. The selected studies were summarised and data was extracted and compared using narrative synthesis based on a set of pre-defined categories. Methodological quality was assessed. Fourteen peer-reviewed studies were identified with the majority being pre-test post-test investigations. No randomised controlled trials were found. Methodological quality was variable with selection bias being the major limitation. There was a great variability in the development and mode of delivery although, interdisciplinary ward based, tailor-made, short sessions using experiential and active learning were the most utilised. The majority of the studies mainly evaluated learning, with few studies evaluating changes in staff behaviour/practices and patients' outcomes. This review indicates that high quality studies are needed that especially evaluate staff behaviours and patient outcomes and their sustainability over time. It also highlights measures that could be used to develop and deliver training programmes in hospital settings.

  7. 75 FR 60485 - NRC Enforcement Policy Revision

    Science.gov (United States)

    2010-09-30

    ... NUCLEAR REGULATORY COMMISSION [NRC-2008-0497] NRC Enforcement Policy Revision AGENCY: Nuclear Regulatory Commission. ACTION: Policy statement. SUMMARY: The Nuclear Regulatory Commission (NRC or Commission) is publishing a major revision to its Enforcement Policy (Enforcement Policy or Policy) to...

  8. NRC Waste Incidental to Reprocessing Program: Overview of Consultation and Monitoring Activities at the Idaho National Laboratory and the Savannah River Site - What We Have Learned - 12470

    Energy Technology Data Exchange (ETDEWEB)

    Suber, Gregory [Nuclear Regulatory Commission (United States)

    2012-07-01

    In 2005 the U.S. Nuclear Regulatory Commission (NRC) began to implement a new set of responsibilities under the Ronald W. Reagan National Defense Authorization Act (NDAA) of Fiscal Year 2005. Section 3116 of the NDAA requires the U.S. Department of Energy (DOE) to consult with the NRC for certain non-high level waste determinations and also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2005, the NRC staff began consulting with DOE and completed reviews of draft waste determinations for salt waste at the Savannah River Site. In 2006, a second review was completed on tank waste residuals including sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center Tank Farm at the Idaho National Laboratory. Monitoring Plans were developed for these activities and the NRC is actively monitoring disposal actions at both sites. NRC is currently in consultation with DOE on the F-Area Tank Farm closure and anticipates entering consultation on the H-Area Tank Farm at the Savannah River Site. This paper presents, from the NRC perspective, an overview of how the consultation and monitoring process has evolved since its conception in 2005. It addresses changes in methods and procedures used to collect and develop information used by the NRC in developing the technical evaluation report and monitoring plan under consultation and the implementation the plan under monitoring. It will address lessons learned and best practices developed throughout the process. The NDAA has presented significant challenges for the NRC and DOE. Past and current successes demonstrate that the NDAA can achieve its intended goal of facilitating tank closure at DOE legacy defense waste sites. The NRC believes many of the challenges in performing the WD reviews have been identified and addressed. Lessons learned have been collected and documented throughout the review process. Future success will be contingent on each agencies commitment to

  9. Interim staff position on environmental qualification of safety-related electrical equipment: including staff responses to public comments. Regulatory report

    International Nuclear Information System (INIS)

    Szukiewicz, A.J.

    1981-07-01

    This document provides the NRC staff positions regarding selected areas of environmental qualification of safety-related electrical equipment, in the resolution of Unresolved Safety Issue A-24, 'Qualification of Class IE Safety-Related Equipment.' The positions herein are applicable to plants that are or will be in the construction permit (CP) or operating license (OL) review process and that are required to satisfy the requirements set forth in either the 1971 or the 1974 version of IEEE-323 standard

  10. Status report on NRC's current below regulatory concern activities

    International Nuclear Information System (INIS)

    Dragonette, K.S.

    1988-01-01

    The concept of below regulatory concern (BRC) is not new to the Nuclear Regulatory Commission (NRC) or its predecessor agency, the Atomic Energy Commission. The regulations and licensing decisions have involved limited and de facto decisions on BRC since the beginning. For example, consumer products containing radioactive materials have been approved for distribution to persons exempt from licensing for some time and procedures for survey and release of equipment have traditionally been a part of many licensees' radiation safety programs. However, these actions have generally been ad hoc decisions in response to specific needs and have not been necessarily consistent. The need to deal with this regulatory matter has been receiving attention from both Congress and the NRC Commissioners. NRC response has grown from addressing specific waste streams, to generic rulemaking for wastes, and finally to efforts to develop a broad generic BRC policy. Section 10 of the Low-Level Radioactive Waste Policy Amendments Act of 1985 addressed NRC actions on specific waste streams. In response, NRC issued guidance on rulemaking petitions for specific wastes. NRC also issued an advance notice of proposed rulemaking indicating consideration of Commission initiated regulations to address BRC wastes in a generic manner. The Commissioners have directed staff to develop an umbrella policy for all agency decisions concerning levels of risk or dose that do not require government regulation

  11. NRC new sustainable building

    International Nuclear Information System (INIS)

    Semczyszyn, D.

    2004-01-01

    'Full text:' The National Research Council Institute For Fuel Cell Innovation is relocating to a purpose-built 71,343 sq. Ft. (6598 sq. M) Research, Testing, Evaluation, and Industry Incubation Facility in the spring of 2006. The new facility will contain Hydrogen-ready laboratories, the existing relocated Hydrogen Safe Environmental Test Chamber, a hydrogen vehicle maintenance bay, a hydrogen vehicle refuelling station, and the following demonstration projects and features: 1. A Ground Source Heat Pump: This long-proven natural-source heating and cooling technology to provide climate control for the new IFCI's atrium and galleria. It is being designed by Keen Engineering of North Vancouver, BC. 2. 5 KW Solid Oxide Fuel Cell System: Fuelled by natural gas and in the future, from biomass, the fuel cell will also produce approximately 15 kW of waste heat, which will be captured and used to supply heat for the building. The Solid Oxide Fuel Cell will be supplied by Fuel Cell Technologies in Kingston, ON. 3. LEED Building certification: Attaining LEED 'green building' certification is considered an important complement to the plans for the new NRC-IFCI, because it will provide respected third-party verification of government's commitment to efficient building design and construction. Project architects Bunting Coady of Vancouver, BC believe the IFCI has strong potential to earn gold LEED certification. 4. Photovoltaic hydrogen source for back-up power fuel cell system: A photovoltaic array will capture energy from sunlight to power an electrolyzer that will produce and store hydrogen for a PEM fuel cell emergency backup power system. The electrolyzer will be provided by Hydrogenics of Mississauga, ON. Photovoltaics are being designed and installed by the British Columbia Institute of Technology. (author)

  12. NRC nuclear waste geochemistry 1983

    International Nuclear Information System (INIS)

    Alexander, D.H.; Birchard, G.F.

    1984-05-01

    The purpose of the meeting was to present results from NRC-sponsored research and to identify regulatory research issues which need to be addressed prior to licensing a high-level waste repository. Important summaries of technical issues and recommendations are included with each paper. The issue reflect areas of technical uncertainty addressed by the NRC Research program in geochemistry. The objectives of the NRC Research Program in geochemistry are to provide a technical basis for waste management rulemaking, to provide the NRC Waste Management Licensing Office with information that can be used to support sound licensing decisions, and to identify investigations that need to be conducted by DOE to support a license application. Individual papers were processed for inclusion in the Energy Data Base

  13. 75 FR 57779 - Science Advisory Board Staff Office; Notification of a Public Meeting of the SAB Dioxin Review Panel

    Science.gov (United States)

    2010-09-22

    ... a Public Meeting of the SAB Dioxin Review Panel AGENCY: Environmental Protection Agency (EPA...) Staff Office announces a public meeting of the SAB Dioxin Review Panel to continue its review of EPA's Reanalysis of Key Issues Related to Dioxin Toxicity and Response to NAS Comments, External Review Draft...

  14. Development of Mitigation Strategy for Beyond Design Basis External Events for NRC Design Certification

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dong Hak; Lee, Jae Jong; Kim, Myung Ki [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    In this study, how to develop FLEX strategy for beyond-design-basis external events for U. S. NRC design certification is examined. The development method of FLEX strategy for U. S. NRC design certification is examined. The applicants should make unit-specific FLEX strategy and establish the minimum coping capabilities consistent with unit-specific evaluation of the potential impacts and responses to BDBEEs. NEI 12-06 outlines the process to define and deploy the diverse and flexible mitigation strategies(FLEX strategy) that will increase defense-in-depth for beyond-design-basis scenarios to address the extended loss of alternating current (ac) power (ELAP) and loss of normal access to the ultimate heat sink (LUHS) occurring simultaneously at all units on a site. The order (EA-12-049) is issued to all reactor licensees, including holders of active, Construction Permit (CP) holders, and Combined License (COL) holders. Applicants for the new reactor design certification should prepare and submit FLEX strategy for NRC staff's review. Site-specific data related with the new reactor can't be determined during the new reactor design certification applications so that the unit-specific FLEX strategy should be developed.

  15. Development of Mitigation Strategy for Beyond Design Basis External Events for NRC Design Certification

    International Nuclear Information System (INIS)

    Kim, Dong Hak; Lee, Jae Jong; Kim, Myung Ki

    2013-01-01

    In this study, how to develop FLEX strategy for beyond-design-basis external events for U. S. NRC design certification is examined. The development method of FLEX strategy for U. S. NRC design certification is examined. The applicants should make unit-specific FLEX strategy and establish the minimum coping capabilities consistent with unit-specific evaluation of the potential impacts and responses to BDBEEs. NEI 12-06 outlines the process to define and deploy the diverse and flexible mitigation strategies(FLEX strategy) that will increase defense-in-depth for beyond-design-basis scenarios to address the extended loss of alternating current (ac) power (ELAP) and loss of normal access to the ultimate heat sink (LUHS) occurring simultaneously at all units on a site. The order (EA-12-049) is issued to all reactor licensees, including holders of active, Construction Permit (CP) holders, and Combined License (COL) holders. Applicants for the new reactor design certification should prepare and submit FLEX strategy for NRC staff's review. Site-specific data related with the new reactor can't be determined during the new reactor design certification applications so that the unit-specific FLEX strategy should be developed

  16. Advanced Light Water Reactor Program: Program management and staff review methodology

    International Nuclear Information System (INIS)

    Moran, D.H.

    1986-12-01

    This report summarizes the NRC/EPRI coordinated effort to develop design requirements for a standardized advanced light water reactor (ALWR) and the procedures for screening and applying new generic safety issues to this program. The end-product will be an NRC-approved ALWR Requirements Document for use by the nuclear industry in generating designs of LWRs to be constructed for operation in the 1990s and beyond

  17. NRC's geotechnical engineering research needs for the high-level waste repository program

    International Nuclear Information System (INIS)

    Gupta, D.C.; Philip, J.; Lorig, L.J.; Chowdhury, A.H.

    1992-01-01

    To develop the capability for independently assessing the US Department of Energy's (DOE's) geologic repository design within a limited time, the US Nuclear Regulatory Commission (NRC) staff needs to perform certain research well before receiving the license application. The NRC staff is using a number of factors to identify the areas that it needs to research. The staff assigns priorities to the needed research based on programmatic considerations and the significance of the work. In the geotechnical engineering field, the staff is conducting research in the following three areas: response of the repository to repeated strong ground motion, rock-mass sealing, and coupled thermo-hydro-mechanical interactions. In this paper, the NRC staff also presents the areas of additional research needed in the geotechnical engineering field

  18. Constructive staff-family relationships in the care of older adults in the institutional setting: A systematic review.

    Science.gov (United States)

    Haesler, Emily; Bauer, Michael; Nay, Rhonda

    2004-01-01

    Modern health care philosophy espouses the virtues of holistic care and acknowledges that family involvement is appropriate and something to be encouraged due to the role it plays in physical and emotional healing. In the aged care sector, the involvement of families is a strong guarantee of a resident's wellbeing. The important role family plays in the support and care of the older adult in the residential aged care environment has been enshrined in the Australian Commonwealth Charter of Residents' Rights and Responsibilities and the Aged Care Standards of Practice. Despite wide acknowledgement of the importance of family imvolvement in the health care of the older adult, many barriers to the implementation of participatory family care have been identified in past research. For older adults in the health care environment to benefit from the involvement of their family members, health care professionals need an understanding of the issues surrounding family presence in the health care environement and the strategies to best support it. The objectives of the systematic review were to present the best available evidence on the strategies, practices and organisational characteristics that promote constructive staff-family relationships in the care of older adults in the health care setting. Specifically this review sought to investigate how staff and family members perceive their relationships with each other; staff characteristics that promote constructive relationships with the family; and interventions that support staff-family relationships. A literature search was performed using the following databases for the years 1990-2005: Ageline, APAIS Health, Australian Family & Society Abstracts (FAMILY), CINAHL, Cochrane Library, Dare, Dissertation Abstracts, Embase, MEDLINE, PsycINFO, and Social Science Index. Personal communication from expert panel members was also used to identify studies for inclusion. A second search stage was conducted through review of reference

  19. NRC iterative performance assessment Phase 2. Development of capabilities for review of a performance assessment for a high-level waste repository

    International Nuclear Information System (INIS)

    Wescott, R.G.; Lee, M.P.; Eisenberg, N.A.; Baca, R.G.

    1995-10-01

    In order to better review a potential license application to construct and operate a geologic repository for spent nuclear fuel and high-level radioactive waste (HLW), the Nuclear Regulatory Commission staff (and its contractor) has expanded and improved its capability to conduct performance assessments. This report documents the demonstration of the second phase of this capability. The demonstration made use of the scenario selection procedure developed by Sandia National Laboratories to provide a set of scenarios, with corresponding probabilities, for use in the consequence analysis of a potential HLW disposal site in unsaturated tuff. Models of release of radionuclides from the waste form and transport in ground water, air and by direct pathways provided preliminary estimates of releases to the accessible environment for a 10,000 year period. The input values of parameters necessary for the consequence models were sampled numerous times using Latin Hypercube Sampling from assumed probability distributions. The results from the consequence models were then used to generate Complementary Cumulative Distribution Functions (CCDFs) for either release to the accessible environment or effective dose equivalents to a target population. CCDFs were calculated for probabilistically significant combinations (scenarios) of four disruptive events; drilling, pluvial climate, seismicity and magmatism. Sensitivity and uncertainty analyses of the calculated releases and effective dose equivalents were also used to determine the importance of the parameters. Because of the preliminary nature of the analysis and the lack of an adequate data base, the results and conclusions presented in this report should be carefully interpreted. They should not be misconstrued to represent the actual performance of the proposed Yucca Mountain repository nor serve as an endorsement of the methods used

  20. 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...

  1. Information to licensees regarding two NRC Inspection Manual sections on resolution of degraded and nonconforming conditions and on operability (Generic Letter 91-18)

    International Nuclear Information System (INIS)

    Partlow, J.G.

    1992-01-01

    The NRC staff has issued two sections to be included in Part 9900, Technical Guidance, of the NRC Inspection Manual. The first is, ''Resolution of Degraded and Nonconforming Conditions.'' The second is, ''Operable/Operability: Ensuring the Functional Capability of a System or Component.'' Copies of the additions to the NRC Inspection Manual are provided for information only. No specific licensee actions are required. The additions to the NRC Inspection Manual are based upon previously issued guidance. However, because of the complexity involved in operability determinations and the resolution of degraded and nonconforming conditions, there have been differences in application by NRC staff during past inspection activities. Thus, the purpose of publishing this guidance is to ensure consistency in application of this guidance by the NRC. Regional inspection personnel have been briefed on this guidance. The NRC will conduct further training on these topics to ensure uniform staff understanding

  2. NRC comprehensive records disposition schedule

    International Nuclear Information System (INIS)

    1982-07-01

    Effective January 1, 1982, NRC will institute records retention and disposal practices in accordance with the approved Comprehensive Records Disposition Schedule (CRDS). CRDS is comprised of NRC Schedules (NRCS) 1 to 4 which apply to the agency's program or substantive records and General Records Schedules (GRS) 1 to 22 which apply to housekeeping or facilitative records. The schedules are assembled functionally/organizationally to facilitate their use. Preceding the records descriptions and disposition instructions for both NRCS and GRS, there are brief statements on the organizational units which accumulate the records in each functional area, and other information regarding the schedules' applicability

  3. NRC comprehensive records disposition schedule

    International Nuclear Information System (INIS)

    1983-05-01

    Effective January 1, 1982, NRC will institute records retention and disposal practives in accordance with the approved Comprehensive Records Disposition Schedule (CRDS). CRDS is comprised of NRC Schedules (NRCS) 1 to 4 which apply to the agency's program or substantive records and General Records Schedules (GRS) 1 to 24 which apply to housekeeping or facilitative records. NRCS-I applies to records common to all or most NRC offices; NRCS-II applies to program records as found in the various offices of the Commission, Atomic Safety and Licensing Board Panel, and the Atomic Safety and Licensing Appeal Panel; NRCS-III applies to records accumulated by the Advisory Committee on Reactor Safeguards; and NRCS-IV applies to records accumulated in the various NRC offices under the Executive Director for Operations. The schedules are assembled functionally/organizationally to facilitate their use. Preceding the records descriptions and disposition instructions for both NRCS and GRS, there are brief statements on the organizational units which accumulate the records in each functional area, and other information regarding the schedules' applicability

  4. The attitudes of health care staff to information technology: a comprehensive review of the research literature.

    Science.gov (United States)

    Ward, Rod; Stevens, Christine; Brentnall, Philip; Briddon, Jason

    2008-06-01

    What does the publicly available literature tell us about the attitudes of health care staff to the development of information technology in practice, including the factors which influence them and the factors which may be used to change these attitudes? Twelve databases were searched for literature published between 2000 and 2005 that identified research related to information technology (IT), health professionals and attitude. English language studies were included which described primary research relating to the attitudes of one or more health care staff groups towards IT. Letters, personal viewpoints, reflections and opinion pieces were not included. Complex factors contribute to the formation of attitudes towards IT. Many of the issues identified were around the flexibility of the systems and whether they were 'fit for purpose', along with the confidence and experience of the IT users. The literature suggests that attitudes of practitioners are a significant factor in the acceptance and efficiency of use of IT in practice. The literature also suggested that education and training was a factor for encouraging the use of IT systems. A range of key issues, such as the need for flexibility and usability, appropriate education and training and the need for the software to be 'fit for purpose', showed that organizations need to plan carefully when proposing the introduction of IT-based systems into work practices. The studies reviewed did suggest that attitudes of health care professionals can be a significant factor in the acceptance and efficiency of use of IT in practice. Further qualitative and quantitative research is needed into the approaches that have most effect on the attitudes of health care staff towards IT.

  5. 78 FR 25487 - Final License Renewal Interim Staff Guidance LR-ISG-2012-01: Wall Thinning Due to Erosion Mechanisms

    Science.gov (United States)

    2013-05-01

    ..., ``Flow- Accelerated Corrosion,'' based on the staff's review of several license renewal applications' flow-accelerated corrosion AMPs and stakeholder input. ADDRESSES: Please refer to Docket ID NRC-2012... learned and to address emergent issues not covered in license renewal guidance documents, such as the GALL...

  6. Topical report review status. Bi-annual report 15 July 1980-15 July 1981

    International Nuclear Information System (INIS)

    1981-07-01

    The primary purpose of this document is to provide periodic progress reports of on-going topical report reviews, to identify those topical reports for which the Nuclear Regulatory Commission (NRC) staff review has been completed and, to the extent practicable, to provide NRC management with sufficient information regarding the conduct of the topical report program to permit taking whatever actions deemed necessary or appropriate

  7. Final report of the NRC-Agreement State Working Group to evaluate control and accountability of licensed devices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    US NRC staff acknowledged that licensees were having problems maintaining control over and accountability for devices containing radioactive material. In June 1995, NRC approved the staff`s suggestion to form a joint NRC-Agreement State Working Group to evaluate the problem and propose solutions. The staff indicated that the Working Group was necessary to address the concerns from a national perspective, allow for a broad level of Agreement State input, and to reflect their experience. Agreement State participation in the process was essential since some Agreement States have implemented effective programs for oversight of device users. This report includes the 5 recommendations proposed by the Working Group to increase regulatory oversight, increase control and accountability of devices, ensure proper disposal, and ensure disposal of orphaned devices. Specifically, the Working Group recommends that: (1) NRC and Agreement States increase regulatory oversight for users of certain devices; (2) NRC and Agreement State impose penalties on persons losing devices; (3) NRC and Agreement States ensure proper disposal of orphaned devices; (4) NRC encourage States to implement similar oversight programs for users of Naturally-Occurring or Accelerator- Produced Material; and (5) NRC encourage non-licensed stakeholders to take appropriate actions, such as instituting programs for material identification.

  8. Dementia-specific training for nursing home staff : A systematic literature review.

    Science.gov (United States)

    Riesch, Julia; Meyer, Lucy; Lehr, Bosco; Severin, Thomas

    2017-08-22

    For people with dementia high-quality care is vital, since at present dementia cannot be cured. In nursing homes this care is provided by the staff, who therefore require dementia-specific training enabling them to improve the quality of life for people with dementia. This article compares existing dementia-specific training for nursing home staff with recommendations, based on the current state of research, by the Alzheimer's Association and the National Institute for Health and Care Excellence, and discusses the outcome of this training. A systematic review of the literature was conducted to identify studies addressing dementia-specific training. The electronic databases Embase, Medline, Cochrane, CINAHL, PsychINFO, PSYNDEX, and ScienceDirect were searched. The training topics most commonly considered were person-centered care, communicating with people affected by dementia, and information about dementia. The roles of different social and healthcare professionals, palliative care of people with dementia, and understanding family dynamics are least featured in the training. There are training concepts which focus not only on the transfer of knowledge but also on practical exercises. In general, the recommended topics were addressed in dementia-specific training concepts, but there is potential for optimization. Further research is needed to identify success criteria in dementia-specific training and identify the successful combination of theoretical knowledge and practical exercise.

  9. Reassessment of the NRC`s program for protecting allegers against retaliation

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    On July 6, 1993, the Nuclear Regulatory Commission`s (NRC`s) Executive Director for Operations established a review team to reassess the NRC`s program for protecting allegers against retaliation. The team evaluated the current system, and solicited comments from various NRC offices, other Federal agencies, licensees, former allegers, and the public. This report is subject to agency review. The report summarizes current processes and gives an overview of current problems. It discusses: (1) ways in which licensees can promote a quality-conscious work environment, in which all employees feel free to raise concerns without fear of retaliation; (2) ways to improve the NRC`s overall handling of allegations; (3) the NRC`s involvement in the Department of Labor process; (4) related NRC enforcement practices; and (5) methods other than investigation and enforcement that may be useful in treating allegations of potential or actual discrimination. Recommendations are given in each area.

  10. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1991-12-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facilities throughout the country for the third quarter of 1991

  11. AECB staff review of Bruce NGS 'B' operation for the year 1989

    International Nuclear Information System (INIS)

    1990-06-01

    The operation of the Bruce Nuclear Generating Station 'B' is monitored and licensing requirements are enforced by the Atomic Energy Control Board (AECB), which observes operation of the reactors, conducts audits, witnesses important activities, reviews station documentation and reports, and issue approvals, where appropriate, in accordance with licence conditions. This report records the conclusions of the AECB staff assessment of Bruce NGS 'B' during 1989. In general, the station operated within acceptable safety standards. Quality improvement initiatives started in 1989 should lead to improved station maintenance and operation in coming years. Ontario Hydro still needs to improve the administration of operating memos, deficiency reports and call-ups. Station management must ensure that shift supervisors and reactor first operators operate the station in a conservative manner at all times and put safety interests first when responding to a unit upset. (2 tabs.)

  12. Outcomes of classroom-based team training interventions for multiprofessional hospital staff. A systematic review

    DEFF Research Database (Denmark)

    Rabøl, Louise Isager; Østergaard, Doris; Mogensen, Torben

    2010-01-01

    Several studies show that communication errors in healthcare teams are frequent and can lead to adverse events. Team training has been suggested as a way to safer communication and has been implemented in healthcare as classroom-based or simulation-based team training or a combination of both. Th....... The objective of this paper is to systematically review studies evaluating the outcomes of classroom-based multiprofessional team training for hospital staff.......Several studies show that communication errors in healthcare teams are frequent and can lead to adverse events. Team training has been suggested as a way to safer communication and has been implemented in healthcare as classroom-based or simulation-based team training or a combination of both...

  13. The roles of NRC research in risk-informed, performance-based regulation

    International Nuclear Information System (INIS)

    Morrison, D.L.; Murphy, J.A.; Hodges, M.W.; Cunningham, M.A.; Drouin, M.T.; Ramey-Smith, A.M.; VanderMolen, H.

    1997-01-01

    The NRC is expanding the use of probabilistic risk analysis (PRA) throughout the spectrum of its regulatory activities. The NRC's research program in PRA supports this expansion in a number of ways, from performing basic research to developing guidance for regulatory applications. The author provides an overview of the NRC's PRA research program, then focuses on two key activities - the review of individual plant examinations, and the development of guidance for use of PRA in reactor regulation

  14. Recent developments in NRC guidelines for atmosphere cleanup systems

    International Nuclear Information System (INIS)

    Bellamy, R.R.

    1976-01-01

    The Nuclear Regulatory Commission (NRC) maintains the policy of updating when necessary, its published guidance for the design of engineered safety feature (ESF) and normal ventilation systems. The guidance is disseminated by means of issuing new, or revisions to, existing Regulatory Guides, Standard Review Plans, Branch Technical Positions and Technical Specifications. A revised Regulatory Guide, new Technical Specifications and new Standard Review Plans with Branch Technical Positions for atmosphere cleanup systems are discussed. Regulatory Guide 1.52, ''Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants,'' was issued in July 1973. The major comments received from the nuclear industry since the guide was issued, NRC's experience in implementing the guide in recent license applications, status of operating plants in meeting the guidelines and NRC's continuing assessment of operating data and laboratory tests to assure that the guide reflects the latest technology are discussed

  15. 76 FR 54986 - NRC Enforcement Policy

    Science.gov (United States)

    2011-09-06

    ... NUCLEAR REGULATORY COMMISSION 10 CFR Chapter I [NRC-2011-0209] NRC Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Proposed enforcement policy revision; request for comment. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the Commission) is soliciting comments from interested...

  16. 76 FR 76192 - NRC Enforcement Policy

    Science.gov (United States)

    2011-12-06

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0273] NRC Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Proposed enforcement policy revision; request for comment. SUMMARY: The U.S. Nuclear... licensees, vendors, and contractors), on proposed revisions to the NRC's Enforcement Policy (the Policy) and...

  17. The NRC measurement verification program

    International Nuclear Information System (INIS)

    Pham, T.N.; Ong, L.D.Y.

    1995-01-01

    A perspective is presented on the US Nuclear Regulatory Commission (NRC) approach for effectively monitoring the measurement methods and directly testing the capability and performance of licensee measurement systems. A main objective in material control and accounting (MC and A) inspection activities is to assure the accuracy and precision of the accounting system and the absence of potential process anomalies through overall accountability. The primary means of verification remains the NRC random sampling during routine safeguards inspections. This involves the independent testing of licensee measurement performance with statistical sampling plans for physical inventories, item control, and auditing. A prospective cost-effective alternative overcheck is also discussed in terms of an externally coordinated sample exchange or ''round robin'' program among participating fuel cycle facilities in order to verify the quality of measurement systems, i.e., to assure that analytical measurement results are free of bias

  18. NRC - regulator of nuclear safety

    International Nuclear Information System (INIS)

    1997-01-01

    The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations

  19. 76 FR 57006 - Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX; NRC Regulation of...

    Science.gov (United States)

    2011-09-15

    ... NUCLEAR REGULATORY COMMISSION 10 CFR Parts 30 and 150 [NRC-2011-0146] Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX; NRC Regulation of Military Operational Radium-226... published for public comment the proposed draft RIS 2011-XX; NRC Regulation of Military Operational Radium...

  20. The influence of staff training and education on prosthetic and orthotic service quality: A scoping review.

    Science.gov (United States)

    Forghany, Saeed; Sadeghi-Demneh, Ebrahim; Trinler, Ursula; Onmanee, Pornsuree; Dillon, Michael P; Baker, Richard

    2018-06-01

    Education and training in prosthetics and orthotics typically comply with International Society for Prosthetics and Orthotics standards based on three categories of prosthetic and orthotic professionals. This scoping study sought to describe the evidence base available to answer the question, How are prosthetic and orthotic services influenced by the training of staff providing them? Scoping review. A structured search of the peer-reviewed literature catalogued in major electronic databases yielded 3039 papers. Following review of title and abstract, 93 articles were considered relevant. Full-text review reduced this number to 25. Only two articles were identified as providing direct evidence of the effects of training and education on service provision. While both suggested that there was an impact, it is difficult to see how the more specific conclusions of either could be generalised. The other 23 articles provide a useful background to a range of issues including the specification of competencies that training programmes should deliver (3 articles), descriptions of a range of training programmes and the effects of training and education on student knowledge and skills. Although it is considered axiomatic, the service quality is dependent on practitioner education and training. There is insufficient evidence to establish whether levels of training and education in prosthetics and orthotics have an effect on the quality of prosthetic and orthotic services. Clinical relevance There is very little evidence about the effects of training and education of prosthetists and orthotists on service quality. While this is a somewhat negative finding, we feel that it is important to bring this to the attention of the prosthetics and orthotics community.

  1. 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

  2. Final report of the NRC-Agreement State Working Group to evaluate control and accountability of licensed devices

    International Nuclear Information System (INIS)

    1996-10-01

    US NRC staff acknowledged that licensees were having problems maintaining control over and accountability for devices containing radioactive material. In June 1995, NRC approved the staff's suggestion to form a joint NRC-Agreement State Working Group to evaluate the problem and propose solutions. The staff indicated that the Working Group was necessary to address the concerns from a national perspective, allow for a broad level of Agreement State input, and to reflect their experience. Agreement State participation in the process was essential since some Agreement States have implemented effective programs for oversight of device users. This report includes the 5 recommendations proposed by the Working Group to increase regulatory oversight, increase control and accountability of devices, ensure proper disposal, and ensure disposal of orphaned devices. Specifically, the Working Group recommends that: (1) NRC and Agreement States increase regulatory oversight for users of certain devices; (2) NRC and Agreement State impose penalties on persons losing devices; (3) NRC and Agreement States ensure proper disposal of orphaned devices; (4) NRC encourage States to implement similar oversight programs for users of Naturally-Occurring or Accelerator- Produced Material; and (5) NRC encourage non-licensed stakeholders to take appropriate actions, such as instituting programs for material identification

  3. 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

  4. 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

  5. Systematic evaluation program review of NRC Safety Topic VI-10.A associated with the electrical, instrumentation and control portions of the testing of reactor trip system and engineered safety features, including response time for the Dresden station, Unit II nuclear power plant

    International Nuclear Information System (INIS)

    St Leger-Barter, G.

    1980-11-01

    This report documents the technical evaluation and review of NRC Safety Topic VI-10.A, associated with the electrical, instrumentation, and control portions of the testing of reactor trip systems and engineered safety features including response time for the Dresden II nuclear power plant, using current licensing criteria

  6. Public meeting on radiation safety for industrial radiographerss: remarks, questions and answers at five NRC regional meetings

    International Nuclear Information System (INIS)

    1978-11-01

    Over the past several years thenumber of radiation overexposures experienced in the radiography industry has been higher than for any other single group of NRC licensees. To inform radiography licensees of NRC's concern fo these recurring overexposure incidents, NRC staff representatives met with licensees in a series of five regional meetings. At these meetings the staff presented prepared remarks and answered questions on NRC regulations and operations. The main purposes of the meetings were to express NRC's concern for the high incidence of overexposures, and to open a line of communication between the NRC and radiography licensees in an effort to achieve the common goal of improved radiation safety. The remarks presented by the staff and subjects discussed at these meetings included: the purpose, scope, findings and goals of the NRC inspection program; ways and means of incorporating safety into radiography operations; and case histories of overexposure incidents, with highlights of the causes and possible preventions. At each of the regional meetings the staff received a request for a copy of the prepared remarks and a consolidation of the questions and answers that were discussed. This document includes that information, and a copy is being provided to each organizaion or firm attending the regional meetings. Requests for other copies should be made in accordance with the directions printed inside the front cover of this document

  7. 78 FR 101 - Guidance for Industry and Food and Drug Administration Staff; Acceptance and Filing Reviews for...

    Science.gov (United States)

    2013-01-02

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2012-D-0524] Guidance for Industry and Food and Drug Administration Staff; Acceptance and Filing Reviews for Premarket Approval Applications; Availability AGENCY: Food and Drug Administration, HHS. ACTION: Notice. SUMMARY: The...

  8. 77 FR 45357 - Draft Guidance for Industry and Food and Drug Administration Staff; Acceptance and Filing Review...

    Science.gov (United States)

    2012-07-31

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2012-D-0524] Draft Guidance for Industry and Food and Drug Administration Staff; Acceptance and Filing Review for Premarket Approval Applications; Availability AGENCY: Food and Drug Administration, HHS. ACTION: Notice...

  9. Academic Benefits of Transitional Bilingual Education: A Literary Review, Staff Development, and Guidebook for Elementary Administrators and Educators.

    Science.gov (United States)

    Nunez, Jean Ann; Karr-Kidwell, PJ

    This paper provides a literature review, staff development information, and a guidebook for elementary administrators and educators that explains the academic benefits of Transitional Bilingual Education (TBE) for prekindergarten through fifth grade students. TBE allows limited English speaking students to learn a second language while being…

  10. 75 FR 71702 - Science Advisory Board Staff Office; Request for Nominations of Experts for Review of EPA's Draft...

    Science.gov (United States)

    2010-11-24

    ... men of all racial and ethnic groups. The EPA SAB Staff Office will acknowledge receipt of nominations...) absence of financial conflicts of interest; (d) absence of an appearance of a lack of impartiality; and (e... conflicts of interest will include a review of the ``Confidential Financial Disclosure Form for Special...

  11. Congress, NRC mull utility access to FBI criminal files

    International Nuclear Information System (INIS)

    Ultroska, D.

    1984-01-01

    Experiences at Alabama Power Company and other nuclear utilities have promped a request for institutionalizing security checks of personnel in order to eliminated convicted criminals and drug users. The Nuclear Regulatory Commission (NRC), which could provide FBI criminal history information by submitting fingerprints, does not do so, and would require new legislation to take on that duty. Believing that current malevolent employees can be managed with existing procedures, NRC allows criminal background checks only on prospective employees in order to avoid a negative social impact on personnel. Legislation to transfer criminal histories to nuclear facilities is now pending, and NRC is leaning toward a request for full disclosure, partly because of terrorist threats and partly to save manpower time and costs in reviewing case histories

  12. Canister storage building compliance assessment SNF project NRC equivalency criteria - HNF-SD-SNF-DB-003

    International Nuclear Information System (INIS)

    BLACK, D.M.

    1999-01-01

    This document presents the Project's position on compliance with the SNF Project NRC Equivalency Criteria - HNF-SD-SNF-DE-003, Spent Nuclear Fuel Project Path Forward Additional NRC Requirements. No non-compliances are shown. The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion

  13. Current perspectives on performance assessment at the NRC

    International Nuclear Information System (INIS)

    Coplan, S.M.; Eisenberg, N.A.; Federline, M.V.; Randall, J.D.

    1992-01-01

    The Nuclear Regulatory Commission (NRC) staff is engaging in a number of activities involving performance assessment in order to support NRC's program in high-level waste management. Broad areas of activity include: (1) reactive work responding to products and activities of the Department of Energy (DOE), (2) proactive work, including development of an independent performance assessment capability, development of guidance for DOE, support for technical and programmatic integration, (3) a program of regulatory research, and (4) participation in a number of international activities. As the U.S. high-level waste program continues to mature, performance assessment is seen as playing a more prominent role in evaluating safety and focussing technical activities

  14. Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2a, Below-ground vaults

    International Nuclear Information System (INIS)

    Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

    1987-12-01

    The US Army Engineer Waterways Experiment Station (WES) and the US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the below-ground vault (BGV) alternative method of low-level radioactive waste (LLW) disposal. A BGV is a reinforced concrete vault (floor, walls, and roof) placed underground below the frost line, and above the water table, surrounded by filter blanket and drainage zones and covered with a low permeability earth layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the BGV structure through material quality and durability considerations. Specific design review criteria have been developed in detail for seven of the eight major categories. 59 refs., 14 figs., 2 tabs

  15. Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2b: Earth-mounded concrete bunkers

    International Nuclear Information System (INIS)

    Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

    1988-01-01

    The US Army Engineers Waterways Experiment Station (WES) and US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste (LLW) disposal. An EMCB is generally described as a reinforced concrete vault placed below grade, underneath a tumulus, surrounded by filter-blanket and drainage zones. The tumulus is covered over with a low permeability cover layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the EMCB structure through material quality and durability considerations. Specific design review criteria have been developed in detail for each of the eight major categories. 63 refs., 13 figs., 2 tabs

  16. The Influence of Staff Training on Challenging Behaviour in Individuals with Intellectual Disability: A Review

    Science.gov (United States)

    Cox, Alison D.; Dube, Charmayne; Temple, Beverley

    2015-01-01

    Many individuals with intellectual disability engage in challenging behaviour. This can significantly limit quality of life and also negatively impact caregivers (e.g., direct care staff, family caregivers and teachers). Fortunately, efficacious staff training may alleviate some negative side effects of client challenging behaviour. Currently, a…

  17. NRC policy on future reactor designs

    International Nuclear Information System (INIS)

    1985-07-01

    On April 13, 1983, the US Nuclear Regulatory Commission issued for public comment a ''Proposed Commission Policy Statement on Severe Accidents and Related Views on Nuclear Reactor Regulation'' (48 FR 16014). This report presents and discusses the Commission's final version of that policy statement now entitled, ''Policy Statement on Severe Reactor Accidents Regarding Future Designs and Existing Plants.'' It provides an overview of comments received from the public and the Advisory Committee on Reactor Safeguards and the staff response to these. In addition to the Policy Statement, the report discusses how the policies of this statement relate to other NRC programs including the Severe Accident Research Program; the implementation of safety measures resulting from lessons learned in the accident at Three Mile Island; safety goal development; the resolution of Unresolved Safety Issues and other Generic Safety Issues; and possible revisions of rules or regulatory requirements resulting from the Severe Accident Source Term Program. Also discussed are the main features of a generic decision strategy for resolving Regulatory Questions and Technical Issues relating to severe accidents; the development and regulatory use of new safety information; the treatment of uncertainty in severe accident decision making; and the development and implementation of a Systems Reliability Program for both existing and future plants to ensure that the realized level of safety is commensurate with the safety analyses used in regulatory decisions

  18. Status of NRC approval of EPRI electromagnetic interference susceptibility testing guidelines for digital equipment

    International Nuclear Information System (INIS)

    James, R.W.; Shank, J.W.; Yoder, C.

    1996-01-01

    Historically, nuclear power plants installing digital equipment have been required to conduct expensive, site-specific electromagnetic interference (EMI) surveys to demonstrate that EMI will not affect the operation of sensitive electronic equipment. Consequently, EPRI formed a Utility Working Group which developed a set of generic EMI susceptibility testing guidelines, which were published as an EPRI report in September 1994. These guidelines are based upon EMI survey data obtained from several different plants and include criteria for determining their applicability. The Working Group interacted with NRC staff to obtain NRC approval. In April 1996, the NRC issued a Safety Evaluation Report (SER) endorsing the guidelines as a valid means of demonstrating EMI compatibility. The issuance of this SER was conditional on issuing a revision to the EPRI EMI Guidelines. This paper summarizes the guidelines, the NRC SER, and the current status of Revision 1 to the report

  19. Pilot program: NRC severe reactor accident incident response training manual. Overview and summary of major points

    International Nuclear Information System (INIS)

    McKenna, T.J.; Martin, J.A. Jr.; Giitter, J.G.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Watkins

    1987-02-01

    Overview and Summary of Major Points is the first in a series of volumes that collectively summarize the U.S. Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assessment. Other volumes in the series are: Volume 2-Severe Reactor Accident Overview; Volume 3- Response of Licensee and State and Local Officials; Volume 4-Public Protective Actions-Predetermined Criteria and Initial Actions; Volume 5 - U.S. Nuclear Regulatory Commission. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. The volumes have been organized into these training modules to accommodate the scheduling and duty needs of participating NRC staff. Each volume is accompanied by an appendix of slides that can be used to present this material

  20. Rapid realist review of the evidence: achieving lasting change when mental health rehabilitation staff undertake recovery-oriented training.

    Science.gov (United States)

    Gee, Melanie; Bhanbhro, Sadiq; Cook, Sarah; Killaspy, Helen

    2017-08-01

    The aim of this study was to identify the factors contributing to lasting change in practice following a recovery-based training intervention for inpatient mental health rehabilitation staff. Staff training may help nurses and other staff groups in inpatient mental health rehabilitative settings to increase their recovery-oriented practice. There are no published reviews on the effectiveness of such training and few long-term evaluations. This review informed a realist evaluation of a specific intervention (GetREAL). Rapid realist review methodology was used to generate and prioritize programme theories. ASSIA, CINAHL, Cochrane Library, Medline, PsycINFO, Scopus, Web of Science and grey literature searches were performed in September 2014-March 2015 with no date restrictions. Stakeholders suggested further documents. GetREAL project documentation was consulted. Programme theory development took place iteratively with literature identification. Stakeholders validated and prioritized emerging programme theories and the prioritized theories were refined using literature case studies. Fifty-one relevant documents fed into 49 programme theories articulating seven mechanisms for lasting change. Prioritized mechanisms were: staff receptiveness to change; and staff feeling encouraged, motivated and supported by colleagues and management to change. Seven programme theories were prioritized and refined using data from four case studies. Lasting change can be facilitated by collaborative action planning, regular collaborative meetings, appointing a change agent, explicit management endorsement and prioritization and modifying organizational structures. Conversely, a challenging organizational climate, or a prevalence of 'change fatigue', may block change. Pre-intervention exploration may help identify any potential barriers to embedding recovery in the organizational culture. © 2016 John Wiley & Sons Ltd.

  1. NRC licensing requirements: DOD options

    International Nuclear Information System (INIS)

    Pike, W.J.; O'Reilly, P.D.

    1982-09-01

    This report describes the licensing process (both safety and environmental) that would apply if the Department of Defense (DOD) chooses to obtain licenses from the US Nuclear Regulatory Commission (NRC) for using nuclear energy for power and luminous sources. The specific nuclear energy sources being considered include: small or medium-size nuclear power reactors; radioisotopic thermoelectric generators with 90 Sr or 238 Pu; radioisotopic dynamic electric generators with 90 Sr or 238 Pu; and applications of radioisotopes for luminous sources (lights) with 3 H, 85 Kr, or 147 Pm. The steps of the licensing process are summarized in the following sections, with particular attention given to the schedule and level of effort necessary to support the process

  2. The NRC and utility finances

    International Nuclear Information System (INIS)

    Byus, L.C.

    1992-01-01

    In a speech before the National Association of Regulatory Utility Commissioners in November 1991, Nuclear Regulatory Commission Chairman Ivan Selin presented what he called an open-quotes expansion of the concept of safety beyond our previous narrow bounds.close quotes He went on to explain, open-quotes To be seen as successful and safe operators of nuclear facilities, utilities must have safe and predictable cash flows.close quotes While there is little disagreement that the concepts of successful plant operations and financial strength go hand in hand, the relationship between the two is not clear. Which came first, successful operation of generating plants or financial strength? Selin's views on NRC involvement in financial aspects of utility operation in the United States are sure to stimulate debate on the issue

  3. 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

  4. 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.

  5. Survey by senior NRC management to obtain veiwpoints on the safety impact of regulatory activities from representative utilities operating and constructing nuclear power plants

    International Nuclear Information System (INIS)

    1981-08-01

    A survey of licensee staff members representing the several organizational elements in different licensee corporate and plant staffs was conducted by senior NRC management to obtain licensee views on the potential safety consequences and impact of NRC regulatory activities. The comments received addressed the full scope of NRC activities and the negative impact of agency actions on licensee resources, staff performance, planning and scheduling, and organizational effectiveness. The findings of the survey is that the pace and nature of regulatory actions have created a potential safety problem which deserves further evaluation by the agency

  6. Review process for low-level radioactive waste disposal license application under Low-Level Radioactive Waste Policy Amendments Act

    International Nuclear Information System (INIS)

    Pittiglio, C.L. Jr.

    1987-08-01

    This document estimates the level of effort and expertise that is needed to review a license application within the required time. It is intended to be used by the NRC staff as well as States and interested parties to provide a better understanding of what the NRC envisions will be involved in licensing a low-level radioactive waste disposal facility. 5 refs., 3 figs., 1 tab

  7. A Systematic Review of Interventions to Change Staff Care Practices in Order to Improve Resident Outcomes in Nursing Homes.

    Directory of Open Access Journals (Sweden)

    Lee-Fay Low

    Full Text Available We systematically reviewed interventions that attempted to change staff practice to improve long-term care resident outcomes.Studies met criteria if they used a control group, included 6 or more nursing home units and quantitatively assessed staff behavior or resident outcomes. Intervention components were coded as including education material, training, audit and feedback, monitoring, champions, team meetings, policy or procedures and organizational restructure.Sixty-three unique studies were broadly grouped according to clinical domain-oral health (3 studies, hygiene and infection control (3 studies, nutrition (2 studies, nursing home acquired pneumonia (2 studies, depression (2 studies appropriate prescribing (7 studies, reduction of physical restraints (3 studies, management of behavioral and psychological symptoms of dementia (6 studies, falls reduction and prevention (11 studies, quality improvement (9 studies, philosophy of care (10 studies and other (5 studies. No single intervention component, combination of, or increased number of components was associated with greater likelihood of positive outcomes. Studies with positive outcomes for residents also tended to change staff behavior, however changing staff behavior did not necessarily improve resident outcomes. Studies targeting specific care tasks (e.g. oral care, physical restraints were more likely to produce positive outcomes than those requiring global practice changes (e.g. care philosophy. Studies using intervention theories were more likely to be successful. Program logic was rarely articulated, so it was often unclear whether there was a coherent connection between the intervention components and measured outcomes. Many studies reported barriers relating to staff (e.g. turnover, high workload, attitudes or organizational factors (e.g. funding, resources, logistics.Changing staff practice in nursing homes is possible but complex. Interventionists should consider barriers and

  8. NRC/AMRMC Resident Research Associateship Program

    Science.gov (United States)

    2018-05-01

    conducted the following activities in support of the subject contract: Outreach and Promotion The promotional schedule to advertise the NRC Research...Approved for Public Release; Distribution Unlimited 13. SUPPLEMENTARY NOTES 14. ABSTRACT During this reporting period, the NRC promoted research...Associateship Programs included the following: 1) attendance at meetings of major scientific and engineering professional societies; 2) advertising in

  9. 78 FR 5838 - NRC Enforcement Policy

    Science.gov (United States)

    2013-01-28

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0014] NRC Enforcement Policy AGENCY: Nuclear Regulatory Commission. ACTION: Policy revision; issuance and request for comments. SUMMARY: The U.S. Nuclear Regulatory... Nuclear Regulatory Commission Enforcement Policy,'' December 30, 2009 (ADAMS Accession No. ML093200520);(2...

  10. COUNCIL DECISIONS ON THE 5-YEARLY REMUNERATION REVIEW, AJUSTMENTS FOR 2001 AND CHANGES TO THE STAFF RULES AND REGULATIONS

    CERN Document Server

    Human Resources Division

    2001-01-01

    As announced by the Director-General in December last year, Council approved the package of measures concerning the 5-yearly remuneration review, recommended by the TREF Restricted Group, as well as the adjustments for 2001 related to salaries and pensions. These measures, as summarised below, enter into force on 1 January 2001, subject to later implementation of some items. Related changes to the Staff Rules and Regulations will be published as soon as possible in the mean time, changes which were annexed to the Council Resolution can be viewed on the HR Division Web site. 1. Scale of basic salaries (Annex R A 1 of the Staff Regulations) : increased by 4.32% resulting from the 5-yearly Review, and by 0.6% which corresponds to the salary adjustment for 2001. This includes the increases in social insurance contributions indicated below. 2. Scale of stipends of Fellows (Annex R A 2 of the Staff Regulations) : increased by 1.52% resulting from the 5-yearly Review, and by 0.6% which corresponds to the adjustment ...

  11. NRC/RSR Data Bank Program description

    International Nuclear Information System (INIS)

    Bankert, S.F.

    1979-01-01

    The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., at Idaho National Engineering Laboratory. The NRC/RSR Data Bank Program provides a central computer storage mechanism and access software for data to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, and training and advisory services to users and the NRC. The NRC/RSR Data Bank Program and the capabilities of the data access software are described

  12. Building confidence in nuclear waste regulation: how NRC is adapting in response to stakeholder concerns

    International Nuclear Information System (INIS)

    Kotra, Janet P.

    2004-01-01

    Increasing public confidence in the U.S. Nuclear Regulatory Commission as an effective and independent regulator is an explicit goal of the Agency. When developing new, site-specific regulations for the proposed geologic repository at Yucca Mountain, Nevada, NRC sought to improve its efforts to inform and involve the public in NRC's decision-making process. To this end, NRC has made, and continues to make significant organizational, process and policy changes. NRC successfully applied these changes as it completed final regulations for Yucca Mountain, when introducing a draft license review plan for public comment, and when responding to public requests for information on NRC's licensing and hearing process. It should be understood, however, that these changes emerged, and continue to be applied, in the context of evolving agency concern for increasing stakeholder confidence reflected in institutional changes within the agency as a whole. (author)

  13. 78 FR 49782 - Interim Staff Guidance on Changes During Construction

    Science.gov (United States)

    2013-08-15

    ... Construction AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim staff guidance; request for comment... During Construction.'' This ISG provides guidance to the NRC staff on the Preliminary Amendment Request...-ISG-025 ``Interim Staff Guidance on Changes during Construction under 10 CFR Part 52'' is available...

  14. 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.

  15. Improving the wellbeing of staff who work in palliative care settings: A systematic review of psychosocial interventions.

    Science.gov (United States)

    Hill, Rebecca C; Dempster, Martin; Donnelly, Michael; McCorry, Noleen K

    2016-10-01

    Staff in palliative care settings perform emotionally demanding roles which may lead to psychological distress including stress and burnout. Therefore, interventions have been designed to address these occupational risks. To investigate quantitative studies exploring the effectiveness of psychosocial interventions that attempt to improve psychological wellbeing of palliative care staff. A systematic review was conducted according to methodological guidance from UK Centre for Reviews and Dissemination. A search strategy was developed based on the initial scans of palliative care studies. Potentially eligible research articles were identified by searching the following databases: CINAHL, MEDLINE (Ovid), PsycINFO and Web of Science. Two reviewers independently screened studies against pre-set eligibility criteria. To assess quality, both researchers separately assessed the remaining studies using the Quality Assessment Tool for Quantitative Studies. A total of 1786 potentially eligible articles were identified - nine remained following screening and quality assessment. Study types included two randomised controlled trials, two non-randomised controlled trial designs, four one-group pre-post evaluations and one process evaluation. Studies took place in the United States and Canada (5), Europe (3) and Hong Kong (1). Interventions comprised a mixture of relaxation, education, support and cognitive training and targeted stress, fatigue, burnout, depression and satisfaction. The randomised controlled trial evaluations did not improve psychological wellbeing of palliative care staff. Only two of the quasi-experimental studies appeared to show improved staff wellbeing although these studies were methodologically weak. There is an urgent need to address the lack of intervention development work and high-quality research in this area. © The Author(s) 2016.

  16. Interventions to support effective communication between maternity care staff and women in labour: A mixed-methods systematic review.

    Science.gov (United States)

    Chang, Yan-Shing; Coxon, Kirstie; Portela, Anayda Gerarda; Furuta, Marie; Bick, Debra

    2018-04-01

    the objectives of this review were (1) to assess whether interventions to support effective communication between maternity care staff and healthy women in labour with a term pregnancy could improve birth outcomes and experiences of care; and (2) to synthesize information related to the feasibility of implementation and resources required. a mixed-methods systematic review. studies which reported on interventions aimed at improving communication between maternity care staff and healthy women during normal labour and birth, with no apparent medical or obstetric complications, and their family members were included. 'Maternity care staff' included medical doctors (e.g. obstetricians, anaesthetists, physicians, family doctors, paediatricians), midwives, nurses and other skilled birth attendants providing labour, birth and immediate postnatal care. Studies from all birth settings (any country, any facility including home birth, any resource level) were included. two papers met the inclusion criteria. One was a step wedge randomised controlled trial conducted in Syria, and the other a sub-analysis of a randomised controlled trial from the United Kingdom. Both studies aimed to assess effects of communication training for maternity care staff on women's experiences of labour care. The study from Syria reported that a communication skills training intervention for resident doctors was not associated with higher satisfaction reported by women. In the UK study, patient-actors' (experienced midwives) perceptions of safety and communication significantly improved for postpartum haemorrhage scenarios after training with patient-actors in local hospitals, compared with training using manikins in simulation centres, but no differences were identified for other scenarios. Both studies had methodological limitations. the review identified a lack of evidence on impact of interventions to support effective communication between maternity care staff and healthy women during labour and

  17. 10 CFR 2.102 - Administrative review of application.

    Science.gov (United States)

    2010-01-01

    ... proceeding to confer with the NRC staff informally. In the case of docketed application for a limited work... 10 Energy 1 2010-01-01 2010-01-01 false Administrative review of application. 2.102 Section 2.102... ORDERS Procedure for Issuance, Amendment, Transfer, or Renewal of a License, and Standard Design Approval...

  18. Evaluation of NRC maintenance team inspection reports for managing aging

    International Nuclear Information System (INIS)

    Fresco, A.; Gunther, W.

    1991-01-01

    A nuclear power plant's maintenance program is the principal vehicle through which age-related degradation is managed. Over the past two years, the NRC [Nuclear Regulatory Commission] has evaluated the maintenance program of every nuclear power plant in the U.S. The reports issued on these in-depth team inspections have been reviewed to ascertain the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear power plant systems, structures, and components. Selected results of this review are presented in this paper, including examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue are also discussed. 6 refs., 1 tab

  19. Mental healthcare staff well-being and burnout: A narrative review of trends, causes, implications, and recommendations for future interventions.

    Science.gov (United States)

    Johnson, Judith; Hall, Louise H; Berzins, Kathryn; Baker, John; Melling, Kathryn; Thompson, Carl

    2018-02-01

    Rising levels of burnout and poor well-being in healthcare staff are an international concern for health systems. The need to improve well-being and reduce burnout has long been acknowledged, but few interventions target mental healthcare staff, and minimal improvements have been seen in services. This review aimed to examine the problem of burnout and well-being in mental healthcare staff and to present recommendations for future research and interventions. A discursive review was undertaken examining trends, causes, implications, and interventions in burnout and well-being in healthcare staff working in mental health services. Data were drawn from national surveys, reports, and peer-reviewed journal articles. These show that staff in mental healthcare report poorer well-being than staff in other healthcare sectors. Poorer well-being and higher burnout are associated with poorer quality and safety of patient care, higher absenteeism, and higher turnover rates. Interventions are effective, but effect sizes are small. The review concludes that grounding interventions in the research literature, emphasizing the positive aspects of interventions to staff, building stronger links between healthcare organizations and universities, and designing interventions targeting burnout and improved patient care together may improve the effectiveness and uptake of interventions by staff. © 2017 Australian College of Mental Health Nurses Inc.

  20. 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

  1. Reduce, Manage or Cope: A Review of Strategies for Training School Staff to Address Challenging Behaviours Displayed by Students with Intellectual/Developmental Disabilities

    Science.gov (United States)

    Stoesz, Brenda M.; Shooshtari, Shahin; Montgomery, Janine; Martin, Toby; Heinrichs, Dustin J.; Douglas, Joyce

    2016-01-01

    Members of a knowledge translation and exchange (KTE) research team assessed the training needs of the teaching staff at a school for individuals with intellectual/developmental disabilities (IDD). In response to this need, KTE researchers retrieved peer-reviewed articles for training staff working with individuals with IDD who exhibit challenging…

  2. Bench-to-bedside review: Dealing with increased intensive care unit staff turnover: a leadership challenge

    Science.gov (United States)

    Laporta, Denny P; Burns, Judy; Doig, Chip J

    2005-01-01

    Critical care leaders frequently must face challenging situations requiring specific leadership and management skills for which they are, not uncommonly, poorly prepared. Such a fictitious scenario was discussed at a Canadian interdisciplinary critical care leadership meeting, whereby increasing intensive care unit (ICU) staff turnover had led to problems with staff recruitment. Participants discussed and proposed solutions to the scenario in a structured format. The results of the discussion are presented. In situations such as this, the ICU leader should first define the core problem, its complexity, its duration and its potential for reversibility. These factors often reside within workload and staff support issues. Some examples of core problems discussed that are frequently associated with poor retention and recruitment are a lack of a positive team culture, a lack of a favorable ICU image, a lack of good working relationships between staff and disciplines, and a lack of specific supportive resources. Several tools or individuals (typically outside the ICU environment) are available to help determine the core problem. Once the core problem is identified, specific solutions can be developed. Such solutions often require originality and flexibility, and must be planned, with specific short-term, medium-term and long-term goals. The ICU leader will need to develop an implementation strategy for these solutions, in which partners who can assist are identified from within the ICU and from outside the ICU. It is important that the leader communicates to all stakeholders frequently as the process moves forward. PMID:16277732

  3. Education and training to enhance end-of-life care for nursing home staff: a systematic literature review.

    Science.gov (United States)

    Anstey, Sally; Powell, Tom; Coles, Bernadette; Hale, Rachel; Gould, Dinah

    2016-09-01

    The delivery of end-of-life care in nursing homes is challenging. This situation is of concern as 20% of the population die in this setting. Commonly reported reasons include limited access to medical care, inadequate clinical leadership and poor communication between nursing home and medical staff. Education for nursing home staff is suggested as the most important way of overcoming these obstacles. To identify educational interventions to enhance end-of-life care for nursing home staff and to identify types of study designs and outcomes to indicate success and benchmark interventions against recent international guidelines for education for palliative and end-of-life care. Thirteen databases and reference lists of key journals were searched from the inception of each up to September 2014. Included studies were appraised for quality and data were synthesised thematically. Twenty-one studies were reviewed. Methodological quality was poor. Education was not of a standard that could be expected to alter clinical behaviour and was evaluated mainly from the perspectives of staff: self-reported increase in knowledge, skills and confidence delivering care rather than direct evidence of impact on clinical practice and patient outcomes. Follow-up was often short term, and despite sound economic arguments for delivering effective end-of-life care to reduce burden on the health service, no economic analyses were reported. There is a clear and urgent need to design educational interventions that have the potential to improve end-of-life care in nursing homes. Robust evaluation of these interventions should include impact on residents, families and staff and include economic analysis. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

  4. Topical report review status, July 15, 1983. Vol. 7, No. 1

    International Nuclear Information System (INIS)

    1983-08-01

    A Topical Report Review Status is scheduled to be published semi-annually. The primary purpose of this document is to provide periodic progress reports of on-going topical report reviews, to identify those topical reports for which the Nuclear Regulatory Commission (NRC) staff review has been completed and, to the extent practicable, to provide NRC management with sufficient information regarding the conduct of the topical report program to permit taking whatever actions deemed necessary or appropriate. This document is also intended to be a source of information to NRC Licensing Project Managers and other NRC personnel regarding the status of topical reports which may be referenced in applications for which they have responsibility

  5. COMPOSITION OF STAFF REVIEW ADVISORY BODIES - 2000 COMPOSITION OF THE JOINT TRAINING BOARD (JTB) - 2000/2001

    CERN Multimedia

    HR Division

    2000-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows:Senior Staff Advancement Committee (SSAC)D. Treille / EP (Convener)C. Benvenuti / ESTD. O. Williams /ITTechnical Engineers & Administrative Careers Committee (TEACC) C. Hauviller / EPL. Leistam / ESTS. Jarp / IT [Chairman]F. Pedersen / PSR. Lauckner / SLC. Roche / ETTLong-term contract Boards (LTCBs) (Categories 2 &5a)Tiziano Camporesi / EP [Convener]Florence Ranjard / EP\t[Alternate]Jacques Gruber / PSPeter Sievers / LHCThomas Pettersson / ESTMichel Mayoud / ESTSue Foffano / ASThierry Lagrange / SPLWerner Zapf / HR (Secretary) LTCB 2(Categories 3, 4, 5b & 5c)Véronique Paris / SL [Convener]Fabien Pérriolat / PS\t [Alternate]Mats Wilhelmsson / STVéronique Fassnacht / TISLucie Linssen / EPMichel Mayoud / ESTPatrick Geeraert / FIJohn Cuthbert / HRSeamus Hegarty / HR (Secretary) Composition of the Joint Training Board (JT...

  6. Impact of the design of neonatal intensive care units on neonates, staff, and families: a systematic literature review.

    Science.gov (United States)

    Shahheidari, Marzieh; Homer, Caroline

    2012-01-01

    Newborn intensive care is for critically ill newborns requiring constant and continuous care and supervision. The survival rates of critically ill infants and hospitalization in neonatal intensive care units (NICUs) have improved over the past 2 decades because of technological advances in neonatology. The design of NICUs may also have implications for the health of babies, parents, and staff. It is important therefore to articulate the design features of NICU that are associated with improved outcomes. The aim of this study was to explore the main features of the NICU design and to determine the advantages and limitations of the designs in terms of outcomes for babies, parents, and staff, predominately nurses. A systematic review of English-language, peer-reviewed articles was conducted for a period of 10 years, up to January 2011. Four online library databases and a number of relevant professional Web sites were searched using key words. There were 2 main designs of NICUs: open bay and single-family room. The open-bay environment develops communication and interaction with medical staff and nurses and has the ability to monitor multiple infants simultaneously. The single-family rooms were deemed superior for patient care and parent satisfaction. Key factors associated with improved outcomes included increased privacy, increased parental involvement in patient care, assistance with infection control, noise control, improved sleep, decreased length of hospital stay, and reduced rehospitalization. The design of NICUs has implications for babies, parents, and staff. An understanding of the positive design features needs to be considered by health service planners, managers, and those who design such specialized units.

  7. NRC Information No. 89-89: Event notification worksheets

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    The NRC ''Event Notification Worksheet,'' NRC Form 361, has been revised to assist the NRC Headquarters Operations Officers in obtaining adequate information for evaluation of significant events reported to the NRC Operations Center. The new forms more accurately reflect the event classifications and the 10 CFR 50.72 categories that must be reported. A copy of the new worksheet is enclosed for your reference. NRC Form 361 can be ordered from the NRC Information and Records Management Branch

  8. NRC testimony before the Subcommittee on Nuclear Regulation of the Committee on Environment and Public Works, United States Senate

    International Nuclear Information System (INIS)

    1977-10-01

    NRC staff testimony before the U.S. Senate's Subcommittee on Nuclear Regulation, Committee on Environment and Public, is presented. The testimony pertains to the staff's role in the licensing process affecting the Virginia Electric and Power Company's North Anna nuclear plant. It explains the steps taken since 1973, and particularly since formation of the U.S. Nuclear Regulatory Commission in January 1975, to improve the timeliness of submission of information from the staff to the Commission licensing boards

  9. Interventions to improve communication between people with dementia and nursing staff during daily nursing care: A systematic review.

    Science.gov (United States)

    Machiels, Mariska; Metzelthin, Silke F; Hamers, Jan P H; Zwakhalen, Sandra M G

    2017-01-01

    To provide adequate nursing care it is important for nursing staff to communicate effectively with people with dementia. Due to their limited communication skills, people with dementia have difficulties in understanding communication and expressing themselves verbally. Nursing staff members often report communication difficulties with people with dementia, which emphasises the urgent need for interventions to improve their communication with people in this specific target group. To provide an up-to-date overview of communication interventions that are applicable during daily nursing care activities, irrespective of care setting, and to describe the effects on communication outcomes in people with dementia and nursing staff. Systematic literature review DATA SOURCES: The Cochrane Library, CINAHL, PsycINFO, and Pubmed databases were searched for all articles published until the 23rd of February 2016. Papers were included, if: (1) interventions focused on communication between nursing staff and people with dementia and were applicable during daily nursing care; (2) studies were (randomised) controlled trials; (3) papers were written in English, Dutch, or German. Data were extracted on content and communication outcomes of interventions, and on methodological quality of the studies. The data extraction form and methodological quality checklist were based on the Method Guidelines for Systematic Reviews for the Cochrane Back Review Group. Six studies on communication interventions were included. All of the studies incorporated a communication skills training for nursing staff with a broad range in frequency, duration and content. In addition, there was wide variation in the communication outcome measures used. Four studies measured non-verbal communication, all found positive effects on at least some of the communication outcomes. Four studies measured verbal communication, of which three found positive effects on at least one of the measured outcomes. Methodological

  10. Typical NRC inspection procedures for model plant

    International Nuclear Information System (INIS)

    Blaylock, J.

    1984-01-01

    A summary of NRC inspection procedures for a model LEU fuel fabrication plant is presented. Procedures and methods for combining inventory data, seals, measurement techniques, and statistical analysis are emphasized

  11. NRC/AMRMC Resident Research Associateship Program

    Science.gov (United States)

    2016-04-01

    8. Curcumin : A Prototype Anti-inflammatory Therapeutic for Burn Pain and Wound Healing. Burn and Trauma Research Workgroup. BAMMC Burn Center 2014 9...from Burkholderia infection in mice. 9) PUBLICATIONS AND PAPERS RESULTING FROM NRC ASSOCIATESHIP RESEARCH Provide complete citations: author(s), title...PUBLICATIONS AND PAPERS RESULTING FROM NRC ASSOCIATESHIP RESEARCH Provide complete citations: author(s), title, full name of journal, volume number, page

  12. NRC's object-oriented simulator instructor station

    International Nuclear Information System (INIS)

    Griffin, J.I.; Griffin, J.P.

    1995-06-01

    As part of a comprehensive simulator upgrade program, the simulator computer systems associated with the Nuclear Regulatory Commission's (NRC) nuclear power plant simulators were replaced. Because the original instructor stations for two of the simulators were dependent on the original computer equipment, it was necessary to develop and implement new instructor stations. This report describes the Macintosh-based Instructor Stations developed by NRC engineers for the General Electric (GE) and Babcock and Wilcox (B and W) simulators

  13. 1996 NRC annual report. Volume 13

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    This 22nd annual report of the US Nuclear Regulatory Commission (NRC) describes accomplishments, activities, and plans made during Fiscal Year 1996 (FH 1996)--October 1, 1995, through September 30, 1996. Significant activities that occurred early in FY 1997 are also described, particularly changes in the Commission and organization of the NRC. The mission of the NRC is to ensure that civilian uses of nuclear materials in the US are carried out with adequate protection of public health and safety, the environment, and national security. These uses include the operation of nuclear power plants and fuel cycle plants and medical, industrial, and research applications. Additionally, the NRC contributes to combating the proliferation of nuclear weapons material worldwide. The NRC licenses and regulates commercial nuclear reactor operations and research reactors and other activities involving the possession and use of nuclear materials and wastes. It also protects nuclear materials used in operation and facilities from theft or sabotage. To accomplish its statutorily mandated regulatory mission, the NRC issues rules and standards, inspects facilities and operations, and issues any required enforcement actions.

  14. 1996 NRC annual report. Volume 13

    International Nuclear Information System (INIS)

    1997-01-01

    This 22nd annual report of the US Nuclear Regulatory Commission (NRC) describes accomplishments, activities, and plans made during Fiscal Year 1996 (FH 1996)--October 1, 1995, through September 30, 1996. Significant activities that occurred early in FY 1997 are also described, particularly changes in the Commission and organization of the NRC. The mission of the NRC is to ensure that civilian uses of nuclear materials in the US are carried out with adequate protection of public health and safety, the environment, and national security. These uses include the operation of nuclear power plants and fuel cycle plants and medical, industrial, and research applications. Additionally, the NRC contributes to combating the proliferation of nuclear weapons material worldwide. The NRC licenses and regulates commercial nuclear reactor operations and research reactors and other activities involving the possession and use of nuclear materials and wastes. It also protects nuclear materials used in operation and facilities from theft or sabotage. To accomplish its statutorily mandated regulatory mission, the NRC issues rules and standards, inspects facilities and operations, and issues any required enforcement actions

  15. Millstone 3 risk evaluation report. An overall review and evaluation of the Millstone Unit 3 probabilistic safety study

    International Nuclear Information System (INIS)

    Kelly, G.; Barrett, R.; Buslik, A.

    1986-06-01

    In 1981, the US Nuclear Regulatory Commission (NRC) requested Northeast Utilities to perform a design-specific probabilistic safety study (PSS) for Millstone Nuclear Power Station, Unit No. 3 (Millstone 3). In 1983, Northeast Utilities submitted the Millstone 3 Probabilistic Safety Study for review by the NRC staff. The NRC staff prepared the Millstone 3 Risk Evaluation Report, which discusses the findings regarding the PSS. The PSS estimates that the mean annual core damage frequency due to internal and external events is 5 x 10 -5 and 2 x 10 -5 , respectively. The NRC staff's Risk Evaluation Report estimates that the mean annual core damage frequency is about 2 x 10 -4 for internal events and lies between 1 x 10 -5 and 2 x 10 -4 for external events. The NRC staff estimates that station blackout dominates internal and external event core damage frequencies. The staff recommends that Northeast Utilities perform an engineering analysis on upgrading the diesel generator lube oil cooler anchorage system and on adding a manually operated, AC-independent containment spray system. The staff also recommends that Northeast Utilities prepare two emergency procedures (loss of room cooling and relay chatter due to an earthquake) to help reduce uncertainties. (Subsequent to the completion of this document, Northeast Utilities and the NRC staff have continued a dialogue regarding station blackout from events other than earthquakes. Both Northeast Utilities and the staff have performed additional evaluations, which have drawn their results closer together. Final requirements, if any, for the prevention or mitigation of station blackout from events other than earthquakes have not yet been determined.) 26 refs., 16 tabs

  16. NRC Support for the Kalinin (VVER) probabilistic risk assessment

    International Nuclear Information System (INIS)

    Bley, D.; Diamond, D.J.; Chu, T.L.; Azarm, A.; Pratt, W.T.; Johnson, D.; Szukiewicz, A.; Drouin, M.; El-Bassioni, A.; Su, T.M.

    1998-01-01

    The US Nuclear Regulatory Commission (NRC) and the Federal Nuclear and Radiation Safety Authority of the Russian Federation have been working together since 1994 to carry out a probabilistic risk assessment (PRA) of a VVER-1000 in the Russian Federation. This was a recognition by both parties that this technology has had a profound effect on the discipline of nuclear reactor safety in the West and that the technology should be transferred to others so that it can be applied to Soviet-designed plants. The NRC provided funds from the Agency for International Development and technical support primarily through Brookhaven National Laboratory and its subcontractors. The latter support was carried out through workshops, by documenting the methodology to be used in a set of guides, and through periodic review of the technical activity. The result of this effort to date includes a set of procedure guides, a draft final report on the Level 1 PRA for internal events (excluding internal fires and floods), and progress reports on the fire, flood, and seismic analysis. It is the authors belief that the type of assistance provided by the NRC has been instrumental in assuring a quality product and transferring important technology for use by regulators and operators of Soviet-designed reactors. After a thorough review, the report will be finalized, lessons learned will be applied in the regulatory and operational regimes in the Russian Federation, and consideration will be given to supporting a containment analysis in order to complete a simplified Level 2 PRA

  17. The role of research in nuclear regulation: An NRC perspective

    International Nuclear Information System (INIS)

    Morrison, D.L.

    1997-01-01

    The role of research in the US Nuclear Regulatory Commission was broadly defined by the US Congress in the Energy Reorganization Act of 1975. This Act empowered the Commission to do research that it deems necessary for the performance of its licensing and regulatory functions. Congress cited a need for an independent capability that would support the licensing and regulatory process through the development and analysis of technical information related to reactor safety, safeguards and environmental protection. Motivation for establishing such a safety research function within the regulatory agency is the need to address the defects, abnormal occurrences and shutdowns involving light water reactors. Congress further stated that the NRC should limit its research to open-quotes confirmatory assessmentclose quotes and that the Agency open-quotes should never be placed in a position to generate, and then have to defend, basic design data of its own.close quotes The author reviews the activities of the research arm as related to regulatory research, performed in the past, today, and projected for the future. NRC's public health and safety mission demands that its research products be developed independently from its licensees; be credible and of the highest technical quality as established through peer review; and open to the public scrutiny through publication in technical journals as well as NRC documents. A special trust is placed on regulatory research through the products it produces as well as the three dimensions that underlie the processes through which they are produced

  18. Staff radiation doses associated with nuclear medicine procedures - a review of some recent measurements

    International Nuclear Information System (INIS)

    Harding, L.K.; Mostafa, A.B.; Thomson, W.H.

    1990-01-01

    Despite publication of the Approved Code of Practice and the Notes for Guidance, implementation of the UK Ionising Radiation Regulations has required local interpretation by nuclear medicine departments. One problem has been the lack of data upon which decisions can be based. In the last five years we and others have made a number of measurements of radiation doses to staff relating to nuclear medicine practice. This paper collates, summarizes and comments on this information. Where possible, results have been expressed in relation to the workload of an average nuclear medicine department. (author)

  19. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1995-11-01

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement

  20. 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

  1. Comments on the NRC Safety Research Program budget

    International Nuclear Information System (INIS)

    1979-07-01

    This report includes comments on the budget levels and program plans for the supplemental request for FY 1980 to support research related to the accident at Three Mile Island, Unit 2 (TMI) as well as for the FY 1981 Budget. For both budgets, the funding levels considered by the ACRS are the original requests by RES and the Budget Review Group (BRG) markup as of July 10, 1979. In its current review of the NRC research program, the ACRS has given special attention to both the short- and long-term implications of the TMI accident and their significance to research for both the short- and long-term research programs

  2. NRC Information No. 88-12: Overgreasing of electric motor bearings

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    NRC personnel observed accumulations of grease on the air vent screens of electric motors used for driving such rotating equipment as fans and pumps at the Millstone and Calvert Cliffs nuclear power plants. The grease appeared to have come from overgreasing of the electric motor bearings. Grease was forced out of the bearing seals, onto the stator windings and rotor, from where it either fell or was thrown onto the inside of the motor housing. Because of these observations, the NRC began an investigation into problems that have been caused in the past, or could be caused in the future, by the overgreasing of electric motor bearings. The NRC staff has solicited technical information and operating experience on the problems caused by the overgreasing of electric motor bearings from motor and bearing manufacturers, as well as from other licensees. Their responses are summarized in this discussion

  3. 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)

  4. Changing emphasis at the NRC's Office of Nuclear Regulatory Research

    International Nuclear Information System (INIS)

    Remick, F.J.

    1994-01-01

    One of the major objectives of the Office of Research is to ensure availability of sound technical information for timely decision making in support of the NRC's safety mission. The Office of Research is changing some of its emphasis to better meet the expected needs of the NRC's regulatory offices. Long-standing programs in support of operating reactors are nearing completion. These programs include plant aging and severe accident research for currently operating plants. This meeting will also address the new challenges faced by the NRC in its review of the advanced light water and non-light water reactors. As plant aging and severe accident research programs are nearing completion, the research activities are coming to focus on the emerging technologies, for example, digital instrumentation and control systems, both as replacement equipment for operating plants and as the technology of choice and necessity for the advanced reactors. Necessity, because analog equipment is becoming obsolete. Other examples include the use of new materials in operating plants, human factors considerations in the design and operation of the advanced plants, thermal-hydraulic characteristics of the advanced reactors, and new construction techniques

  5. Preparing as an organization to review a construction license application for a DGR for HLW and SF in the USA

    International Nuclear Information System (INIS)

    Hill, Brittain

    2014-01-01

    Although formally opposed by the State of Nevada, the Yucca Mountain site (Nevada) recommendation was approved by the U.S. Congress and the President, which authorized DOE to prepare and submit a license application for a deep geologic repository for the nation's spent nuclear fuel and high-level waste. In June of 2008, DOE submitted this application to the U.S. Nuclear Regulatory Commission (NRC) for its review and formal adjudication of contested issues during a 3-4 year period. Although subsequent actions by the Administration and Congress have changed the direction for geologic disposal in the U.S., the NRC staff was able to conduct a thorough technical review of the DOE license application and issue technical evaluation reports before the review and hearings were suspended in September 2011. This paper provides the author's perspective on how the NRC prepared for, and conducted, this first-of-a-kind licensing review: planning framework, key preparations for staff and for processes, events after the receipt of a license application, retrospective on staff preparations and on processes. By the end of September 2011, the NRC staff had issued three Technical Evaluation Reports using a risk-informed, performance-based approach to review the DOE license application for this deep geologic repository at Yucca Mountain

  6. Overview of the NRC performance monitoring program

    International Nuclear Information System (INIS)

    Jordan, E.L.

    1987-01-01

    In response to the accident at Three Mile Island, the NRC developed the Systematic Assessment of Licensee Performance (SALP) Program to aid in the identification of those licensees that were more likely than others to have safety problems and to provide a rational basis for allocation of inspection resources. The NRC also has an ongoing program of screening and evaluating operating reactor event reports on a daily basis for promptly identifying safety problems. Although the SALP and event report evaluation programs have been successful in identifying potential performance problems, a concern developed recently about the adequacy and timeliness of NRC programs to detect poor or declining performance. The performance indicator program as approved by the commission is in the implementation phase. The program is expected to undergo refinements as new indicators are developed and experience is gained in the use of indicators

  7. NRC/RSR Data Bank Program

    International Nuclear Information System (INIS)

    Bankert, S.F.; Evans, C.D.; Hardy, H.A.; Litteer, G.L.; Schulz, G.L.; Smith, N.C.

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program to provide a means of collecting, processing, and making available experimental data from the many domestic and foreign water reactor safety research programs. The NRC/RSR Data Bank Program collects qualified engineering data from experimental program data bases, stores the data in a single data bank in a common format, and makes the data available to users. The program is designed to be user oriented to minimize the effort required to obtain and manipulate data of interest. The data bank concept and structure embodied in the data bank processing system are applicable to any program where large quantities of scientific (numeric) data are generated and require compiling, storage, and accessing in order to be collected and made available to multiple users. 3 figures

  8. Georgia; First Review Under the Stand-By Arrangement-Staff Report; Press Release on the Executive Board Discussion; and Statement by the Executive Director for Georgia

    OpenAIRE

    International Monetary Fund

    2009-01-01

    The staff report for the First Review Under the Stand-By Arrangement with the officials of Georgia highlights economic developments and policies. Sustaining economic growth and maintaining confidence in the currency and the financial system within the constraints of available external financing are the main program priorities. IMF staff recommended a more active role for monetary policy in encouraging market interest rate adjustments. With global markets in distress, the authorities should wo...

  9. Compilation of fastener testing data received in response to NRC Compliance Bulletin 87-02

    International Nuclear Information System (INIS)

    Cwalina, G.C.; Conway, J.T.; Parker, L.B.

    1989-06-01

    On November 6, 1987, the Nuclear Regulatory Commission (NRC) issued Bulletin 87-02, ''Fastener Testing to Determine Conformance With Applicable Material Specifications,'' to all holders of operating licenses or construction permits for nuclear power reactors (licensees). The bulletin was issued so that the NRC staff could gather data to determine whether counterfeit fasteners are a problem in the nuclear power industry. The bulletin requested nuclear power plant owners to determine whether fasteners obtained from suppliers and/or manufacturers for use in their facilities meet the mechanical and chemical specifications stipulated in the procurement documents. The licensees were requested to sample a minimum of 10 safety-related and 10 non-safety-related fasteners (studs, bolts, and/or cap screws) and a sample of typical nuts that would be used with each fastener and to report the testing results to the NRC. The results of this study did not indicate a safety concern relating to the use of mismarked or counterfeit fasteners in the nuclear industry, but they did indicate a nonconformance rate of 8 to 12 percent for fasteners. The NRC staff is considering taking action to improve the effectiveness of receipt inspection and testing programs for all materials at nuclear power plants

  10. NRC/RSR Data Bank Program

    International Nuclear Information System (INIS)

    Bankert, S.F.; Evans, C.D.; Hardy, H.A.; Litteer, G.L.; Schulz, G.L.; Smith, N.C.

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program at the Idaho National Engineering Laboratory (INEL). The program provides the means of collecting, storing, and making available experimental data from the many water reactor safety research programs in the United States and other countries. The program collects qualified engineering data on a prioritized basis from experimental program data bases, stores the data in a single data bank in a common format, and makes the data available to users

  11. NRC program of inspection and enforcement

    International Nuclear Information System (INIS)

    LeDoux, J.C.; Rehfuss, C.

    1978-01-01

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

  12. A systematic review of clinician and staff views on the acceptability of incorporating remote monitoring technology into primary care.

    Science.gov (United States)

    Davis, Melinda M; Freeman, Michele; Kaye, Jeffrey; Vuckovic, Nancy; Buckley, David I

    2014-05-01

    Remote monitoring technology (RMT) may enhance healthcare quality and reduce costs. RMT adoption depends on perceptions of the end-user (e.g., patients, caregivers, healthcare providers). We conducted a systematic review exploring the acceptability and feasibility of RMT use in routine adult patient care, from the perspectives of primary care clinicians, administrators, and clinic staff. We searched the databases of Medline, IEEE Xplore, and Compendex for original articles published from January 1996 through February 2013. We manually screened bibliographies of pertinent studies and consulted experts to identify English-language studies meeting our inclusion criteria. Of 939 citations identified, 15 studies reported in 16 publications met inclusion criteria. Studies were heterogeneous by country, type of RMT used, patient and provider characteristics, and method of implementation and evaluation. Clinicians, staff, and administrators generally held positive views about RMTs. Concerns emerged regarding clinical relevance of RMT data, changing clinical roles and patterns of care (e.g., reduced quality of care from fewer patient visits, overtreatment), insufficient staffing or time to monitor and discuss RMT data, data incompatibility with a clinic's electronic health record (EHR), and unclear legal liability regarding response protocols. This small body of heterogeneous literature suggests that for RMTs to be adopted in primary care, researchers and developers must ensure clinical relevance, support adequate infrastructure, streamline data transmission into EHR systems, attend to changing care patterns and professional roles, and clarify response protocols. There is a critical need to engage end-users in the development and implementation of RMT.

  13. AECB staff review of Bruce NGS 'A' operation for the year 1989

    International Nuclear Information System (INIS)

    1990-06-01

    The operation of the Bruce Nuclear Generating Station 'B' is monitored and licensing requirements are enforced by the Atomic Energy Control Board (AECB). This report records the conclusions of the AECB staff assessment of Bruce NGS 'A' during 1989 and the early part of 1990. Overall operation of the station met acceptable safety standards. Despite numerous problems and technical difficulties encountered, station management and supervisory personnel acted with due caution and made decisions in the interests of safety. There was evidence of improvement in a number of key areas, supported by pertinent indicators in the objective measures table. The extensive inspection and maintenance programs carried out during the year revealed the extent of component deterioration due to aging to be larger than expected. Hydrogen embrittlement of pressure tubes, erosion/corrosion of steam and feed water valves, heat exchanger tubes and piping, fouling of boilers and heat exchangers, and environmental damage of electrical equipment are examples. Continued aging of plant equipment and its potential for reducing the margins for safe operation must be taken into account by Ontario Hydro in establishing priorities and target dates for completion of actions to resolve identified problems at Bruce NGS 'A'. (2 tabs.)

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

    International Nuclear Information System (INIS)

    Moore, V.A.

    1985-01-01

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

  15. Effects of person-centered care on residents and staff in aged-care facilities: a systematic review

    Directory of Open Access Journals (Sweden)

    Brownie S

    2013-01-01

    Full Text Available Sonya Brownie, Susan NancarrowSchool of Health and Human Sciences, Southern Cross University, Lismore, NSW, AustraliaBackground: Several residential aged-care facilities have replaced the institutional model of care to one that accepts person-centered care as the guiding standard of practice. This culture change is impacting the provision of aged-care services around the world. This systematic review evaluates the evidence for an impact of person-centered interventions on aged-care residents and nursing staff.Methods: We searched Medline, Cinahl, Academic Search Premier, Scopus, Proquest, and Expanded Academic ASAP databases for studies published between January 1995 and October 2012, using subject headings and free-text search terms (in UK and US English spelling including person-centered care, patient-centered care, resident-oriented care, Eden Alternative, Green House model, Wellspring model, long-term care, and nursing homes.Results: The search identified 323 potentially relevant articles. Once duplicates were removed, 146 were screened for inclusion in this review; 21 were assessed for methodological quality, resulting in nine articles (seven studies that met our inclusion criteria. There was only one randomized, controlled trial. The majority of studies were quasi-experimental pre-post test designs, with a control group (n = 4. The studies in this review incorporated a range of different outcome measures (ie, dependent variables to evaluate the impact of person-centered interventions on aged-care residents and staff. One person-centered intervention, ie, the Eden Alternative, was associated with significant improvements in residents' levels of boredom and helplessness. In contrast, facility-specific person-centered interventions were found to impact nurses' sense of job satisfaction and their capacity to meet the individual needs of residents in a positive way. Two studies found that person-centered care was actually associated with an

  16. Education and training of healthcare staff in the knowledge, attitudes and skills needed to work effectively with breastfeeding women: a systematic review.

    Science.gov (United States)

    Gavine, Anna; MacGillivray, Steve; Renfrew, Mary J; Siebelt, Lindsay; Haggi, Haggi; McFadden, Alison

    2016-01-01

    Current evidence suggests that women need effective support to breastfeed, but many healthcare staff lack the necessary knowledge, attitudes and skills. There is therefore a need for breastfeeding education and training for healthcare staff. The primary aim of this review is to determine whether education and training programs for healthcare staff have an effect on their knowledge and attitudes about supporting breastfeeding women. The secondary aim of this review was to identify whether any differences in type of training or discipline of staff mattered. A systematic search of the literature was conducted using the Cochrane Pregnancy and Childbirth Group's trial register. Randomised controlled trials comparing breastfeeding education and training for healthcare staff with no or usual training and education were included if they measured the impact on staff knowledge, attitudes or compliance with the Baby Friendly Hospital Initiative (BFHI). From the 1192 reports identified, four distinct studies were included. Three studies were two-arm cluster-randomised trials and one was a two-arm individual randomised trial. Of these, three contributed quantitative data from a total of 250 participants. Due to heterogeneity of outcome measures meta-analysis was not possible. Knowledge was included as an outcome in two studies and demonstrated small but significant positive effects. Attitudes towards breastfeeding was included as an outcome in two studies, however, results were inconsistent both in terms of how they were measured and the intervention effects. One study reported a small but significant positive effect on BFHI compliance. Study quality was generally deemed low with the majority of domains being judged as high or unclear risk of bias. This review identified a lack of good evidence on breastfeeding education and training for healthcare staff. There is therefore a critical need for research to address breastfeeding education and training needs of multidisciplinary

  17. Work-based learning in health care organisations experienced by nursing staff: A systematic review of qualitative studies.

    Science.gov (United States)

    Nevalainen, Marja; Lunkka, Nina; Suhonen, Marjo

    2018-03-01

    The aim of this review is to systematically summarise qualitative evidence about work-based learning in health care organisations as experienced by nursing staff. Work-based learning is understood as informal learning that occurs inside the work community in the interaction between employees. Studies for this review were searched for in the CINAHL, PubMed, Scopus and ABI Inform ProQuest databases for the period 2000-2015. Nine original studies met the inclusion criteria. After the critical appraisal by two researchers, all nine studies were selected for the review. The findings of the original studies were aggregated, and four statements were prepared, to be utilised in clinical work and decision-making. The statements concerned the following issues: (1) the culture of the work community; (2) the physical structures, spaces and duties of the work unit; (3) management; and (4) interpersonal relations. Understanding the nurses' experiences of work-based learning and factors behind these experiences provides an opportunity to influence the challenges of learning in the demanding context of health care organisations. Copyright © 2017 Elsevier Ltd. All rights reserved.

  18. NRC comprehensive records disposition schedule. Revision 3

    International Nuclear Information System (INIS)

    1998-02-01

    Title 44 US Code, ''Public Printing and Documents,'' regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ''Management and Use of Information and Records,'' and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ''Records Management,'' require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA's General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ''NRC's Comprehensive Records Disposition Schedule,'' and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA's General Records Schedule (dated August 1995)

  19. Abstracts: NRC Waste Management Program reports

    Energy Technology Data Exchange (ETDEWEB)

    Heckman, R.A.; Minichino, C.

    1979-11-01

    This document consists of abstracts of all reports published by the Nuclear Regulatory Commission (NRC) Waste Management Program at Lawrence Livermore Laboratory (LLL). It will be updated at regular intervals. Reports are arranged in numerical order, within each category. Unless otherwise specified, authors are LLL scientists and engineers.

  20. NRC/AMRMC Resident Research Associateship Program

    Science.gov (United States)

    2015-05-01

    maintaining a presence on social media sites such as Facebook . The NRC attended a number of minority focused events in which we maintained exhibit booths...PROPOSAL The Use of Glial Inhibitors to Increase the Efficacy of Opioid Analgesics while Eliminating the Propensity for Addiction 7) SUMMARY OF RESEARCH

  1. Abstracts: NRC Waste Management Program reports

    International Nuclear Information System (INIS)

    Heckman, R.A.; Minichino, C.

    1979-11-01

    This document consists of abstracts of all reports published by the Nuclear Regulatory Commission (NRC) Waste Management Program at Lawrence Livermore Laboratory (LLL). It will be updated at regular intervals. Reports are arranged in numerical order, within each category. Unless otherwise specified, authors are LLL scientists and engineers

  2. 77 FR 33786 - NRC Enforcement Policy Revision

    Science.gov (United States)

    2012-06-07

    ... methods: Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2011... search, select ``ADAMS Public Documents'' and then select ``Begin Web- based ADAMS Search.'' For problems... either 2.3.2.a. or b. must be met for the disposition of a violation as an NCV.'' The following new...

  3. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.

    1994-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1993. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  4. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1993-03-01

    This report present the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1992. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  5. 48 CFR 2009.100 - NRC policy.

    Science.gov (United States)

    2010-10-01

    ... noncompetitive award of contracts to organizations where former NRC employees have dominant management interests...) Contracts awarded noncompetitively under the Small Business Administration's 8(a) Program; (2) Individual... consulting with the Executive Director for Operations. This is in addition to any justification and approvals...

  6. NRC/RSR data bank program

    International Nuclear Information System (INIS)

    Bankert, S.F.; Evans, C.D.; Hardy, H.A.; Litteer, G.L.; Schulz, G.L.; Smith, N.C.

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) has established at the Idaho National Engineering Laboratory (INEL) the NRC/Reactor Safety Research (RSR) Data Bank Program. The program is under the direction of EG and G Idaho, Inc., and is intended to provide the means of collecting, processing, and making available experimental data from the many water reactor safety research programs. The NRC/RSR Data Bank Program collects qualified engineering data on a prioritized basis from experimental program data bases, stores the data in a single data bank in a common format, and makes the data available to users. The NRC/RSR Data Bank specializes in water reactor safety experimental data, but it has a number of other scientific applications where large amounts of numeric data are or will be available. As an example of size, a single water reactor safety test may generate 10 million data words. Future examples of the use of a data bank might be in gathering data on low head hydraulics, solar projects, and liquid metal reactor safety data

  7. NRC comprehensive records disposition schedule. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

    Title 44 US Code, ``Public Printing and Documents,`` regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ``Management and Use of Information and Records,`` and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA`s General Records Schedule (dated August 1995).

  8. Report of the Committee to review safeguards requirements at power reactors

    International Nuclear Information System (INIS)

    1983-05-01

    In October 1982, NRC's Executive Director for Operations appointed a five-member Committee to review NRC security requirements at nuclear power plants with a view toward evaluating the impact of these requirements on operational safety. During visits to five power reactor sites and more than a dozen days of meetings over a period of four months, the Committee observed plant operating conditions and obtained views from abut 100 persons representing 16 nuclear utilities and industry organizations. They also interviewed about 40 NRC employees, including Resident Inspectors, and members of the Regional and Headquarters staffs. Overall, the Committee did not identify any clear operational safety problems associated with implementation of the NRC's security requirements. However, they did find that the potential existed, to varying degrees, at licensed facilities. The Committee's report, dated February 28, 1983, contains five basic findings and a number of associated recommendations intended to minimize the potential impact of security on safety

  9. Education of staff in preschool aged classrooms in child care centers and child outcomes: A meta-analysis and systematic review.

    Science.gov (United States)

    Falenchuk, Olesya; Perlman, Michal; McMullen, Evelyn; Fletcher, Brooke; Shah, Prakesh S

    2017-01-01

    Staff education is considered key to quality of early childhood education and care (ECEC) programs. However, findings about associations between staff education and children's outcomes have been inconsistent. We conducted a systematic review and meta-analysis of associations between ECEC staff education and child outcomes. Searches of Medline, PsycINFO, and ERIC, websites of large datasets and reference sections of all retrieved articles were conducted. Eligible studies provided a statistical link between staff education and child outcomes for preschool-aged children in ECEC programs. Titles, abstracts and paper reviews as well as all data extraction were conducted by two independent raters. Of the 823 studies reviewed for eligibility, 39 met our inclusion criteria. Research in this area is observational in nature and subject to the inherent biases of that research design. Results from our systematic review were hampered by heterogeneity in how staff education was defined, variability in whose education was measured and the child outcomes that were assessed. However, overall the qualitative summary indicates that associations between staff education and childhood outcomes are non-existent to very borderline positive. In our meta-analysis of more homogeneous studies we identified certain positive, albeit very weak, associations between staff education and children's language outcomes (specifically, vocabulary and letter word identification) and no significant association with a mathematics outcome (WJ Applied Problems). Thus, our findings suggest that within the range of education levels found in the existing literature, education is not a key driver of child outcomes. However, since we only explored levels of education that were reported in the literature, our findings cannot be used to argue for lowering education standards in ECEC settings.

  10. Development and utilization of the NRC policy statement on the regulation of advanced nuclear power plants

    International Nuclear Information System (INIS)

    Williams, P.M.; King, T.L.

    1988-06-01

    On March 26, 1985, the US Nuclear Regulatory Commission issued for public comment a ''Proposed Policy for Regulation of Advanced Nuclear Power Plants'' (50 FR 11884). This report presents and discusses the Commission's final version of that policy as titled and published on July 8, 1986 ''Regulation of Advanced Nuclear Power Plants, Statement of Policy'' (51 FR 24643). It provides an overview of comments received from the public, of the significant changes from the proposed Policy Statement to the final Policy Statement, and of the Commission's response to six questions contained in the proposed Policy Statement. The report also discusses the definition for advanced reactors, the establishment of an Advanced Reactors Group, the staff review approach and information needs, and the utilization of the Policy Statement in relation to other NRC programs, including the policies for safety goals, severe accidents and standardization. In addition, guidance for advanced reactors with respect to operating experience, technology development, foreign information and data, and prototype testing is provided. Finally, a discussion on the use of less prescriptive and nonprescriptive design criteria for advanced reactors, which the Policy Statement encourages, is presented

  11. Pilot program: NRC severe reactor accident incident response training manual: Public protective actions: Predetermined criteria and initial actions

    International Nuclear Information System (INIS)

    Martin, J.A. Jr.; McKenna, T.J.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

    1987-02-01

    This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Public Protective Actions - Predetermined Criteria and Initial Actions is the fourth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume reviews public protective action criteria and objectives, their bases and implementation, and the expected public response. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

  12. Streamlining the license renewal review process

    International Nuclear Information System (INIS)

    Dozier, J.; Lee, S.; Kuo, P.T.

    2001-01-01

    The staff of the NRC has been developing three regulatory guidance documents for license renewal: the Generic Aging Lessons Learned (GALL) report, Standard Review Plan for License Renewal (SRP-LR), and Regulatory Guide (RG) for Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses. These documents are designed to streamline the license renewal review process by providing clear guidance for license renewal applicants and the NRC staff in preparing and reviewing license renewal applications. The GALL report systematically catalogs aging effects on structures and components; identifies the relevant existing plant programs; and evaluates the existing programs against the attributes considered necessary for an aging management program to be acceptable for license renewal. The GALL report also provides guidance for the augmentation of existing plant programs for license renewal. The revised SRP-LR allows an applicant to reference the GALL report to preclude further NRC staff evaluation if the plant's existing programs meet the criteria described in the GALL report. During the review process, the NRC staff will focus primarily on existing programs that should be augmented or new programs developed specifically for license renewal. The Regulatory Guide is expected to endorse the Nuclear Energy Institute (NEI) guideline, NEI 95-10, Revision 2, entitled 'Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule', which provides guidance for preparing a license renewal application. This paper will provide an introduction to the GALL report, SRP-LR, Regulatory Guide, and NEI 95-10 to show how these documents are interrelated and how they will be used to streamline the license renewal review process. This topic will be of interest to domestic power utilities considering license renewal and international ICONE participants seeking state-of-the-art information about license renewal in the United States

  13. Independent peer review of nuclear safety computer codes

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  14. NRC Information No. 90-01: Importance of proper response to self-identified violations by licensees

    International Nuclear Information System (INIS)

    Cunningham, R.E.

    1992-01-01

    NRC expects a high standard of compliance by its licensees and requires that licensees provide NRC accurate and complete information and that required records will also be complete and accurate in all material respects. Licensees should be aware of the importance placed by NRC on licensee programs for self detection, correction and reporting of violations or errors related to regulatory requirements. The General Statement of Policy and Procedures for NRC Enforcement Actions in Appendix C to 10 CFR Part 2 underscores the importance of licensees responding promptly and properly to self-identified violations in two ways. It is suggested that when a licensee identifies a violation involving an NRC-required record, the licensee should make a dated notation indicating identification, either on the record itself or other appropriate documentation retrievable for NRC review. The record with the self-identified violation noted should not be altered in any way to mask the correction. The licensee should determine the cause of the violation, correct the root cause of the violation, and document such findings in an appropriate manner. Licensees should also assure that if a report of the violation is required, the report is submitted to NRC in a timely manner. These actions will be considered by NRC in making any enforcement decision, and generally lead to lesser or no civil penalty

  15. United States Nuclear Regulatory Commission Staff practice and procedure digest

    International Nuclear Information System (INIS)

    1991-12-01

    This sixth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to December 31, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This sixth edition replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through December 31, 1990

  16. Managing aging in nuclear power plants: Insights from NRC's maintenance team inspection reports

    International Nuclear Information System (INIS)

    Fresco, A.; Subudhi, M.

    1994-01-01

    Age-related degradation is managed through the maintenance program of a nuclear plant. From 1988 to 1991, the Nuclear Regulatory Commission (NRC) evaluated the maintenance program of every nuclear power plant in the United States. The authors reviewed 44 out of a total of 67 of the reports issued by the NRC on these in-depth team inspections. The reports were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant structures, systems, and components. The authors' conclusions are presented. 6 refs

  17. NRC Regulatory Agenda: Quarterly report, October--December 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The NRC Regulatory Agenda is a compilation of all rules which the NRC has proposed or is considering action on, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission

  18. Nursing staff under heavy stress: focus on Greece A critical review

    Directory of Open Access Journals (Sweden)

    Dimitrios Theofanidis

    2011-01-01

    Full Text Available Background: Current global financial constrains place a burden on the development of health care services worldwide. Although nurses are the backbone of any health establishment, they seem are under constant occupational stress which varies from country to country.Aim: This paper aims to present and analyze critically the key stress factors on contemporary nursing.Method: A strategically planned four-step literature review was used focusing on identifying key stress factors in selected papers.Results: The refining process identified 26 key references which were analyzed and tabulated. These revealed areas of concern such as: insufficient work recourses, poor communication with superiors, dissatisfaction with psychosocial work environment, lowering levels of education achieved and pay, split-shifts and prolonged night shifts, high demanding tasks, verbal abuse, mobbing and antagonistic attitudes in work place and poor organization at work.Conclusions: A number of intervention strategies to avoid excess stress are presented which include: improved education of the workforce and awareness building; assessment-focused interventions; therapeutic counseling; skill-building and reorganizing the work environment.

  19. Health Facility Staff Training for Improving Breastfeeding Outcome: A Systematic Review for Step 2 of the Baby-Friendly Hospital Initiative.

    Science.gov (United States)

    Balogun, Olukunmi O; Dagvadorj, Amarjargal; Yourkavitch, Jennifer; da Silva Lopes, Katharina; Suto, Maiko; Takemoto, Yo; Mori, Rintaro; Rayco-Solon, Pura; Ota, Erika

    2017-11-01

    The Baby-Friendly Hospital Initiative (BFHI) implemented through the "Ten Steps to Successful Breastfeeding" has been widely promoted as an intervention that improves breastfeeding rates. Step 2 requires the training of all healthcare staff in skills that are necessary to implement the policy. This systematic review provides evidence about the effect of training healthcare staff in hospitals and birth centers on breastfeeding outcomes. Randomized controlled trials (RCT), quasi-RCT, and controlled before and after (CBA) studies comparing training of healthcare staff on breastfeeding and supportive feeding practices with no training were included in this review. We searched CENTRAL PubMed, EMBASE, CINAHL, Web of Science, and the British Nursing Index for studies. Studies were screened against predetermined criteria, and risk of bias of included studies was assessed using the Risk of Bias Assessment tool for Non-Randomized Studies for non-RCT studies and the Cochrane Handbook for Systematic Reviews of Interventions for RCT studies. Of the six studies included in this review, three were RCT whereas three were CBA studies. The studies were conducted in 5 countries and involved 390 healthcare staff. Provision of educational interventions aimed at increasing knowledge and practice of BFHI and support was found to improve health worker's knowledge, attitude, and compliance with the BFHI practices. In one study, the rate of exclusive breastfeeding increased at the intervention site but no differences were found for breastfeeding initiation rates. All included studies had methodological limitations, and study designs and methodologies lacked comparability.

  20. 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.

  1. Current NRC activities related to MQA

    Energy Technology Data Exchange (ETDEWEB)

    Trottier, C.A.; Nellis, D.O. [Nuclear Regulatory Commission, Washington, DC (United States)

    1993-12-31

    The U.S. Nuclear Regulatory Commission`s (NRC`s) interest in measurement quality assurance (MQA) goes back to before 1963, when the Atomic Energy Commission (AEC) published a notice in the Federal Register concerning the need for establishing a Film Dosimetry Calibration Laboratory, and also provided a set of minimum performance criteria to be used by the laboratory in evaluating film dosimetry services used by licensees. The proposed laboratory was not established, but in 1967 the AEC contracted with Battelle`s Pacific Northwest Laboratory (PNL) to evaluate film dosimeter performance criteria and provide a basis for establishing a Film Dosimetry Calibration Laboratory if the study showed that it was needed. Then, in 1973, the Conference of Radiation Control Program Directors (CRCPD), concerned with the state of dosimetry processing and the lack of adequate standards, recommended that the National Bureau of Standards (NBS) direct a performance testing program for personnel dosimetry processing services. Later, in 1976, NRC asked PNL to conduct a study to evaluate the four existing performance standards for personnel dosimetry processing. One result of this study was that the HPSSC standard, which later became ANSI N13.11, was recommended as the standard for use in a national dosimetry processing program. The rest is common knowledge. With the support of numerous other federal agencies and the CRCPD, NRC published a regulation, effective in 1988, that required all processors of personnel dosimeters be accredited under the National Voluntary Laboratory Accreditation Program (NVLAP), operated by the NBS, which is now called the National Institute of Standards and Technology (NIST). At present, there are 75 dosimetry processing laboratories accredited under NVLAP. NRC has also been involved in extremity dosimeters, health physics survey instruments, bioassay measurements, electronic personnel dosimeters, and environmental monitoring around nuclear power plants.

  2. NRC/AMRMC Resident Research Associateship Program

    Science.gov (United States)

    2018-05-01

    2- 0010 Report Period: 02/06/2012-02/28/2018 4/11/2018, 12:17 PM During the reporting period, the National Academies of Sciences, Engineering , and...to advertise the NRC Research Associateship Programs included the following: 1) attendance at meetings of major scientific and engineering ...professional societies; 2) advertising in programs and career centers for these and other professional society meetings; 3) direct mailing and emailing of

  3. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1991-04-01

    This report presents the results of the NRC [Nuclear Regulatory Commission] Direct Radiation Monitoring Network for the fourth quarter of 1990. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs

  4. NRC as referee (reactor licensing following the Three Mile Island accident)

    International Nuclear Information System (INIS)

    Eisenhut, D.G.

    1984-01-01

    In this article, the NRC's licensing director reports on the progress made by US utilities in complying with the key regulations stemming from the Three Mile Island accident. Over 130 items must be improved at more than 65 reactors. The actions taken by France in response to its own analysis of the accident are discussed. New NRC requirements with regard to operational safety, design, and emergency-response capability are outlined. Nearly all the training, or software, items in Nureg-0737 (''Clarification of TMI Action Plan Requirements'') and more than half of the mechanical, or hardware, items have been completed at plants with operating reactors. The Committee to Review Generic Requirements was created to develop means for controlling the number and nature of NRC requirements placed on licensees. Probabilistic risk-assessment techniques were not widely used by the NRC until after the Three Mile Island accident. The NRC has directed licensees and applicants for operating licenses to conduct control-room design reviews to identify and correct human-engineering discrepancies. Includes 2 tables

  5. The evolution of the structure and application of U.S. NRC regulations and standards

    International Nuclear Information System (INIS)

    Murley, T.E.; Rosztoczy, Z.R.; McPherson, G.D.

    1991-01-01

    NRC regulations and standards and their implementation have evolved from early adaptations of conventional engineering practices to a mature, cohesive set of regulations that govern NRC regulation of nuclear power plant safety in the United States. From a simple set of rules and design criteria and from the standards of the professional engineering societies, a hierarchy of practices, standards, guides, rules and goals has developed. Resting on a foundation of industrial practices, this hierarchy rises through levels of national standards, regulatory guides and standard review plans, policy statements and NRC regulations. The licensing process is evolving today toward one that permits both site approval and standard design certification before the plant is constructed. At the present time, NRC is reviewing five standard designs for certification for a period of 15 years. NRC focuses its regulation of operating nuclear plants on inspections conducted from five regional offices. Resident inspectors, specialist inspectors, and multi-disciplinary inspection teams examine specific plant situations. The results of all these inspections are used to develop a complete understanding of a plant's physical condition, its operation, maintenance and management. To improve safe operation of nuclear plants in the U.S., a most important program, the Systematic Assessment of Licensee Performance, measures operational performance, using a broad spectrum of functional areas. (orig.)

  6. The effect of nutrition training for health care staff on learner and patient outcomes in adults: a systematic review and meta-analysis.

    Science.gov (United States)

    Marples, Owen; Baldwin, Christine; Weekes, C Elizabeth

    2017-07-01

    Background: Nutrition training for health care staff has been prioritized internationally as a key means of tackling malnutrition; however, there is a lack of clear evidence to support its implementation. Systematic reviews in other fields of training for health care staff indicate that training strategies may have a beneficial impact on learner and patient outcomes. Objectives: We assessed whether nutrition training for health care staff caring for nutritionally vulnerable adults resulted in improved learner and patient outcomes and evaluated the effectiveness of different training strategies. Design: A systematic review of trials of nutrition training for health care staff was conducted. Six databases were searched with key terms relating to malnutrition and nutrition training. Studies were categorized according to cognitive (didactic teaching), behavioral (practical implementation of skills), and psychological (individualized or group feedback and reflection) training strategies. Where sufficient data were available, meta-analysis was performed according to study design and training strategy. All study designs were eligible. The risk of bias was evaluated in accordance with Cochrane guidance. Results: Twenty-four studies met the eligibility criteria: 1 randomized controlled trial, 4 nonrandomized controlled trials, 3 quasi-experimental trials, 13 longitudinal pre-post trials, 2 qualitative studies, and 1 cross-sectional survey. Results from a number of low-quality studies suggest that nutrition training for health care staff may have a beneficial effect on staff nutrition knowledge, practice, and attitude as well as patient nutritional intake. There were insufficient data to determine whether any particular training strategy was more effective than the others. Conclusions: In the absence of high-quality evidence, low-quality studies suggest that nutrition training for health care staff has some positive effects. However, further randomized controlled trials are

  7. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1992-06-01

    The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network is operated by the NRC in cooperation with participating states to provide continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. Ambient radiation levels result from naturally occurring radionuclides present in the soil, cosmic radiation constantly bombarding the earth from outer space, and the contribution, if any, from the monitored facilities and other man-made sources. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the first quarter of 1992. All radiation measurements are made using small, passive detectors called thermoluminescent dosimeters (TLDs), which provide a quantitative measurement of the radiation levels in the area in which they are placed. Each site is monitored by arranging approximately 40 to 50 TLD stations in two concentric rings extending to about five miles from the facility. All TLD stations are outside the site boundary of the facility

  8. 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

  9. Consistent assignment of nursing staff to residents in nursing homes: a critical review of conceptual and methodological issues.

    Science.gov (United States)

    Roberts, Tonya; Nolet, Kimberly; Bowers, Barbara

    2015-06-01

    Consistent assignment of nursing staff to residents is promoted by a number of national organizations as a strategy for improving nursing home quality and is included in pay for performance schedules in several states. However, research has shown inconsistent effects of consistent assignment on quality outcomes. In order to advance the state of the science of research on consistent assignment and inform current practice and policy, a literature review was conducted to critique conceptual and methodological understandings of consistent assignment. Twenty original research reports of consistent assignment in nursing homes were found through a variety of search strategies. Consistent assignment was conceptualized and operationalized in multiple ways with little overlap from study to study. There was a lack of established methods to measure consistent assignment. Methodological limitations included a lack of control and statistical analyses of group differences in experimental-level studies, small sample sizes, lack of attention to confounds in multicomponent interventions, and outcomes that were not theoretically linked. Future research should focus on developing a conceptual understanding of consistent assignment focused on definition, measurement, and links to outcomes. To inform current policies, testing consistent assignment should include attention to contexts within and levels at which it is most effective. Published by Oxford University Press on behalf of the Gerontological Society of America 2013.

  10. Effectiveness of interventions to improve family-staff relationships in the care of people with dementia in residential aged care: a systematic review protocol.

    Science.gov (United States)

    Nguyen, Mynhi; Pachana, Nancy A; Beattie, Elizabeth; Fielding, Elaine; Ramis, Mary-Anne

    2015-11-01

    The objective of this review is to identify and appraise existing evidence regarding the effectiveness of interventions designed to enhance staff-family relationships for people with dementia living in residential aged care facilities.More specifically, the objectives are to identify the effectiveness of constructive communication, cooperation programs, and practices or strategies to enhance family-staff relationships. The effectiveness of these interventions will be measured by comparing the intervention to no intervention, comparing one intervention with another, or comparing pre- and post-interventions.Specifically the review question is: What are the most effective interventions for improving communication and cooperation to enhance family-staff relationships in residential aged care facilities? In our aging world, dementia is prevalent and is a serious health concern affecting approximately 35.6 million people worldwide. This figure is expected to increase two-fold by 2030 and three-fold by 2050. Although younger-onset dementia is increasingly recognized, dementia is most commonly a disease that affects the elderly. Among those aged 65 to 85, the prevalence of dementia increases exponentially, and doubles with every five-year increase in age.Dementia is defined as a syndrome, commonly chronic or progressive in nature, and caused by a range of brain disorders that affect memory, thinking and the ability to perform activities of daily living. While the rate of progression and manifestation of decline differs, all cases of dementia share a similar trajectory of decline. The progressive decline in cognitive functions and ultimately physical function that these people face affects not only the person with the disease but also their family caregivers and health care staff.The manifestation of dementia presents unique and extreme challenges for the family caregiver. Generally it causes great physical, emotional and social strain because the caregiving process is long

  11. [Single-family rooms for neonatal intensive care units impacts on preterm newborns, families, and health-care staff. A systematic literature review].

    Science.gov (United States)

    Servel, A-C; Rideau Batista Novais, A

    2016-09-01

    The quality of the environment is an essential point in the care of preterm newborns. The design of neonatal intensive care units (NICUs) (open-bay, single-patient room, single-family room) directly affects both the preterm newborns and their caregivers (parents, healthcare staff). The aim of this systematic review was to evaluate the impact of single-family rooms on the preterm newborn, its parents, and the staff. Single-family rooms improve outcome for the preterm newborn, with increasing parental involvement and better control of the environment (fewer inappropriate stimulations such as high levels of noise and illumination). This kind of NICU design also improves parental and staff satisfaction. Copyright © 2016 Elsevier Masson SAS. All rights reserved.

  12. Staff Association

    CERN Multimedia

    Staff Association

    2014-01-01

    Remove of the staff association office   The Staff Association offices are going to be renovated during the coming four months, February to May 2014. The physical move from our current premises 64/R-002 to our temporary office in  510/R-010 will take place on Friday January 31st, so the Secretariat will be closed on that day. Hence, from Monday February 3rd until the end of May 2014 the Staff Association Secretariat will be located in 510/R-010 (entrance just across the CERN Printshop).    

  13. General statement of policy and procedures for NRC enforcement actions: Enforcement policy. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    This document includes the US Nuclear Regulatory Commission`s (NRC`s or Commission`s) revised General Statement of Policy and Procedure for Enforcement Actions (Enforcement Policy) as it was published in the Federal Register on May 13, 1998 (63 ER 26630). The Enforcement Policy is a general statement of policy explaining the NRC`s policies and procedures in initiating enforcement actions, and of the presiding officers and the Commission in reviewing these actions. This policy statement is applicable to enforcement matters involving the radiological health and safety of the public, including employees` health and safety, the common defense and security, and the environment.

  14. General statement of policy and procedures for NRC enforcement actions: Enforcement policy. Revision 1

    International Nuclear Information System (INIS)

    1998-05-01

    This document includes the US Nuclear Regulatory Commission's (NRC's or Commission's) revised General Statement of Policy and Procedure for Enforcement Actions (Enforcement Policy) as it was published in the Federal Register on May 13, 1998 (63 ER 26630). The Enforcement Policy is a general statement of policy explaining the NRC's policies and procedures in initiating enforcement actions, and of the presiding officers and the Commission in reviewing these actions. This policy statement is applicable to enforcement matters involving the radiological health and safety of the public, including employees' health and safety, the common defense and security, and the environment

  15. NRC Information No. 88-04: Inadequate qualification and documentation of fire barrier penetration seals

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    The current NRC review was prompted by reports, inspection findings, allegations, and other information that indicated the possibility that NRC requirements for fire barrier penetration seals were not being met in all aspects. The review included: evaluations of fire barrier penetration seal specifications and procedures developed by licensees, licensee agents, and licensee contractors; evaluations of various fire barrier penetration seal tests and test data; and inspections of various fire barrier penetrations seal designs and installations. The types of concerns identified to date and mentioned below are related to weaknesses in the implementation of NRC requirements and guidelines as related to fire barrier penetration seal design qualification. The NRC review also has identified a current practice that can affect the qualification status of installed seals. Plant modifications are being made that require running new cable and conduits through existing penetration seals. These modifications are generally being made without an associated technical review to ensure that the resulting penetration seal design configuration or design parameters are consistent with those validated by initial qualification tests. Over a period of time, numerous minor modifications to the same area could cumulatively result in a degraded fire barrier rating

  16. NRC safety research in support of regulation - FY 1994. Volume 9

    International Nuclear Information System (INIS)

    1995-06-01

    This report, the tenth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1994. The goal of the Office of Nuclear Regulatory Research (RES) is to ensure the availability of sound technical bases for timely rulemaking and related decisions in support of NRC regulatory/licensing/inspection activities. RES also has responsibilities related to the resolution of generic safety issues and to the review of licensee submittals regarding individual plant examinations. It is the responsibility of RES to conduct the NRC's rulemaking process, including the issuance of regulatory guides and rules that govern NRC licensed activities

  17. Estimated incremental costs for NRC licensees to implement the US/IAEA safeguards agreement

    International Nuclear Information System (INIS)

    Clark, R.G.; Brouns, R.J.; Chockie, A.D.; Davenport, L.C.; Merrill, J.A.

    1979-01-01

    A study was recently completed for the US Nuclear Regulatory Commision (NRC) by the Pacific Northwest Laboratory (PNL) to identify the incremental cost of implementing the US/IAEA safeguards treaty agreement to eligible NRC licensees. Sources for the study were cost estimates from several licensees who will be affected by the agreement and cost analyses by PNL staff. The initial cost to all eligible licensees to implement the agreement is estimated by PNL to range from $1.9 to $7.2 million. The annual cost to these same licensees for the required accounting and reporting activities is estimated at $0.5 to $1.5 million. Annual inspection costs to the industry for the limited IAEA inspection being assumed is estimated at $80,000 to $160,000

  18. NRC high-level radioactive waste program. Annual progress report: Fiscal Year 1996

    International Nuclear Information System (INIS)

    Sagar, B.

    1997-01-01

    This annual status report for fiscal year 1996 documents technical work performed on ten key technical issues (KTI) that are most important to performance of the proposed geologic repository at Yucca Mountain. This report has been prepared jointly by the staff of the Nuclear Regulatory Commission (NRC) Division of Waste Management and the Center for Nuclear Waste Regulatory Analyses. The programmatic aspects of restructuring the NRC repository program in terms of KTIs is discussed and a brief summary of work accomplished is provided. The other ten chapters provide a comprehensive summary of the work in each KTI. Discussions on probability of future volcanic activity and its consequences, impacts of structural deformation and seismicity, the nature of of the near-field environment and its effects on container life and source term, flow and transport including effects of thermal loading, aspects of repository design, estimates of system performance, and activities related to the U.S. Environmental Protection Agency standard are provided

  19. NRC/FEMA operational response procedures for response to a commercial nuclear reactor accident

    International Nuclear Information System (INIS)

    1983-11-01

    Procedures have been developed by the US Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) which provide the response teams of both agencies with the steps to be taken in responding to an emergency at a commercial nuclear power plant. The emphasis of these procedures is mainly on the interface between NRC and FEMA at their respective Headquarters and Regional Offices and at the various sites at which such an emergency could occur. Detailed procedures are presented that cover for both agencies, notification schemes and manner of activation, organizations at Headquaters and the site, interface procedures, coordination of onsite and offsite operations, the role of the Senior FEMA Official, and the cooperative efforts of each agency's public information staff

  20. NRC/FEMA operational response procedures for response to a commercial nuclear reactor accident. Revision 1

    International Nuclear Information System (INIS)

    1985-02-01

    Procedures have been developed by the US Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) which provide the response teams of both agencies with the steps to be taken in responding to an emergency at a commercial nuclear power plant. The emphasis of these procedures is mainly on the interface between NRC and FEMA at their respective Headquarters and Regional Offices and at the various sites at which such an emergency could occur. Detailed procedures are presented that cover for both agencies, notification schemes and manner of activation, organizations at Headquarters and the site, interface procedures, coordination of onsite and offsite operations, the role of the Senior FEMA Official, and the cooperative efforts of each agency's public information staff

  1. Funding for reactor decommissioning: the NRC perspective

    International Nuclear Information System (INIS)

    Wood, R.S.

    1981-01-01

    The cost of decommissioning a nuclear power plant is discussed. Four funding approaches that have received the most attention from the NRC are: prepayment into a trust fund of estimated decommissioning funds at the start of facility operation; annual contributions into a trust fund outside the control of the utility over the estimated life of a facility; internal reserve or sinking fund amortizations over the estimated life of a facility; and insurance or other surety mechanisms used separately or in conjunction with any of the first three mechanisms

  2. Elections to Staff Council

    CERN Multimedia

    Staff Association

    2013-01-01

    Elections to fill all seats in the Staff Council are being organized this month. The voting takes place from the 28 of October to the 11th of November, at noon. As you may have noted when reading Echo, many issues concerning our employment conditions are on the agenda of the coming months, and in particular the Five-yearly-Review 2015, subject of the questionnaire that you probably recently filled out. All this will keep the next Staff Council very busy indeed. So, make your voice heard and take part in the elections for a new Staff Council. By doing so, you will be encouraging the men and women who will be representing you over the next two years and they will doubtless appreciate your gratitude. Every member of the Staff Association will have received an email containing a link to the webpage which will allow voting. If you are a member of the Staff Association and you did not receive such an email, please contact the Staff Association secretariat (staff.association@cern.ch). Do not forget to v...

  3. NRC Response to an Act or Threat of Terrorism at an NRC-Licensed Facility

    International Nuclear Information System (INIS)

    Frank Congel

    2000-01-01

    The mandated response to a threat or act of terrorism at a U.S. Nuclear Regulatory Commission (NRC)-licensed facility was examined through a tabletop exercise in May 2000 and a limited field exercise in August 2000. This paper describes some of the new issues addressed and lessons learned from those exercises

  4. Effectiveness of team nursing compared with total patient care on staff wellbeing when organizing nursing work in acute care wards: a systematic review.

    Science.gov (United States)

    King, Allana; Long, Lesley; Lisy, Karolina

    2015-11-01

    The organization of the work of nurses, according to recognized models of care, can have a significant impact on the wellbeing and performance of nurses and nursing teams. This review focuses on two models of nursing care delivery, namely, team and total patient care, and their effect on nurses' wellbeing. To examine the effectiveness of team nursing compared to total patient care on staff wellbeing when organizing nursing work in acute care wards. Participants were nurses working on wards in acute care hospitals.The intervention was the use of a team nursing model when organizing nursing work. The comparator was the use of a total patient care model.This review considered quantitative study designs for inclusion in the review.The outcome of interest was staff wellbeing which was measured by staff outcomes in relation to job satisfaction, turnover, absenteeism, stress levels and burnout. The search strategy aimed to find both published and unpublished studies from 1995 to April 21, 2014. Quantitative papers selected for retrieval were assessed by two independent reviewers for methodological validity prior to inclusion in the review using standardized critical appraisal instruments from the Joanna Briggs Institute. Data was extracted from papers included in the review using the standardized data extraction tool from the Joanna Briggs Institute. The data extracted included specific details about the interventions, populations, study methods and outcomes of significance to the review question and its specific objectives. Due to the heterogeneity of the included quantitative studies, meta-analysis was not possible. Results have been presented in a narrative form. The database search returned 10,067 records. Forty-three full text titles were assessed, and of these 40 were excluded, resulting in three studies being included in the review. Two of the studies were quasi experimental designs and the other was considered an uncontrolled before and after experimental study

  5. Staff rules and regulations

    CERN Multimedia

    HR Department

    2007-01-01

    The 11th edition of the Staff Rules and Regulations, dated 1 January 2007, adopted by the Council and the Finance Committee in December 2006, is currently being distributed to departmental secretariats. The Staff Rules and Regulations, together with a summary of the main modifications made, will be available, as from next week, on the Human Resources Department's intranet site: http://cern.ch/hr-web/internal/admin_services/rules/default.asp The main changes made to the Staff Rules and Regulations stem from the five-yearly review of employment conditions of members of the personnel. The changes notably relate to: the categories of members of the personnel (e.g. removal of the local staff category); the careers structure and the merit recognition system; the non-residence, installation and re-installation allowances; the definition of family, family allowances and family-related leave; recognition of partnerships; education fees. The administrative circulars, some of which are being revised following the ...

  6. Status of ECCS Acceptance Criteria Revision in U. S. NRC and Perspective

    International Nuclear Information System (INIS)

    Lee, Joosuk; Woo, Swengwoong

    2013-01-01

    Subsequently the NRC had conducted a fuel cladding research program to investigate the behavior of high burnup fuel cladding under LOCA conditions. This research program conducted at Argonne National Laboratory (ANL), as well as conducted as jointly-funded programs at the Kurchatov Institute and the Halden Reactor. From these programs, several important technical findings, listed in following section, for rule revision were obtained. On March 14, 2000, the Nuclear Energy Institute (NEI) submitted a petition for rulemaking (PRM) requesting that the NRC amend its regulations in 50.44 and 50.46 (PRM 50-71). The NEI petition stated that these regulations apply to only two specific zirconium-alloy fuel cladding materials (zircaloy and ZIRLO TM ). The NRC resolved PRM-50-71 by deciding that it should be considered in the following rulemaking process. Meanwhile, on March 15, 2007, Mark Leyse submitted a PRM to the NRC (PRM 50-84). The petitioner requests that the NRC conduct rulemaking in the following areas: Establish regulations that require licensees to operate light-water power reactors under conditions that are effective in limiting the thickness of crud and/or oxide layers. Amend Appendix K to Part 50 to explicitly require that steady-state temperature distribution and stored energy in the reactor fuel at the onset of a postulated LOCA be calculated by factoring in the role of the thermal resistance of crud and oxide layers. Amend 50.46 to specify a maximum allowable percentage of hydrogen content in the cladding. The NRC resolved PRM-50-84 by deciding that the petitioner's issues should be considered in the rulemaking process. On August 13, 2009, the NRC published an Advance Notice of Proposed Rulemaking (ANPR) to obtain stakeholder views on issues associated with amending 50.46. On March 1, 2012, and subsequently modified by the staff's June 1, 2012, SECY-12-0034 was submitted to the Commission to obtain approval to publish for public comment, and it was approved

  7. Status of ECCS Acceptance Criteria Revision in U. S. NRC and Perspective

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Joosuk; Woo, Swengwoong [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-05-15

    Subsequently the NRC had conducted a fuel cladding research program to investigate the behavior of high burnup fuel cladding under LOCA conditions. This research program conducted at Argonne National Laboratory (ANL), as well as conducted as jointly-funded programs at the Kurchatov Institute and the Halden Reactor. From these programs, several important technical findings, listed in following section, for rule revision were obtained. On March 14, 2000, the Nuclear Energy Institute (NEI) submitted a petition for rulemaking (PRM) requesting that the NRC amend its regulations in 50.44 and 50.46 (PRM 50-71). The NEI petition stated that these regulations apply to only two specific zirconium-alloy fuel cladding materials (zircaloy and ZIRLO{sup TM}). The NRC resolved PRM-50-71 by deciding that it should be considered in the following rulemaking process. Meanwhile, on March 15, 2007, Mark Leyse submitted a PRM to the NRC (PRM 50-84). The petitioner requests that the NRC conduct rulemaking in the following areas: Establish regulations that require licensees to operate light-water power reactors under conditions that are effective in limiting the thickness of crud and/or oxide layers. Amend Appendix K to Part 50 to explicitly require that steady-state temperature distribution and stored energy in the reactor fuel at the onset of a postulated LOCA be calculated by factoring in the role of the thermal resistance of crud and oxide layers. Amend 50.46 to specify a maximum allowable percentage of hydrogen content in the cladding. The NRC resolved PRM-50-84 by deciding that the petitioner's issues should be considered in the rulemaking process. On August 13, 2009, the NRC published an Advance Notice of Proposed Rulemaking (ANPR) to obtain stakeholder views on issues associated with amending 50.46. On March 1, 2012, and subsequently modified by the staff's June 1, 2012, SECY-12-0034 was submitted to the Commission to obtain approval to publish for public comment, and it

  8. Do interventions with staff in long-term residential facilities improve quality of care or quality for life people with dementia? A systematic review of the evidence.

    Science.gov (United States)

    Bird, Mike; Anderson, Katrina; MacPherson, Sarah; Blair, Annaliese

    2016-12-01

    Common sense suggests and research indicates relationships between staff factors in residential dementia care and quality of life (QOL) for residents, with poor care increasing suffering. However, we do not have a coherent picture of which staff interventions have an impact on quality of care (QOC) or resident QOL. A comprehensive search of 20 years' peer-reviewed literature using Medline, PsycINFO, Embase, PubMed, CINAHL, and the Cochrane, Campbell Collaboration identified 4,760 studies meriting full text review. Forty-six met the inclusion criteria, namely interventions in long-term facilities helping staff develop their capacity to provide better care and/or QOL for residents with dementia. Thirty-five other papers comprised an associated predictor review. Conclusions from these limited data are further compromised because nine studies failed to measure effects on residents and only half assessed effects after the project team withdrew. Of these, excellent studies produced change over the medium (3-4 months) or longer term, including reduction in challenging behavior and restraint use but this applied only to a minority. A number of studies failed to measure effects on QOC, limiting conclusions about mechanisms underlying change. In general, level of intervention required depended on the target. For outcomes like restraint use, structured education sessions with some support appear adequate. Programs to reduce pain require more support. For complicated issues like challenging behavior and increasing co-operation in showering, detailed, supportive, on-site interventions are required. Improvements in restraint and staff/resident interactions were the most promising findings. (Review registration number: PROSPERO 2014:CRD42014015224).

  9. 78 FR 48504 - Proposed Revisions to Maintenance Rule Standard Review Plan

    Science.gov (United States)

    2013-08-08

    ... (ML13015A125), Current Revision 1 (ML072920088), Redline (ML13015A426). NRC's PDR: You may examine and purchase.... The NRC staff has no intention to impose the SRP positions on existing licensees either now or in the...

  10. Licensing considerations in converting NRC-licensed non-power reactors from high-enriched to low-enriched uranium fuels

    International Nuclear Information System (INIS)

    Carter, R.E.

    1985-01-01

    During the mid-1970s, there was increasing concern with the possibility that highly enriched uranium (HEU), widely used in non-power reactors around the world, might be diverted from its intended peaceful uses. In 1982 the U.S. Nuclear Regulatory Commission (NRC) issued a policy statement that was intended to conform with the perceived international thinking, and that addressed the two relevant areas in which NRC has statutory responsibility, namely, export of special nuclear materials for non-USA non-power reactors, and the licensing of USA-based non-power reactors not owned by the Federal government. To further address the second area, NRC issued a proposed rule for public comment that would require all NRC-licensed non-power reactors using HEU to convert to low enriched uranium (LEU) fuel, unless they could demonstrate a unique purpose. Currently the NRC staff is revising the proposed rule. An underlying principle guiding the staff is that as long as a change in enrichment does not lead to safety-related reactor modifications, and does not involve an unreviewed safety question, the licensee could convert the core without prior NRC approval. At the time of writing this paper, a regulatory method of achieving this principle has not been finalized. (author)

  11. Licensing considerations in converting NRC-licensed non-power reactors from high-enriched to low-enriched uranium fuels

    Energy Technology Data Exchange (ETDEWEB)

    Carter, R E

    1985-07-01

    During the mid-1970s, there was increasing concern with the possibility that highly enriched uranium (HEU), widely used in non-power reactors around the world, might be diverted from its intended peaceful uses. In 1982 the U.S. Nuclear Regulatory Commission (NRC) issued a policy statement that was intended to conform with the perceived international thinking, and that addressed the two relevant areas in which NRC has statutory responsibility, namely, export of special nuclear materials for non-USA non-power reactors, and the licensing of USA-based non-power reactors not owned by the Federal government. To further address the second area, NRC issued a proposed rule for public comment that would require all NRC-licensed non-power reactors using HEU to convert to low enriched uranium (LEU) fuel, unless they could demonstrate a unique purpose. Currently the NRC staff is revising the proposed rule. An underlying principle guiding the staff is that as long as a change in enrichment does not lead to safety-related reactor modifications, and does not involve an unreviewed safety question, the licensee could convert the core without prior NRC approval. At the time of writing this paper, a regulatory method of achieving this principle has not been finalized. (author)

  12. The 1997 NRC IST workshops and the status of questions and issues directed to the ASME O and M committee

    International Nuclear Information System (INIS)

    DiBiasio, A.M.

    1998-05-01

    This paper describes the results of the four NRC Inservice Testing (IST) Workshops which were held in early 1997 pertaining to NRC Inspection Procedure P 73756, Inservice Testing of Pumps and Valves. It also presents the status of the ASME code committees' resolution of certain questions forwarded to the ASME by the NRC. These questions relate to code interpretations, inconsistencies in the code, and industry concerns that are most appropriately resolved through the ASME consensus process. The ASME committees reviewed the questions at their December 1997 and March 1998 code meetings. Of particular interest are those questions for which the ASME code committees did not agree with the NRC response. These questions, as well as those which the committees provided some additional insight or input, are presented in this paper

  13. 75 FR 44992 - Review of Management Directive 8.11

    Science.gov (United States)

    2010-07-30

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0242] Review of Management Directive 8.11 AGENCY: Nuclear... (NRC) is requesting public comment on Management Directive (MD) 8.11, ``Review Process for 10 CFR 2.206... members of the public and the NRC, the NRC is soliciting comments from the public, on what, if any...

  14. Berkeley Lab Pilot on External Regulation of DOE National Laboratories by the U.S. NRC

    International Nuclear Information System (INIS)

    Zeman, Gary H.

    1999-01-01

    The US Department of Energy and the US Nuclear Regulatory Commission entered into an agreement in November 1997 to pursue external regulation of radiation safety at DOE national laboratories through a Pilot Program of simulated regulation at 6-10 sites over a 2 year period. The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab), the oldest of the DOE national laboratories, volunteered and was selected as the first Pilot site. Based on the similarities and linkages between Berkeley Lab and nearby university research laboratories, Berkeley Lab seemed a good candidate for external regulation and a good first step in familiarizing NRC with the technical and institutional issues involved in regulating laboratories in the DOE complex. NRC and DOE team members visited Berkeley Lab on four occasions between October 1997 and January 1998 to carry out the Pilot. The first step was to develop a detailed Work Plan, then to carry out both a technical review of the radiation safety program and an examination of policy and regulatory issues. The Pilot included a public meeting held in Oakland, CA in December 1997. The Pilot concluded with NRC's assessment that Berkeley Lab has a radiation protection program adequate to protect workers, the public and the environment, and that it is ready to be licensed by the NRC with minor programmatic exceptions. A draft final report of the Pilot was prepared and circulated for comment as a NUREG document (dated May 7, 1998). The report's recommendations include extending NRC regulatory authority to cover all ionizing radiation sources (including accelerators, x-ray units, NARM) at Berkeley Lab. Questions remaining to be resolved include: who should be the licensee (DOE, the Lab, or both)?; dealing with legacy issues and NRC D and D requirements; minimizing dual oversight; quantifying value added in terms of cost savings, enhanced safety, and improved public perception; extrapolating results to other national laboratories; and

  15. Nuclear Regulatory Commission Staff practice and procedure digest. Commission, Appeal Board and Licensing Board Decision, July 1972 - June 1995

    International Nuclear Information System (INIS)

    1996-04-01

    This is the seventh edition of the Nuclear Regulatory Commission (NRC) Staff Practice and Procedure Digest. It contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 1995 interpreting the NRC rules of practice in 10 CFR part 2

  16. Design basis for the NRC Operations Center

    Energy Technology Data Exchange (ETDEWEB)

    Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

    1983-05-01

    This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project.

  17. Design basis for the NRC Operations Center

    International Nuclear Information System (INIS)

    Lindell, M.K.; Wise, J.A.; Griffin, B.N.; Desrosiers, A.E.; Meitzler, W.D.

    1983-05-01

    This report documents the development of a design for a new NRC Operations Center (NRCOC). The project was conducted in two phases: organizational analysis and facility design. In order to control the amount of traffic, congestion and noise within the facility, it is recommended that information flow in the new NRCOC be accomplished by means of an electronic Status Information Management System. Functional requirements and a conceptual design for this system are described. An idealized architectural design and a detailed design program are presented that provide the appropriate amount of space for operations, equipment and circulation within team areas. The overall layout provides controlled access to the facility and, through the use of a zoning concept, provides each team within the NRCOC the appropriate balance of ready access and privacy determined from the organizational analyses conducted during the initial phase of the project

  18. U.S. N.R.C. special safeguards study on nuclear material control and accounting

    International Nuclear Information System (INIS)

    Smith, G.D.

    1976-01-01

    In Feb. 1975, NRC directed that an effort be made to determine a safeguards program for Pu recycle. This paper summarizes results of individual contractor evaluations of upgrading material control and accounting concepts as applied to strategically important special nuclear material and describes staff interpretations of these results as applied to future high-throughput fuel-cycle facilities. Real-time material control, design for physical inventory, Pu isotopics control and calorimetry, and material control and accounting for highly enriched uranium fuel materials were the concepts studied. 1 table, 15 references

  19. U.S. NRC's generic issues program

    International Nuclear Information System (INIS)

    Kauffman, J.V.; Foster, J.W.

    2008-01-01

    The United States Nuclear Regulatory Commission (NRC) has a Generic Issues Program (GIP) to address Generic Issues (GI). A GI is defined as 'a regulatory matter involving the design, construction, operation, or decommissioning of several, or a class of, NRC licensees or certificate holders that is not sufficiently addressed by existing rules, guidance, or programs'. This rather legalistic definition has several practical corollaries: First, a GI must involve safety. Second, the issue must involve at least two plants, or it would be a plant-specific issue rather than a GI. Third, the potential safety question must not be covered by existing regulations and guidance (compliance). Thus, the effect of a GI is to potentially change the body of regulations and associated guidance (e.g., regulatory guides). The GIP was started in 1976, thus it is a relatively mature program. Approximately 850 issues have been processed by the program to date. More importantly, even after 30 years, new GIs continue to be proposed. The entire set of Generic Issues (GIs) is updated annually in NUREG-0933, 'A Prioritization of Generic Safety Issues'. GIs normally involve complex questions of safety and regulation. Efficient and effective means of addressing these issues are very important for regulatory effectiveness. If an issue proves to pose a genuine, significant safety question, then swift, effective, enforceable, and cost-effective action needs to be taken. Conversely, if an issue is of little safety significance, the issue should be dismissed in an expeditious manner, avoiding unnecessary expenditure of resources and regulatory burden or uncertainty. This paper provides a summary of the 5-stage program, from identification through the regulatory assessment stage. The paper also includes a discussion of the program's seven criteria, sources of proposed GIs, recent improvements, publicly available information, historical performance, and status of current GIs. (authors)

  20. NRC Licensing Status Summary Report for NGNP

    Energy Technology Data Exchange (ETDEWEB)

    Moe, Wayne Leland [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kinsey, James Carl [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-11-01

    The Next Generation Nuclear Plant (NGNP) Project, initiated at Idaho National Laboratory (INL) by the U.S. Department of Energy (DOE) pursuant to provisions of the Energy Policy Act of 2005, is based on research and development activities supported by the Department of Energy Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of high temperature gas-cooled reactor (HTGR) technology. The HTGR is a helium-cooled and graphite moderated reactor that can operate at temperatures much higher than those of conventional light water reactor (LWR) technologies. The NGNP will be licensed for construction and operation by the Nuclear Regulatory Commission (NRC). However, not all elements of current regulations (and their related implementation guidance) can be applied to HTGR technology at this time. Certain policies established during past LWR licensing actions must be realigned to properly accommodate advanced HTGR technology. A strategy for licensing HTGR technology was developed and executed through the cooperative effort of DOE and the NRC through the NGNP Project. The purpose of this report is to provide a snapshot of the current status of the still evolving pre-license application regulatory framework relative to commercial HTGR technology deployment in the U.S. The following discussion focuses on (1) describing what has been accomplished by the NGNP Project up to the time of this report, and (2) providing observations and recommendations concerning actions that remain to be accomplished to enable the safe and timely licensing of a commercial HTGR facility in the U.S.

  1. Update of NRC uranium mill licensing activities

    International Nuclear Information System (INIS)

    Martin, J.B.

    1978-01-01

    Increased vigilance must be given to controlling emissions from active milling operations, particularly windblown tailings, to assure that the soon-to-be-effective EPA Fuel Cycle Standard is met. Comprehensive environmental monitoring programs will have to be developed to confirm that, in fact, the limit is met. Just as was the case last year, tailings management and disposal is still the major item of concern relating to uranium milling operations. As stated earlier, the NRC feels that below-grade disposal is the preferred method of tailings disposal in that it provides the greatest assurances of long-term isolation. In any event, tailings must be disposed of in such a way that no active care is required of disposal sites, to avoid committing future generations to a significant, lingering obligation to care for wastes generated to produce benefits which they will only indirectly receive, if at all. While the primary means of providing long-term isolation of tailings must be by physical barriers, as a prudent, supplementary measure of control, we are concluding in the GEIS on Uranium Milling that ownership of disposal sites by a Government agency is desirable. We expect a low level of continued surveillance at disposal sites with small expense involved. We are concluding that requiring operators to contribute on the order of $100,000 per disposal site to cover ongoing expenses would be the most apropriate means of conforming to the principle that the waste generator should pay full costs of waste disposal. We feel such an arrangement would be fair, simple, and efficient, favoring it over complicated schemes involving such things as taxes on product or tailings generated and continued management of ear-marked funds. Legislation is now pending in the Congress which would give NRC direct regulatory control over mill tailings and put into place the authorities needed to implement the long-term control and funding arrangements discussed above

  2. NRC licensing of uranium enrichment plants

    International Nuclear Information System (INIS)

    Moran, B.W.

    1991-01-01

    The US Nuclear Regulatory Commission (NRC) is preparing a rule making that establishes the licensing requirements for low-enriched uranium enrichment plants. Although implementation of this rule making is timed to correspond with receipt of a license application for the Louisiana Energy Services centrifuge enrichment plant, the rule making is applicable to all uranium enrichment technologies. If ownership of the US gaseous diffusion plants and/or atomic vapor laser isotope separation is transferred to a private or government corporation, these plants also would be licensable under the new rule making. The Safeguards Studies Department was tasked by the NRC to provide technical assistance in support of the rule making and guidance preparation process. The initial and primary effort of this task involved the characterization of the potential safeguards concerns associated with a commercial enrichment plant, and the licensing issues associated with these concerns. The primary safeguards considerations were identified as detection of the loss of special nuclear material, detection of unauthorized production of material of low strategic significance, and detection of production of uranium enriched to >10% 235 U. The primary safeguards concerns identified were (1) large absolute limit of error associated with the material balance closing, (2) the inability to shutdown some technologies to perform a cleanout inventory of the process system, and (3) the flexibility of some technologies to produce higher enrichments. Unauthorized production scenarios were identified for some technologies that could prevent conventional material control and accounting programs from detecting the production and removal of 5 kg 235 U as highly enriched uranium. Safeguards techniques were identified to mitigate these concerns

  3. Assessing User Perceptions of Staff Training Requirements in the Substance Use Workforce: A Review of the Literature

    Science.gov (United States)

    Wylie, Leon W. J.

    2010-01-01

    Although the potential range of the workforce that may positively interact with substance users is large, and takes in all who may have to deal with substance use issues in some way, the literature mainly focuses on user views of specialist substance use or health and social care staff. With client-centred care a key policy of modern service…

  4. Classroom-based and distance learning education and training courses in end-of-life care for health and social care staff: a systematic review.

    Science.gov (United States)

    Pulsford, David; Jackson, Georgina; O'Brien, Terri; Yates, Sue; Duxbury, Joy

    2013-03-01

    Staff from a range of health and social care professions report deficits in their knowledge and skills when providing end-of-life and palliative care, and education and training has been advocated at a range of levels. To review the literature related to classroom-based and distance learning education and training initiatives for health and social care staff in end-of-life and palliative care, in terms of their target audience, extent, modes of delivery, content and teaching and learning strategies, and to identify the most effective educational strategies for enhancing care. A systematic review of the literature evaluating classroom-based and distance learning education and training courses for health and social care staff in end-of-life and palliative care. Online databases CINAHL, MEDLINE, EMBASE and PSYCHINFO between January 2000 and July 2010. Studies were selected that discussed specific education and training initiatives and included pre-and post-test evaluation of participants' learning. 30 studies met eligibility criteria. The majority reported successful outcomes, though there were some exceptions. Level of prior experience and availability of practice reinforcement influenced learning. Participative and interactive learning strategies were predominantly used along with discussion of case scenarios. Multi-professional learning was infrequently reported and service user and carer input to curriculum development and delivery was reported in only one study. Classroom-based education and training is useful for enhancing professionals' skills and perceived preparedness for delivering end-of-life care but should be reinforced by actual practice experience.

  5. A systematic review of the relationship between staff perceptions of organizational readiness to change and the process of innovation adoption in substance misuse treatment programs.

    Science.gov (United States)

    Kelly, Peter; Hegarty, Josephine; Barry, Joe; Dyer, Kyle R; Horgan, Aine

    2017-09-01

    Translating innovation, such as contemporary research evidence, into policy and practice is a challenge, not just in substance misuse treatment programs, but across all spheres of healthcare. Organizational readiness to change (ORC) has been described as a fundamental concept, and an important determinant of the process of innovation adoption. The aim of this review was to describe the relationship between staff perceptions of ORC and the process of innovation adoption: exposure, adoption, implementation and integration into practice, in substance misuse treatment programs. This systematic review was conducted in accordance with PRISMA guidelines and fourteen papers were identified as being eligible for inclusion. This review was designed to include all constructs of ORC, but only one tool was used in all of the included papers. Despite this, the heterogeneity of studies in this review made a direct comparison of ORC related variables challenging. None of the included papers clearly related to one stage of the process of innovation adoption, and all of the included papers related to the early stages of the process. Only one paper attempted to measure the sustained integration of an innovation into practice. Overall, the papers were assessed as being low in terms of evidential hierarchy and the quality of the papers was assessed as being on average fair. ORC measurements provide us with a measure of organizational functioning which can be important in terms of predicting how successfully new innovations are adopted. Motivation for change was high in programs where staff identified more program deficits and these staff could also identify more specific needs, but were less likely to have exposure to new innovations. Better program resources and specific staff attributes, increase the likely hood of successful innovation adoption. A good organizational climate is potentially the strongest predictor for the adoption of new practices. It may be beneficial to measure ORC

  6. NRC Regulatory Agenda: Quarterly report, July-September 1987

    International Nuclear Information System (INIS)

    1987-11-01

    The NRC Regulatory agenda is a compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received by the commission and are pending disposition by the commission. The regulatory agenda is updated and issued each quarter

  7. NRC Regulatory Agenda quarterly report, July--September 1993

    International Nuclear Information System (INIS)

    1993-10-01

    The NRC Regulator Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  8. NRC regualtory agenda. Semiannual report, July 1997--December 1997

    International Nuclear Information System (INIS)

    1998-02-01

    The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition

  9. NRC regulatory agenda: Quarterly report, April--June 1988

    International Nuclear Information System (INIS)

    1988-08-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has proposed or is considering action and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued each quarter

  10. NRC regulatory agenda. Seminnual progress report, January 1996--June 1996

    International Nuclear Information System (INIS)

    1996-08-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rule making which have been received by the Commission and are pending disposition by the Commission. The regulatory Agenda is updated and issued semiannually

  11. The impact of a Critical Care Information System (CCIS) on time spent charting and in direct patient care by staff in the ICU: a review of the literature.

    Science.gov (United States)

    Mador, Rebecca L; Shaw, Nicola T

    2009-07-01

    The introduction of a Critical Care Information System (CCIS) into an intensive care unit (ICU) is purported to reduce the time health care providers (HCP) spend on documentation and increase the time available for direct patient care. However, there is a paucity of rigorous empirical research that has investigated these assertions. Moreover, those studies that have sought to elucidate the relationship between the introduction of a CCIS and the time spent by staff on in/direct patient care activities have published contradictory findings. The objective of this literature review is to establish the impact of a CCIS on time spent documenting and in direct patient care by staff in the ICU. Five electronic databases were searched including PubMed Central, EMBASE, CINAHL, IEEE Xplore, and the Cochrane Database of Systematic Reviews. Reference lists of all published papers were hand searched, and citations reviewed to identify extra papers. We included studies that were empirical articles, published in English, and provided original data on the impact of a CCIS on time spent documenting and in direct patient care by staff in the ICU. In total, 12 articles met the inclusion criteria. Workflow analysis (66%) and time-and-motion analysis (25%) were the most common forms of data collection. Three (25%) studies found an increase in time spent charting, five (42%) found no difference, and four (33%) studies reported a decrease. Results on the impact of a CCIS on direct patient care were similarly inconclusive. Due to the discrepant findings and several key methodological issues, the impact of a CCIS on time spent charting and in direct patient care remains unclear. This review highlights the need for an increase in rigorous empirical research in this area and provides recommendations for the design and implementation of future studies.

  12. Development of the NRC's Human Performance Investigation Process (HPIP)

    International Nuclear Information System (INIS)

    Paradies, M.; Unger, L.; Haas, P.; Terranova, M.

    1993-10-01

    The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume III, is a detailed documentation of the development effort and the pilot training program

  13. Development of the NRC's Human Performance Investigation Process (HPIP)

    International Nuclear Information System (INIS)

    Paradies, M.; Unger, L.; Haas, P.; Terranova, M.

    1993-10-01

    The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume I is a concise description of the need for the human performance investigation process, the process' components, the methods used to develop the process, the methods proposed to test the process, and conclusions on the process' usefulness

  14. Safeguards at NRC licensed facilities: Are we doing enough

    International Nuclear Information System (INIS)

    Asselstine, J.K.

    1986-01-01

    Safeguards at the Nuclear Regulatory Commission (NRC) facilities are discussed in this paper. The NRC is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

  15. Development of the NRC's Human Performance Investigation Process (HPIP)

    International Nuclear Information System (INIS)

    Paradies, M.; Unger, L.; Haas, P.; Terranova, M.

    1993-10-01

    The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause event at nuclear power plants. This document, Volume II, is a field manual for use by investigators when performing event investigations. Volume II includes the HPIP Procedure, the HPIP Modules, and Appendices that provide extensive documentation of each investigation technique

  16. Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.; Mitchell, Mark R.; Gore, Bryan F.; Faris, Drury K.

    2009-10-09

    The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected to come from increasingly diverse educational and experiential backgrounds.

  17. 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.

  18. NRC Seismic Design Margins Program Plan

    International Nuclear Information System (INIS)

    Cummings, G.E.; Johnson, J.J.; Budnitz, R.J.

    1985-08-01

    Recent studies estimate that seismically induced core melt comes mainly from earthquakes in the peak ground acceleration range from 2 to 4 times the safe shutdown earthquake (SSE) acceleration used in plant design. However, from the licensing perspective of the US Nuclear Regulatory Commission, there is a continuing need for consideration of the inherent quantitative seismic margins because of, among other things, the changing perceptions of the seismic hazard. This paper discusses a Seismic Design Margins Program Plan, developed under the auspices of the US NRC, that provides the technical basis for assessing the significance of design margins in terms of overall plant safety. The Plan will also identify potential weaknesses that might have to be addressed, and will recommend technical methods for assessing margins at existing plants. For the purposes of this program, a general definition of seismic design margin is expressed in terms of how much larger that the design basis earthquake an earthquake must be to compromise plant safety. In this context, margin needs to be determined at the plant, system/function, structure, and component levels. 14 refs., 1 fig

  19. NRC ARDC Guidance Support Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Holbrook, Mark R. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-07-01

    This report provides a summary that reflects the progress and status of proposed regulatory design criteria for advanced non-light water reactor (LWR) designs in accordance with the Level 3 milestone M3AT-17IN2001013 in work package AT-17IN200101. These criteria have been designated as advanced reactor design criteria (ARDC) and they provide guidance to future applicants for addressing the general design criteria (GDC) that are currently applied specifically to LWR designs. This report provides a summary of Phase 2 activities related to the various tasks associated with ARDC development and the subsequent development of ARDC regulatory guidance for sodium fast reactor (SFR) and modular high-temperature gas-cooled reactor (HTGR) designs. Status Report Organization: Section 2 discusses the origin of the GDC and their application to LWRs. Section 3 addresses the objective of this initiative and how it benefits the advanced non-LWR reactor vendors. Section 4 discusses the scope and structure of the initiative. Section 5 provides background on the U.S. Department of Energy (DOE) ARDC team’s original development of the proposed ARDC that were submitted to the NRC for consideration. Section 6 provides a summary of recent ARDC Phase 2 activities. Appendices A through E document the DOE ARDC team’s public comments on various sections of the NRC’s draft regulatory guide DG–1330, “Guidance for Developing Principal Design Criteria for Non-Light Water Reactors.”

  20. NRC ARDC Guidance Support Status Report

    International Nuclear Information System (INIS)

    Holbrook, Mark R.

    2017-01-01

    This report provides a summary that reflects the progress and status of proposed regulatory design criteria for advanced non-light water reactor (LWR) designs in accordance with the Level 3 milestone M3AT-17IN2001013 in work package AT-17IN200101. These criteria have been designated as advanced reactor design criteria (ARDC) and they provide guidance to future applicants for addressing the general design criteria (GDC) that are currently applied specifically to LWR designs. This report provides a summary of Phase 2 activities related to the various tasks associated with ARDC development and the subsequent development of ARDC regulatory guidance for sodium fast reactor (SFR) and modular high-temperature gas-cooled reactor (HTGR) designs. Status Report Organization: Section 2 discusses the origin of the GDC and their application to LWRs. Section 3 addresses the objective of this initiative and how it benefits the advanced non-LWR reactor vendors. Section 4 discusses the scope and structure of the initiative. Section 5 provides background on the U.S. Department of Energy (DOE) ARDC team’s original development of the proposed ARDC that were submitted to the NRC for consideration. Section 6 provides a summary of recent ARDC Phase 2 activities. Appendices A through E document the DOE ARDC team’s public comments on various sections of the NRC’s draft regulatory guide DG–1330, “Guidance for Developing Principal Design Criteria for Non-Light Water Reactors.”

  1. Applications of probabilistic techniques at NRC

    International Nuclear Information System (INIS)

    Thadani, A.; Rowsome, F.; Speis, T.

    1984-01-01

    The NRC is currently making extensive use of probabilistic safety assessment in the reactor regulation. Most of these applications have been introduced in the regulatory activities in the past few years. Plant Probabilistic Safety Studies are being utilized as a design tool for applications for standard designs and for assessment of plants located in regions of particularly high population density. There is considerable motivation for licenses to perform plant-specific probabilistic studies for many, if not all, of the existing operating nuclear power plants as a tool for prioritizing the implementation of the many outstanding licensing actions of these plants as well as recommending the elimination of a number of these issues which are judged to be insignificant in terms of their contribution to safety and risk. Risk assessment perspectives are being used in the priorization of generic safety issues, development of technical resolution of unresolved safety issues, assessing safety significance of proposed new regulatory requirements, assessment of safety significance of some of the occurrences at operating facilities and in environmental impact analyses of license applicants as required by the National Environmental Policy Act. (orig.)

  2. NRC Confirmatory Testing Program for SBWR

    International Nuclear Information System (INIS)

    Han, J.T.; Bessette, D.E.; Shotkin, L.M.

    1994-01-01

    The objective of the NRC Confirmatory Testing Program for SBWR is to provide integral data for code assessment, which reasonably reproduce the important phenomena and processes expected in the SBWR under various loss-of-coolant accident (LOCA) and transient conditions. To achieve this objective, the Program consists of four coupled elements: (1) to design and construct an integral, carefully-scaled SBWR test facility at Purdue Univ., (2) to provide pre-construction RELAP5/CONTAIN predictions of the facility design, (3) to provide confirmatory data for code assessment, and (4) to assess the RELAP5/CONTAIN code with data. A description of the open-quotes preliminary designclose quotes of the Purdue test facility and test matrix is presented. The facility is scheduled to be built by December 1994. Approximately 50 tests will be performed from April 1995 through April 1996 and documented by interim data reports. A final and complete data report is scheduled to be published by July 31, 1996

  3. Strategic Planning and NRC Decadal Survey Experience

    Science.gov (United States)

    Lautenbacher, C. C., Jr.

    2015-12-01

    Strategic planning exercises are routinely undertaken by a wide variety of organizations that span the private, public and academic sectors and with a wide variety of corporate goals. It is difficult to single out best procedures as the purposes of strategic planning are as varied as the organizations. As a former head of a governmental agency that requested such a NRC study, namely the first "Earth Sciences and Applications from Space" study, I will examine the process, provide my definitions and assessments of the good and the not-so-good, and compare to my experiences with other similar strategic planning exercises during my Navy, NOAA, and private sector careers. I find that there is always room for improvement, but there is no one process or procedure that can guarantee success. Overarching initial considerations that can position the effort for overall "success" will be defined and applied to the recent NSC Study: "Sea Change: 2015-2025 Decadal Survey of Ocean Science", for which I was neither an initiator nor a participant, but a very interested observer.

  4. The effect of aggression management training programmes for nursing staff and students working in an acute hospital setting. A narrative review of current literature.

    Science.gov (United States)

    Heckemann, B; Zeller, A; Hahn, S; Dassen, T; Schols, J M G A; Halfens, R J G

    2015-01-01

    Patient aggression is a longstanding problem in general hospital nursing. Staff training is recommended to tackle workplace aggression originating from patients or visitors, yet evidence on training effects is scarce. To review and collate current research evidence on the effect of aggression management training for nurses and nursing students working in general hospitals, and to derive recommendations for further research. Systematic, narrative review. Embase, MEDLINE, the Cochrane library, CINAHL, PsycINFO, pubmed, psycArticles, Psychology and Behavioural Sciences Collection were searched for articles evaluating training programs for staff and students in acute hospital adult nursing in a 'before/after' design. Studies published between January 2000 and September 2011 in English, French or German were eligible of inclusion. The methodological quality of included studies was assessed with the 'Quality Assessment Tool for Quantitative Studies'. Main outcomes i.e. attitudes, confidence, skills and knowledge were collated. Nine studies were included. Two had a weak, six a moderate, and one a strong study design. All studies reported increased confidence, improved attitude, skills, and knowledge about risk factors post training. There was no significant change in incidence of patient aggression. Our findings corroborate findings of reviews on training in mental health care, which point to a lack of high quality research. Training does not reduce the incidence of aggressive acts. Aggression needs to be tackled at an organizational level. Copyright © 2014 Elsevier Ltd. All rights reserved.

  5. ITAAC Development for APR1400 NRC Design Certification

    International Nuclear Information System (INIS)

    Kim, Jin Kwon; Kim, Myoung Ki

    2013-01-01

    ITAAC (Inspections, Tests, Analyses and Acceptance Criteria) is essential document for Design Certification, which is certified by NRC and ruled as the Appendix of the 10 CFR Part 52. Approximately 870 ITAAC items were selected for APR1400 Design Certification to be submitted to NRC. In this paper, the code and standard related to ITAAC and process of ITACC development are discussed to seek the way to complete the best ITAAC to get the Design Certification of APR1400 from NRC through the lessons learned from other competitive applicants. For saving the time and manpower to complete ITAAC of APR1400 NRC DC and reduction of the RAIs (Request Additional Information) from NRC, we took advantage of the lessons learned from the competitive designs like US-APWR and AP1000 based on KNGR ITAAC. Finally new and different ITAAC from ITAAC of KNGR was developed for APR1400 DC from NRC. RG 1.206 and SRPs were applied first in Korea to the APR1400 DCD preparation. For testability and acceptability check, ITAAC V and V table was completed by the system designers. APR1400 DCD will be submitted by the end of September this year and we hope that NRC issues lees RAIs on ITAAC document

  6. 76 FR 10072 - Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX, Adequacy of Station...

    Science.gov (United States)

    2011-02-23

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0013] Proposed Generic Communications; Draft NRC Regulatory Issue Summary 2011-XX, Adequacy of Station Electric Distribution System Voltages; Reopening of... (NRC's) Draft Regulatory Issue Summary 2011-XX, Adequacy of Station Electric Distribution System...

  7. Proceedings of the 21st DOE/NRC nuclear air cleaning conference

    International Nuclear Information System (INIS)

    First, M.W.

    1991-02-01

    The 21st meeting of the Department of Energy/Nuclear Regulatory Commission (DOE/NRC) Nuclear Air Cleaning Conference was held in San Diego, CA on August 13--16, 1990. The proceedings have been published as a two volume set. Volume 2 contains sessions covering adsorbents, nuclear codes and standards, modelling, filters, safety, containment venting and a review of nuclear air cleaning programs around the world. Also included is the list of attendees and an index of authors and speakers

  8. 76 FR 29746 - Science Advisory Board Staff Office Notification of a Public Meeting of the SAB Mercury Review Panel

    Science.gov (United States)

    2011-05-23

    ... Public Meeting of the SAB Mercury Review Panel AGENCY: Environmental Protection Agency (EPA). ACTION... Office announces a public meeting of the SAB Mercury Review Panel. DATES: The meeting will be held on... FACA and EPA policy, notice is hereby given that the SAB Mercury Review Panel will hold a public...

  9. The impact of educational interventions on attitudes of emergency department staff towards patients with substance-related presentations: a quantitative systematic review.

    Science.gov (United States)

    Gonzalez, Miriam; Clarke, Diana E; Pereira, Asha; Boyce-Gaudreau, Krystal; Waldman, Celeste; Demczuk, Lisa; Legare, Carol

    2017-08-01

    Visits to emergency departments for substance use/abuse are common worldwide. However, emergency department health care providers perceive substance-using patients as a challenging group to manage which can lead to negative attitudes. Providing education or experience-based exercises may impact positively on behaviors towards this patient population. Whether staff attitudes are similarly impacted by knowledge acquired through educational interventions remains unknown. To synthesize available evidence on the relationship between new knowledge gained through substance use educational interventions and emergency department health care providers' attitudes towards patients with substance-related presentations. Health care providers working in urban and rural emergency departments of healthcare facilities worldwide providing care to adult patients with substance-related presentations. Quantitative papers examining the impact of substance use educational interventions on health care providers' attitudes towards substance using patients. Experimental and non-experimental study designs. Emergency department staff attitudes towards patients presenting with substance use/abuse. A three-step search strategy was conducted in August 2015 with a search update in March 2017. Studies published since 1995 in English, French or Spanish were considered for inclusion. Two reviewers assessed studies for methodological quality using critical appraisal checklists from the Joanna Briggs Institute Meta-Analysis of Statistics Assessment and Review Instrument (JBI-MAStARI). Reviewers agreed on JBI-MAStARI methodological criteria a study must meet in order to be included in the review (e.g. appropriate use of statistical analysis). The data extraction instrument from JBI-MAStARI was used. As statistical pooling of the data was not possible, the findings are presented in narrative form. A total of 900 articles were identified as relevant for this review. Following abstract and full text

  10. Safeguards at NRC licensed facilities: Are we doing enough

    International Nuclear Information System (INIS)

    Asselstine, J.K.

    1986-01-01

    The Nuclear Regulatory Commission is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

  11. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1990-11-01

    This Revision 8 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 30, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 8 replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through June 30, 1990

  12. US nuclear safety review and experience

    International Nuclear Information System (INIS)

    Gilinsky, V.

    1977-01-01

    The nuclear safety review of commercial nuclear power reactors has changed over the years from the relatively simple review of Dresden 1 in 1955 to the highly complex and sophisticated regulatory process which characterizes today's reviews. Four factors have influenced this evolution: (1) maturing of the technology and industry; (2) development of the regulatory process and associated staff; (3) feedback of operating experience; and (4) public awareness and participation. The NRC's safety review responsibilities start before an application is tendered and end when the plant is decommissioned. The safety review for reactor licensing is a comprehensive, two-phase process designed to assure that all the established conservative acceptance criteria are satisfied. Operational safety is assured through a strong inspection and enforcement program which includes shutting down operating facilities when necessary to protect the health and safety of the public. The safety of operating reactors is further insured through close regulation of license changes and selective backfitting of new regulatory requirements. An effective NRC standards development program has been implemented and coordinates closely with the national standards program. A confirmatory safety research program has been developed. Both of these efforts are invaluable to the nuclear safety review because they provide the staff with key tools needed to carry out its regulatory responsibilities. Both have been given increased emphasis since the formation of the NRC in 1975. The safety review process will continue to evolve, but changes will be slower and more deliberate. It will be influenced by standardization, early site reviews and development of advanced reactor concepts. New legislation may make possible changes which will simplify and shorten the regulatory process. Certainly the experience provided by the increasing number and types of operating plants will have a very strong impact on future trends in the

  13. Vogtle Unit 1 readiness review: Assessment of Georgia Power Company readiness review pilot program

    International Nuclear Information System (INIS)

    Lewis, G.

    1987-09-01

    Georgia Power Company (GPC) performed a readiness review at Vogtle Unit 1 as a pilot program. The pilot program was a new and innovative approach for the systematic and disciplined review, with senior management involvement, of GPC's implementation of design, construction, and operational readiness processes. The program's principal objective was to increase the level of assurance that quality programs at Vogtle Unit 1 have been accomplished in accordance with regulatory requirements. This report assesses the effectiveness of the GPC's readiness review pilot program (RRPP) at Vogtle Unit 1. It includes (1) an overview of what was experienced during the program's implementation, (2) an assessment of how well program objectives were met, and (3) lessons learned on the future use of the readiness review concept. Overall, GPC and the NRC staff believe that the RRPP at Vogtle Unit 1 was a success and that the program provided significant added assurance that Vogtle Unit 1 licensing commitments and NRC regulations have been adequately implemented. Although altering the NRC licensing review process for the few plants still in the construction pipeline may not be appropriate, licensees may benefit significantly by performing readiness reviews on their own initiative as GPC did for Vogtle. (7 refs.)

  14. Hydration and nutrition at the end of life: a systematic review of emotional impact, perceptions, and decision-making among patients, family, and health care staff.

    Science.gov (United States)

    Del Río, M I; Shand, B; Bonati, P; Palma, A; Maldonado, A; Taboada, P; Nervi, F

    2012-09-01

    Decrease in oral intake, weight loss, and muscular weakness in the last phases of a terminal illness, particularly in the context of the cachexia-anorexia syndrome, can be an important source of anxiety for the triad of patient, family, and health staff. The present literature review examines the emotional impact of reduced oral intake as well as perceptions and attitudes toward assisted nutrition and hydration for terminally ill patients(1) at the end of life, among patients, family, and health care staff. We have identified the ways in which emotional and cultural factors influence decision-making about assisted nutrition and hydration. Lack of information and misperceptions of medically assisted nutrition and hydration can play a predominant role in the decision to begin or suspend nutritional or hydration support. Our literature review reveals that these social, emotional, and clinical misperception elements should be considered in the decision-making processes to help the triad develop functional forms of care at this final stage of life. Copyright © 2011 John Wiley & Sons, Ltd. Copyright © 2011 John Wiley & Sons, Ltd.

  15. 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

  16. NRC/DAE reactor safety research Data Bank

    International Nuclear Information System (INIS)

    Laats, E.T.

    1982-01-01

    In 1976, the United States Nuclear Regulatory Commission (NRC) established the NRC/Division of Accident Evaluation (DAE) Data Bank to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. This program has since grown from the conceptual stage to a useful, usable service for computer code development, code assessment, and experimentation groups in meeting the needs of the nuclear industry. Data from 20 facilities are now processed and permanently stored in the Data Bank, which utilizes the Control Data Corporation (CDC) CYBER 176 computer system located at the Idaho National Engineering Laboratory (INEL). New data and data sources are continually being added to the Data Bank. In addition to providing data storage and access software, the Data Bank program supplies data entry, documentation, and training and advisory services to users and the NRC. Management of the NRC/DAE Data Bank is provided by EG and G Idaho, Inc

  17. 48 CFR 2009.570 - NRC organizational conflicts of interest.

    Science.gov (United States)

    2010-10-01

    ... conflicts of interest. 2009.570 Section 2009.570 Federal Acquisition Regulations System NUCLEAR REGULATORY COMMISSION COMPETITION AND ACQUISITION PLANNING CONTRACTOR QUALIFICATIONS Organizational Conflicts of Interest 2009.570 NRC organizational conflicts of interest. ...

  18. Regulatory decision with EPA/NRC/DOE/State Session (Panel)

    Energy Technology Data Exchange (ETDEWEB)

    O`Donnell, E.

    1995-12-31

    This panel will cover the Nuclear Regulatory Commission`s (NRC) proposed radiation limits in the Branch Technical Position on Low-Level Radioactive Waste Performance Assessment and the Environmental Protection Agency`s (EPA) draft regulation in Part 193. Representatives from NRC and EPA will discuss the inconsistencies in these two regulations. DOE and state representatives will discuss their perspective on how these regulations will affect low-level radioactive waste performance assessments.

  19. Staged licensing: An essential element of the NRC's revised regulations

    International Nuclear Information System (INIS)

    Echols, F.S.

    1997-01-01

    Over the past several years, Congress has directed the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC), and the Environmental Protection Agency (EPA) to abandon their efforts to assess an array of potential candidate geologic repository sites for the permanent disposal of spent nuclear reactor fuel and high level radioactive waste, to develop generally applicable requirements for licensing geologic repositories, and to develop generally applicable radiation protection standards for geologic repositories, and instead to focus their efforts to determine whether a single site located at Yucca Mountain, Nevada can be developed as a geologic repository which providing reasonable assurance that public health and safety and the environment will be adequately protected. If the Yucca Mountain site is found to be suitable for development as a geologic repository, then at each stage of development DOE will have to provide the NRC with progressively more detailed information regarding repository design and long-term performance. NRC regulations reflect the fact that it will not be until the repository has been operated for a number of years that the NRC will be able to make a final determination as to long-term repository performance. Nevertheless, the NRC will be able to allow DOE to construct and operate a repository, provided that the NRC believes that the documented results of existing studies, together with the anticipated results from continuing and future studies, will enable the NRC to make a final determination that it has reasonable assurance that the repository system's long-term performance will not cause undue risk to the public. Thus, in its efforts to revise its current regulations to assure that the technical criteria are specifically applicable to the Yucca Mountain site, the NRC should also make sure that it preserves and clarifies the concept of staged repository development

  20. Safety Second: the NRC and America's nuclear power plants

    International Nuclear Information System (INIS)

    Adato, M.; MacKenzie, J.; Pollard, R.; Weiss, E.

    1987-01-01

    In 1975, Congress created the Nuclear Regulatory Commission (NRC). Its primary responsibility was to be the regulation of the nuclear power industry in order to maintain public health and safety. On March 28, 1979, in the worst commercial nuclear accident in US history, the plant at Three Mile Island began to leak radioactive material. How was Three Mile Island possible? Where was the NRC? This analysis by the Union of Concerned Scientists (UCS) of the NRC's first decade, points specifically to the factors that contributed to the accident at Three Mile Island. The NRC, created as a watchdog of the nuclear power industry, suffers from problems of mindset, says the UCS. The commission's problems are political, not technical; it repeatedly ranks special interests above the interest of public safety. This book critiques the NRC's performance in four specific areas. It charges that the agency has avoided tackling the most pervasive safety issues; has limited public participation in decision making and power plant licensing; has failed to enforce safety standards or conduct adequate regulation investigations; and, finally, has maintained a fraternal relationship with the industry it was created to regulate, serving as its advocate rather than it adversary. The final chapter offers recommendations for agency improvement that must be met if the NRC is to fulfill its responsibility for safety first

  1. Staff rules and regulations

    CERN Multimedia

    HR Department

    2007-01-01

    The 11th edition of the Staff Rules and Regulations, dated 1 January 2007, adopted by the Council and the Finance Committee in December 2006, is currently being distributed to departmental secretariats. The Staff Rules and Regulations, together with a summary of the main modifications made, will be available, as from next week, on the Human Resources Department's intranet site: http://cern.ch/hr-web/internal/admin_services/rules/default.asp The main changes made to the Staff Rules and Regulations stem from the five-yearly review of employment conditions of members of the personnel. The changes notably relate to: the categories of members of the personnel (e.g. removal of the local staff category); the careers structure and the merit recognition system; the non-residence, installation and re-installation allowances; the definition of family, family allowances and family-related leave; recognition of partnerships; education fees. The administrative circulars, some of which are being revised following the m...

  2. Reactor R ampersand D programs tough to eliminate; just ask NRC staff

    International Nuclear Information System (INIS)

    Lane, E.

    1993-01-01

    Even if the Clinton administration succeeds in eliminating funding for the advanced liquid metal reactor (ALMR) and modular high-temperature gas reactor (MHTGR) in the fiscal year 1994 budget, it will not wipe out the programs entirely as shown by a recent exchange of letters between the Nuclear Regulatory Commission and the Energy Department. This article examines the political and bureaucratic maneuverings involved in the funding of nuclear power projects

  3. STAFF NEEDED

    CERN Multimedia

    2001-01-01

    The English National Programme, part of the Lycée International de Ferney-Voltaire (France) needs the following staff for September 2001: A part-time teacher of primary English The post involves teaching the English curriculum to pupils who are within the French educational system: Classes take place on Tuesday afternoons at the Lycée, Team spirit necessary as teachers work as a team, Induction & training are offered. A part time teacher of senior secondary history-geography in English A part time teacher of secondary mathematics in English Teachers must be mother-tongue English speakers and have a relevant degree and/or teaching qualification. For the history-geography post, either history or geography degrees are acceptable. Please send your c.v. and a letter of application to Peter Woodburn, Head, English National Programme, Lycée International, 01216 Ferney-Voltaire, France. (Email: engnat@hotmail.com) Telephone 04 50 40 82 66 for further details of posts. Ple...

  4. 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

  5. NRC analysis of the environmental impacts and licensing policies for expanded spent fuel storage in the United States

    International Nuclear Information System (INIS)

    Smith, C.V. Jr.

    1978-01-01

    This paper reviews the findings of the U.S. environmental impact studies on spent fuel storage to the year 2000, addresses design criteria for independent spent fuel storage installations and expresses the position of the NRC for licensing expanded spent fuel storage capabilities until such time as final solutions are established

  6. NRC Analysis of the environmental impacts and licensing policies for expanded spent fuel storage in the United States

    International Nuclear Information System (INIS)

    Clifford, V.S.

    1978-01-01

    The findings of the U.S. environmental impact studies on spent fuel storage to the year 2000 are reviewed, the design criteria for independent spent fuel storage installations are addressed and the position of the NRC for licensing expanded spent fuel storage capabilities, until such time as final solutions are established, is expressed. (author)

  7. 75 FR 69069 - Science Advisory Board Staff Office Notification of a Public Meeting of the SAB Lead Review Panel

    Science.gov (United States)

    2010-11-10

    ... Time) and December 7, 2010 from 8:30 a.m. to 12:30 p.m. (Eastern Time). ADDRESSES: The face-to-face... SAB Lead Review Panel will hold a public face-to-face meeting to peer review two draft EPA documents... an oral presentation at a public face-to-face meeting will be limited to five minutes, with no more...

  8. NRC safety research in support of regulation

    International Nuclear Information System (INIS)

    1994-06-01

    This report, the ninth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1993. A special emphasis on accomplishments in nuclear power plant aging research reflects recognition that number of plants are entering the final portion of their original 40-year operating licenses and that, in addition to current aging effects, a focus on safety considerations for license renewal becomes timely. The primary purpose of performing regulatory research is to develop and provide the Commission and its staff with sound technical bases for regulatory decisions on the safe operation of licensed nuclear reactors and facilities, to find unknown or unexpected safety problems, and to develop data and related information for the purpose of revising the Commission's rules, regulatory guides, or other guidance

  9. Summary of Information Presented at an NRC-Sponsored Low-Power Shutdown Public Workshop, April 27, 1999, Rockville, Maryland

    International Nuclear Information System (INIS)

    Wheeler, Timothy A.; Whitehead, Donnie W.; Lois, Erasmia

    1999-01-01

    This report summarizes a public workshop that was held on April 27, 1999, in Rockville, Maryland. The workshop was conducted as part of the US Nuclear Regulatory Commission's (NRC) efforts to further develop its understanding of the risks associated with low power and shutdown operations at US nuclear power plants. A sufficient understanding of such risks is required to support decision-making for risk-informed regulation, in particular Regulatory Guide 1.174, and the development of a consensus standard. During the workshop the NRC staff discussed and requested feedback from the public (including representatives of the nuclear industry, state governments, consultants, private industry, and the media) on the risk associated with low-power and shutdown operations

  10. Summary of Information Presented at an NRC-Sponsored Low-Power Shutdown Public Workshop, April 27, 1999, Rockville, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Wheeler, Timothy A.; Whitehead, Donnie W.; Lois, Erasmia

    1999-07-01

    This report summarizes a public workshop that was held on April 27, 1999, in Rockville, Maryland. The workshop was conducted as part of the US Nuclear Regulatory Commission's (NRC) efforts to further develop its understanding of the risks associated with low power and shutdown operations at US nuclear power plants. A sufficient understanding of such risks is required to support decision-making for risk-informed regulation, in particular Regulatory Guide 1.174, and the development of a consensus standard. During the workshop the NRC staff discussed and requested feedback from the public (including representatives of the nuclear industry, state governments, consultants, private industry, and the media) on the risk associated with low-power and shutdown operations.

  11. A pilot study of "post-seclusion and/or restraint review" intervention with patients and staff in a mental health setting.

    Science.gov (United States)

    Goulet, Marie-Hélène; Larue, Caroline; Lemieux, Ashley J

    2018-04-01

    To develop and evaluate a "post-seclusion and/or restraint review" (PSRR) intervention implemented in an acute psychiatric care unit. Twelve staff members and three patients were enrolled in a participatory case study. To evaluate PSRR intervention, qualitative analysis was carried out. Seclusion and restraint use 6 months before and after the PSRR implementation was compared. Nurses reported that they were able to explore the patient's feelings during the PSRR intervention with patients, which led to restoration of the therapeutic relationship. PSRR with the treatment team was perceived as a learning opportunity, which allowed to improve the therapeutic intervention. Both the use of seclusion and the time spent in seclusion were significantly reduced 6 months after the implementation of PSRR intervention. Our results suggest the efficacy of PSRR in overcoming the discomfort perceived by both staff and patient and, in the meantime, in reducing the need for coercive procedures. Systematic PSRR could permit to improve the quality of care and the safety of aggressiveness management. © 2017 Wiley Periodicals, Inc.

  12. Effectiveness of structured multidisciplinary rounding in acute care units on length of stay and satisfaction of patients and staff: a quantitative systematic review.

    Science.gov (United States)

    Mercedes, Angela; Fairman, Precillia; Hogan, Lisa; Thomas, Rexi; Slyer, Jason T

    2016-07-01

    Consistent, concise and timely communication between a multidisciplinary team of healthcare providers, patients and families is necessary for the delivery of quality care. Structured multidisciplinary rounding (MDR) using a structured communication tool may positively impact length of stay (LOS) and satisfaction of patients and staff by improving communication, coordination and collaboration among the healthcare team. To evaluate the effectiveness of structured MDR using a structured communication tool in acute care units on LOS and satisfaction of patients and staff. Adult patients admitted to acute care units and healthcare providers who provide direct care for adult patients hospitalized in in-patient acute care units. The implementation of structured MDR utilizing a structured communication tool to enhance and/or guide communication. Quasi-experimental studies and descriptive studies. Length of stay, patient satisfaction and staff satisfaction. The comprehensive search strategy aimed to find relevant published and unpublished quantitative English language studies from the inception of each database searched through June 30, 2015. Databases searched include Cumulative Index to Nursing and Allied Health Literature, PubMed, Excerpta Medica Database, Health Source, Cochrane Central Register of Controlled Trials and Scopus. A search of gray literature was also performed. All reviewers independently evaluated the included studies for methodological quality using critical appraisal tools from the Joanna Briggs Institute (JBI). Data related to the methods, participants, interventions and findings were extracted using a standardized data extraction tool from the JBI. Due to clinical and methodological heterogeneity in the interventions and outcome measures of the included studies, statistical meta-analysis was not possible. Results are presented in narrative form. Eight studies were included, three quasi-experimental studies and five descriptive studies of quality

  13. The impact of education and training interventions for nurses and other health care staff involved in the delivery of stroke care: An integrative review.

    Science.gov (United States)

    Jones, Stephanie P; Miller, Colette; Gibson, Josephine M E; Cook, Julie; Price, Chris; Watkins, Caroline L

    2018-02-01

    The aim of this review was to explore the impact of stroke education and training of nurses and other health care staff involved in the delivery of stroke care. We performed an integrative review, following PRISMA guidance where possible. We searched MEDLINE, ERIC, PubMed, AMED, EMBASE, HMIC, CINAHL, Google Scholar, IBSS, Web of Knowledge, and the British Nursing Index from 1980 to 2016. Any intervention studies were included if they focused on the education or training of nurses and other health care staff in relation to stroke care. Articles that appeared to meet the inclusion criteria were read in full. Data were extracted from the articles, and the study quality assessed by two researchers. We assessed risk of bias of included studies using a pre-specified tool based on Cochrane guidance. Our initial search identified 2850 studies of which 21 met the inclusion criteria. Six studies were randomised controlled trials, and one was an interrupted time series. Fourteen studies were quasi-experimental: eight were pretest-posttest; five were non-equivalent groups; one study had a single assessment. Thirteen studies used quality of care outcomes and eight used a patient outcome measure. None of the studies was identified as having a low risk of bias. Only nine studies used a multi-disciplinary approach to education and training and nurses were often taught alone. Interactive education and training delivered to multi-disciplinary stroke teams, and the use of protocols or guidelines tended to be associated with a positive impact on patient and quality of care outcomes. Practice educators should consider the delivery of interactive education and training delivered to multi-disciplinary groups, and the use of protocols or guidelines, which tend to be associated with a positive impact on both patient and quality of care outcomes. Future research should incorporate a robust design. Copyright © 2017. Published by Elsevier Ltd.

  14. Assessment of current NRC/IE professional training program and recommendations for improvement

    International Nuclear Information System (INIS)

    Bartley, H.J.; Hagerup, J.E.; Harrison, O.J.; Heyer, F.H.K.; Kaas, I.W.; Schwartz, E.G.

    1978-05-01

    This document is the General Research Corporation (GRC) report on Task III: to assess the current NRC/IE professional training program and to provide recommendations for improvement. The major objectives of this task were to determine the overall effectiveness of the NRC/IE training program and to provide recommendations for improvements where appropriate. The research involved a review of course manuals and of student critiques, observation in the classroom and person to person interviews; it also included an evaluation of the assignment of instructors to the Career Management Branch. Findings addressed refresher training, retread training and initial training--with emphasis on the last of these. Conclusions are that: (1) The curriculum provides, in general, types and levels of training needed; (2) the mix of training methods used is correct; and (3) the training management is effective. However, the training facilities do not reflect a commitment to quality instruction nor is assignment as instructor to the Career Management Branch attractive to inspectors. Recommendations presented in the report are based upon the findings; all lie within the implementing authority of Headquarters NRC/IE

  15. Development of RESRAD probabilistic computer codes for NRC decommissioning and license termination applications

    International Nuclear Information System (INIS)

    Chen, S. Y.; Yu, C.; Mo, T.; Trottier, C.

    2000-01-01

    In 1999, the US Nuclear Regulatory Commission (NRC) tasked Argonne National Laboratory to modify the existing RESRAD and RESRAD-BUILD codes to perform probabilistic, site-specific dose analysis for use with the NRC's Standard Review Plan for demonstrating compliance with the license termination rule. The RESRAD codes have been developed by Argonne to support the US Department of Energy's (DOEs) cleanup efforts. Through more than a decade of application, the codes already have established a large user base in the nation and a rigorous QA support. The primary objectives of the NRC task are to: (1) extend the codes' capabilities to include probabilistic analysis, and (2) develop parameter distribution functions and perform probabilistic analysis with the codes. The new codes also contain user-friendly features specially designed with graphic-user interface. In October 2000, the revised RESRAD (version 6.0) and RESRAD-BUILD (version 3.0), together with the user's guide and relevant parameter information, have been developed and are made available to the general public via the Internet for use

  16. US NRC research on the integrity of piping in nuclear reactor primary systems

    International Nuclear Information System (INIS)

    Serpan, C.Z. Jr.

    1983-01-01

    This paper has attempted to provide a ''snapshot'' of the activities underway in NRC on the subject of LWR piping integrity as of the summer and fall of 1983. The paper is necessarily vague on certain topics of policy because they are either under review or are under development and the outcome cannot be accurately forecast at this time. Particularly in the area of BWR pipe cracking, events are very rapid so that positions and actions described in this paper may well be obsolete by the time it is published. Nevertheless, the activities and positions are as accurate as possible at the time of writing. Certainly the longer-range aspects of the research program represent the current direction and intent of NRC; nevertheless, as results come in and actions occur in the licensing and regulation arena of operating reactors, the emphasis of the research programs will necessarily shift to accommodate them so as to remain as relevant as possible. Thus, this paper is useful to show the intentions of NRC in the area of research for LWR piping, and it is also useful to document the status of the regulations on piping for which the research is being performed. (orig.)

  17. Recent NRC research activities addressing valve and pump issues

    Energy Technology Data Exchange (ETDEWEB)

    Morrison, D.L.

    1996-12-01

    The mission of the U.S. Nuclear Regulatory Commission (NRC) is to ensure the safe design, construction, and operation of commercial nuclear power plants and other facilities in the U.S.A. One of the main roles that the Office of Nuclear Regulatory Research (RES) plays in achieving the NRC mission is to plan, recommend, and implement research programs that address safety and technical issues deemed important by the NRC. The results of the research activities provide the bases for developing NRC positions or decisions on these issues. Also, RES performs confirmatory research for developing the basis to evaluate industry responses and positions on various regulatory requirements. This presentation summarizes some recent RES supported research activities that have addressed safety and technical issues related to valves and pumps. These activities include the efforts on determining valve and motor-operator responses under dynamic loads and pressure locking events, evaluation of monitoring equipment, and methods for detecting and trending aging of check valves and pumps. The role that RES is expected to play in future years to fulfill the NRC mission is also discussed.

  18. 76 FR 60937 - Draft License Renewal Interim Staff Guidance LR-ISG-2011-02; Aging Management Program for Steam...

    Science.gov (United States)

    2011-09-30

    ...-2011-02; Aging Management Program for Steam Generators AGENCY: Nuclear Regulatory Commission. ACTION... License Renewal Interim Staff Guidance (LR-ISG), LR-ISG-2011-02, ``Aging Management Program for Steam... using Revision 3 of NEI 97-06 to manage steam generator aging. The Draft LR-ISG revises the NRC staff's...

  19. 76 FR 77025 - Office of New Reactors; Notice of Availability of the Final Staff Guidance Section 1.0, Revision...

    Science.gov (United States)

    2011-12-09

    ... the Final Staff Guidance Section 1.0, Revision 2 on Introduction and Interfaces AGENCY: Nuclear... Plants: LWR Edition,'' Section 1.0, Revision 2 on ``Introduction and Interfaces'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112730393). The NRC staff issues revisions to SRP...

  20. Staff meeting

    CERN Document Server

    2006-01-01

    I would like to invite all members of the CERN Personnel to a meeting on Thursday 18 January 2007 at 3:00 p.m. Main Auditorium (bldg.. 500) to convey my best wishes for the new year, to review CERN's activities during 2006 and to present the perspectives for this special year of the LHC start-up. Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (bldg.. 31) and the AT Auditorium (bldg.. 30). Simultaneous translation into English will be available in the main Auditorium. Robert AYMAR

  1. Staff meeting

    CERN Multimedia

    2007-01-01

    Dear Colleagues, 2007 is a very special year for CERN. I would like to review the status of our activities with you, and I invite you to a presentation on Wednesday 27 June 2007 at 3:00 p.m. Main Auditorium (bldg. 500) Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (bldg. 31) and the AT Auditorium (bldg. 30). Simultaneous translation into English will be available in the Main Auditorium. Robert AYMAR

  2. STAFF MEETING

    CERN Multimedia

    Robert Aymar

    2005-01-01

    I would like to invite all members of the CERN Personnel to a meeting on Thursday 12 January 2006 at 4:00 p.m. - Main Auditorium (bldg. 500) to convey my best wishes for the new year, to review CERN's activities during 2005 and to present the perspectives for this coming year. Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (bldg. 31) and the AT Auditorium (bldg. 30). A simultaneous translation into English will be available in the main Auditorium. Best wishes for the festive season Robert AYMAR

  3. 75 FR 31433 - Science Advisory Board Staff Office; Notification of a Public Meeting of the SAB Lead Review Panel

    Science.gov (United States)

    2010-06-03

    ... held on July 6, 2010 from 9 a.m. to 5 p.m. (Eastern Time) and July 7, 2010 from 9 a.m. to 12 p.m. (Eastern Time). ADDRESSES: The face-to-face meeting on July 6-7, 2010 will be held at the St. Regis... (FACA), 5 U.S.C., App. 2, notice is hereby given that the SAB Lead Review Panel will hold a public face...

  4. Personal Staff - Joint Staff - The National Guard

    Science.gov (United States)

    the ARNG Deputy Director of the ARNG Chief of Staff of the ARNG Command Chief Warrant Officer of the Site Maintenance Battle Focused Training Strategy Battle Staff Training Resources News Publications March Today in Guard History Leadership CNGB VCNGB SEA DANG DARNG Joint Staff J-1 J-2 J-3 J-4 J-5 J-6 J

  5. 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

  6. A review of NRC regulatory processes and functions

    International Nuclear Information System (INIS)

    1981-05-01

    A reexamination by the ACRS of the Regulatory Process has been made. Objectives were to provide in a single source, ACRS' understanding of the Regulatory Process and to point out perceived weaknesses and to make appropriate recommendations for change

  7. Lessons learned from NRC systematic evaluation program seismic review

    International Nuclear Information System (INIS)

    Cheng, T.M.; Hermann, R.A.; Russell, W.T.

    1983-01-01

    In October 1977, the Nuclear Regulatory Commission approved initiation of Phase II of the Systematic Evaluation Program (SEP) which consists of a plant-specific reassessment of the safety of 11 older operating nuclear reactors. Many safety criteria have rapidly evolved since the time of initial licensing of these plants. The purpose of the SEP is to develop a current documented basis for the safety of these older facilities by comparing them to current criteria. Phase I of the SEP developed a comprehensive list of 137 topics of safety significance which collectively affect the plant's capability to respond to various Design Basis Events (DBEs). Seismic Design Consideration is one of the 137 safety topics. (orig./GL)

  8. NRC/AMRMC Resident Research Associateship Program

    Science.gov (United States)

    2018-05-01

    data sources, gathering and maintaining the data needed, and completing and reviewing this collection of information. Send comments regarding this...with another U.S. government agency 0 Research/administrative position with foreign government agency 0 Research/teaching at US college/university 1

  9. Initial experience with the NRC significance determination process

    Energy Technology Data Exchange (ETDEWEB)

    Madison, A.L. [Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission (United States)

    2001-07-01

    The U.S. Nuclear Regulatory Commission (NRC) has revamped its inspection, assessment, and enforcement programs for commercial nuclear power plants. The new oversight process uses more objective, timely, and safety-significant criteria in assessing performance, while seeking to more effectively and efficiently regulate the industry. The NRC tested the new process at thirteen reactors at nine sites across the country on a pilot basis in 1999 to identify what things worked well and what improvements were called for before beginning Initial Implementation at all US nuclear power plants on April 2, 2000. After a year of experience has been gained with the new oversight process at all US plants, the NRC anticipates making further improvements based on this wider experience. (author)

  10. Coupled processes in NRC high-level waste research

    International Nuclear Information System (INIS)

    Costanzi, F.A.

    1987-01-01

    The author discusses NRC research effort in support of evaluating license applications for disposal of nuclear waste and for promulgating regulations and issuing guidance documents on nuclear waste management. In order to do this they fund research activities at a number of laboratories, academic institutions, and commercial organizations. One of our research efforts is the coupled processes study. This paper discusses interest in coupled processes and describes the target areas of research efforts over the next few years. The specific research activities relate to the performance objectives of NRC's high-level waste (HLW) regulation and the U.S. Environmental Protection Agency (EPA) HLW standard. The general objective of the research program is to ensure the NRC has a sufficient independent technical base to make sound regulatory decisions

  11. Initial experience with the NRC significance determination process

    International Nuclear Information System (INIS)

    Madison, A.L.

    2001-01-01

    The U.S. Nuclear Regulatory Commission (NRC) has revamped its inspection, assessment, and enforcement programs for commercial nuclear power plants. The new oversight process uses more objective, timely, and safety-significant criteria in assessing performance, while seeking to more effectively and efficiently regulate the industry. The NRC tested the new process at thirteen reactors at nine sites across the country on a pilot basis in 1999 to identify what things worked well and what improvements were called for before beginning Initial Implementation at all US nuclear power plants on April 2, 2000. After a year of experience has been gained with the new oversight process at all US plants, the NRC anticipates making further improvements based on this wider experience. (author)

  12. Terrestrial Analogs to Mars: NRC Community Panel Decadal Report

    Science.gov (United States)

    Farr, T. G.

    2002-12-01

    A report was completed recently by a Community Panel for the NRC Decadal Study of Solar System Exploration. The desire was for a review of the current state of knowledge and for recommendations for action over the next decade. The topic of this panel, Terrestrial Analogs to Mars, was chosen to bring attention to the need for an increase in analog studies in support of the increased pace of Mars exploration. It is well recognized that interpretations of Mars must begin with the Earth as a reference. The most successful comparisons have focused on understanding geologic processes on the Earth well enough to extrapolate to Mars' environment. Several facets of terrestrial analog studies have been pursued and are continuing. These studies include field workshops, characterization of terrestrial analog sites, instrument tests, laboratory measurements (including analysis of martian meteorites), and computer and laboratory modeling. The combination of all of these activities allows scientists to constrain the processes operating in specific terrestrial environments and extrapolate how similar processes could affect Mars. The Terrestrial Analogs for Mars Community Panel has considered the following two key questions: (1) How do terrestrial analog studies tie in to the overarching science questions about life, past climate, and geologic evolution of Mars, and (2) How can future instrumentation be used to address these questions. The panel considered the issues of data collection and archiving, value of field workshops, laboratory measurements and modeling, human exploration issues, association with other areas of solar system exploration, and education and public outreach activities. Parts of this work were performed under contract to NASA.

  13. Staff meeting

    CERN Multimedia

    2007-01-01

    I would like to invite all members of the CERN Personnel to a meeting on Wednesday 16 January 2008 at 3:00 p.m. Main Auditorium (bldg 500) to convey my best wishes for the new year, to review CERN’s activities during 2007 and to present the perspectives for 2008, the year of the LHC start-up. Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (Bldg. 31) and the AT Auditorium (Bldg. 30). Simultaneous translation into English will be available in the main Auditorium. Best wishes for the festive season! Robert AYMAR

  14. Resolution of the Staff Council

    CERN Multimedia

    Staff Association

    2015-01-01

    You were many to attend the public information meetings organised in October and we thank you for your interest. In this decision phase of the current Five-Yearly Review of our employment conditions they provided an opportunity to review the Management proposals in detail. They were a moment of exchange also on the various topics under review, and your comments were many and very valuable. Meeting on Thursday 29th October, the Staff Council discussed once more these proposals. It considered that the "package" of proposed measures is not balanced enough in its current form. It decided to formulate additional requests to the Management, relating mainly to the effects of the introduction of the proposed new career system. The resolution adopted this morning also implies that the consultation of staff, originally foreseen next week, is postponed. The staff Council will reconvene in a special session on Thursday, 5th November to reassess its position depending on the progress made regarding its d...

  15. Armenian nuclear power plant: US NRC assistance programme for seismic upgrade and safety analysis

    International Nuclear Information System (INIS)

    Simos, N.; Perkins, K.; Jo, J.; Carew, J.; Ramsey, J.

    2003-01-01

    This paper summarizes the U.S. Nuclear Regulatory Commission's (US NRC) technical support program activities associated with the Armenian Nuclear Power Plant (ANPP) safety upgrade. The US NRC program, integrated within the overall IAEA-led initiative for safety re-evaluation of the WWER plants, has as its main thrust the technical support to the Armenian Nuclear Regulatory Authority (ANRA) through close collaboration with the scientific staff at Brookhaven National Laboratory (BNL). Several major technical areas of support to ANRA form the basis of the NRC program. These include the seismic re-evaluation and upgrade of the ANPP, safety evaluation of critical systems, and the generation of the Safety Analysis Report (SAR). Specifically, the seismic re-evaluation of the ANPP is part of a broader activity that involves the re-assessment of the seismic hazard at the site, the identification of the Safe Shutdown Equipment at the plant and the evaluation of their seismic capacity, the detailed modeling and analysis of the critical facilities at ANPP, and the generation of the Floor Response Spectra (FRS). Based on the new spectra that incorporate all new findings (hazard, site soil, structure, etc.), the overall capacity of the main structures and the seismic capacity of the critical systems are being re-evaluated. In addition, analyses of critical safe shutdown systems and safe shutdown processes are being performed to ensure both the capabilities of the operating systems and the enhancement of safety due to system upgrades. At present, one of the principal goals of the US NRC's regulatory assistance activities with ANRA is enhancing ANRA's regulatory oversight of high-priority safety issues (both generic and plant-specific) associated with operation of the ANPP. As such, assisting ANRA in understanding and assessing plant-specific seismic and other safety issues associated with the ANPP is a high priority given the ANPP's being located in a seismically active area

  16. Respirator studies for the Nuclear Regulatory Commission (NRC)

    International Nuclear Information System (INIS)

    Skaggs, B.J.; Fairchild, C.I.; DeField, J.D.; Hack, A.L.

    1985-01-01

    A project of the Health, Safety and Environment Division is described. The project provides the NRC with information of respiratory protective devices and programs for their licensee personnel. The following activities were performed during FY 1983: selection of alternate test aerosols for quality assurance testing of high-efficiency particulate air respirator filters; evaluation of MAG-1 spectacles for use with positive and negative-pressure respirators; development of a Manual of Respiratory Protection in Emergencies Involving Airborne Radioactive Materials, and technical assistance to NRC licensees regarding respirator applications. 2 references, 1 figure

  17. A systematic review and meta-analysis of factors that relate to aggression perpetrated against nurses by patients/relatives or staff.

    Science.gov (United States)

    Edward, Karen-leigh; Stephenson, John; Ousey, Karen; Lui, Steve; Warelow, Philip; Giandinoto, Jo-Ann

    2016-02-01

    The aim of this meta-analysis was to identify the factors that related to aggression (verbal abuse or physical abuse/assault) perpetrated against the nurse or other health professionals by patients/relatives or staff. In the light of the paucity of systematic reviews on this common issue in nursing, the objective was to present a comprehensive systematic review and meta-analysis of these papers. Aggression towards nurses is common around the world and can be the impetus for nurses leaving the profession or developing anxiety when working in particular settings. Systematic review with meta-analysis. Meta-analyses were conducted to assess the effect of the factors of gender and context (dichotomised as mental health/psychiatric or nonmental health/psychiatric). The databases of Medline (1966-2015), CINAHL (1982-2015) and PsychInfo (1920-2015). A total of 1571 papers were screened by two reviewers. At the final decision 14 were selected for analysis. A higher proportion of female nurses than male nurses were reported to be the victims of verbal abuse, with the difference in proportions being statistically significant. A statistically significant higher proportion of male nurses than female nurses were reported to be the victims of physical abuse. There was a significantly higher proportion of mental health nurses reported experiencing physical abuse as compared to nonmental health nurses. The analysis reveal female nurses have greater odds of verbal abuse than male nurses and male nurses have greater odds of physical abuse than female nurses. Overall mental health nurses had three times higher odds of physical assault than other nurses. In the light of the findings it is recommended organisational support improve in high aggression potential clinical areas and for nursing curriculums to incorporate education about the management of challenging behaviours in undergraduate programmes. © 2015 John Wiley & Sons Ltd.

  18. Developing effective educational approaches for Liaison Old Age Psychiatry teams: a literature review of the learning needs of hospital staff in relation to managing the confused older patient.

    Science.gov (United States)

    Teodorczuk, Andrew; Welfare, Mark; Corbett, Sally; Mukaetova-Ladinska, Elizabeta

    2010-09-01

    Deficiencies in the knowledge, skills and attitudes of all healthcare professionals working within the general hospital contribute towards the suboptimal care of older hospitalized patients with confusion. In the U.K., policy dictates that Liaison Old Age Psychiatry teams deliver effective education to general hospital clinical staff. The purpose of this paper is to review the literature concerning the learning needs of healthcare professionals in relation to managing confusion in the older patient in order to inform effective educational approaches for Liaison Old Age Psychiatry teams. A broad range of medical and educational databases were searched. Identified English language studies were selected for further analysis if they had a specific educational focus in the hospital setting and then further subdivided into intervention and naturalistic studies. The impact of intervention studies was evaluated by Kirkpatrick's system. Learning needs, as determined from the naturalistic studies, were mapped to identify themes. 13 intervention studies were identified. Despite a high level of effectiveness for educational interventions, it was unclear what the active components were. A further 23 naturalistic studies were identified; their findings focused on knowledge gaps, diagnostic behaviors and experiences, attitudes and training issues. Few studies specifically researched learning needs or the educational role of liaison teams. Conspicuous by its absence was reference to relevant educational theories. The findings of this review can be incorporated in the planning of local curricula by Liaison Teams in order to design educational strategies. There is a need for further research, especially studies exploring the learning needs of all healthcare professionals.

  19. Patient, nursing and medical staff experiences and perceptions of the care of people with palliative esophagogastric cancer: a systematic review of the qualitative evidence.

    Science.gov (United States)

    Cowley, Alison; Evans, Catrin; Bath-Hextall, Fiona; Cooper, Joanne

    2016-10-01

    Esophagogastric cancer is the fifth most common malignancy and its incidence is increasing. The disease progresses quickly and five-year survival rates are poor. Treatment with palliative intent is provided for the majority of patients but there remains a lack of empirical evidence on the most effective service models to support esophagogastric cancer patients. The overall objective of this systematic review was to synthesize the best available evidence on the experiences and perceptions of patients and health professionals with regard to the care of people diagnosed with palliative esophagogastric cancer. The review considered studies that included patients diagnosed with palliative esophagogastric cancer and any health professionals involved in the delivery of palliative care to this patient group in a hospital, home or community setting. The review considered studies that investigated the experiences and perceptions of people diagnosed with palliative esophagogastric cancer and staff working with these people. Studies that were carried out in any setting, including in-patient and outpatient areas, specialist cancer and non-specialist palliative care services and those were any patient were in receipt or had experiences of palliative care services were considered. All types of health practitioners delivering palliative care to esophagogastric cancer patients were considered. Studies that focused on qualitative data, including, but not limited to, designs such as phenomenology, grounded theory, ethnography, action research, feminist research and narrative approaches were considered. Mixed methods studies were considered in the review only if qualitative findings were reported separately. A three-step search strategy was utilized. A total 11 databases were searched for studies from 2000 onward, followed by hand searching of reference lists. Methodological quality was assessed using the Joanna Briggs Institute Qualitative Assessment and Review Instrument critical

  20. Review insights on the probabilistic risk assessment for the Limerick Generating Station

    International Nuclear Information System (INIS)

    1984-08-01

    In recognition of the high population density around the Limerick Generating Station site and the proposed power level, the Philadelphia Electric Company, in response to NRC staff requests, conducted and submitted between March 1981 and November 1983 a probabilistic risk assessment (PRA) on internal event contributors and a severe accident risk assessment on external event contributors to assess risks posed by operation of the plant. The applicant has developed perspectives using PRA models on the safety profile of the Limerick plant and has altered the plant design to reduce accident vulnerabilities identified in these PRAs. The staff's review of the Limerick PRA has particularly emphasized the dominant accident sequences and the resulting insights into demonstration of compliance with regulatory requirments, unique design features and major plant vulnerabilities to assess the need for any additional measures to further improve the safety of the LGS. The staff's review insights and PRA safety review conclusions are presented in this report

  1. GPU v. B and W lawsuit review and its effect on TMI-1 (Docket 50-289)

    International Nuclear Information System (INIS)

    1983-09-01

    This report documents a review by the Nuclear Regulatory Commission (NRC) staff of the General Public Utilities Corporation, et al. v. the Babcock and Wilcox Company, et al. (GPU v. B and W) lawsuit record to assess whether any of the staff's previous conclusions or their principal bases presented at the Three Mile Island Unit 1 (TMI-1) restart hearing, supporting restart of TMI-1, should be amended in light of the information contained in the lawsuit record. Details of the lawsuit record are provided in the appendices contained in Volume II of this report

  2. GPU v. B and W lawsuit review and its effect on TMI-1 (Docket 50-289)

    Energy Technology Data Exchange (ETDEWEB)

    1983-09-01

    This report documents a review by the Nuclear Regulatory Commission (NRC) staff of the General Public Utilities Corporation, et al. v. the Babcock and Wilcox Company, et al. (GPU v. B and W) lawsuit record to assess whether any of the staff's previous conclusions or their principal bases presented at the Three Mile Island Unit 1 (TMI-1) restart hearing, supporting restart of TMI-1, should be amended in light of the information contained in the lawsuit record. Details of the lawsuit record are provided in the appendices contained in Volume II of this report.

  3. What it took to get an NRC license for centralized incineration

    International Nuclear Information System (INIS)

    DiSalvo, R.; Zielenbach, W.

    1987-01-01

    In 1982, Battelle joined five other commercial generators of low level radioactive waste in conducting a study of the technical and economic feasibility and the licensability of a central facility for incinerating LLW. The project generated a license application to the USNRC and supporting documentation related to the safety and environmental impacts of the facility. After thorough review, the NRC has issued a Finding of No Significant Impact and the associated license authorization, which is the first of its kind for an incineration facility

  4. Safety Experts Complete IAEA Nuclear Regulatory Review of the United States

    International Nuclear Information System (INIS)

    2010-01-01

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

  5. 14 CFR 385.3 - Scope of staff action.

    Science.gov (United States)

    2010-01-01

    ...) ORGANIZATION STAFF ASSIGNMENTS AND REVIEW OF ACTION UNDER ASSIGNMENTS General Provisions § 385.3 Scope of staff... manner as if no assignment had been made (see § 385.5). In such proceedings, each staff member may... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Scope of staff action. 385.3 Section 385.3...

  6. NRC Regulatory Agenda. Quarterly report, July-September 1985

    International Nuclear Information System (INIS)

    1985-10-01

    The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed, or is considering action as well as those on which it has recently completed action, and all petitions for rulemaking which have been received and are pending disposition by the Commission

  7. Risk-informed inservice test activities at the NRC

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, D.; Cheok, M.; Hsia, A.

    1996-12-01

    The operational readiness of certain safety-related components is vital to the safe operation of nuclear power plants. Inservice testing (IST) is one of the mechanisms used by licensees to ensure this readiness. In the past, the type and frequency of IST have been based on the collective best judgment of the NRC and industry in an ASME Code consensus process and NRC rulemaking process. Furthermore, IST requirements have not explicitly considered unique component and system designs and contribution to overall plant risk. Because of the general nature of ASME Code test requirements and non-reliance on risk estimates, current IST requirements may not adequately emphasize testing those components that are most important to safety and may overly emphasize testing of less safety significant components. Nuclear power plant licensees are currently interested in optimizing testing by applying resources in more safety significant areas and, where appropriate, reducing measures in less safety-significant areas. They are interested in maintaining system availability and reducing overall maintenance costs in ways that do not adversely affect safety. The NRC has been interested in using probabilistic, as an adjunct to deterministic, techniques to help define the scope, type and frequency of IST. The development of risk-informed IST programs has the potential to optimize the use of NRC and industry resources without adverse affect on safety.

  8. Risk-informed inservice test activities at the NRC

    International Nuclear Information System (INIS)

    Fischer, D.; Cheok, M.; Hsia, A.

    1996-01-01

    The operational readiness of certain safety-related components is vital to the safe operation of nuclear power plants. Inservice testing (IST) is one of the mechanisms used by licensees to ensure this readiness. In the past, the type and frequency of IST have been based on the collective best judgment of the NRC and industry in an ASME Code consensus process and NRC rulemaking process. Furthermore, IST requirements have not explicitly considered unique component and system designs and contribution to overall plant risk. Because of the general nature of ASME Code test requirements and non-reliance on risk estimates, current IST requirements may not adequately emphasize testing those components that are most important to safety and may overly emphasize testing of less safety significant components. Nuclear power plant licensees are currently interested in optimizing testing by applying resources in more safety significant areas and, where appropriate, reducing measures in less safety-significant areas. They are interested in maintaining system availability and reducing overall maintenance costs in ways that do not adversely affect safety. The NRC has been interested in using probabilistic, as an adjunct to deterministic, techniques to help define the scope, type and frequency of IST. The development of risk-informed IST programs has the potential to optimize the use of NRC and industry resources without adverse affect on safety

  9. 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

  10. NRC Regulatory Agenda: Quarterly report, January--March 1988

    International Nuclear Information System (INIS)

    1988-07-01

    The Regulatory Agenda is a quarterly compilation of all rules on which the NRC has proposed, or is considering action as well as those on which it has recently completed action, and all petitions for rulemaking which have been received and are pending disposition by the Commission

  11. 75 FR 6063 - Availability of NRC Open Government Web Site

    Science.gov (United States)

    2010-02-05

    ... ( http://www.nrc.gov/open ) will be available by February 6, 2010, and directs that, after February 10... http://www.regulations.gov Web site. FOR FURTHER INFORMATION CONTACT: James B. Schaeffer, Deputy..., 2010, and provided options for submitting comments by mail, fax, or at http://www.regulations.gov , but...

  12. Aligning institutional priorities: engaging house staff in a quality improvement and safety initiative to fulfill Clinical Learning Environment Review objectives and electronic medical record Meaningful Use requirements.

    Science.gov (United States)

    Flanagan, Meghan R; Foster, Carolyn C; Schleyer, Anneliese; Peterson, Gene N; Mandell, Samuel P; Rudd, Kristina E; Joyner, Byron D; Payne, Thomas H

    2016-02-01

    House staff quality improvement projects are often not aligned with training institution priorities. House staff are the primary users of inpatient problem lists in academic medical centers, and list maintenance has significant patient safety and financial implications. Improvement of the problem list is an important objective for hospitals with electronic health records under the Meaningful Use program. House staff surveys were used to create an electronic problem list manager (PLM) tool enabling efficient problem list updating. Number of new problems added and house staff perceptions of the problem list were compared before and after PLM intervention. The PLM was used by 654 house staff after release. Surveys demonstrated increased problem list updating (P = .002; response rate 47%). Mean new problems added per day increased from 64 pre-PLM to 125 post-PLM (P house staff in institutional quality and safety initiatives with tangible institutional benefits. Copyright © 2016 Elsevier Inc. All rights reserved.

  13. NRC regulations and positions concerning decontamination

    International Nuclear Information System (INIS)

    McCracken, C.

    1982-09-01

    The U.S. Nuclear Regulatory Commission encourages the use of decontamination to reduce man-rem exposure. The Commission feels that there are several processes developed to the point where soft decontamination can be applied to an entire plant in the near future. A utility can do a decontamination under its own licence without coming in for regulatory review if the process does not involve a change in technical specifications for the plant or does not involve unreviewed safety questions. Prior verbal notification is required for some steam generator secondary side cleaning or for decontamination of individual components that have not been removed from the reactor using chemicals not normally added to the reactor coolant. Prior written notification is required for steam generator secondary side crevice cleaning or sludge removal at a dented unit, or for chemical decontamination of reactor coolant systems or safety-related systems using chemicals not normally added to the coolant

  14. Staff experiences within the implementation of computer-based nursing records in residential aged care facilities: a systematic review and synthesis of qualitative research.

    Science.gov (United States)

    Meißner, Anne; Schnepp, Wilfried

    2014-06-20

    Since the introduction of electronic nursing documentation systems, its implementation in recent years has increased rapidly in Germany. The objectives of such systems are to save time, to improve information handling and to improve quality. To integrate IT in the daily working processes, the employee is the pivotal element. Therefore it is important to understand nurses' experience with IT implementation. At present the literature shows a lack of understanding exploring staff experiences within the implementation process. A systematic review and meta-ethnographic synthesis of primary studies using qualitative methods was conducted in PubMed, CINAHL, and Cochrane. It adheres to the principles of the PRISMA statement. The studies were original, peer-reviewed articles from 2000 to 2013, focusing on computer-based nursing documentation in Residential Aged Care Facilities. The use of IT requires a different form of information processing. Some experience this new form of information processing as a benefit while others do not. The latter find it more difficult to enter data and this result in poor clinical documentation. Improvement in the quality of residents' records leads to an overall improvement in the quality of care. However, if the quality of those records is poor, some residents do not receive the necessary care. Furthermore, the length of time necessary to complete the documentation is a prominent theme within that process. Those who are more efficient with the electronic documentation demonstrate improved time management. For those who are less efficient with electronic documentation the information processing is perceived as time consuming. Normally, it is possible to experience benefits when using IT, but this depends on either promoting or hindering factors, e.g. ease of use and ability to use it, equipment availability and technical functionality, as well as attitude. In summary, the findings showed that members of staff experience IT as a benefit when

  15. The NRC weighs public input on plant cleanup standards

    International Nuclear Information System (INIS)

    Simpson, J.

    1993-01-01

    In the wake of seven public open-quotes work-shopsclose quotes held around the country over the past several months, the Nuclear Regulatory Commission (NRC) is preparing to develop radiological criteria for decommissioning nuclear power plants. The criteria will apply to plants that operate for their normal lifespan, those that shut down prematurely, as well as a range of other NRC-licensed facilities, including materials licensees, fuel reprocessing and fabrication plants, and independent spent fuel storage installations. The criteria have been years in the making, and their progress is being monitored closely by the Environmental Protection Agency (EPA), which shares with the NRC the authority to regulate radiological hazards. Both agencies have made abortive attempts to promulgate standards in the past. The EPA's most recent proposal, dating from 1986, has yet to reach the final rule stage. The NCRC's 1990 policy statement, open-quotes Below Regulatory Concern,close quotes was overturned by the Energy Policy Act of 1992, a setback that prompted the Commission's call for open-quotes enhanced participatory rulemakingclose quotes-a.k.a., public meetings-last December. In its Rulemaking Issues Paper, the NRC outlined for discussion four open-quotes fundamentalclose quotes objectives as a basis for developing decommissioning criteria: (1) establishing limits above which the risks to the public are deemed open-quotes unacceptableclose quotes; (2) establishing open-quotes goalsclose quotes below which the risks to the public are deemed open-quotes trivialclose quotes; (3) establishing criteria for what is achievable using the open-quotes best availableclose quotes cleanup technology; and (4) removing all radioactivity attributable to plant activity. The NRC expects to publish a proposed rule and a draft generic environmental impact statement in April 1994; the final rule is scheduled for May 1995

  16. NRC integrated program for the resolution of Unresolved Safety Issues A-3, A-4 and A-5 regarding steam generator tube integrity: Final report

    International Nuclear Information System (INIS)

    1988-09-01

    This report presents the results of the NRC integrated program for the resolution of Unresolved Safety Issues (USIs) A-3, A-4, and A-5 regarding steam generator tube integrity. A generic risk assessment is provided and indicates that risk from steam generator tube rupture (SGTR) events is not a significant contributor to total risk at a given site, nor to the total risk to which the general public is routinely exposed. This finding is considered to be indicative of the effectiveness of licensee programs and regulatory requirements for ensuring steam generator tube integrity in accordance with 10 CFR 50, Appendices A and B. This report also identifies a number of staff-recommended actions that the staff finds can further improve the effectiveness of licensee programs in ensuring the integrity of steam generator tubes and in mitigating the consequences of an SGTR. As part of the integrated program, the staff issued Generic Letter 85-02 encouraging licensees of pressurized water reactors (PWRs) to upgrade their programs, as necessary, to meet the intent of the staff-recommended actions; however, such actions do not constitute NRC requirements. In addition, this report describes a number of ongoing staff actions and studies involving steam generator issues which are being pursued to provide added assurance that risk from SGTR events will continue to be small. 146 refs., 5 figs., 11 tabs

  17. The staff regulations of the Agency

    International Nuclear Information System (INIS)

    2002-01-01

    Following the first comprehensive review of the Provisional Staff Regulations conducted by the Secretariat, the Board of Governors approved on 12 June 2002 amendments to the Provisional Staff Regulations including the removal of the attribute 'provisional' from their title. The revised Staff Regulations of the Agency are set forth in this document for the information of all Members of the Agency. There is a subject index at the end of the document

  18. Session Report - S. Smith (US NRC)

    International Nuclear Information System (INIS)

    Smith, Shawn

    2014-01-01

    - environment needed for safety functions; some degree of flexibility in regulatory review and assessment; education of workers: identify differences as compared to conventional rock engineering; applicability of mining regulations. In Sweden the site selection process for the final repository for spent nuclear fuel was initiated in 1992 and resulted, in June 2009, in the selection of Forsmark as the selected site for the final repository. Nuclear facilities require permits in accordance with the Swedish Environmental Code and the Nuclear Activities Act. SKB has submitted two applications to SSM (the Swedish Radiation Safety Authority) according to the Nuclear Activities Act and one to the Environmental Court according to the Environmental Code. The application according the Environmental Code includes the whole KBS-3-system - the final repository in Forsmark, the existing interim storage facility and the encapsulation plant in Oskarshamn. The challenges for the implementer and the regulator are the following: number of documents to elaborate and structure of these documents; right of veto of municipalities; management of a complex licensing process; change from R and D to industrial operations implying the creation of a sizeable construction department in SKB; strengthening of technical bases; application of regulatory framework in a different situation compared to conventional process type nuclear facilities; understanding and addressing constraints from post-closure safety related to the construction and operation of the repository; management of the time frames of repository operation requiring flexibility and continued development of disposal concept; flexible regulations: first use as basis for licensing a new nuclear facility; making adjustments for structural changes during construction and operation; ensuring excavation/construction/backfill activities do not jeopardize conditions for passive post-closure; application of general regulations for a KBS-3 type repository

  19. NRC [Nuclear Regulatory Commission] TLD [thermoluminescent dosimeter] direct radiation monitoring network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1989-09-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the second quarter of 1989

  20. NRC TLD [thermoluminescent dosimeter] Direct Radiation Monitoring Network: Progress report, January-March 1988

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1988-06-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the first quarter of 1988

  1. NRC TLD direct radiation monitoring network: Progress report, April--June 1988

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1988-09-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the second quarter of 1988

  2. 76 FR 74834 - Interim Staff Guidance on Aging Management Program for Steam Generators

    Science.gov (United States)

    2011-12-01

    ... for Steam Generators AGENCY: Nuclear Regulatory Commission. ACTION: Interim staff guidance; issuance... (LR-ISG), LR-ISG-2011-02, ``Aging Management Program for Steam Generators.'' This LR-ISG provides the...) document, NEI 97-06, ``Steam Generator Program Guidelines,'' (NRC's Agencywide Documents Access and...

  3. Summary of comments received on staff draft proposed rule on radiological criteria for decommissioning

    International Nuclear Information System (INIS)

    Caplin, J.; Page, G.; Smith, D.; Wiblin, C.

    1994-08-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC licensed facilities. The NRC obtained comments on the scope, issues, and approaches through a series of workshops (57 FR 58727), Generic Environmental Impact Statement (GEIS) scoping meetings (58 FR 33570), a dedicated electronic bulletin board system (58 FR 37760), and written submissions. A summary of workshop and scope-meeting comments was published as NUREG/CR-6156. On February 2, 1994, the Commission published in the Federal Register (59 FR 4868) a notice that the NRC staff had prepared a ''staff draft'' proposed rule on radiological criteria for decommissioning. Copies of the staff draft were distributed to the Agreement States, participants in the earlier meetings, and other interested parties for comment. This report summarizes the comments identified from the 96 docketed letters received on the staff draft. No analysis or response is included in this report. The comments reflect a broad spectrum of viewpoints. Two subjects on which the commenters were in general agreement were (1) that the enhanced participatory rulemaking should proceed, and (2) that the forthcoming GEIS and guidance documents are needed for better understanding of the draft rule

  4. 76 FR 9381 - Notice of Availability of Interim Staff Guidance Documents for Spent Fuel Storage Casks

    Science.gov (United States)

    2011-02-17

    .... FOR FURTHER INFORMATION CONTACT: Matthew Gordon, Structural Mechanics and Materials Branch, Division... transportation packaging licensing actions.'' This ISG document would provide guidance to the NRC staff when... a fee. Comments and questions on ISG-23 should be directed to Matthew Gordon, Structural Mechanics...

  5. Proceedings of the 21st DOE/NRC nuclear air cleaning conference; Volume 2, Sessions 9--16

    Energy Technology Data Exchange (ETDEWEB)

    First, M.W. [ed.] [Harvard Univ., Boston, MA (United States). Harvard Air Cleaning Lab.

    1991-02-01

    The 21st meeting of the Department of Energy/Nuclear Regulatory Commission (DOE/NRC) Nuclear Air Cleaning Conference was held in San Diego, CA on August 13--16, 1990. The proceedings have been published as a two volume set. Volume 2 contains sessions covering adsorbents, nuclear codes and standards, modelling, filters, safety, containment venting and a review of nuclear air cleaning programs around the world. Also included is the list of attendees and an index of authors and speakers. (MHB)

  6. 76 FR 57767 - Proposed Generic Communication; Draft NRC Generic Letter 2011-XX: Seismic Risk Evaluations for...

    Science.gov (United States)

    2011-09-16

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0204] Proposed Generic Communication; Draft NRC Generic Letter 2011-XX: Seismic Risk Evaluations for Operating Reactors AGENCY: Nuclear Regulatory Commission... FR 54507), that requested public comment on Draft NRC Generic Letter 2011- XX: Seismic Risk...

  7. NRC wants plant-specific responses on Thermo-Lag

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    Dissatisfied with recent industry-backed efforts to assure fire safety at nuclear power plants, the Nuclear Regulatory Commission announced on November 24 that it would direct all nuclear plant owners to specify the actions they would take to assure that the use of the Thermo-Lag 330 fire barrier material would not lead to insufficient protection of electrical cables connected to safe-shutdown systems. Previously, the NRC had been content to let the matter wait until tests sponsored by the Nuclear Management and Resources Council (Numarc) could show whether Thermo-Lag, used and installed in certain ways, would provide sufficient protection, but the NRC and Numarc have disagreed over the test methodology, and the Numarc tests are now considered to be several months behind schedule

  8. Occupational radiation exposures at NRC-licensed facilities

    International Nuclear Information System (INIS)

    Brooks, B.G.

    1980-01-01

    For the past ten years, the Nuclear Regulatory Commission and its predecessor, the Atomic Energy Commission, have required certain licensees to routinely submit two types of occupational radiation exposure reports: termination and annual reports. Each licensee engaged in any one of the activities: (1) operation of nuclear power reactors, (2) industrial radiography, (3) fuel fabrication, processing and reprocessing, and (4) large supply of byproduct material, is required to submit an annual statistical report and a termination report for each monitored employee who ends his employment or work assignment. A new regulation now requires all NRC licensees to submit annual reports for the years 1978 and 1979. These reports have been collected, computerized and maintained by the Commission at Oak Ridge, Tennessee. They are useful to the NRC in the evaluation of the risk of radiation exposure associated with the related activities. (author)

  9. NRC nuclear-plant-analyzer concept and status at INEL

    International Nuclear Information System (INIS)

    Aguilar, F.; Wagner, R.J.

    1982-01-01

    The Office of Research of the US NRC has proposed development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes how we of the INEL envision the nuclear-plant analyzer. The paper also describes a pilot RELAP5 plant-analyzer project completed during the past year and current work. A great deal of analysis is underway to determine nuclear-steam-system response. System transient analysis being so complex, there is the need to present analytical results in a way that interconnections among phenomena and all the nuances of the transient are apparent. There is the need for the analyst to dynamically control system calculations to simulate plant operation in order to perform what if studies as well as the need to perform system analysis within hours of a plant emergency to diagnose the state of the stricken plant and formulate recovery actions. The NRC-proposed nuclear-plant analyzer can meet these needs

  10. NRC drug-free workplace plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    On September 15, 1986, President Reagan signed Executive Order 12564, establishing the goal of a Drug-Free Federal Workplace. The Order made it a condition of employment that all Federal employees refrain from using illegal drugs on or off duty. On July 11, 1987, Congress passed legislation affecting implementation of the Executive Order under Section 503 of the Supplemental Appropriations Act of 1987, Public Law 100-71 (the Act). The Nuclear Regulatory Commission first issued the NRC Drug Testing Plan to set forth objectives, policies, procedures, and implementation guidelines to achieve a drug-free Federal workplace, consistent with the Executive Order and Section 503 of the Act. Revision 1, titled, ``NRC Drug-Free Workplace Plan,`` supersedes the previous version and its supplements and incorporates changes to reflect current guidance from the Department of Justice, the Department of Health and Human Services, as well as other guidance.

  11. Implementation study for the NRC Application and Development Facility

    International Nuclear Information System (INIS)

    Sherwood, R.J.; Ross, D.J.; Sasser, D.W.

    1979-01-01

    The Nuclear Regulatory Commission (NRC) has expressed the desire to establish an Application and Development Facility (ADF) for NRC Headquarters. The ADF is a computer system which will provide safeguards analysts access to safeguards analysis computer software. This report analyzes the issues, requirements and options available in the establishment of an ADF. The purpose and goals of the ADF are presented, along with some general issues to be considered in the implementation of such a system. A phased approach for ADF implementation, which will allow for the earliest possible access to existing codes and also allow for future expansion, is outlined. Several options for central computers are discussed, along with the characteristics and approximate costs for each. The report concludes with recommended actions proposed to start the development of the ADF

  12. NRC drug-free workplace plan. Revision 1

    International Nuclear Information System (INIS)

    1997-11-01

    On September 15, 1986, President Reagan signed Executive Order 12564, establishing the goal of a Drug-Free Federal Workplace. The Order made it a condition of employment that all Federal employees refrain from using illegal drugs on or off duty. On July 11, 1987, Congress passed legislation affecting implementation of the Executive Order under Section 503 of the Supplemental Appropriations Act of 1987, Public Law 100-71 (the Act). The Nuclear Regulatory Commission first issued the NRC Drug Testing Plan to set forth objectives, policies, procedures, and implementation guidelines to achieve a drug-free Federal workplace, consistent with the Executive Order and Section 503 of the Act. Revision 1, titled, ''NRC Drug-Free Workplace Plan,'' supersedes the previous version and its supplements and incorporates changes to reflect current guidance from the Department of Justice, the Department of Health and Human Services, as well as other guidance

  13. Gaming: a creative strategy for staff education.

    Science.gov (United States)

    Swartzendruber, D

    1994-02-01

    Providing staff development in a stimulating, innovative manner is the challenge of all nurse educators. This article discusses gaming, a creative teaching strategy that can help meet these needs. Games designed specifically for the education of dialysis staff will be reviewed. Advantages of the various games will also be examined.

  14. Future of Nuclear Power: NRC emergency preparedness licensing activities agenda

    International Nuclear Information System (INIS)

    Essig, T.H.

    1995-01-01

    This talk summary addresses the issue of how future policies of the NRC will affect nuclear power in areas such as construction, emergency preparedness, and licensing. Specific topics covered include the following: Emergent EP licensing issues for operating nuclear Power Plants; 10CFR Part 52 and the process for licensing of Advanced Light Water Reactors (ALWRs); and potential revisions to emergency preparedness programs for future nuclear power plants

  15. NRC safety research in support of regulation. Selected highlights

    International Nuclear Information System (INIS)

    1986-05-01

    The report presents selected highlights of how research has contributed to the regulatory effort. It explains the research role of the NRC and nuclear safety research contributions in the areas of: pressure vessel integrity, piping, small- and large-break loss-of-coolant accidents, hydrogen and containment, source term analysis, seismic hazards and high-level waste management. The report also provides a summary of current and future research directions in support of regulation

  16. NRC regulatory agenda: Quarterly report, April-June 1987

    International Nuclear Information System (INIS)

    1987-07-01

    This compilation summarizes significant enforcement actions that have been resolved during one quarterly period and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication

  17. Overview of the NRC nuclear waste management program

    International Nuclear Information System (INIS)

    Malaro, J.C.

    1976-01-01

    The NRC has firmly established waste management as a high-priority effort and has made the commitment to act rapidly and methodically to establish a sound regulatory base for licensing waste management activities. We believe the priorities for NRC work in waste management are consistent with the needs of the overall national waste management program. Present licensing procedures and criteria are adequate for the short term, and priority attention is being given to the longer term, when the quantities of waste to be managed will be greater and licensing demands will increase. Recognizing that its decision will affect industry, other governmental jurisdictions, private interest groups, and the public at large, NRC has encouraged and will continue to encourage their participation in planning our program. We also recognize that the problems of nuclear waste management are international in scope. Many waste management problems (e.g., potential for contamination of oceans and atmosphere, need for isolation of some wastes for longer periods than governments and political boundaries have remained stable in the past), require a set of internationally acceptable and accepted solutions. The wastes from the U.S. nuclear industry will account for only about one third of the nuclear waste generated in the world. Therefore, we propose to cooperate and where appropriate take the lead in establishing acceptable worldwide policies, standards and procedures for handling nuclear wastes

  18. Handbook for value-impact assessments of NRC regulatory actions

    International Nuclear Information System (INIS)

    Mullen, M.F.; DiPalo, A.J.

    1985-01-01

    According to current Nuclear Regulatory Commission (NRC) procedures, value-impact (cost-benefit) assessments must be prepared for all rulemaking actions and for a broad range of other regulatory requirements and guidance. Probabilistic risk assessment (PRA) methods furnish an important part of the information base for these assessments. PRA methods are frequently the principal quantitative tool for estimating the benefits (e.g., public risk reduction) of proposed regulatory actions. In December 1983, the NRC published A Handbook for Value-Impact Assessment, NUREG/CR-3568, which provides a set of systematic procedures for performing value-impact assessments. The Handbook contains methods, data, and sources of information that can assist the regulatory analyst in conducting such assessments. The use of probabilistic risk analysis to estimate the benefits of proposed regulatory actions is described. Procedures and methods are also given for evaluating the costs and other consequences associated with regulatory actions. The Handbook has been adopted by the NRC as the recommended guideline for value impact assessments. This paper presents the background, objectives, and scope of the Handbook, describes the value-impact assessment methods (including the use of probabilistic risk assessment to estimate benefits), and discusses a selection of current and planned applications, with examples to illustrate how the methods are used

  19. Research Staff | Buildings | NREL

    Science.gov (United States)

    Research Staff Research Staff Photo of Roderick Jackson Roderick Jackson Laboratory Program Manager -related research at NREL. He works closely with senior laboratory management to set the strategic agenda for NREL's buildings portfolio, including all research, development, and market implementation

  20. E3 Staff Database

    Data.gov (United States)

    US Agency for International Development — E3 Staff database is maintained by E3 PDMS (Professional Development & Management Services) office. The database is Mysql. It is manually updated by E3 staff as...

  1. Research Staff | Wind | NREL

    Science.gov (United States)

    Research Staff Research Staff Learn more about the expertise and technical skills of the wind power research team and staff at NREL. Name Position Email Phone Anstedt, Sheri Professional III-Writer/Editor /Web Content Sheri.Anstedt@nrel.gov 303-275-3255 Baker, Donald Research Technician V-Electrical

  2. CBE Faculty and Staff

    Science.gov (United States)

    About Us Research Staff Edward Arens Fred Bauman Gail Brager Darryl Dickerhoff Ali Ghahramani Partners Facilities Graduate Programs Visiting Scholar Program Careers CBE Faculty and Staff CBE is an performance of buildings. The core research group for CBE includes faculty and research staff members

  3. NO to sacrificing future staff!

    CERN Multimedia

    Staff Association

    2011-01-01

    During our public meetings last week, we reviewed several subjects. However, the most urgent one today is the 2nd package of measures for our Pension Fund. In our previous issue, we devoted a long article to the Management’s plan for staff recruited from January 2012. A disaster! As we announced at our meetings, the Staff Association will organize a referendum at the beginning of April. For the message to be heard it is vital that as many staff as possible take part. By voting you will express your support to your staff representatives to stand in the way of these unacceptable measures. It is a matter of urgency that the staff makes their voice heard. Time is short, the decisions will be made in June. The future of our Organization is as stake. This is our future colleagues we are talking about. We must prevent this sacrifice. They must be welcomed in such a manner that there is no uneasiness between us. They must be made to feel welcome in their new family, CERN, our CERN. That they should pay an ...

  4. Memorandum of Understanding Between U.S. EPA Superfund and U.S. NRC

    International Nuclear Information System (INIS)

    Walker, Stuart

    2008-01-01

    The Environmental Protection Agency (EPA) Office of Superfund Remediation and Technology Innovation (OSRTI) and the Nuclear Regulatory Commission (NRC) are responsible for implementing the 'Memorandum of Understanding Between the Environmental Protection Agency and the Nuclear Regulatory Commission: Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites'. This paper provides a brief overview of the origin of the Memorandum of Understanding (MOU), the major features of the MOU, and how the MOU has been implemented site specifically. EPA and NRC developed the MOU in response to direction from the House Committee on Appropriations to EPA and NRC to work together to address the potential for dual regulation. The MOU was signed by EPA on September 30, 2002 and NRC on October 9, 2002. The two agencies had worked on the MOU since March 2000. While both EPA and NRC have statutory authority to clean up these sites, the MOU provides consultation procedures between EPA and NRC to eliminate dual regulation. Under the MOU, EPA and NRC identified the interactions of the two agencies for the decommissioning and decontamination of NRC-licensed sites and the ways in which those responsibilities will be exercised. Except for Section VI, which addresses corrective action under the Resource Conservation and Recovery Act (RCRA), this MOU is limited to the coordination between EPA, when acting under its CERCLA authority, and NRC, when a facility licensed by the NRC is undergoing decommissioning, or when a facility has completed decommissioning, and the NRC has terminated its license. EPA believes that implementation of the MOU between the two agencies will ensure that future confusion about dual regulation does not occur regarding the cleanup and reuse of NRC-licensed sites. NRC and EPA have so far exchanged MOU consultation letters on eight NRC-licensed sites. EPA has responded to each consultation request with a letter expressing its views on actions

  5. Human Factors Engineering Review Model for advanced nuclear power reactors

    International Nuclear Information System (INIS)

    O'Hara, J.; Higgins, J.; Goodman, C.; Galletti, G.: Eckenrode, R.

    1993-01-01

    One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model's rationale, scope, objectives, development, general characteristics. and application

  6. Elections to Staff Council

    CERN Multimedia

    Saff Association

    2013-01-01

    2013 Elections to Staff Council   Vote! Make your voice heard and be many to elect the new Staff Council. More details on the elections can be found on the Staff Association web site (https://ap-vote.web.cern.ch/elections-2013).   Timetable elections Monday 28 October to Monday 11 November, 12:00 am voting Monday 18 and Monday 25 November, publication of the results in Echo Tuesday 19 November, Staff Association Assizes Tuesday 3 December, first meeting of the new Staff Council and election of the new Executive Committee The voting procedure is monitored by the Election Committee.

  7. Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports

    Energy Technology Data Exchange (ETDEWEB)

    Fresco, A.; Subudhi, M.; Gunther, W.; Grove, E.; Taylor, J. [Brookhaven National Lab., Upton, NY (United States)

    1993-12-01

    A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of 67 of the reports issued on these in-depth team inspections were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant systems, structures, and components. Relevant information was extracted from these inspection reports and sorted into several categories, including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified. The information also was sorted according to systems and components, including: Auxiliary Feedwater, Main Feedwater, High Pressure Injection for both BWRs and PWRs, Service Water, Instrument Air, and Emergency Diesel Generator Air Start Systems, and Emergency Diesel Generators Air Start Systems, emergency diesel generators, electrical components such as switchgear, breakers, relays, and motor control centers, motor operated valves and check valves. This information was compared to insights gained from the Nuclear Plant Aging Research (NPAR) Program. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue also are discussed.

  8. Topical report review status

    International Nuclear Information System (INIS)

    1997-08-01

    This report provides industry with procedures for submitting topical reports, guidance on how the U.S. Nuclear Regulatory Commission (NRC) processes and responds to topical report submittals, and an accounting, with review schedules, of all topical reports currently accepted for review schedules, of all topical reports currently accepted for review by the NRC. This report will be published annually. Each sponsoring organization with one or more topical reports accepted for review copies

  9. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

    International Nuclear Information System (INIS)

    1980-02-01

    This first supplement to the second edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from April 1, 1978 to September 30, 1978 interpreting the NRC's Rules of Practice in 10 CFR Part 2. The supplement also includes additional material from adjudicatory decisions rendered prior to April 1, 1978 and, to a very limited degree, material from adjudicatory decisions and regulation changes after September 30, 1978. The supplement, which is intended to be used as a pocket-part supplement to the Digest itself, includes a number of new subsections and topics not covered in the Digest. The new subsections are noted in the index for the supplement

  10. United States Nuclear Regulatory Commission Staff Practice and Procedure Digest. Digest No. 2

    International Nuclear Information System (INIS)

    1978-08-01

    This second edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to March 31, 1978 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This second edition replaces the first edition and its supplements and includes appropriate changes reflecting the recent amendments to the Rules of Practice which became effective on May 26, 1978

  11. Risk-based regulation - an NRC perspective and status

    International Nuclear Information System (INIS)

    King, T.L.; Murphy, J.A.

    1993-01-01

    The consideration of risk in regulatory decision making has traditionally been part of the US Nuclear Regulatory Commission's (NRC's) policy and practice. In the early days of regulation, this consideration was more qualitative in nature and was reflected in prescriptive/deterministic regulatory requirements. However, with the development of quantitative risk assessment methods, more detailed and comprehensive (although not complete) risk information on nuclear power plants is available to the designer, operator, and regulator. The availability of such information provides an opportunity to assess the need for change in the current regulatory structure and to develop future regulatory requirements in a less prescriptive, more performance-oriented fashion

  12. Neutron spectral characterization of the NRC-HSST experiments

    International Nuclear Information System (INIS)

    Stallmann, F.W.; Kam, F.B.K.

    1979-01-01

    Irradiation experiments are being performed for the US Nuclear Regulatory Commission (NRC) Heavy Section Steel Technology (HSST) program. Results of dosimetry performed in the second experiment have been previously reported. Similar procedures were followed in the third experiment. The experiences gained in these two experiments have led to modifications in the composition and distribution of foil dosimeters which monitor the neutron flux-spectra in the irradiated steel specimens. It is expected that in the new experiments much higher accuracies than previously possible can be achieved in the determination of irradiation damage parameters

  13. Neutron spectral characterization of the NRC-HSST experiments

    Energy Technology Data Exchange (ETDEWEB)

    Stallmann, F. W.; Kam, F. B.K.

    1979-01-01

    Irradiation experiments are being performed for the US Nuclear Regulatory Commission (NRC) Heavy Section Steel Technology (HSST) program. Results of dosimetry performed in the second experiment have been previously reported. Similar procedures were followed in the third experiment. The experiences gained in these two experiments have led to modifications in the composition and distribution of foil dosimeters which monitor the neutron flux-spectra in the irradiated steel specimens. It is expected that in the new experiments much higher accuracies than previously possible can be achieved in the determination of irradiation damage parameters.

  14. NRC safety research in support of regulation, 1986

    International Nuclear Information System (INIS)

    1987-09-01

    This report is the second in a series of annual reports responding to congressional inquiries as to the utilization of nuclear regulatory research. NUREG-1175, ''NRC Safety Research in Support of Regulation,'' published in May 1986, reported major research accomplishments between about FY 1980 and FY 1985. This report narrates the accomplishments of FY 1986 and does not restate earlier accomplishments. Earlier research results are mentioned in the context of current results in the interest of continuity. Both the direct contributions to scientific and technical knowledge and their regulatory applications, when there has been a definite regulatory outcome during FY 1986, have been described

  15. Software for automated tracking of open items at NRC

    International Nuclear Information System (INIS)

    DeWispelare, A.R.; Mackin, P.C.; Johnson, R.L.

    1995-01-01

    The Open Item Tracking System (OITS) was developed in response to the Nuclear Regulatory Commission (NRC) need for a reliable, easy to use automated database system, to track all open (awaiting resolution) items related to regulatory, institutional, and technical uncertainties for the Department of Energy's (DOE's) high-level waste (HLW) disposal program. The OITS system was integrated with the Regulatory Program Database (RPD) Version 1.1, resulting in the RPD/OITS Version 2.0 system. RPD/OITS is a network bases system with client server architecture and a graphical user interface. This paper outlines the system and results of its implementation

  16. United State Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board, and Licensing Board decisions, July 1972--June 1988

    International Nuclear Information System (INIS)

    1989-04-01

    This fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 30, 1988 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This edition replaces in their entirety earlier editions and supplements and includes appropriate changes reflecting the amendments to the Rules of Practice effective through June 30, 1988

  17. United States Nuclear Regulatory Commission staff practice and procedure digest. Commission, Appearl Board and Licensing Board decisions, July 1972-June 1985. Digest No. 4

    International Nuclear Information System (INIS)

    1986-01-01

    This edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period July 1, 1972 to June 30, 1985 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This edition replaces earlier editions and supplements and includes appropriate changes reflecting the amendment to the Rules of Practice effective June 30, 1985

  18. A Review of Research on Direct-Care Staff Data Collection Regarding the Severity and Function of Challenging Behavior in Individuals with Intellectual and Developmental Disabilities

    Science.gov (United States)

    Madsen, Emily K.; Peck, Janelle A.; Valdovinos, Maria G.

    2016-01-01

    In working with individuals with intellectual and developmental disabilities (IDDs), it is direct care staff who are often required to collect data on individuals' behavior which is used as the basis for implementation of empirically based approaches for intervention and treatment. Due to limited resources, indirect and descriptive measures of…

  19. NRC proposes changes to nuke decommissioning funding rules

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The Nuclear Regulatory Commission (NRC) has proposed to amend its regulations to allow self-guarantee as a means of assuring adequate funding for nuclear plant decommissioning. It acted in response to a rulemaking petition filed by General Electric Co. and Westinghouse Electric Corp. The proposal would allow self-guarantees if certain conditions are met: Tangible net worth of at least $1 billion; Tangible net worth at least 10 times the present decommissioning cost estimate for all activities the utility is responsible for as a self-guaranteeing licensee and as parent guarantor; Domestic assets amounting to at least 90 percent of total assets or at least 10 times the present decommissioning cost estimate; A credit rating for the utility's most recent bond issuance of AAA, AA, or A (Standard ampersand Poor's), or Aaa, Aa, or A (Moody's). Additional requirements include that the utility licensee must have at least one class of equity securities registered under the Securities Exchange Act of 1934, and that an independent auditor must verify that the utility met the financial test. A utility also would be responsible for reporting any change in circumstances affecting the criteria used to meet the financial test, and would be responsible for meeting that test within 90 days of each financial year. The NRC will accept written comments until March 29, 1993

  20. MHTGR demonstration role in the NRC design certification process

    International Nuclear Information System (INIS)

    Kelley, A.P. Jr.; Jones, G.

    1986-01-01

    A modular high-temperature gas-cooled reactor (MHTGR) design is being developed by the US HTGR Program. Because of the small size of the individual modules that would make up a commercial facility, it appears feasible to design and construct a single-module demonstration plant within the funding constraints on the public and private-sector program participants. Furthermore, the safety margins that can be made inherent to the design permit full-scale testing that could supply a new basis for demonstrating investment protection and safety adequacy to the public, the US Nuclear Regulatory Commission (NRC), and potential users. With this in mind, a Project Definition Study was sponsored by Gas-Cooled Reactor Associates and the Tennessee Valley Authority to study the potential benefits of undertaking such a demonstration project. One of the areas investigated was the potential benefits of such a facility in supporting the NRC design certification process, which is envisioned as a necessary commercialization step for the MHTGR

  1. Analysis of NRC Regulatory Guide 1.21 Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Il; Yook, Dae Sik; Lee, Byung Soo [KINS, Daejeon (Korea, Republic of)

    2015-05-15

    It is essential to have a degree of uniformity in the methods used for measuring, evaluating, recording, and reporting data on radioactive material in effluents and solid wastes. For this purpose, the U.S. Nuclear Regulatory Commission (NRC) released a revised version of the Regulatory Guide 1.21 'Measuring, evaluating, and reporting radioactive material in liquid and gaseous effluents and solid waste' (revision 2) in 2009, updating the revision 1 version released in 1974. This study compares the previous revision 1 (1974) version with the revision 2 (2009) version to elaborate on the application of the guidelines to Korea. This study consists of an analysis of the 2009 Revision 2 version of the U.S. NRC Regulatory Guidelines 1.21 and an exposition of methods for its application in the domestic environment. Major revisions were made to allow for the adoption of a risk informed approach. Radionuclides with lower than 1% contribution to emission or radiation levels can be selected as principal radionuclides. Requirements for analysis of leaks and spills have been reinforced, with additional groundwater monitoring and hydrological data analysis becoming necessary.

  2. NRC Information No. 90-23: Improper installation of Patel conduit seals

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    On November 6, 1989, the staff at the H.B. Robinson plant notified the NRC that they had discovered that some of the conduit seal grommets used to seal insulated wire conductors entering environmentally qualified instrument housings were oversized for the application. The seals are used to prevent moisture from entering safety-related electrical components following loss-of-coolant accidents. The problem was attributed to inadequate installation instructions that were used when the seals were installed in 1986 and 1987. These instructions listed the grommets by wire gauge size and gave maximum wire insulation diameters for each wire size. In accordance with these instructions, the seals were selected based on wire gauge alone. However, since the insulation thickness for a given wire gauge the correct grommet size would have been the minimum wire insulation diameter for which a particular grommet will achieve an effective seal. The selection of grommet size based only on wire gauge size resulted in the installation of some grommets that were too large to provide an effective seal. As a result, some of the seals failed pressure tests that were designed to simulate post-LOCA pressures. During the investigation of the grommet leakage problem, the Robinson staff also checked the torque on the conduit seal union nuts that are used to compress the seals. EGS Corporation recommends that the union nuts be torqued to 50 ft-lb. On approximately half of the 90 seals inspected, the union nut moved about 1/4 inch when this torque was applied. EGS Corporation reports that 1/4 inch of movement does not necessarily indicate a degraded seal but recommends that the correct torque be verified on a representative sample of installed conduit seals

  3. Managing aging in nuclear power plants: Insights from NRC's Maintenance Team Inspection reports

    International Nuclear Information System (INIS)

    Fresco, A.; Subudhi, M.

    1992-01-01

    A plant's maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of sixty-seven of the reports issued on these in-depth team inspections have been reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant structures, systems, and components (SSCs). Relevant information has been extracted from these inspection reports sorted into several categories; including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified

  4. Annual technical meeting of the NRC cooperative severe accident research program

    International Nuclear Information System (INIS)

    Silver, E.G.

    1993-01-01

    This brief report summarizes the 1992 annual technical meeting of the NRC Cooperative Severe Accident Research Program (CSARP-92) held at the Hyatt Regency Hotel in Bethesda, Maryland, May 4-8, 1992. The report is taken mainly from coverage of the meeting published in the June 5, 1992, issue of Atomic Energy Clearinghouse. Results of this meeting are formalized at the Water Reactor Safety Information Meetings (WRSIM) that are held annually in October. Nuclear Safety summarizes the annual WRSIM meetings and provides a list of the presentations that were given. Interested readers are encouraged to review listed topics to identify specific topic areas in severe accident research. Sessions were held on in-vessel core melt progression; fuel-coolant interactions; fission-product behavior; direct containment heating; and severe accident code development, assessment, and validation. Summaries of the individual technical sessions and the current state of the art in these areas were given by the chairmen

  5. NRC Information No. 88-98: Electrical relay degradation caused by oxidation of contact surfaces

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    The NRC staff was recently informed by Clinton Power Station that a reactor scram on June 24, 1988, was caused by an electrical relay failure from oxide buildup on relay contact surfaces. Other information on relay failure from contact oxidation indicates that this problem may be more prevalent than previously thought. For example, a July 17, 1988, 10 CFR Part 21 report from Palo Verde, Unit 2, reported relay failures from contact oxidation that were due to the low current application of the relays. The relay contact surfaces in both of these examples are silver-nickel alloys, and both applications were for low current (i.e., milli-ampere current). Electrical relay contacts made of silver-nickel or silver-cadmium alloys will oxidize (tarnish) when used in low current applications because of the absence of contact surface sparking from the typical relay contact ''making and breaking'' functions. The sparking in the contact surfaces promotes a self-cleaning mechanism that reduces the tarnish buildup on the silver-nickel or silver-cadmium contacts. Discussions with one relay manufacturer revealed that the normal industry practice for low current circuit applications is either to use a contact surface material that will not oxidize or to compensate for the oxidation by increased maintenance activities to ensure reliability. The applied voltage may also influence contact oxidation

  6. Pilot program: NRC severe reactor accident incident response training manual: US Nuclear Regulatory Commission response

    International Nuclear Information System (INIS)

    Sakenas, C.A.; McKenna, T.J.; Perkins, K.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

    1987-02-01

    This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. US Nuclear Regulatory Commission Response is the fifth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes NRC response modes, organizations, and official positions; roles of other federal agencies are also described briefly. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

  7. Peru; Third Review and Inflation Consultation Under the Stand-By Arrangement and Request for Waiver of Applicability of Performance Criteria: Staff Report; Staff Supplement; Press Release on the Executive Board Discussion; and Statement by the Executive Director for Peru

    OpenAIRE

    International Monetary Fund

    2008-01-01

    This paper discusses key findings of the Third Review for Peru and Inflation Consultation Under the Stand-By Arrangement. All performance criteria for end-December 2007 and end-March 2008 were observed, but inflation in March exceeded the upper limit of the program’s consultation band around the official inflation target range. The end-March structural benchmark was observed and progress has been made on end-June benchmarks. The outlook for 2008 remains favorable, with the economy continuing ...

  8. Research Staff | Bioenergy | NREL

    Science.gov (United States)

    Research Staff Research Staff Photo of Adam Bratis, Ph.D. Adam Bratis Associate Lab Director-Bio research to accomplish the objectives of the Department of Energy's Bioenergy Technologies Office, and to serve as a spokesperson for the bioenergy research effort at NREL, both internally and externally. This

  9. Elections to Staff Council

    CERN Multimedia

    Staff Association

    2011-01-01

    Elections to fill all seats in the Staff Council are being organized this month. The voting takes place from the 31st of October to the 14th of November, at noon. As you may have noted when reading Echo, many issues concerning our employment conditions are on the agenda of the coming months and will keep the next Staff Council very busy. So, make your voice heard and take part in the elections for a new Staff Council. By doing so, you will be encouraging the men and women who will be representing you over the next two years and they will doubtless appreciate your gratitude. Every member of the Staff Association will have received an email containing a link to the webpage which will allow voting. If you are a member of the Staff Association and you did not receive such an email, please contact the Staff Association secretariat (staff.association@cern.ch). Do not forget to vote * * * * * * * Vote Make your voice heard and be many to elect the new Staff Council. More details on the election...

  10. 75 FR 8412 - Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of...

    Science.gov (United States)

    2010-02-24

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0047] Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of Accidental Radionuclide Releases; Solicitation of Public... ground water flow and transport of accidental radionuclide releases necessary to demonstrate compliance...

  11. Decentralized Ground Staff Scheduling

    DEFF Research Database (Denmark)

    Sørensen, M. D.; Clausen, Jens

    2002-01-01

    scheduling is investigated. The airport terminal is divided into zones, where each zone consists of a set of stands geographically next to each other. Staff is assigned to work in only one zone and the staff scheduling is planned decentralized for each zone. The advantage of this approach is that the staff...... work in a smaller area of the terminal and thus spends less time walking between stands. When planning decentralized the allocation of stands to flights influences the staff scheduling since the workload in a zone depends on which flights are allocated to stands in the zone. Hence solving the problem...... depends on the actual stand allocation but also on the number of zones and the layout of these. A mathematical model of the problem is proposed, which integrates the stand allocation and the staff scheduling. A heuristic solution method is developed and applied on a real case from British Airways, London...

  12. New staff contract policy

    CERN Document Server

    HR Department

    2006-01-01

    Following discussion at TREF and on the recommendation of the Finance Committee, Council approved a new staff contract policy, which became effective on 1 January 2006. Its application is covered by a new Administrative Circular No. 2 (Rev. 3) 'Recruitment, appointment and possible developments regarding the contractual position of staff members'. The revised circular replaces the previous Circulars No. 9 (Rev. 3) 'Staff contracts' and No. 2 (Rev. 2) 'Guidelines and procedures concerning recruitment and probation period for staff members'. The main features of the new contract policy are as follows: The new policy provides chances for long-term employment for all staff recruits staying for four years without distinguishing between those assigned to long-term or short-term activities when joining CERN. In addition, it presents a number of simplifications for the award of ICs. There are henceforth only 2 types of contract: Limited Duration (LD) contracts for all recruitment and Indefinite Contracts (IC) for...

  13. Background as a residual radioactivity criterion for decommissioning: Appendix A to the Generic Environmental Impact Statement in support of rulemaking on radiological criteria for decommissioning of NRC-licensed nuclear facilities. Draft report

    International Nuclear Information System (INIS)

    Huffert, A.M.; Meck, R.A.; Miller, K.M.

    1994-08-01

    This report was originally published as an appendix to the draft U.S. Nuclear Regulatory Commission (NRC) document entitled, open-quotes Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for Decommissioning of NRC-Licensed Nuclear Facilities.close quotes Because of the great interest in this report by members of the public, citizen and environmental organizations, academicians, licensees, and regulators, the NRC staff is publishing this report separately, so that it can be readily available to a diverse audience. This report was created to assist both the NRC staff and interested members of the public in evaluating background radiation (background) as a decommissioning criterion, by serving as a primer on background and providing information on the existing applications of background in regulatory criteria and standards. This report also discusses some of the methods available to measure and distinguish between the very low radiation levels associated with background and man-made sources of radiation. Two approaches are considered for applying background as a decommissioning criterion; these are the use of background dose rates and background radionuclide concentrations. This report concludes that the temporal and spatial variability of background produces a wide range of doses to United States residents, which prevents the application of background dose rates as a decommissioning criterion. Instead, this report recommends that local background radionuclide concentrations serve as a benchmark for decommissioning criteria, while taking into account the concept of reducing residual radioactivity to a level as low as is reasonably achievable

  14. NRC safety research in support of regulation, FY 1991

    International Nuclear Information System (INIS)

    1992-04-01

    This report, the seventh in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1991. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  15. NRC safety research in support of regulation, FY 1990

    International Nuclear Information System (INIS)

    1991-04-01

    This report, the sixth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1990. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  16. NRC safety research in support of regulation--FY 1989

    International Nuclear Information System (INIS)

    1990-04-01

    This report, the fifth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1989. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  17. The development of the advanced cryogenic radiometer facility at NRC

    Science.gov (United States)

    Gamouras, A.; Todd, A. D. W.; Côté, É.; Rowell, N. L.

    2018-02-01

    The National Research Council (NRC) of Canada has established a next generation facility for the primary realization of optical radiant power. The main feature of this facility is a new cryogenic electrical substitution radiometer with a closed-cycle helium cryocooler. A monochromator-based approach allows for detector calibrations at any desired wavelength. A custom-designed motion apparatus includes two transfer standard radiometer mounting ports which has increased our measurement capability by allowing the calibration of two photodetectors in one measurement cycle. Measurement uncertainties have been improved through several upgrades, including newly designed and constructed transimpedance amplifiers for the transfer standard radiometers, and a higher power broadband light source. The most significant improvements in uncertainty arise from the enhanced characteristics of the new cryogenic radiometer including its higher cavity absorptance and reduced non-equivalence effects.

  18. NRC safety research in support of regulation, 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This report, the fourth in a series of annual reports, was prepared in response to Congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during 1988. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

  19. Optimisation of staff protection

    International Nuclear Information System (INIS)

    Faulkner, K.; Marshall, N.W.; Rawlings, D.J.

    1997-01-01

    It is important to minimize the radiation dose received by staff, but it is particularly important in interventional radiology. Staff doses may be reduced by minimizing the fluoroscopic screening time and number of images, compatible with the clinical objective of the procedure. Staff may also move to different positions in the room in an attempt to reduce doses. Finally, staff should wear appropriate protective clothing to reduce their occupational doses. This paper will concentrate on the optimization of personal shielding in interventional radiology. The effect of changing the lead equivalence of various protective devices on effective dose to staff has been studied by modeling the exposure of staff to realistic scattered radiation. Both overcouch x-ray tube/undercouch image intensified and overcouch image intensifier/undercouch x-ray tube geometries were simulated. It was deduced from this simulation that increasing the lead apron thickness from 0.35 mm lead to 0.5 mm lead had only a small reducing effect. By contrast, wearing a lead rubber thyroid shield or face mask is a superior means of reducing the effective dose to staff. Standing back from the couch when the x-ray tube is emitting radiation is another good method of reducing doses, being better than exchanging a 0.35 mm lead apron for a 0.5 mm apron. In summary, it is always preferable to shield more organs than to increase the thickness of the lead apron. (author)

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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