WorldWideScience

Sample records for reviewing license applications

  1. Review process for license renewal applications

    International Nuclear Information System (INIS)

    Craig, John W.; Kuo, P.T.

    1991-01-01

    In preparation for license renewal reviews, the Nuclear Regulatory Commission has recently published for public review and comment a proposed rule for license renewal and a draft Standard Review Plan as well as a draft Regulatory Guide relating to the implementation of the proposed rule. In support of future license renewal applications, the nuclear industry has also submitted 11 industry reports for NRC review and approval. This paper briefly describe how these parallel regulatory and industry activities will be factored into the NRC review process for license renewal. (author)

  2. 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

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

    Science.gov (United States)

    2012-04-10

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

  6. Generic licensing issues applicable to Wolsong 3 and 4 licensing review

    International Nuclear Information System (INIS)

    Boyd, Frederick C.

    1994-01-01

    The Wolsong 3 and 4 nuclear power plants are of CANDU type which were designed according to the rules and regulations of the Atomic Energy Control Board (AECB) of Canada. In 1992 AECB staff issued a first formal report (to the AECB Board) on 'generic safety issues affecting power reactors'. This was followed by a second report in 1993. These reports dealt with safety issues associated with Canadian CANDU nuclear power plants that applied to all or several plants and were considered insufficiently resolved. In most cases the concern was lack of certainty in the related safety analyses. The AECB staff report of 1993 identified eight 'generic action items' and six 'long-term research issues', three of which AECB staff have indicated may be moved into the 'action' category. This report, prepared for the Korea Institute of Nuclear Safety (KINS), reviews the background of the AECB 'generic action items' and the three 'long-term research issues' noted above. It also reviews an additional topic - steam line failure outside of containment - which was included in the request from KINS. In all, twelve issues are covered. These background reviews are followed by a discussion of the relevance of each issue to the licensing review (for Construction Permit) of Wolsong 3 and 4 and recommended actions to be taken by KINS

  7. Preparing to review the license application of the French geological disposal facility - Issues, challenges and perspectives

    International Nuclear Information System (INIS)

    Dandrieux, Geraldine

    2014-01-01

    This paper briefly describes the French context for GDR authorization, the French dedicated legislative framework (28 June 2006 Act on sustainable management of radioactive materials and waste), the challenges (regulatory issues, long-term project supervision, technical issues, procedural issues), and the preparing for the review of the DGR license application. A planning schedule is propose with Andra to submit license application for DGR in 2015

  8. 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

  9. 76 FR 63668 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Science.gov (United States)

    2011-10-13

    ..., Research and Test Reactors Projects Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor... NUCLEAR REGULATORY COMMISSION [NRC-2011-0135] Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim...

  10. The regulatory review of construction license application and the supporting safety case

    International Nuclear Information System (INIS)

    Heinonen, Jussi

    2014-01-01

    Finland is one of the foremost countries in the world in developing the disposal of spent fuel. The construction license application for the Olkiluoto spent fuel disposal facility was submitted to the authorities at the end of 2012 and the facility is expected to start operation around 2020. This has been a long-term project with over 30 years of parallel development of the repository project and the regulatory approach to spent fuel management. In 1983 the government made a strategic decision on the objectives and target time schedule for the research, development and technical planning of nuclear waste management. While an export and international disposal solution was still the preferred option, this decision required the licensees without this possibility to prepare for disposal in Finland and it also gave the time line for the milestones on the way to an operating disposal facility by 2020. The licensing procedure for a disposal facility has several steps that are similar to all nuclear facilities in Finland and are defined in Nuclear Energy Act and Decree (1987, 1988). These licensing steps are: - Decision-in-principle is required for a nuclear facility having considerable general significance. This is essentially a political decision: the government decides if the construction project is in line with the overall good of society. The decision can be applied for one or more sites, the host municipality has a veto right and the parliament has the choice of ratifying or not ratifying the decision. - Construction license is granted by the government and authorises the construction of the disposal facility. The actual construction is regulated by STUK and includes several review and approval steps, hold points and viewpoints. - Operational license is granted by the government and authorises the operation of the facility for a certain period. The operational license is needed before nuclear waste can be disposed. The first step in the licensing process was reached

  11. Automation of the DoD Export License Application Review Process

    National Research Council Canada - National Science Library

    Young, Shelton

    2002-01-01

    .... The overall audit objective was to determine whether Federal automation programs supporting the export license and review process could be used to establish a common electronic interface creating...

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

    International Nuclear Information System (INIS)

    1994-04-01

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

  13. Product Licenses Database Application

    CERN Document Server

    Tonkovikj, Petar

    2016-01-01

    The goal of this project is to organize and centralize the data about software tools available to CERN employees, as well as provide a system that would simplify the license management process by providing information about the available licenses and their expiry dates. The project development process is consisted of two steps: modeling the products (software tools), product licenses, legal agreements and other data related to these entities in a relational database and developing the front-end user interface so that the user can interact with the database. The result is an ASP.NET MVC web application with interactive views for displaying and managing the data in the underlying database.

  14. 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

  15. 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

  16. 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

  17. 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

  18. Licensing an assured isolation facility for low-level radioactive waste. Volume 2: Recommendations on the content and review of an application

    Energy Technology Data Exchange (ETDEWEB)

    Silverman, D.J.; Bauser, M.A. [Morgan, Lewis and Bockius, Washington, DC (United States); Baird, R.D. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

    1998-07-01

    This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application.

  19. Licensing an assured isolation facility for low-level radioactive waste. Volume 2: Recommendations on the content and review of an application

    International Nuclear Information System (INIS)

    Silverman, D.J.; Bauser, M.A.; Baird, R.D.

    1998-07-01

    This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application

  20. How a regulator is preparing for reviewing a license application file: The case of ASN

    International Nuclear Information System (INIS)

    Tanguy, Loic

    2014-01-01

    The French Nuclear Safety Authority (ASN) is an independent administrative authority. It prepares regulation pertaining to the management of radioactive waste, monitors the control of safety of basic nuclear installations that produce or treat waste or are involved in their disposal and performs inspections of waste producers (EDF, AREVA, CEA, hospitals, research centres, etc.) and Andra, the French National Radioactive Waste Management Agency. It regulates the overall system set up by Andra for accepting waste from producers and assesses waste management policy and the practices of radioactive waste producers. It reviews license applications and authorises commissioning of nuclear installations. In order to review technical documents, ASN benefits from the expertise of technical support organisations. The French Institute for Radiation Protection and Nuclear Safety (IRSN) is the main such organisation. ASN has been making efforts to diversify its experts for several years. In preparing its decisions, ASN also calls on the opinions and recommendations of seven Advisory Committees of Experts (GPE), with expert knowledge in the areas of waste, nuclear pressure equipment, medical exposure, non-medical radiation protection, reactors, transport, and laboratories and nuclear plants. ASN consults the GPEs in preparing its main decisions. In particular, they review the preliminary, provisional and final safety analysis reports for each nuclear installation. They can also be consulted about changes in regulations or doctrine. (authors)

  1. IRIS pre-application licensing

    International Nuclear Information System (INIS)

    Carelli, Mario D.; Kling, Charles L.; Ritterbusch, Stanley E.

    2003-01-01

    This paper presents the approach to pre-application licensing by the International Reactor Innovative and Secure (IRIS), and advanced, integral reactor design with a thermal power of 1000 MW. The rationale for the pre-application licensing is discussed. Since IRIS technology is based on proven LWR experience, the project will rely on AP600/AP1000 precedent and will focus during the pre-application on long lead and novel items. A discussion of the evolution of the project to significantly reduce licensing issues is provided, followed by a summary of the IRIS safety-by-design which provides a formidable first step in the Defense in Depth approach. The effects of the safety-by-design, as well as of passive systems, on the IRIS safety will be investigated in a proposed testing program that will be reviewed by NRC during the pre-application. Documentation to be provided to NRC is discussed. Early design analyses indicate that the benefits of the IRIS safety-by-design approach are so significant that the basic premise of current emergency planning regulations (i.e., likelihood of core damage) will be reduced to the extent that special emergency response planning beyond the exclusion area boundary may not be needed. How this very significant outcome can be effected through a highly risk-informed licensing is discussed. (author)

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

    International Nuclear Information System (INIS)

    1987-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

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

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

    International Nuclear Information System (INIS)

    1988-01-01

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

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

    International Nuclear Information System (INIS)

    1987-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

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

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

    International Nuclear Information System (INIS)

    1996-02-01

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

  8. Teacher License Reciprocity. 50-State Review

    Science.gov (United States)

    Aragon, Stephanie

    2017-01-01

    This policy report defines and provides a 50-state review of teacher license reciprocity, explores how state-specific licensing requirements impact the teacher labor market, and includes examples of national and state efforts to facilitate reciprocity.

  9. A review of tritium licensing requirements

    International Nuclear Information System (INIS)

    Meikle, A.B.

    1982-12-01

    Present Canadian regulations and anticipated changes to these regulations relevant to the utilization of tritium in fusion facilities and in commercial applications have been reviewed. It is concluded that there are no serious licensing obstacles, but there are a number of requirements which must be met. A license will be required from Atomic Energy Control Board if Ontario Hydro tritium is to be applied by other users. A license is required from the Federal Government to export or import tritium. A licensed container will be required for the storage and shipping of tritium. The containers being designed by AECL and Ontario Hydro and which are currently being tested will adequately store and ship all of the Ontario Hydro tritium but are unnecessarily large for the small quantities required by the commercial tritium users. Also, some users may prefer to receive tritium in gaseous form. An additional, smaller container should be considered. The licensing of overseas fusion facilities for the use of tritium is seen as a major undertaking offering opportunities to Canadian Fusion Fuels Technology Project to undertake health, safety and environmental analysis on behalf of these facilities

  10. 14 CFR 431.73 - Continuing accuracy of license application; application for modification of license.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Continuing accuracy of license application; application for modification of license. 431.73 Section 431.73 Aeronautics and Space COMMERCIAL SPACE... Conditions § 431.73 Continuing accuracy of license application; application for modification of license. (a...

  11. Development of radioactive waste management licensing review assistant

    International Nuclear Information System (INIS)

    Wei-Whua Loa; Suan Chen; Wei-Chu Yu

    1992-01-01

    Regulations on radioactive waste disposal are now in urgent need due to our increasing consumption of electric power from nuclear origin. It is set forth that actually applying the regulations to evaluate the license application of new repositories for interim storage and final disposal of High-Level Waste and Low-Level Waste before the year of 2000. In the mean time, it is expected to establish the basis for the decision on issuing the license. The license review procedure can be very complicated, because too many factors must be taken into consideration. For the time being, licensing review is as much an art as it is a science. The authority usually faces three major problems; (1) the availability of domain expert, (2) maintaining of high quality and consistent reviews, and (3) the documentation of the review process. However, to maintain a more efficient, accurate, and systematic review procedure, and at the same time to reduce costs, the Artificial Intelligence (AI) techniques may be used. An expert system is designed as a radioactive waste management licensing review aid for the staff those are in charge of the license application. Tasks such as completeness checking, functional areas of review distribution, participation confirmation, knowledge acquisition, review comment collection, weighting calculation, and degree of satisfaction are considered. In this paper we will discuss the development of the radioactive waste management licensing review assistant

  12. Application of up-front licensing

    International Nuclear Information System (INIS)

    Grant, S.D.; Snell, V.G.

    1995-01-01

    AECL has been pioneering 'up-front' licensing of new reactor designs. The CANDU 3 design has been formally reviewed by AECB staff for a number of years. The CANDU 9 design has just started the up-front licensing process. The process gives designers, regulators and potential customers early confidence in the licensability of future plants. (author). 4 refs., 2 tabs

  13. Application of up-front licensing

    Energy Technology Data Exchange (ETDEWEB)

    Grant, S D [Atomic Energy of Canada Ltd., Saskatoon, SK (Canada); Snell, V G [Atomic Energy of Canada Ltd., Mississauga, ON (Canada)

    1996-12-31

    AECL has been pioneering `up-front` licensing of new reactor designs. The CANDU 3 design has been formally reviewed by AECB staff for a number of years. The CANDU 9 design has just started the up-front licensing process. The process gives designers, regulators and potential customers early confidence in the licensability of future plants. (author). 4 refs., 2 tabs.

  14. Methodology to identify, review, and evaluate components for license renewal

    International Nuclear Information System (INIS)

    Carlson, D.D.; Gregor, F.E.; Walker, R.S.

    1988-01-01

    A methodology has been developed to systematically identify, review, and evaluate plant equipment for license renewal. The method builds upon the existing licensing basis, operating history, and accepted deterministic and probabilistic techniques. Use of these approaches provides a focus for license renewal upon those safety-significant systems and components that are not routinely replaced, refurbished, or subject to detailed inspection as part of the plant's existing test, maintenance, and surveillance programs. Application of the method identified the PWR and BWR systems that should be subjected to detailed license renewal review. Detailed examination of two example systems demonstrates the approach. The review and evaluation of plant equipment for license renewal differ from the initial licensing of the plant. A substantial operating history has been established, the licensing basis has evolved from the original one, and plant equipment has been subject to periodic maintenance and surveillance throughout its life. In consideration of these differences, a basis for license renewal is needed. License renewal should be based upon continuation of the existing licensing basis and recognition of existing programs and operating history

  15. 15 CFR 748.9 - Support documents for license applications.

    Science.gov (United States)

    2010-01-01

    ... licensing action, since end-uses and other considerations are important factors in the decision making... promptly notifying BIS of any change in the facts contained in the support document that comes to your attention. (h) Effect on license application review. BIS reserves the right in all respects to determine to...

  16. Preparing as an organization, to submit or to review a construction license application for a DGR of ILW and HLW in France. French National Case - Andra - Preparing to Submit Cigeo's Creation License Application

    International Nuclear Information System (INIS)

    Boissier, Fabrice; Labalette, T.; Leverd, Pascal C.; Voinis, Sylvie

    2014-01-01

    The reversible repository in a deep geological formation is the French reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste. Since the first French Act on nuclear waste management research (1991), Andra has carried out twenty years of conceptual and basic studies on the subject, leading in particular to the feasibility demonstration in 2005 and to the choice of the detailed reconnaissance zone (ZIRA) in 2010. Taking advantage from this work, Andra has now reached a new phase where the project is engaging in the design of the industrial installation named Cigeo. At this stage, the further development of the project implies that Andra undertakes a multiplicity of actions in order to successfully reach various external and internal key milestones. Of paramount importance is the careful articulation between the regulatory authorization and decision processes and the outcome of the industrial installation design phases. In 2006 was built a regulatory framework that plans a succession of step by step decisions stages: 2013: Public debate on reversibility, memory keeping, environmental and health survey modalities, dialogue with the local stakeholders to harmoniously define and plan the external infrastructures that have to be developed to support the construction and the operation of Cigeo (roads, railway tracks and terminal, power and water supplies, etc.). 2015: Creation license application and start of the regulatory review process (notably various plans of the installation, the description of the solution envisaged for the closure of the facility, the preliminary safety case (operational safety, long-term safety, protection against malevolent actions, management of incidental situations, preliminary acceptance criteria), environmental impact studies (health, salubrity, transports, human activities, nature, patrimonial aspects). 2016-2017: new parliamentary Act on the reversibility conditions of the

  17. Development of radioactive waste management licensing review assistant

    International Nuclear Information System (INIS)

    Loa, W.W.; Chen, S.; Yu, W.C.; Peng, C.M.; Huang, C.L.; Lin, C.

    1992-01-01

    Regulations on radioactive waste disposal are now in urgent need due to our increasing consumption of electric power from nuclear origin. It is set forth that actually applying the regulations to evaluate the license application of new repositories for interim storage and final disposal fo High-Level Waste and Low-Level Waste before the year of 2000. In the mean time, it is expected to establish the basis for the decision on issuing the license. The license review procedure can be very complicated because too many factors must be taken into consideration. However, to maintain a more efficient, accurate, and systematic review procedure, and at the same time to reduce costs, the Artificial Intelligence (AI) techniques may be used. An expert system is designed as a radioactive waste management licensing review aid for the staff those are in charge of the license application. Tasks such as completeness checking, functional areas of review distribution, participation confirmation, knowledge acquisition, review comment collection, weighting calculation, and degree of satisfaction are considered. In this paper the authors will discuss the development of the radioactive waste management licensing review assistant

  18. Decentralization of operating reactor licensing reviews: NRR Pilot Program

    International Nuclear Information System (INIS)

    Hannon, J.N.

    1984-07-01

    This report, which has incorporated comments received from the Commission and ACRS, describes the program for decentralization of selected operating reactor licensing technical review activities. The 2-year pilot program will be reviewed to verify that safety is enhanced as anticipated by the incorporation of prescribed management techniques and application of resources. If the program fails to operate as designed, it will be terminated

  19. The Swedish radiological environmental protection regulations applied in a review of a license application for a geological repository for spent nuclear fuel.

    Science.gov (United States)

    Andersson, Pål; Stark, Karolina; Xu, Shulan; Nordén, Maria; Dverstorp, Björn

    2017-11-01

    For the first time, a system for specific consideration of radiological environmental protection has been applied in a major license application in Sweden. In 2011 the Swedish Nuclear Fuel & Waste Management Co. (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel at the Forsmark site. The license application is supported by a post-closure safety assessment, which in accordance with regulatory requirements includes an assessment of environmental consequences. SKB's environmental risk assessment uses the freely available ERICA Tool. Environmental media activity concentrations needed as input to the tool are calculated by means of complex biosphere modelling based on site-specific information gathered from site investigations, as well as from supporting modelling studies and projections of future biosphere conditions in response to climate change and land rise due to glacial rebound. SKB's application is currently being reviewed by the Swedish Radiation Safety Authority (SSM). In addition to a traditional document review with an aim to determine whether SKB's models are relevant, correctly implemented and adequately parametrized, SSM has performed independent modelling in order to gain confidence in the robustness of SKB's assessment. Thus, SSM has used alternative stylized reference biosphere models to calculate environmental activity concentrations for use in subsequent exposure calculations. Secondly, an alternative dose model (RESRAD-BIOTA) is used to calculate doses to biota that are compared with SKB's calculations with the ERICA tool. SSM's experience from this review is that existing tools for environmental dose assessment are possible to use in order to show compliance with Swedish legislation. However, care is needed when site representative species are assessed with the aim to contrast them to generic reference organism. The alternative modelling of environmental concentrations resulted in much lower

  20. Issues in the review of a license application for an above grade low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Ringenberg, J.D. [Nebraska Dept. of Environmental Quality, NE (United States)

    1993-03-01

    In December 1987, Nebraska was selected by the Central Interstate Compact (CIC) Commission as the host state for the construction of a low-level radioactive waste disposal facility. After spending a year in the site screening process, the Compact`s developer, US Ecology, selected three sites for detailed site characterization. These sites were located in Nemaha, Nuckolls and Boyd Counties. One year later the Boyd County site was selected as the preferred site and additional site characterization studies were undertaken. On July 29, 1990, US Ecology submitted a license application to the Nebraska Department of Environmental Control (now Department of Environmental Quality-NDEQ). This paper will present issues that the NDEQ has dealt with since Nebraska`s selection as the host state for the CIC facility.

  1. License application approach for the California LLRW disposal facility

    International Nuclear Information System (INIS)

    Gaynor, R.K.; Romano, S.A.; Hanrahan, T.P.

    1990-01-01

    US Ecology, Inc. is the State of California's license designee to site, develop and operate a low-level radioactive waste (LLRW) disposal facility to serve member states of the Southwestern Compact. US Ecology identified a proposed site in the Ward Valley of southeastern California in March 1988. Following proposed site selection, US Ecology undertook studies required to prepare a license application. US Ecology's license application for this desert site was deemed complete for detailed regulatory review by the California Department of Health Services (DHS) in December 1989. By mutual agreement, disposal of mixed waste is not proposed pending the State of California's decision on appropriate management of this small LLRW subset

  2. Aging management review for license renewal and plant life management

    International Nuclear Information System (INIS)

    Rinckel, M.A.; Young, G.G.

    2002-01-01

    Full text: United States nuclear power plants are initially licensed for a period of 40-years. The 40-year term, which was established by the Atomic Energy Commission in the 1950s, is believed to be based on engineering judgement and is consistent with the typical amortization schedule for purchasing fossil power plants. Under 10 CFR Part 54, the license renewal rule, additional terms of 20-years may be obtained through the preparation of a license renewal application that must be reviewed and approved by the Nuclear Regulatory Commission (NRC). The license renewal rule requires that applicants perform ageing management reviews on passive long-lived structures and components to demonstrate that ageing will be managed during the period of extended operation (i.e., additional 20 years of operation). ageing of active components, which are excluded from 10 CFR Part 54, is accomplished through the Maintenance Rule, 10 CFR Part 65, using performance-based monitoring. The license renewal rule, 10 CFR Part 54, was initially published in 1991. After significant interaction with the nuclear industry from 1991 through 1994, the NRC revised the rule in 1995 to focus on passive long-lived structures and components. In 1998, the first two applications for license renewal were submitted to the NRC by Baltimore Gas and Electric for the two-unit Calvert Cliffs nuclear power plant and by Duke Energy for the three-unit Oconee nuclear power plant. In March 2000, the NRC approved the application for the two-unit Calvert Cliffs nuclear power plant for an additional 20 years. Two months later, the NRC approved the renewal of the operating licenses for the three-unit Oconee nuclear station. The NRC completed these reviews in a timely, predictable, and stable manner. As of February 2002, the NRC has approved renewal of operating licenses for eight nuclear units and has applications under review for 15 more units. Twelve additional companies have notified the NRC of their intention to seek

  3. 21 CFR 515.10 - Medicated feed mill license applications.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 6 2010-04-01 2010-04-01 false Medicated feed mill license applications. 515.10... (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Applications § 515.10 Medicated feed mill license applications. (a) Medicated feed mill license applications (Forms FDA 3448) may...

  4. Personality traits of Turkish handgun license applicants.

    Science.gov (United States)

    Selek, Salih; Can, Serdar S; Yabanoglu, Ihsan

    2012-10-01

    Several theories have sought to explain the motivations for handgun possession and the relationship with personality. Perception of handguns also has cultural variations. The aim of the study is to evaluate handgun license applicants' personality profiles. 109 handgun license applicants were included in the study. Temperament and Character Inventory (TCI) scores of the applicants were recorded. Scores were compared with Turkish and American normative data for the Inventory. The study group had significantly lower subscores on novelty seeking, harm avoidance, and higher subscores on reward dependence and persistence compared to Turkish norms and significantly lower subscores on novelty seeking, reward dependence, and self-directedness compared to American norms. Results indicate that Turkish handgun license applicants' personality features are more similar to American norms.

  5. The post-closure radiological safety case for a spent fuel repository in Sweden - An international peer review of the SKB license-application study of March 2011

    International Nuclear Information System (INIS)

    2012-01-01

    Sweden is at the forefront among countries developing plans for a deep geological repository of highly radioactive waste. There is no such repository in operation yet worldwide, but Sweden, Finland and France are approaching the licensing stage. At the request of the Swedish government, the NEA organised an international peer review of the post-closure radiological safety case produced by the Swedish Nuclear Fuel and Waste Management Company (SKB) in support of the application for a general licence to construct and operate a spent nuclear fuel geological repository in the municipality of Oesthammar. The purpose of the review was to help the Swedish government, the public and relevant organisations by providing an international reference regarding the maturity of SKB's spent fuel disposal programme vis-a-vis best practices in long-term disposal safety and radiological protection. The International Review Team (IRT) consisted of ten international specialists, who were free of conflict of interest with the SKB and brought complementary expertise to the review. This report provides the background and findings of the international peer review. The review's findings are presented at several levels of detail in order to be accessible to both specialist and non-specialist readers

  6. Licensing and accident reviews for an HNEC

    International Nuclear Information System (INIS)

    Clark, R.G.

    1978-09-01

    The purpose of this review was to identify siting or other concerns that may indicate limitations on the ability to license a nuclear energy center at Hanford. Several studies on nuclear energy centers have been completed and some have included licensing (regulatory) aspects of siting nuclear power centers. This review however, was primarily to identify any limitations that may affect licensing specifically at an HNEC. The scope included examining existing criteria for siting nuclear facilities, including single reactor and multireactor (multi-unit) sites. To fill a void in other analyses and to gain some perspective on another impact of an HNEC, the scope was extended to analyze the consequences within the HNEC, of a class nine accident at a unit at one site. A predictive model utilized in this analysis was developed from meteorological parameters based on thirty years of meteorological records at Hanford. From this analysis, additional perspective was developed on the relative severity of the effects of rare events, both man made and from unstable conditions in nature, on the operation of (and the ability to license) an energy center at Hanford

  7. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    1993-11-01

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards

  8. 75 FR 46938 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-08-04

    ... Logistics LLC (NVO), 120 S. Woodland Blvd., 216, DeLand, FL 32720, Officers: Dietmar Lutte, Manager Member, (Qualifying Individual), Susan Lutte, Member, Application Type: New NVO License. Bridgeline Logistics..., (Qualifying Individual), Application Type: New OFF License. [[Page 46939

  9. Patterns of use and impact of standardised MedDRA query analyses on the safety evaluation and review of new drug and biologics license applications.

    Science.gov (United States)

    Chang, Lin-Chau; Mahmood, Riaz; Qureshi, Samina; Breder, Christopher D

    2017-01-01

    Standardised MedDRA Queries (SMQs) have been developed since the early 2000's and used by academia, industry, public health, and government sectors for detecting safety signals in adverse event safety databases. The purpose of the present study is to characterize how SMQs are used and the impact in safety analyses for New Drug Application (NDA) and Biologics License Application (BLA) submissions to the United States Food and Drug Administration (USFDA). We used the PharmaPendium database to capture SMQ use in Summary Basis of Approvals (SBoAs) of drugs and biologics approved by the USFDA. Characteristics of the drugs and the SMQ use were employed to evaluate the role of SMQ safety analyses in regulatory decisions and the veracity of signals they revealed. A comprehensive search of the SBoAs yielded 184 regulatory submissions approved from 2006 to 2015. Search strategies more frequently utilized restrictive searches with "narrow terms" to enhance specificity over strategies using "broad terms" to increase sensitivity, while some involved modification of search terms. A majority (59%) of 1290 searches used descriptive statistics, however inferential statistics were utilized in 35% of them. Commentary from reviewers and supervisory staff suggested that a small, yet notable percentage (18%) of 1290 searches supported regulatory decisions. The searches with regulatory impact were found in 73 submissions (40% of the submissions investigated). Most searches (75% of 227 searches) with regulatory implications described how the searches were confirmed, indicating prudence in the decision-making process. SMQs have an increasing role in the presentation and review of safety analysis for NDAs/BLAs and their regulatory reviews. This study suggests that SMQs are best used for screening process, with descriptive statistics, description of SMQ modifications, and systematic verification of cases which is crucial for drawing regulatory conclusions.

  10. Patterns of use and impact of standardised MedDRA query analyses on the safety evaluation and review of new drug and biologics license applications.

    Directory of Open Access Journals (Sweden)

    Lin-Chau Chang

    Full Text Available Standardised MedDRA Queries (SMQs have been developed since the early 2000's and used by academia, industry, public health, and government sectors for detecting safety signals in adverse event safety databases. The purpose of the present study is to characterize how SMQs are used and the impact in safety analyses for New Drug Application (NDA and Biologics License Application (BLA submissions to the United States Food and Drug Administration (USFDA.We used the PharmaPendium database to capture SMQ use in Summary Basis of Approvals (SBoAs of drugs and biologics approved by the USFDA. Characteristics of the drugs and the SMQ use were employed to evaluate the role of SMQ safety analyses in regulatory decisions and the veracity of signals they revealed.A comprehensive search of the SBoAs yielded 184 regulatory submissions approved from 2006 to 2015. Search strategies more frequently utilized restrictive searches with "narrow terms" to enhance specificity over strategies using "broad terms" to increase sensitivity, while some involved modification of search terms. A majority (59% of 1290 searches used descriptive statistics, however inferential statistics were utilized in 35% of them. Commentary from reviewers and supervisory staff suggested that a small, yet notable percentage (18% of 1290 searches supported regulatory decisions. The searches with regulatory impact were found in 73 submissions (40% of the submissions investigated. Most searches (75% of 227 searches with regulatory implications described how the searches were confirmed, indicating prudence in the decision-making process.SMQs have an increasing role in the presentation and review of safety analysis for NDAs/BLAs and their regulatory reviews. This study suggests that SMQs are best used for screening process, with descriptive statistics, description of SMQ modifications, and systematic verification of cases which is crucial for drawing regulatory conclusions.

  11. Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

    International Nuclear Information System (INIS)

    Wilmot, Roger D.

    2011-02-01

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

  12. 75 FR 72824 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-11-26

    ... & OFF License. Everglory Logistics, Inc. (NVO & OFF), 440 McClellan Highway, 105F2, East Boston, MA..., Application Type: New NVO & OFF License. Hawaii Intermodal Tank Transport, LLC (NVO & OFF), 2350 S. Dock... Tran, Manager, Application Type: New NVO & OFF License. ITL USA Inc. dba International Transport...

  13. 75 FR 80499 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-12-22

    ... Individual), Jeffrey Cullen, President. Application Type: QI Change. Cala Distribution, LLC (NVO), 2705 NW..., (Qualifying Individual), William S. Askew, Manager. Application Type: New NVO License. Encar Trading, Corp...

  14. 78 FR 20106 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-04-03

    ... M. Tsai, President (QI). Application Type: New NVO License. American International Shipping Company... Type: New NVO License. Nippon Concept America, LLC (OFF), 2203 Timberloch Place, Suite 218D, The...

  15. License renewal - an idea whose time has come. Hatch nuclear plant license renewal program: an actual example of application of the license renewal rule to the Intake Structure

    International Nuclear Information System (INIS)

    Chandiwala, F.; Evans, W.P.

    1999-01-01

    After the NRC issued a revised license renewal rule in May 1995, the nuclear industry focussed on developing generic industry for implementing the rule and testing the guidance through various demonstration programs and work products in conjunction with the NRC. In addition, plant-specific programs also proceeded forward. These activities show that implementation issues continue to exist. Since the issuance of the rule, the NRC has issued a draft standard review plan for license renewal (SRP-LR), working draft, September 1997. Southern Nuclear Operating Company (SNC) has begun development work on a license renewal application for Plant Hatch Units 1 and 2. Plant Hatch Units 1 and 2 are BWR 4, Mark I plants whose operating licenses expire in 2014 and 2018, respectively. The Plant Hatch initiative also involves teaming with other boiling water reactors (BWRs) to develop the license renewal technology within the BWR fleet, and to support Plant Hatch by providing an oversight role for the application process. The teaming effort involved two other utilities, each being assigned to prepare a common report on a mechanical system or a structure. The common report could be presented to the NRC with modifications to suit the individual plants, thereby saving time and money, and hopefully resulting in quicker approval by the NRC. The desired license renewal process end result is a renewed license with up to a 20 year extension (10CFR 54.31(b)). (orig.)

  16. 77 FR 59193 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-09-26

    ... Type: New OFF License. Bring Logistics US, Inc. (NVO & OFF), 4500 N. Sam Houston Parkway W., 130...: New NVO & OFF License. Contract Logistics, LLC (NVO & OFF), 4911 N. Portland Avenue, Suite 200.... Roush, Manager, Application Type: New NVO & OFF License. Crescent Line Inc. dba Globe Express Services...

  17. 76 FR 70145 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-11-10

    ...). Application Type: New NVO License. Alomar Transport, Inc. (NVO & OFF), 150-30 132nd Avenue, Suite 303, Jamaica... & OFF License. Forward System Logistics Inc. (NVO), 144-54 156th Street, Jamaica, NY 11434. Officers... NVO License. Green Line Shipping & Logistics Services Inc. (NVO & OFF), 16230 Lake View Lane, Apple...

  18. 75 FR 20997 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-04-22

    ... 77354. Officers: Thomas C. Gaze, President, Qualifying Individual). Lori L. Gaze, Secretary/Treasurer... Services, (Qualifying Individual). George T. Cook, President/Treasurer, Application Type: New OFF License...

  19. 25 CFR 141.9 - Application for license renewal.

    Science.gov (United States)

    2010-04-01

    ... Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR FINANCIAL ACTIVITIES BUSINESS PRACTICES ON... the applicant has made as a reservation business owner and the applicant's present fitness to reside... pending consideration of application for license renewal. (c) Prior to expiration of the existing license...

  20. LTO License Application Project NPP Borssele

    International Nuclear Information System (INIS)

    Jong, A.E. de; Blom, F.J.; Leilich, J.

    2012-01-01

    Borssele NPP plans to extend its operating life with 20 years until 2034. Borssele has started the project LTO 'bewijsvoering' (LTO 'Justification') in order to meet the requirements of the Dutch regulator. The outline of the project is based on IAEA safety guide 57 'Safe Long Term Operation of Nuclear Power Plants'. This paper describes the contents and coherence of the different parts in the project and how these respond to the IAEA guidelines on LTO. The goal of the project LTO 'bewijsvoering' is to ensure that safety and safety relevant systems, structures and components continue to perform their intended functions during long term operation. The outcome of the project LTO 'bewijsvoering' will be used for a license change application and this will be submitted to the Dutch regulator KFD for approval of prolonged operation of Borssele NPP after 2013. (author)

  1. Determination of ABOS 1-3+ system components belonging to the scope of license application of Paks Nuclear Power Plant Unit 1 for extension of service life, designated for the review, and verification of completeness of the scope

    International Nuclear Information System (INIS)

    Biro, Agnes Janosine; Tanits, Katalin Baumann-ne; Gosi, Peter; Kovacs, Andras; Ratkai, Sandor

    2012-01-01

    It is one major requirement of licensing the extension of design service life to determine the systems, structures and components that belong to the scope of licensing. According to the domestic regulatory requirements the ABOS 1-3 safety class components, the non safety system components of seismic safety class 3 and those non safety class components whose failure would occur due to its unmanaged ageing process and which may jeopardize safety class components with the released medium shall be involved into the scope of licensing of service life extension (SLE). In the task the components for the scope of SLE licensing of Unit 1 was determined using and, if necessary, further developing the tools provided by and exploiting, verifying and, as appropriate, supplementing the data included in the central technical database (IMR/MDM) of the NPP. As basis for determination of the scope the systems, structures and individual components categorized into safety class in the Final Safety Report were taken. Digitalized mechanical technological schemes were also used in determining the components of the systems fulfilling safety functions and in verifying the completeness. In order to assign the components belonging to the fulfillment of the function of the systems and to review the scope, the digitalization of the ABOS 2-3 electric and the ABOS 2 I and C circuit diagrams and distributor single-line diagrams and the processing and analysis of the digitalized data was performed. The ABOS + scope components were verified by walkdown. The completed component lists were compared to the components of the SLE licensing scope of the IMR/MDM database and the necessary supplementation, correction of the IMR/MDM data was also performed. In order to identify the components requiring review during licensing, also the active/passive safety function fulfillment modes were determined for every component of the licensing scope for Unit 1, which is now regarded as complete. As the results of

  2. 77 FR 20398 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-04-04

    ...), Svi Soudai, Manager, Application Type: New OFF License. Armada USA, LLC dba Armada Logistics (NVO... Logistics (NVO & OFF), 435 Division Street, Elizabeth, NJ 07076, Officer: Carlos E. Feliu, President.../Treasurer, (Qualifying Individual), Application Type: New NVO License. HYC Logistics, Inc. (NVO & OFF), 2600...

  3. 76 FR 44330 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-07-25

    .... Nguyen, Secretary/CFO, Application Type: New NVO & OFF License. Atlas Logistics LLC (NVO & OFF), 2801 NW...), Application Type: New NVO & OFF License. Bulk Cargo Services & Logistics Inc. (OFF), 15400 N.E. 103rd Drive..., Member/Chief Executive Manager, (Qualifying Individual), Stina Storr, Member/ Managing Member...

  4. 77 FR 24712 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-04-25

    ... Global Logistics LLC (OFF), 9816 Whithorn Drive, Suite B, Houston, TX 77095, Officer: Herbert R. Hogg, Operating Manager (Qualifying Individual), Application Type: New OFF License. Toyo Logistics America, Inc... Individual), Application Type: New NVO License. Choiceone Logistics, Inc. (NVO & OFF), 10025 NW 116th Way, 17...

  5. 78 FR 66713 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-11-06

    ..., Washington, DC 20573, by telephone at (202) 523-5843 or by email at [email protected] . Action One Logistics, Inc..., Operating Manager (QI), Joseph Lam, Member, Application Type: New NVO License. Altex US, LLC (NVO & OFF), 1... President, Application Type: New NVO & OFF License. Andes Logistics USA LLC (NVO & OFF) 7500 NW 25 Street, 7...

  6. 76 FR 79682 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-12-22

    ... at (202) 523-5843 or by email at [email protected] . A.C.T. Logistics, LLC (NVO), 154-09 146th Avenue, 3rd...-President/Secretary. Application Type: License Transfer. Canyon Global Logistics, LLC (NVO & OFF), 2928-B..., General Manager, (Qualifying Individual), Oleg Ardachev, President. Application Type: New OFF License...

  7. 75 FR 61757 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-10-06

    ...), Jinho Um, CFO. Application Type: New NVO & OFF License. Junction Int'l Logistics, Inc. (NVO), 17870 Castleton Street, Suite 107, City of Industry, CA 91748. Officers: Charles Kuo, Secretary (Qualifying.... Application Type: New NVO & OFF License. Red Arrow Consulting, Inc. dba Red Arrow Logistics (OFF), 14925 SE...

  8. 76 FR 30360 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-05-25

    .... Application Type: Trade Name Change. B&O Logistics, Inc. (NVO), 19310 Pacific Gateway Drive, Torrance, CA.... Application Type: New NVO License. Charity Cargo L.L.C. (NVO & OFF), 1423 Kaleilani Street, Pearl City, HI... License. GreenLine Trade, LLC dba GreenLine Logistics (OFF), 14205 SE 36th, Suite 100, Bellevue, WA 98006...

  9. 77 FR 71002 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-11-28

    ..., Washington, DC 20573, by telephone at (202) 523-5843 or by email at [email protected] . 5G Logistics Solutions LLC..., President. Application Type: New NVO & OFF License. Bennett International Transport, L.L.C. (NVO & OFF.... Castano, COO. Application Type: New NVO & OFF License. James J. Boyle & Co. dba JJB Global Logistics Co...

  10. 78 FR 6325 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-01-30

    .... Application Type: New NVO & OFF License. Naca Logistics (USA), Inc. dba Brennan International Transport, dba...). Application Type: New NVO & OFF License. Miami Freight & Logistics Services, Inc. (NVO & OFF), 3630 NW 76th... World Shipping, dba OWS, dba Ocean Express, dba Oceanexpress Vanguard Logistics Services, dba Vanguard...

  11. Licensing Review in R+D Projects

    OpenAIRE

    Alessandro, Orsi

    2014-01-01

    FOSS packages are becoming ever more present in R&D projects carried out a variety of entities, including large corporations. I will focus on how legal risks associated with the use of FOSS licenses can be assessed and discuss measures directed to risk mitigation.

  12. INTERNAL HAZARDS ANALYSIS FOR LICENSE APPLICATION

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-02-17

    The purpose of this internal hazards analysis is to identify and document the internal hazards and potential initiating events associated with preclosure operations of the repository at Yucca Mountain. Internal hazards are those hazards presented by the operation of the facility and by its associated processes that can potentially lead to a radioactive release or cause a radiological hazard. In contrast to external hazards, internal hazards do not involve natural phenomena and external man-made hazards. This internal hazards analysis was performed in support of the preclosure safety analysis and the License Application for the Yucca Mountain Project. The methodology for this analysis provides a systematic means to identify internal hazards and potential initiating events that may result in a radiological hazard or radiological release during the repository preclosure period. These hazards are documented in tables of potential internal hazards and potential initiating events (Section 6.6) for input to the repository event sequence categorization process. The results of this analysis will undergo further screening and analysis based on the criteria that apply to the performance of event sequence analyses for the repository preclosure period. The evolving design of the repository will be re-evaluated periodically to ensure that internal hazards that have not been previously evaluated are identified.

  13. NUCLEAR SAFETY DESIGN BASES FOR LICENSE APPLICATION

    International Nuclear Information System (INIS)

    Garrett, R.J.

    2005-01-01

    The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111 [DIRS 156605] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113 [DIRS 156605] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period

  14. Nuclear Safety Design Base for License Application

    International Nuclear Information System (INIS)

    R.J. Garrett

    2005-01-01

    The purpose of this report is to identify and document the nuclear safety design requirements that are specific to structures, systems, and components (SSCs) of the repository that are important to safety (ITS) during the preclosure period and to support the preclosure safety analysis and the license application for the high-level radioactive waste (HLW) repository at Yucca Mountain, Nevada. The scope of this report includes the assignment of nuclear safety design requirements to SSCs that are ITS and does not include the assignment of design requirements to SSCs or natural or engineered barriers that are important to waste isolation (ITWI). These requirements are used as input for the design of the SSCs that are ITS such that the preclosure performance objectives of 10 CFR 63.111(b) [DIRS 173273] are met. The natural or engineered barriers that are important to meeting the postclosure performance objectives of 10 CFR 63.113(b) and (c) [DIRS 173273] are identified as ITWI. Although a structure, system, or component (SSC) that is ITS may also be ITWI, this report is only concerned with providing the nuclear safety requirements for SSCs that are ITS to prevent or mitigate event sequences during the repository preclosure period

  15. INTERNAL HAZARDS ANALYSIS FOR LICENSE APPLICATION

    International Nuclear Information System (INIS)

    Garrett, R.J.

    2005-01-01

    The purpose of this internal hazards analysis is to identify and document the internal hazards and potential initiating events associated with preclosure operations of the repository at Yucca Mountain. Internal hazards are those hazards presented by the operation of the facility and by its associated processes that can potentially lead to a radioactive release or cause a radiological hazard. In contrast to external hazards, internal hazards do not involve natural phenomena and external man-made hazards. This internal hazards analysis was performed in support of the preclosure safety analysis and the License Application for the Yucca Mountain Project. The methodology for this analysis provides a systematic means to identify internal hazards and potential initiating events that may result in a radiological hazard or radiological release during the repository preclosure period. These hazards are documented in tables of potential internal hazards and potential initiating events (Section 6.6) for input to the repository event sequence categorization process. The results of this analysis will undergo further screening and analysis based on the criteria that apply to the performance of event sequence analyses for the repository preclosure period. The evolving design of the repository will be re-evaluated periodically to ensure that internal hazards that have not been previously evaluated are identified

  16. Application and licensing requirements of the Framatome ANP RLBLOCA methodology

    International Nuclear Information System (INIS)

    Martin, R.P.; Dunn, B.M.

    2004-01-01

    The Framatome ANP Realistic Large-Break LOCA methodology (FANP RLBLOCA) is an analysis approach approved by the US NRC for supporting the licensing basis of 3- and 4-loop Westinghouse PWRs and CE 2x4 PWRs. It was developed consistent with the NRC's Code Scaling, Applicability, and Uncertainty (CSAU) methodology for performing best-estimate large-break LOCAs. The CSAU methodology consists of three key elements with the second and third element addressing uncertainty identification and application. Unique to the CSAU methodology is the use of engineering judgment and the Process Identification and Ranking Table (PIRT) defined in the first element to lay the groundwork for achieving the ultimate goal of quantifying the total uncertainty in predicted measures of interest associated with the large-break LOCA. It is the PIRT that not only directs the methodology development, but also directs the methodology review. While the FANP RLBLOCA methodology was generically approved, a plant-specific application is customized in two ways addressing how the unique plant characterization 1) is translated to code input and 2) relates to the unique methodology licensing requirements. Related to the former, plants are required by 10 CFR 50.36 to define a technical specification limiting condition for operation based on the following criteria: 1. Installed instrumentation that is used in the control room to detect, and indicate, a significant abnormal degradation of the reactor coolant pressure boundary. 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a

  17. Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-02-15

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

  18. PROCESS FOR LICENSE APPLICATION DEVELOPMENT FOR THE GEOLOGIC REPOSITORY

    International Nuclear Information System (INIS)

    DOUGLAS M. FRANKS AND NORMAN C. HENDERSON

    1997-01-01

    The Department of Energy (DOE), specifically the Office of Civilian Radioactive Waste Management (OCRWM) has been charged by the U.S. Congress, through the Nuclear Waste Policy Act (NWPA), with the responsibility for obtaining a license to develop a geologic repository. The NRC is the licensing authority for geologic disposal, and its regulations pertinent to construction authorization and license application are specified in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, (section)60.21ff and (section)60.31ff. This paper discusses the process the Yucca Mountain Site Site Characterization Project (YMP) will use to identify and apply regulatory and industry guidance to development of the license application (LA) for a geologic repository at Yucca Mountain, Nevada. This guidance will be implemented by the ''Technical Guidance Document for Preparation of the License Application'' (TGD), currently in development

  19. Process for license application development for the geologic repository

    International Nuclear Information System (INIS)

    Franks, D.M.; Henderson, N.C.

    1998-01-01

    The Department of Energy (DOE), specifically the Office of Civilian Radioactive Waste Management (OCRWM) has been charged by the US Congress, through the Nuclear Waste Policy Act (NWPA), with the responsibility for obtaining a license to develop a geologic repository. The NRC is the licensing authority for geologic disposal, and its regulations pertinent to construction authorization and license application are specified in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, section 60.21ff and section 60.31ff. This paper discusses the process the Yucca Mountain Site Characterization Project (YMP) will use to identify and apply regulatory and industry guidance to development of the license application (LA) for a geologic repository at Yucca Mountain, Nevada. This guidance will be implemented by the Technical Guidance Document for Preparation of the License Application (TGD), currently in development

  20. 75 FR 48686 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-08-11

    ...: New NVO License. Maritime and Intermodal Logistics Systems, Inc. dba MILS dba Fesco Integrated..., Senior Vice President/General Manager (Qualifying Individual), Kenryo Senda, President/CEO, Application...: New NVO & OFF License. Rado International, Inc. dba Rado Logistics (NVO & OFF), 2251 Sylvan Road...

  1. 77 FR 18815 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-03-28

    ... NVO License. American Patriot Lines, Inc. dba Tier One Logistics (NVO), 8616 La Tijera Boulevard, 401..., AL 36608. Officer: Samford T. Myers, Manager (Qualifying Individual). Application Type: New NVO & OFF License. Bluesea Logistics Corporation (NVO), 327 Elizabeth Avenue, Apt. A, Monterey Park, CA 91755-2044...

  2. 77 FR 43599 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-07-25

    ... OFF License. Logistics International Parcel Shipping Transport LLC (NVO), 182 West Melrose Avenue, 2... Schwartz, Director, Application Type: New OFF License. Brox Logistics USA, LLC (NVO,) 244 5th Avenue, V-280... Agency Corporation, dba C&F Worldwide Logistics. Cargois Inc. dba Star Vision Logis (NVO), 2700 Coyle...

  3. 76 FR 28778 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-05-18

    ... Individual), Application Type: New NVO & OFF License. Asian Link Logistics, LLC dba Best Global (NVO & OFF... Type: New NVO License. Hansa Meyer Global Transport USA, LLC dba Hansa Shipping LLC, (OFF), 712 Main... & Logistics (Private) Limited dba, Nashrah Shipping and Logistics (NVO), Mezzanine Floor, Trade Ave., Tower 1...

  4. Review of the Brazilian experience in the licensing of nuclear power plants

    International Nuclear Information System (INIS)

    Lederman, L.; Laborne, J.J.

    1983-01-01

    Survey of the licensing of the Brazilian Nuclear Power Plants (NPPs) is presented. The organization and technical expertise of the Comissao Nacional de Energia Nuclear, the Brazilian Regulatory Body, is reviewed with regard to in-house experience, foreign consultants, agreements with regulatory bodies of other countries and research contracts with Brazilian univerisities. The application of the two-stage licensing process and the stage of development of Brazilian nuclear standards is described. Finally, the paper speculates about the future role of probabilistic risk assessment in the Brazilian licensing process

  5. The U.S. Nuclear Regulatory Commission's antitrust review of nuclear power plants: the conditioning of licenses

    International Nuclear Information System (INIS)

    Penn, D.W.; Delaney, J.B.; Honeycutt, T.C.

    1976-04-01

    The 1970 amendments to Section 105 of the Atomic Energy Act require the Nuclear Regulatory Commission to conduct a prelicensing antitrust review of applications for licenses to construct and operate nuclear power plants. The Commission must make a finding as to whether the granting of a license 'would create or maintain a situation inconsistent with the antitrust laws,' and it has the authority to issue or continue a license, to refuse to issue a license, to rescind or amend a license, and to issue a license with conditions that it deems appropriate. This report provides information about the antitrust license conditions that have resulted from the NRC's antitrust review process. The process itself is described and a catalog of the applications requiring antitrust license conditions is presented. For each application, the license conditions are put into the general categories of unit access, transmission services, coordination, and contractual provisions. For completeness, the report also catalogs applications requiring no antitrust license conditions, and lists applications that were exempted from the 1970 amendments, are the subject of litigation, or have been withdrawn

  6. Fort Calhoun Station, Unit 2. License application, PSAR, general information

    International Nuclear Information System (INIS)

    1975-09-01

    Application for construction and operating licenses for Calhoun-2 Reactor is presented. Financial data concerning the Omaha Public Power District and the Nebraska Public Power District are included. (DCC)

  7. 76 FR 47182 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-08-04

    ... Street, Tampa, FL 33619, Officers: Margara L. Barillas, President (Qualifying Individual), Danihel I. Barillas, Secretary, Application Type: New NVO License. Russell A. Farrow (U.S.) Inc. (OFF & NVO), 4950...

  8. 77 FR 72863 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-12-06

    ... & D Transport, Inc. (NVO & OFF), 4869 Peavey Drive, Meridian, MS 39301. Officers: Uros Pejanovic, Vice... Nucete, Director. Application Type: New NVO & OFF License. Embarque Los Hidalgos LLC (NVO & OFF), 326...

  9. 77 FR 12583 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-03-01

    ... Hermo, Vice President, Application Type: New NVO & OFF License. B2B Global Logistics Incorporated (NVO... Change. Global Logistics New Jersey Limited Liability Company (NVO & OFF) 275 Veterans Boulevard...

  10. 77 FR 64991 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-10-24

    ..., Manager/Member. Application Type: New NVO & OFF License. Hospitality Logistics International LLC (NVO...), 11690 NW. 105th Street, Law 4W, Miami, FL 33178. Officers: Chris Merritt, Vice President (QI), John H...

  11. 77 FR 26008 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-05-02

    .... Forth-Matthews, President, Application Type: New OFF License. Azimuth Lines Inc. (OFF), 111 Ivy Lane.... (NVO), 1000 Lakes Drive, 260, West Covina, CA 91760, Officers: Larry Lee, Treasurer (Qualifying...

  12. 75 FR 67973 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-11-04

    ... Individual), Joy V. Pareckattil, President/Director, Application Type: New NVO License. CJC Logistics Limited Liability Company dba CJC Container Line (NVO & OFF), 186 Alps Road, Wayne, NJ 07470. Officers: Oliver Rosca...

  13. 76 FR 78007 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-12-15

    ..., (Qualifying Individual), Ruba Hindi, Member, Application Type: New OFF License. Kemka USA Limited Liability Company (NVO & OFF), 421 Lucy Court, South Plainfield, NJ 07080, Officer: Hsiang (Rita) Y. Hsiao, Member...

  14. 77 FR 70162 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-11-23

    ...), 900 Center Park Drive, Suite F, Charlotte, NC 28217, Officers: Paul L. Carter, Vice President (QI...), Application Type: New NVO License. Transport Partner (USA), Inc. (NVO & OFF), 2006 Cherry Hill Lane...

  15. 78 FR 38336 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-06-26

    ..., President (QI), Stephen B. Schwark, Treasurer, Application Type: License Transfer to EFL Container Lines...., Suite K, Mobile, AL 36609, Officers: Thomas (Mac) H. McPhillips IV, Assistant Vice President (QI), Oscar...

  16. 76 FR 23598 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-04-27

    ... Angeles, CA 90045, Officers: Ann L. Shang, CFO (Qualifying Individual), Yon L. Li, President, Application... Type: New NVO & OFF License. PME Logistics, Inc. (NVO), 19401 S. Main Street, Suite 102, Gardena, CA...

  17. 76 FR 56759 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-09-14

    ...), Ariel S. Villamayor, Limited Partner, Application Type: New OFF License. UTi, United States, Inc. dba UTi (NVO & OFF), 1660 Walt Whitman Road, Melville, NY 11747. Officers: Charles N. Deller, Vice...

  18. SSM's licensing review of a spent nuclear fuel repository in Sweden

    International Nuclear Information System (INIS)

    Dverstorpand, Bjoern; Stroemberg, Bo

    2014-01-01

    On 16 March 2011 the Swedish Nuclear Fuel and Waste Management Co. (SKB) submitted license applications for a general license to construct, possess and operate a KBS-3 type spent nuclear fuel repository at the Forsmark site, in Oesthammar municipality, and an encapsulation plant in Oskarshamn municipality. The KBS-3 method, which has been developed by SKB over a period of more than 30 years, entails disposing of the spent fuel in copper canisters, surrounded by a swelling bentonite clay, at about 500 m depth in crystalline basement rock. SKB's applications are being evaluated in parallel by the Swedish Radiation Safety Authority (SSM) according to the Act on Nuclear Activities and by the Land and Environmental Court according to the Environmental Code. During the review SSM will act as an expert review body to the Land and Environmental Court in the areas of radiation protection, safety and security/non-proliferation. Both SSM and the court will produce a statement with a recommendation regarding a licensing decision and licensing conditions to the government. The government will make the final decision after consulting the municipalities concerned by SKB's facilities (municipal veto applies). The current licensing decision is just one of several licensing decisions that will be required for the repository. However it is arguably the most important one, because it is the last licensing stage with a broad societal involvement including an environmental impact assessment (EIA) process, national consultations and municipal veto for the concerned municipalities. The licensing steps to follow, should SKB be granted a license by the government, only require approval by SSM. These steps include application for start of actual construction work, test operation and routine operation. (authors)

  19. Total System Performance Assessment-License Application Methods and Approach

    Energy Technology Data Exchange (ETDEWEB)

    J. McNeish

    2002-09-13

    ''Total System Performance Assessment-License Application (TSPA-LA) Methods and Approach'' provides the top-level method and approach for conducting the TSPA-LA model development and analyses. The method and approach is responsive to the criteria set forth in Total System Performance Assessment Integration (TSPAI) Key Technical Issue (KTI) agreements, the ''Yucca Mountain Review Plan'' (CNWRA 2002 [158449]), and 10 CFR Part 63. This introductory section provides an overview of the TSPA-LA, the projected TSPA-LA documentation structure, and the goals of the document. It also provides a brief discussion of the regulatory framework, the approach to risk management of the development and analysis of the model, and the overall organization of the document. The section closes with some important conventions that are utilized in this document.

  20. Total System Performance Assessment - License Application Methods and Approach

    International Nuclear Information System (INIS)

    McNeish, J.

    2003-01-01

    ''Total System Performance Assessment-License Application (TSPA-LA) Methods and Approach'' provides the top-level method and approach for conducting the TSPA-LA model development and analyses. The method and approach is responsive to the criteria set forth in Total System Performance Assessment Integration (TSPAI) Key Technical Issues (KTIs) identified in agreements with the U.S. Nuclear Regulatory Commission, the ''Yucca Mountain Review Plan'' (YMRP), ''Final Report'' (NRC 2003 [163274]), and the NRC final rule 10 CFR Part 63 (NRC 2002 [156605]). This introductory section provides an overview of the TSPA-LA, the projected TSPA-LA documentation structure, and the goals of the document. It also provides a brief discussion of the regulatory framework, the approach to risk management of the development and analysis of the model, and the overall organization of the document. The section closes with some important conventions that are used in this document

  1. 10 CFR 781.62 - Contents of a license application.

    Science.gov (United States)

    2010-01-01

    ... royalty fees or other consideration, if any, that the applicant would be willing to pay the Government for... application. An application for a license under a DOE invention must be accompanied by a processing fee of $25... towards royalty if royalties are charged, and must include the following information: (a) Identification...

  2. 78 FR 17205 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-03-20

    .... Sicilia, Member, Application Type: New NVO & OFF License. Brookfield Relocation Inc. (OFF), Two Corporate... Schwartz, President, Application Type: QI Change. Covenant Global Logistics Inc (NVO & OFF), 440 Benmar..., President, Application Type: Add Trade Name CGL Shipping. EXL Logistics, Inc. (NVO), 1444 NW 82nd Avenue...

  3. 78 FR 75345 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-12-11

    .... Romero, President (QI). Application Type: New NVO & OFF License. F.H.L. Logistics, Inc. (NVO & OFF), 1354.... Officers: Arif H. Butt, General Manager (QI), Unni Krishnan Nair, President. Application Type: New NVO...: Stephen F. Crooks, Vice President (QI), Scott Kelly, President. Application Type: Adding NVO Service...

  4. 76 FR 22104 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-04-20

    ...), Application Type: Business Structure Change Foothills Logistics, Inc. (NVO), 2045 John Crosland Jr. Way... Individual), Daniel Gelpi, President, Application Type: Add NVO Service ADM Logistics, Inc. (NVO & OFF), 4666... (Qualifying Individual), Application Type: New NVO & OFF License ATC Logistics, Inc. (NVO & OFF), 14350...

  5. 78 FR 50054 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-08-16

    ...), Ross V. Stemmler, President, Application Type: QI Change. Dawson Logistics, Inc. (OFF), 2220 South... (QI), Chad Earwood, President, Application Type: Add NVO Service. Fesco Integrated Transport North...), Ugochukwu O. Ene, President, Application Type: New NVO & OFF License. Icon Logistics Services LLC (OFF...

  6. 78 FR 55698 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-09-11

    ...), Karla Costilla, Member/Manager, Application Type: New NVO & OFF License. ICAT Logistics, Inc. (OFF..., Washington, DC 20573, by telephone at (202) 523-5843 or by email at [email protected] . Abaco Logistics Corporation..., CFO, Application Type: QI Change & Add OFF Service. American General Logistics, Inc. (NVO), 626 N...

  7. 77 FR 37044 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-06-20

    ... 95695, Officer: Nasrullah Chaudhry, Member/Manager (Qualifying Individual), Application Type: Add NVO... (Qualifying Individual), Margaret Kong, CFO/Secretary, Application Type: New NVO & OFF License. FSG Logistics (USA), Inc. dba FSG Logistics, Inc. (NVO & OFF), 27013 Pacific Highway South, PMB386, Des Moines, WA...

  8. 78 FR 48435 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-08-08

    ... Change. Ever Line Logistics Inc. (NVO & OFF), 147-35 Farmers Blvd., Suite 208, Jamaica, NY 11434, Officer: Caihong Yang, President (QI), Application Type: Name Change to Bona Logistics US Inc. Global Container.... Bote, Member/Manager, Edgar T. Bote, Member/Manager, Application Type: New NVO License. National Air...

  9. 76 FR 55909 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-09-09

    ..., LLC dba AIM Global Logistics (NVO & OFF), 6402 Teluco Street, Houston, TX 77055, Officer: Angelica Garcia-Dunn, Manager/President/Treasurer (Qualifying Individual), Application Type: New OFF & NVO License... Individual), Application Type: Name Change. BestOcean Worldwide Logistics, Inc. (NVO & OFF), 1300 Valley...

  10. 78 FR 18592 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-03-27

    ...), Veronica Alcestte, Manager, Application Type: New NVO & OFF License Worldcraft Logistics LLC (NVO & OFF.... Salvat, Vice President, Application Type: Add NVO Service Bayshore Logistics & Services, LLC (NVO & OFF), 909 Westfield Avenue, Elizabeth, NJ 07208, Officers: Raquel Velez, Operating Manager (QI), Jose Moreno...

  11. 76 FR 62407 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-10-07

    ... & Product Logistics Manager (Qualifying Individual), Thomas B. Crowley, Director, Application Type: QI... at (202) 523-5843 or by e-mail at [email protected] . Alltransport International Logistics, Inc. (NVO), 63... Individual), Application Type: New NVO License. American Global Logistics LLC dba AGL (NVO & OFF), 3399...

  12. 78 FR 14792 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-03-07

    ...: Mohamed Y. Ali, Manager (QI); Abdul S. Mohamed, Member. Application Type: Add Trade Name Compass Logistics... Ugueto, Secretary. Application Type: New NVO & OFF License American Forwarding & Logistics, LLC (NVO & OFF), 1919 NW 19th Street, Unit 624, Ft. Lauderdale, FL 33311. Officers: Gabriele Awada, Manager (QI...

  13. 77 FR 45610 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-08-01

    ...), Richard A. Arkey, Vice President, Application Type: New NVO License. Aequus Worldwide Logistics Inc. (NVO..., Application Type: Name Change to Concepts in Freight, Inc. FGN Global Logistics, Inc. (NVO & OFF), 4770...), 341 Erickson Avenue, P.O. Box 124, Essington, PA 19029, Officers: Ari M. Bobrow, Export Manager...

  14. 10 CFR 81.40 - Contents of a license application.

    Science.gov (United States)

    2010-01-01

    ... categories: (i) Small business firm; (ii) Minority business enterprise; (iii) Location in a surplus labor... correspondence should be sent and any notices served; (4) Nature and type of applicant's business; (5...; (6) Purpose for which the license is desired, and a brief description of applicant's plan to achieve...

  15. 77 FR 40882 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-07-11

    ..., Director, Application Type: License Transfer & QI Change. Gulf Premier Logistics LLC (NVO & OFF), 340 N... & OFF), 1163 Fairway Drive, 106, City of Industry, CA 91789, Officer: XiuJi Zhang, President, (Qualifying Individual), Application Type: Add NVO Service. Simple Logistics Inc. (NVO), 147-35 Farmers...

  16. 77 FR 38288 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-06-27

    ..., President. Application Type: QI Change. Freight Logistics Services USA Forwarding Ltd (OFF), 15955 W. Hardy... Individual). Application Type: Add OFF Service. Pudong Prime Int'l Logistics, Inc. (NVO), 9660 Flair Drive... License. Benchmark Worldwide Logistics, Inc. dba Star Ocean Lines (NVO & OFF), 24900 South Route 53...

  17. 78 FR 48870 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-08-12

    ...: Tufan Duygun, Manager (QI), Ozisik Serhat, Member, Application Type: Add Trade Name Daimon Logistics USA. Logistics International Parcel Shipping Transport LLC (NVO), 391 Kent Avenue, Elk Grove, IL 60007, Officers...), Application Type: NVO & OFF License. Kesco Logistics, Inc. (NVO & OFF), 20 E. Sunrise Highway, Suite 308...

  18. 75 FR 57798 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-09-22

    ..., (Qualifying Individual). Application Type: New NVO & OFF License. Cambria Global Logistics, LLC (OFF), 12140...). Application Type: QI Change. K&K Express, LLC dba K2 Logistics (NVO & OFF), 2980 Commers Drive, 100, Eagan, MN... Global Transport (NVO), 8636 York Circle, La Palma, CA 90623. Officer: Smile Cha, Sole Proprietor...

  19. 76 FR 67730 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-11-02

    ..., President, Application Type: Name Change/Trade Name Change Lion Transport, Inc. dba Amex Logistics (NVO... Individual), Caetano R. Lopes, Vice President, Application Type: Add NVO Service Eztrans Logistics Ltd. (NVO... Type: New OFF License LF Freight USA LLC dba LF Logistics dba LF Freight dba IDS Logistics USA, dba IDS...

  20. 77 FR 30530 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-05-23

    ... Individual), Application Type: New NVO License. Global Wine Logistics, Inc. (NVO & OFF), 197 Route 19 South... Hextall, President/CEO, Application Type: Add NVO Service/Trade Name Change. M & D Global Logistics, Inc... Service. Metro Freight Services, Inc. dba Maritime Express Lines (M.E.L.) (NVO & OFF), 1225 W. St. George...

  1. 47 CFR 80.53 - Application for a portable ship station license.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Application for a portable ship station license... SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Applications and Licenses § 80.53 Application for a portable ship station license. The Commission may grant a license permitting operation of a...

  2. Conceptual Design of On-line Based Licensing Review and Assesment System of Nuclear Installations and Nuclear Materials ('PRIBEN')

    International Nuclear Information System (INIS)

    Melani, Ai; Chang, Soon Heung

    2008-01-01

    At the present Indonesia has no nuclear power plant in operation yet, although it is expected that the first nuclear power plant will be operated and commercially available in around the year of 2016 to 2017 in Muria Peninsula. There are only three research reactors, one nuclear fuel fabrication plant for research reactors, and one experimental fuel fabrication plant for nuclear power, one isotope production facility and some other research facilities. All the facility is under Nuclear Energy Regulatory Agency (BAPETEN) controlling through regulation, licensing and inspection. The organizations operation submits licensing application to BAPETEN before utilizing the facility. According to the regulation before BAPETEN give license they perform review and assessment for the utility application. Based on the review and assessment result, BAPETEN may stipulate, reject, delay or terminate the license. In anticipation of expansion of the nuclear program in Indonesia, BAPETEN should have an integrated and updated system for review and asses the licensing application. For this reason, an expert system for the review and asses the licensing application, so-called PRIBEN (Perizinan Reaktor, Instalasi dan Bahan Nuklir/Licensing of Reactor, Nuclear Installations and Nuclear Materials), is developed which runs on the online-based reality environment

  3. Licensing review process of the European Spallation Source (ESS) research facility

    International Nuclear Information System (INIS)

    Brewitz, Erica

    2014-01-01

    On 3 January 2012 a license application under the Radiation Protection Act (SFS, 1988b) for the European Spallation Source research facility was submitted to the Swedish Radiation Safety Authority. The European Spallation Source research facility will be the site of a new and quite unusual kind of neutron source, based on a large proton accelerator that bombards a heavy material with protons. The Swedish Radiation Safety Authority is now reviewing the application. (authors)

  4. Resolving the issues arisen during the development of License Renewal Application at PAKS NPP

    International Nuclear Information System (INIS)

    Ratkai, Sandor; Katona, Tamas Janos

    2012-01-01

    Operational license of the four VVER-440/213 units at Paks NPP, Hungary is limited to the design lifetime of 30 years. Extension by an additional 20 years of the original license is one of the main goals of the plant owner. In 2008 a programme for long-term operation (LTO) was developed and submitted to the Hungarian Atomic Energy Authority. The LTO Programme defines the activities for ensuring the extension of the operational lifetime and contains the justification of the safe LTO. The LTO Programme has to be implemented and comprehensive justification of the safe LTO has to be provided in the formal License Renewal Applications unit by unit. This work has been completed by the end of 2011, and the application has been submitted for approval for the Unit 1. The authority review and the approval of the License Renewal Application for Unit 1 should be finished before the expiration of the original design lifetime in 2012. In line with the regulations and supporting the License Renewal Application, a large number of engineering tasks have been performed. In this paper the entire project will be reported. The issues will be discussed, which have been arisen during the development of the application. The difficulties caused by the Hungarian technical and regulatory peculiarities will be presented. (author)

  5. 76 FR 6135 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-02-03

    ... Lawin Cargo dba, Bahaghari Express Cargo (NVO), 761 Highland Place, San Dimas, CA 91773, Officer..., Application Type: New NVO License. Four Points Ocean Inc. (NVO & OFF), 1460 Route 9 North, Suite 303.... Grannell, President/CEO (Qualifying Individual), Michael Kuhn, Vice President, Sales & Marketing...

  6. Fuel Receiving and Storage Station. License application, amendment 4

    International Nuclear Information System (INIS)

    1975-04-01

    Amendment No. 4 of the application for licensing the Barnwell Fuel Processing Plant is presented. Information is included on: the quantity and characteristics of nuclear fuel assemblies which can be received and stored; specifications limiting the outside washdown of contaminated casks received for unloading; and definition of environmental monitoring program. (U.S.)

  7. 78 FR 35634 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-06-13

    ..., Washington, DC 20573, by telephone at (202) 523-5843 or by email at [email protected] . China Interocean Transport.... Taleon, Sole Proprietor (QI). Application Type: New NVO & OFF License. Dulce Auto Import & Export, Inc...), Parque de Granada No. 71, P.H. 504, Huixquilucan, Estado de Mexico 52785 Mexico. Officers: Moises S. Leon...

  8. 76 FR 3636 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-01-20

    ..., Vice President, Application Type: New NVO & OFF License. CDS Global Logistics, Inc. (NVO & OFF), 1001... & Logistics LLC (NVO & OFF), Hoboken Business Center, 50 Harrison Street, Suite 204B, Hoboken, NJ 07030, Officers: Michelle L. Hasenauer, Manager (Qualifying Individual), Harbans S. Shrinkant, Manager...

  9. 77 FR 65887 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-10-31

    ..., Washington, DC 20573, by telephone at (202) 523-5843 or by email at [email protected] . ACM Logistics & Consulting... Type: New OFF License; Highland Project Logistics, Inc. (NVO & OFF), 35 Constitution Drive, Suite A.... Bonner, Special Manager (QI), Martine L. Plunkett, Manager, Application Type: Additional QI; Radiant...

  10. 76 FR 41258 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-07-13

    ... Individual), Gediminas Garmus, Member/Manager. Application Type: New OFF License. World Logistics USA, Inc... at (202) 523-5843 or by e-mail at [email protected] . 3 Plus Logistics Co. dba Touchdown Freight Co. (NVO... Logistics, Inc. (NVO), 3120 Via Mondo, Rancho Dominguez, CA 90220. Officer: Simon Hwang, President/CEO...

  11. 75 FR 35815 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-06-23

    ..., TX 76011. Officers: Omar Kolaghassi, Manager (Qualifying Individual), Laura Alicia, Manager. Application Type: New OFF & NVO License. CALS Logistics USA, Inc. (OFF & NVO), 755 North Route 83, Suite 215.... Premium Star Logistics LLC dba O.P. Premium Star Logistics (OFF & NVO), 4200 Lightning Court, Bakersfield...

  12. 77 FR 74186 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-12-13

    ... Logistics, Inc. (NVO & OFF), 7685 NW. 80th Terrace, Medley, FL 33166, Officers: Hugo E. Martinez, Secretary... & OFF), 1834 Harden Blvd., Lakeland, FL 33803, Officers: Steven C. Pniewski, Manager (QI), Manuel R. Echevarria, President, Application Type: New NVO & OFF License, Global Wide Logistics, Inc. (NVO), 1937 Davis...

  13. 78 FR 43202 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-07-19

    .... Alsea Global Logistics, LLC dba Alsea Global Logistics (NVO & OFF), 4836 SE Powell Blvd., Portland, OR... NVO & OFF License. Atlant Consulting Inc. dba Avro Logistics (NVO & OFF), 3626 Geary Blvd., Suite 206..., Officers: Paul Selvage, Member (QI), Steven Periman, Member/Manager, Application Type: Add Trade Name Blu...

  14. 76 FR 14395 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-03-16

    ..., Manager/President. Application Type: QI Change. Geoffrey Au dba ABC Logistics Company (NVO), 2250 Gellert... at (202) 523-5843 or by e-mail at [email protected] . Arkman Logistics Inc. (NVO), 1001 Fargo Avenue, Elk... Type: New NVO & OFF License. BCargo Logistics, S.A. de C.V. (NVO), Av. Revolucion 725-A, Col. Jardin...

  15. 75 FR 29545 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-05-26

    .... Atlantic Cargo Logistics LLC (OFF & NVO), 120 South Woodland Blvd., 216, Deland, FL 32720. Officers: Dietmar Lutte, Manager, (Qualifying Individual) Susan Lutte, Member, Application Type: New OFF & NVO License. Direct Delivery Logistics and Supply, LLC (OFF & NVO) 2006 Wilson Road, Humble, TX 77396...

  16. 77 FR 35384 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-06-13

    ... Logistics LLC (NVO), 9814 Goldenglade Drive, Houston, TX 77064, Officer: Sandra Lesage, Member/Manager... telephone at (202) 523-5843 or by email at [email protected] . ABC Trucking and Logistics L.L.C. (OFF), 3080...), Lawrence R. Lammers, President/CEO, Application Type: License Transfer Atlantic Cargo Logistics LLC (NVO...

  17. 9 CFR 2.11 - Denial of initial license application.

    Science.gov (United States)

    2010-01-01

    ... have violated any Federal, State, or local laws or regulations pertaining to animal cruelty within 1... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Denial of initial license application. 2.11 Section 2.11 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT...

  18. 76 FR 7209 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-02-09

    ... 77032. Officer: Walter Krauklis, OTI Compliance Officer (Qualifying Individual), Thomas B. Crowley, Jr... Road, Suite 14, Newtown Square, PA 19073. Officer: Thomas D. Torcomian, CEO/ Member (Qualifying...). Application Type: New OFF License. Solomon Emeke dba Desaiah Limited (OFF), 3696 Park Avenue, 300, Ellicott...

  19. 76 FR 38651 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-07-01

    ... Shipping (NVO), 1861 Western Way, Torrance, CA 90501. Officers: Hseanrus (Stephen) H. Lin, President/Vice..., President, Application Type: New NVO & OFF License. F.H.L. Logistics, Inc. (NVO & OFF), 1354 NW 78th Avenue..., Gardena, CA 90248. Officers: Anna W. Liu, Vice President (Operations), (Qualifying Individual), Quincy H...

  20. 76 FR 33757 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-06-09

    ... NVO & OFF License. The Ultimate Logistics Service Corporation (NVO & OFF), 3 Birch Place, Pine Brook... Logistics, Corp. (NVO), 4713 Deeboyar, Lakewood, CA 90712. Officer: Tan Sek, Pres/VP/Sec/Treasurer...), Application Type: Add OFF Service. Oceanic Link USA LLC (NVO & OFF), 5430 Jimmy Carter Blvd., Suite 216...

  1. 77 FR 13604 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-03-07

    ... A. Rincon, Manager (Qualifying Individuals), Application Type: Business Structure Change. De Well... Type: New NVO License. King Solomon Logistics Inc. (NVO), 135-14 Liberty Avenue, South [[Page 13605... Logistics Inc. (NVO), 167-16 146th Avenue, Suite 203, Jamaica, NY 11434, Officer: Yau Fung Ling, President...

  2. 78 FR 60282 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-10-01

    ...) pursuant to section 19 of the Shipping Act of 1984 (46 U.S.C. 40101). Notice is also given of the filing of... Castleton Street, Suite 105, City of Industry, CA 91748, Officers: Ya Liu, Deputy General Manager (QI), Jian C. Feng, Director, Application Type: New NVO License, By the Commission. Dated: September 27, 2013...

  3. 77 FR 39707 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-07-05

    ..., Application Type: New OFF License. Best Global Logistics USA, Inc dba Siam Intercargo Services (NVO & OFF... International Transport, LLC (NVO), 6048 Lido Lane, Long Beach, CA 90803, Officer: Charles Brennan, Member...: Add NVO Service. Sinai Logistics LLC (NVO & OFF), 11419 NW. 112th Street, Medley, FL 33178, Officer...

  4. 76 FR 16420 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-03-23

    ...), Andrew P. Bottomley, Managing Partner, Application Type: QI Change and Add OFF Service. All Transport... Type: New NVO & OFF License. Andrea Bigi dba AB Global Logistics Consulting (OFF), 1010 19th Street, 10.... Officers: Joanne Kirkpatrick, International Logistics Officer (Qualifying Individual), Jack R. Lentz, CEO...

  5. 76 FR 65193 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-10-20

    ... at (202) 523-5843 or by e-mail at [email protected] . AB Global Logistics Consulting Inc. (OFF), 1010 19th..., Application Type: New NVO License. All Transport Export Inc (NVO & OFF), 4224 Shackleford Road, 3, Norcross... Type: Name Change. CR & J Logistics, Inc. (OFF), 8401 Lake Worth Road, Lake Worth, FL 33467. Officers...

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

    Science.gov (United States)

    2011-08-24

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

  7. Application of coupled codes for safety analysis and licensing issues

    International Nuclear Information System (INIS)

    Langenbuch, S.; Velkov, K.

    2006-01-01

    An overview is given on the development and the advantages of coupled codes which integrate 3D neutron kinetics into thermal-hydraulic system codes. The work performed within GRS by coupling the thermal-hydraulic system code ATHLET and the 3D neutronics code QUABOX/CUBBOX is described as an example. The application of the coupled codes as best-estimate simulation tools for safety analysis is discussed. Some examples from German licensing practices are given which demonstrate how the improved analytical methods of coupled codes have contributed to solve licensing issues related to optimized and more economical use of fuel. (authors)

  8. Fuel Receiving and Storage Station. License application, amendment 7

    International Nuclear Information System (INIS)

    1976-02-01

    Amendment No. 7 to Allied-General Nuclear Services application for licensing of the Fuel Receiving and Storage Station consists of revised pages for: Amendment No. 7 to AG-L 105, ''Technical Description in Support of Application for FRSS Operation''; Amendment No. 1 to AG-L 105A, ''Early Operation of the Service Concentrator''; and Amendment No. 2 to AG-L 110, ''FRSS Summary Preoperational Report.''

  9. Total System Performance Assessment - License Application Methods and Approach

    Energy Technology Data Exchange (ETDEWEB)

    J. McNeish

    2003-12-08

    ''Total System Performance Assessment-License Application (TSPA-LA) Methods and Approach'' provides the top-level method and approach for conducting the TSPA-LA model development and analyses. The method and approach is responsive to the criteria set forth in Total System Performance Assessment Integration (TSPAI) Key Technical Issues (KTIs) identified in agreements with the U.S. Nuclear Regulatory Commission, the ''Yucca Mountain Review Plan'' (YMRP), ''Final Report'' (NRC 2003 [163274]), and the NRC final rule 10 CFR Part 63 (NRC 2002 [156605]). This introductory section provides an overview of the TSPA-LA, the projected TSPA-LA documentation structure, and the goals of the document. It also provides a brief discussion of the regulatory framework, the approach to risk management of the development and analysis of the model, and the overall organization of the document. The section closes with some important conventions that are used in this document.

  10. 21 CFR 515.20 - Approval of medicated feed mill license applications.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 6 2010-04-01 2010-04-01 false Approval of medicated feed mill license... SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Administrative Actions on Licenses § 515.20 Approval of medicated feed mill license applications. Within 90 days after an...

  11. 21 CFR 515.21 - Refusal to approve a medicated feed mill license application.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 6 2010-04-01 2010-04-01 false Refusal to approve a medicated feed mill license... SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Administrative Actions on Licenses § 515.21 Refusal to approve a medicated feed mill license application. (a) The...

  12. NPP long term operation in Spain - First application for license renewal

    International Nuclear Information System (INIS)

    Francia, L.; Gorrochategui, I.; Marcos, R.

    2007-01-01

    Full text: In the operation of the Spanish nuclear power plants (NPP), safety is always the prime consideration. Plant Life Management Programmes have been set up with the strategic objective to operate the NPPs as long as they are considered safe and reliable. The safety of each NPP is reviewed by the Spanish nuclear regulatory authority (CSN) under a continuous process. In addition, experience is gained from operating the plants and from exchanges with operators of similar units. Current Spanish regulatory framework for renewing NPP operating licenses requires performing a Periodic Safety Review (PSR) to be performed every 10 years and submitted when applying for a new renewal of the NPP operating license. A few years ago, CSN issued a document regarding the licensing requirements that nuclear power plants should meet in order to be granted with an operating license for long term operation (i.e, operation beyond the original plant design life, typically 40 years). Besides the traditional PSR requirements, specific requirements regarding to long term operation (LTO) include: - An Aging Management and Evaluation Program, including the identification and evaluation of Time Limited Aging Analysis (TLAA). - An updated Radiological Impact Study. - A review and assessment of regulation/standard applicability. Garona NPP (GE, BWR/3 design) operated by Spanish utility Nuclenor from 1971 has a current operating license up to 2009. A decision was made to apply for a new operating license, being Garona plant the first one in Spain to face with the new long term operation requirements. The paper will provide an overview of the methodology used in Spain to address and perform the required analyses to support the LTO application for the operating license renewal. In particular, focus will be paid on the project developed in Garona (2002-2006) whose result has been the first Spanish application for License Renewal for LTO. Also it will be reported the ongoing work necessary to

  13. 78 FR 37324 - Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications

    Science.gov (United States)

    2013-06-20

    ... Environmental Reports for Nuclear Power Plant License Renewal Applications AGENCY: Nuclear Regulatory Commission... for Nuclear Power Plant License Renewal Applications.'' This regulatory guide provides guidance to... renewal of a nuclear power plant operating license. Applicants should use this regulatory guide when...

  14. 47 CFR 87.47 - Application for a portable aircraft station license.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Application for a portable aircraft station... SPECIAL RADIO SERVICES AVIATION SERVICES Applications and Licenses § 87.47 Application for a portable aircraft station license. A person may apply for a portable aircraft radio station license if the need...

  15. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

  16. Do US Medical Licensing Applications Treat Mental and Physical Illness Equivalently?

    Science.gov (United States)

    Gold, Katherine J; Shih, Elizabeth R; Goldman, Edward B; Schwenk, Thomas L

    2017-06-01

    State medical licensing boards are responsible for evaluating physician impairment. Given the stigma generated by mental health issues among physicians and in the medical training culture, we were interested in whether states asked about mental and physical health conditions differently and whether questions focused on current impairment. Two authors reviewed physician medical licensing applications for US physicians seeking first-time licensing in 2013 in the 50 states and the District of Columbia. Questions about physical and mental health, as well as substance abuse, were identified and coded as to whether or not they asked about diagnosis and/or treatment or limited the questions to conditions causing physician impairment. Forty-three (84%) states asked questions about mental health conditions, 43 (84%) about physical health conditions, and 47 (92%) about substance use. States were more likely to ask for history of treatment and prior hospitalization for mental health and substance use, compared with physical health disorders. Among states asking about mental health, just 23 (53%) limited all questions to disorders causing functional impairment and just 6 (14%) limited to current problems. While most state medical licensing boards ask about mental health conditions or treatment, only half limited queries to disorders causing impairment. Differences in how state licensing boards assess mental health raise important ethical and legal questions about assessing physician ability to practice and may discourage treatment for physicians who might otherwise benefit from appropriate care.

  17. 76 FR 65544 - Standard Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities

    Science.gov (United States)

    2011-10-21

    ... NUCLEAR REGULATORY COMMISSION [NRC-2009-0323] Standard Format and Content of License Applications... revision to regulatory guide (RG) 3.39, ``Standard Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities.'' This guide endorses the standard format and content for license...

  18. 21 CFR 515.11 - Supplemental medicated feed mill license applications.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 6 2010-04-01 2010-04-01 false Supplemental medicated feed mill license... SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Applications § 515.11 Supplemental medicated feed mill license applications. (a) After approval of a medicated feed...

  19. 75 FR 3261 - Powertech (USA) Inc.; Dewey-Burdock Project; New Source Material License Application; Notice of...

    Science.gov (United States)

    2010-01-20

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 40-9075; NRC-2009-0575] Powertech (USA) Inc.; Dewey... review process related to the Dewey- Burdock Uranium Project application, please contact the NRC... documents associated with the Dewey-Burdock Uranium Project, including the license application, are...

  20. Independent modelling in SSM's licensing review of a spent nuclear fuel repository

    International Nuclear Information System (INIS)

    Xu, Shulan; Dverstorp, Bjoern; Norden, Maria

    2014-01-01

    In 2011 the Swedish Nuclear Fuel and Waste Management Co. (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel at Forsmark. SKB's disposal method, the KBS-3 method, involves disposing of the spent nuclear fuel in cast iron canisters with an outer layer of 5 cm copper. The canisters will be placed in vertical deposition holes at approximately 500 m depths in crystalline bedrock. Each canister is surrounded by a buffer of swelling bentonite clay. The repository is designed to accommodate 6 000 canisters, corresponding to 12 000 tonnes of spent nuclear fuel. The license application is supported by a post-closure safety assessment, SR-Site. Along with other parts of the application, SR-Site is currently being reviewed by the Swedish Radiation Safety Authority (SSM). The main method for review of SKB's licensing documentation is document review carried out by SSM, supported by SSM's external experts. However, SSM's document review is also supported by regulatory modelling, technical reviews of SKB's quality assurance programme and consideration of external review comments partly from two broad national consultations and an international peer review organised by the OECD's Nuclear Energy Agency (NEA, 2012). SSM's review is divided into three main phases: the initial review phase, the main review phase and the reporting phase. The overall goal of the initial review phase is to achieve a broad coverage of SR-Site and its supporting references and in particular to identify the need for complementary information and clarifications to be provided by SKB, as well as to identify critical review issues that require a more comprehensive treatment in the main review phase. SSM completed the initial review phase at the end of 2012. During the initial review phase SSM has identified a number of issues requiring either clarifications, complementary information from SKB or further in-depth review by SSM. Important issues include the

  1. License Application Design Selection Feature Report: Aging and Blending

    International Nuclear Information System (INIS)

    Coltoni, B.; Anderson, M.J.

    1999-01-01

    The purpose of this document is to evaluate the concepts of Aging and Blending for waste sent to the Monitored Geologic Repository (MGR). These design features are based on pre-emplacement treatment of the waste stream. The envelope of the analysis has been performed under the direction of the License Application Design Selection Team (LADST), which advocated utilizing the Viability Assessment (VA) repository design (DOE 1998c) as the basis. Therefore, this evaluation attempts to modify the VA design only to the extent that Aging and Blending can be accomplished. This modified VA design will be contrasted to the VA Design and the difference in design, costs, and performance will be presented

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

    International Nuclear Information System (INIS)

    1989-07-01

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

  3. 21 CFR 515.25 - Revocation of order refusing to approve a medicated feed mill license application or suspending...

    Science.gov (United States)

    2010-04-01

    ... medicated feed mill license application or suspending or revoking a license. 515.25 Section 515.25 Food and..., FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Administrative Actions on Licenses § 515.25 Revocation of order refusing to approve a medicated feed mill license application or suspending or revoking a...

  4. 78 FR 21930 - Aquenergy Systems, Inc.; Notice of Intent To File License Application, Filing of Pre-Application...

    Science.gov (United States)

    2013-04-12

    ... Systems, Inc.; Notice of Intent To File License Application, Filing of Pre-Application Document, and Approving Use of the Traditional Licensing Process a. Type of Filing: Notice of Intent to File License...: November 11, 2012. d. Submitted by: Aquenergy Systems, Inc., a fully owned subsidiaries of Enel Green Power...

  5. A meta-analytic review of moral licensing.

    Science.gov (United States)

    Blanken, Irene; van de Ven, Niels; Zeelenberg, Marcel

    2015-04-01

    Moral licensing refers to the effect that when people initially behave in a moral way, they are later more likely to display behaviors that are immoral, unethical, or otherwise problematic. We provide a state-of-the-art overview of moral licensing by conducting a meta-analysis of 91 studies (7,397 participants) that compare a licensing condition with a control condition. Based on this analysis, the magnitude of the moral licensing effect is estimated to be a Cohen's d of 0.31. We tested potential moderators and found that published studies tend to have larger moral licensing effects than unpublished studies. We found no empirical evidence for other moderators that were theorized to be of importance. The effect size estimate implies that studies require many more participants to draw solid conclusions about moral licensing and its possible moderators. © 2015 by the Society for Personality and Social Psychology, Inc.

  6. Health physics aspects of advanced reactor licensing reviews

    International Nuclear Information System (INIS)

    Hinson, C.S.

    1995-01-01

    The last Construction Permit to be issued by the U.S. Nuclear Regulatory Commission (NRC) for a U.S. light water reactor (LWR) was granted in the late 1970s. In 1989 the NRC issued 10 CFR Part 52 which is intended to serve as a framework for the licensing of future reactor designs. The NRC is currently reviewing four different future on open-quotes next-generationclose quotes reactor designs. Two of these designs are classified as evolutionary designs (modified versions of current generation LWRs) and two are advanced designs (reactors incorporating simplified designs and passive means for accident mitigation). These open-quotes next-generationclose quotes reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four open-quotes next-generationclose quotes reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four open-quotes next-generationclose quotes reactor designs currently being reviewed by the NRC

  7. Health physics aspects of advanced reactor licensing reviews

    Energy Technology Data Exchange (ETDEWEB)

    Hinson, C.S. [Nuclear Regulatory Commission, Washington, DC (United States)

    1995-03-01

    The last Construction Permit to be issued by the U.S. Nuclear Regulatory Commission (NRC) for a U.S. light water reactor (LWR) was granted in the late 1970s. In 1989 the NRC issued 10 CFR Part 52 which is intended to serve as a framework for the licensing of future reactor designs. The NRC is currently reviewing four different future on {open_quotes}next-generation{close_quotes} reactor designs. Two of these designs are classified as evolutionary designs (modified versions of current generation LWRs) and two are advanced designs (reactors incorporating simplified designs and passive means for accident mitigation). These {open_quotes}next-generation{close_quotes} reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} reactor designs currently being reviewed by the NRC.

  8. A Meta-Analytic Review of Moral Licensing

    NARCIS (Netherlands)

    Blanken, Irene; van de Ven, Niels; Zeelenberg, Marcel

    2015-01-01

    Moral licensing refers to the effect that when people initially behave in a moral way, they are later more likely to display behaviors that are immoral, unethical, or otherwise problematic. We provide a state-of-the-art overview of moral licensing by conducting a meta-analysis of 91 studies (7,397

  9. A meta-analytic review of moral licensing

    NARCIS (Netherlands)

    Blanken, I.; van de Ven, N.; Zeelenberg, M.

    2015-01-01

    Moral licensing refers to the effect that when people initially behave in a moral way, they are later more likely to display behaviors that are immoral, unethical, or otherwise problematic. We provide a state-of-the-art overview of moral licensing by conducting a meta-analysis of 91 studies (7,397

  10. EC6 design features and pre-project licensing review

    Energy Technology Data Exchange (ETDEWEB)

    Yu, S.; Lee, A.G.; Dinh, N.B.; Soulard, M. [CANDU Energy Inc., Mississauga, Ontario, (Canada)

    2013-07-01

    The Enhanced CANDU 6 (EC6) is the new Generation III CANDU reactor design that meets the most up to date Canadian regulatory requirements and customer expectations. Candu Energy Inc. is finalizing development of the EC6 which incorporates the CANDU 6's well-proven features, and adds enhancements that strengthened reactor safety margin and improved operability. The EC6 builds on the proven high performance design and the defence-in-depth features of CANDU 6 units, and has incorporated extensive operational feedback including lessons learned from Fukushima. This paper will provide status of the engineering program including progress on the pre-licensing review of the EC6 design by the Canadian Regulator, CNSC, and will also highlight the design and safety enhancements incorporated in the EC6 product. Safety enhancements to meet safety goals and to improve robustness of systems to respond to design basis accidents and beyond design basis accidents include: new severe accident recovery and heat removal system; improved emergency heat removal system; faster shutoff rods with improved safety margins; mechanical guaranteed shutdown rods; daily load cycling capability; robust containment with containment filter venting system; and improved backed-up electrical supply and cooling services. (author)

  11. Strategic Basis for License Application Planning for a Potential Yucca Mountain Repository

    International Nuclear Information System (INIS)

    Newberry, C. M.; Brocoum, S. J.; Gamble, R. P.; Murray, R. C.; Cline, M.

    2002-01-01

    If Yucca Mountain, Nevada is designated as the site for development of a geologic repository for disposal of spent nuclear fuel and high-level radioactive waste, the Department of Energy (DOE) must obtain Nuclear Regulatory Commission (NRC) approval first for repository construction, then for an operating license, and, eventually, for repository closure and decommissioning. The licensing criteria defined in Code of Federal Regulations, Title 10, Part 63 (10 CFR Part 63) establish the basis for these NRC decisions. Submittal of a license application (LA) to the NRC for authorization to construct a repository at the Yucca Mountain site is, at this point, only a potential future action by the DOE. The policy process defined in the Nuclear Waste Policy Act (NWPA), as amended, for recommendation and designation of Yucca Mountain as a repository site makes it difficult to predict whether or when the site might be designated. The DOE may only submit a LA to the NRC if the site designation takes effect. In spite of this uncertainty, the DOE must take prudent and appropriate action now, and over the next several years, to prepare for development and timely submittal of a LA. This is particularly true given the need for the DOE to develop, load, and certify the operation of its electronic information system to provide access to its relevant records as part of the licensing support network (LSN) in compliance with NRC requirements six months prior to LA submittal. The DOE must also develop a LA, which is a substantially different document from those developed to support a Site Recommendation (SR) decision. The LA must satisfy NRC licensing criteria and content requirements, and address the acceptance criteria defined by the NRC in its forthcoming Yucca Mountain Review Plan (YMRP). The content of the LA must be adequate to facilitate NRC acceptance and docketing for review, and the LA and its supporting documents must provide the documented basis for the NR C findings required

  12. License Application Design Selection Report, REV 01. August 1999

    International Nuclear Information System (INIS)

    Hastings, C.R.

    1999-01-01

    In December 1998, the U.S. Department of Energy (DOE) published the ''Viability Assessment of a Repository at Yucca Mountain'' (DOE 1998b). The Viability Assessment described a preliminary design of a potential repository at Yucca Mountain, Nevada, for disposal of spent nuclear fuel and high-level radioactive waste, and assessed the probable behavior of that repository design in the Yucca Mountain geologic setting. The report concluded that 'Yucca Mountain remains a promising site for a geologic repository and that work should proceed to support a decision in 2001 on whether to recommend the site to the President for development as a repository'. It also concluded that 'uncertainties remain about key natural processes, the preliminary design, and how the site and design would interact'. Recognizing that the design that was evaluated will be refined before a license application could be submitted, the Viability Aassesment notes that 'DOE is evaluating several design options and alternatives that could reduce existing uncertainty and improve the performance of the repository system'. During the preparation of the Viability Assessment, DOE asked the contractor for the Civilian Radioactive Waste Management Program to study alternative design concepts for a potential geologic repository for high-level radioactive waste at Yucca Mountain. The License Application Design Selection (LADS) project was initiated to conduct that study. The goal of the project was to develop and evaluate a diverse range of conceptual repository designs that work well in concert with the Yucca Mountain site and to recommend an initial design concept for the possible Site Recommendation and License Apllication. This report presents the results of the LADS project. The design process consisted of two phases. In Phase I, a series of basic design concepts (design alternatives) and components (design features) were analyzed for their potential value as elements of a repository design. In Phase II

  13. Licensing of spent fuel dry storage and consolidated rod storage: A Review of Issues and Experiences

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, W.J.

    1990-02-01

    The results of this study, performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE), respond to the nuclear industry's recommendation that a report be prepared that collects and describes the licensing issues (and their resolutions) that confront a new applicant requesting approval from the US Nuclear Regulatory Commission (NRC) for dry storage of spent fuel or for large-scale storage of consolidated spent fuel rods in pools. The issues are identified in comments, questions, and requests from the NRC during its review of applicants' submittals. Included in the report are discussions of (1) the 18 topical reports on cask and module designs for dry storage fuel that have been submitted to the NRC, (2) the three license applications for dry storage of spent fuel at independent spent fuel storage installations (ISFSIs) that have been submitted to the NRC, and (3) the three applications (one of which was later withdrawn) for large-scale storage of consolidated fuel rods in existing spent fuel storage pools at reactors that were submitted tot he NRC. For each of the applications submitted, examples of some of the issues (and suggestions for their resolutions) are described. The issues and their resolutions are also covered in detail in an example in each of the three subject areas: (1) the application for the CASTOR V/21 dry spent fuel storage cask, (2) the application for the ISFSI for dry storage of spent fuel at Surry, and (3) the application for full-scale wet storage of consolidated spent fuel at Millstone-2. The conclusions in the report include examples of major issues that applicants have encountered. Recommendations for future applicants to follow are listed. 401 refs., 26 tabs.

  14. 78 FR 46255 - Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction

    Science.gov (United States)

    2013-07-31

    ... Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction AGENCY: Nuclear... nuclear power plant. Compliance with the provisions of the rule is required by June 20, 2014. This... environmental effect of renewing the operating license of a nuclear power plant. This document is necessary to...

  15. Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses

    Energy Technology Data Exchange (ETDEWEB)

    Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

    1994-08-01

    This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected.

  16. Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses

    International Nuclear Information System (INIS)

    Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

    1994-08-01

    This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected

  17. NUPLEX Licensing Subcommittee

    International Nuclear Information System (INIS)

    Edwards, D.W.; Allen, S.R.

    1988-01-01

    The NUPLEX Licensing Subcommittee was organized to seek a formal license renewal mechanism that institutionalizes the current licensing basis and consequent level of safety of a plant as the legitimate standard for acceptance and approval of an application for extended operation. Along with defining the most workable approach to and scope of review for license renewal, this paper explains the reasons why a regulatory framework is needed by the early 1990s. The initial results of development work on two key issues, licensing criteria and hearing process, are also presented. at this point six potential license renewal criteria have emerged: evaluation of existing monitoring/maintenance programs, revalidation of current licensing basis, conformance to special regulations, evaluation to a safety goal, plant performance history, and environmental assessment. The work on a hearing process has led to the development of two models for future consideration: hybrid legislative and hybrid adjudicatory

  18. 77 FR 70837 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-11-27

    ... intervene shall be filed in accordance with the Commission's ``Rules of Practice for Domestic Licensing... request: The proposed change will delete Function 14, SG [Steam Generator] Water Level--Low, Coincident... capability to shut down the reactor when required on Low--Low Steam Generator water level. The ability to...

  19. 78 FR 16876 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-03-19

    ... intervene shall be filed in accordance with the Commission's ``Rules of Practice for Domestic Licensing... proposes to replace the VHS with an onsite diesel generator as the AAC power source providing this... power source (the VHS) with an additional onsite AAC power source (diesel generator). This equipment can...

  20. 77 FR 63343 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-10-16

    ... in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10... for an inoperable diesel generator (DG). A commensurate change is also proposed to extend the maximum... alternating current power source (i.e., a supplemental diesel generator) with the capability to power any E...

  1. 77 FR 73684 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-12-11

    ... in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10... emergency diesel generator, and the stored lube oil inventory will also continue to require that a 7-day supply be available for each diesel generator. The changes are consistent with NRC-approved Technical...

  2. 77 FR 67679 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-11-13

    ... diesel generator surveillance requirements. Margin of safety is related to the ability of the fission... evaluated; or (3) involve a significant reduction in a margin of safety. The basis for this proposed... accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2...

  3. 78 FR 14126 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-03-04

    ... in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10... of the document. The E-Filing system also distributes an email notice that provides access to the... Completion Time has no impact on the consequences of any design basis accident since the consequences of an...

  4. List of Nuclear Materials Licensing Actions Received

    Data.gov (United States)

    Nuclear Regulatory Commission — A catalog of all Materials Licensing Actions received for review. The catalog lists the name of the entity submitting the license application, their city and state,...

  5. 76 FR 72984 - Revised Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2011-11-28

    ... NUCLEAR REGULATORY COMMISSION Revised Application for a License To Export High-Enriched Uranium The application for a license to export high-enriched Uranium has been revised as noted below. Notice... fabricate fuel France. Security Complex; October 18, Uranium (93.35%). uranium (174.0 elements in France...

  6. 76 FR 49462 - Newfound Hydroelectric Company, KTZ Hydro, LLC; Notice of Application for Transfer of License...

    Science.gov (United States)

    2011-08-10

    ... Hydroelectric Company, KTZ Hydro, LLC; Notice of Application for Transfer of License, and Soliciting Comments and Motions To Intervene On July 25, 2011, Newfound Hydroelectric Company (transferor) and KTZ Hydro, LLC (transferee) filed an application for transfer of license for the Newfound Hydroelectric Project...

  7. 76 FR 59173 - Standard Format and Content of License Applications for Conventional Uranium Mills

    Science.gov (United States)

    2011-09-23

    ... NUCLEAR REGULATORY COMMISSION [NRC-2008-0302] Standard Format and Content of License Applications for Conventional Uranium Mills AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide..., ``Standard Format and Content of License Applications for Conventional Uranium Mills.'' DG- 3024 was a...

  8. 75 FR 70350 - Liberty Natural Gas LLC, Liberty Liquefied Natural Gas (LNG) Deepwater Port License Application

    Science.gov (United States)

    2010-11-17

    ... DEPARTMENT OF TRANSPORTATION Maritime Administration [USCG-2010-0993] Liberty Natural Gas LLC, Liberty Liquefied Natural Gas (LNG) Deepwater Port License Application AGENCY: Maritime Administration... announce they have received an application for the licensing of a natural gas deepwater port and the...

  9. SKB's safety case for a final repository license application

    International Nuclear Information System (INIS)

    Hedin, Allan; Andersson, Johan

    2014-01-01

    The safety assessment SR-Site is a main component in SKB's license application, submitted in March 2011, to construct and operate a final repository for spent nuclear fuel at Forsmark in the municipality of Oesthammar, Sweden. Its role in the application is to demonstrate long-term safety for a repository at Forsmark. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. The principal regulatory acceptance criterion, issued by the Swedish Radiation Safety Authority (SSM), requires that the annual risk of harmful effects after closure not exceed 10 -6 for a representative individual in the group exposed to the greatest risk. SSM's regulations also imply that the assessment time for a repository of this type is one million years after closure. The licence applied for is one in a stepwise series of permits, each requiring a safety report. The next step concerns a permit to start excavation of the repository and requires a preliminary safety assessment report (PSAR) covering both operational and post-closure safety. Later steps include permission to commence trial operation, to commence regular operation and to close the final repository. (authors)

  10. 75 FR 69080 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-11-10

    ... license as a Non-Vessel-Operating Common Carrier (NVO), and/or Ocean Freight Forwarder (OFF)--Ocean..., Building 14-A, Kenner, LA 70062, Officers: Gary J. Cheramie, President (Qualifying Individual), George...: License Transfer. Total Global Solutions, Inc. (NVO & OFF), 4290 Bells Ferry Road 224, Suite 106, Kennesaw...

  11. 78 FR 32650 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-05-31

    ... Change Abaco Logistics Corporation (OFF), 8051 NW 67th Street, Miami, FL 33166, Officers: Manuel T. Soto...: New NVO & OFF License Star Cluster Logistics (NVO & OFF), 4 Executive Circle, Suite 170, Irvine, CA... License Straight Forwarding, Inc. (NVO & OFF), 20974 Currier Road, City of Industry, CA 91789, Officer: Yi...

  12. Standard format and content for the physical protection section of a license application (for facilities other than nuclear power plants)

    International Nuclear Information System (INIS)

    1976-06-01

    The document presented has been prepared as an aid to uniformity and completeness in the preparation and review of the physical protection section of license applications. It is applicable to fuel reprocessing plants, fuel manufacturing plants, SNM tranportation, or other special nuclear material operations involving the possession and use of uranium 235 (contained in uranium enriched to 20 percent or more in the U-235 isotope), uranium 233, or plutonium alone or in any combination in a quantity of 5000 grams or more computed by the formula: grams = (grams contained U-235) + 2.5 (grams U-233 + grams plutonium). The document is not intended to be used for nuclear power plants. The information specified is the minimum needed for a license application. Additional information may be required for completion of the staff review of a particular application

  13. Conduct of regulatory review and assessment during the licensing process for nuclear power plants

    International Nuclear Information System (INIS)

    1980-01-01

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Code of Practice on Governmental Organization for the Regulation of Nuclear Power Plants (IAEA Safety Series No. 50-C-G) and is concerned with the review and assessment by the regulatory body of all information submitted in support of licence applications, in the various phases of the licensing process. The purpose of the Guide is to provide information, recommendations and guidance for the conduct of these activities. The scope of the review and assessment will encompass the safety aspects of siting, construction, commissioning, operation and decommissioning of each nuclear power plant

  14. Medical review practices for driver licensing volume 3: guidelines and processes in the United States.

    Science.gov (United States)

    2017-04-01

    This is the third of three reports examining driver medical review practices in the United States and how : they fulfill the basic functions of identifying, assessing, and rendering licensing decisions on medically or : functionally at-risk drivers. ...

  15. 75 FR 76757 - Licensing Support System Advisory Review Panel

    Science.gov (United States)

    2010-12-09

    ... provide advice on the fundamental issues of design and development of an electronic information management... the disposal of high-level radioactive waste, and on the operation and maintenance of the system. This electronic information management system was known as the Licensing Support System (LSS). In November, 1998...

  16. PSA in licensing, safety reviews and design as applied in Germany

    International Nuclear Information System (INIS)

    Berg, H.P.; Goertz, R.; Schott, H.; Wendling, R.D.

    1994-01-01

    In this paper, two topics - the application of PSA in the regulatory process and the effort to improve PSA methods and models - are addressed. From the regulators' point of view, the most important application of PSA in Germany is presently within the safety reviews of nuclear power plants in operation. The current status of regulatory guidance which shall be provided to establish a uniform procedure for a periodic safety review is described with special emphasis on the role of PSA. An important goal is to have all plant-specific PSAs comparable as far as possible. Guidance for PSA review is under development likewise. Furthermore, the application of PSA in licensing of nuclear power plants is addressed as well as its use in the design process of future pressurized water reactors. The development of models and methods to be applied in PSA has been and will be supported by a number of studies and investigations. An overview of the main issues of these investigations is provided. A specific task was the elaboration of a proposal for incorporating fire events into the PSA. The status of these efforts is outlined. (author). 7 refs, 3 figs, 2 tabs

  17. Licensing process for future applications of advanced-design nuclear reactors

    International Nuclear Information System (INIS)

    Miller, C.L.

    1990-01-01

    The existing 10CFR50 two-step licensing process in the Code of Federal Regulations can continue to be a viable licensing vehicle for future applications, at least for the near future. The US Nuclear Regulatory Commission (NRC) Commissioners and staff, the public, and the utilities (along with supporting architect/engineers and nuclear steam supply system vendors) have a vast body of experience and knowledge of the existing part 50 licensing process. All these participants are familiar with their respective roles in this process, and history shows this process to be a workable licensing vehicle. Nevertheless, the use of 10CFR52 should be encouraged for future applications. This proposed new rule is intended to achieve the early resolution of licensing issues, to reduce the complexity and uncertainty of the licensing process, and enhance the safety and reliability of nuclear power plants. Part 52's overall purpose is to improve reactor safety and streamline the licensing process by encouraging the use of standard reactor designs and by allowing the early resolution of site environmental and reactor safety issues. The public should be afforded an earlier entry into the licensing process as a result of design certification rulemaking process and combined construction permit/operating license hearings

  18. Medical review practices for driver licensing volume 2: case studies of medical referrals and licensing outcomes in Maine, Ohio, Oregon, Texas, Washington, and Wisconsin.

    Science.gov (United States)

    2017-03-01

    This is the second of three reports examining driver medical review practices in the United States and how : they fulfill the basic functions of identifying, assessing, and rendering licensing decisions on medically at-risk : drivers. This volume pre...

  19. Recommendations for the hydrogeologic review and assessment of sites for nuclear power installations within the framework of the radiation protection licensing procedure

    International Nuclear Information System (INIS)

    Adam, C.; Petschel, M.; Koerner, W.

    1985-01-01

    Article 4 of the Nuclear Facility Licensing Ordinance requires the information to be submitted in support of licensing applications for nuclear power installations to include an expertise on the hydrogeologic characteristics of the site environment with main emphasis on the movement of radionuclides through groundwater in the event of accident conditions, and on measures to protect ground and surface waters. Recommendations are given for the conduct of a hydrogeologic review and assessment process and its timing relative to the individual stages in the licensing procedure. (author)

  20. 78 FR 69852 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-11-21

    .... dba Freight Team dba iGlobal US (NVO & OFF), 15930 Valley Boulevard, City of Industry, CA 91744.... Amexlog Corporation dba Amex Logistics Corp (NVO & OFF), 1970 NW 70th Avenue, Miami, FL 33126. Officers... License. Canfleet Logistics Ltd. (NVO), 1408-700 West Pender Street, Vancouver, B.C. V6C 1G8. Officers...

  1. 76 FR 72409 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-11-23

    ... NVO Service. Pink City Logistics USA LLC (NVO & OFF), 7 Emily Road, Manalapan, NJ 07726; Officers... at (202) 523-5843 or by email at [email protected] . AE Eagle Logistics Inc. (NVO & OFF), 765 Route 83... License. Daybreak Logistics, Inc. (NVO & OFF), 2804 N. Cannon Blvd., Kannapolis, NC 28083; Officers...

  2. 77 FR 3773 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-01-25

    .... Hartwig Gdynia dba C. Hartwig Transport (NVO), 7, Derdowskiego Street, 81-369 Gdynia, Poland. Officers...: New OFF License. Cheryl G. Wilson dba JC Logistics (NVO & OFF), 28612 Redondo Beach Drive South, Des...: Add NVO Service. CR & J Logistics, Inc. dba Brightwater Shipping Services (NVO & OFF), 8401 Lake Worth...

  3. Use of limited information in a license application to construct a repository

    International Nuclear Information System (INIS)

    McGarry, J.M. III; Echols, F.S.

    1996-01-01

    The purpose of this paper is to provide a rationale for the proposition that the Department of Energy's (DOE's) submittal of a license application (LA) for the construction of a geologic repository to the Nuclear Regulatory Commission (NRC) may be, and arguably must be, based on statutorily-limited site characterization data and design information. The Nuclear Waste Policy Act of 1982 (NWPA), as amended, is the controlling statute for the disposal of spent nuclear fuel in a licensed geologic repository. Applicable NRC regulations for the licensing of such a repository are found for the most part in 10 C.F.R. Part 60

  4. 77 FR 74841 - Alabama Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2012-12-18

    ... patrons who access the restaurant by boat. l. Locations of the Application: A copy of the application is... Company; Notice of Application for Amendment of License and Soliciting Comments, Motions To Intervene, and Protests Take notice that the following hydroelectric application has been filed with the Commission and is...

  5. 78 FR 73566 - Standard Format and Content for a License Application for an Independent Spent Fuel Storage...

    Science.gov (United States)

    2013-12-06

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0264] Standard Format and Content for a License...), DG-3042, ``Standard Format and Content for a License Application for an Independent Spent Fuel..., Form, and Contents,'' specifies the information that must be in an application for a license to store...

  6. 77 FR 33243 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Science.gov (United States)

    2012-06-05

    ... expansion process, thermal expansion mismatch between the tube and tubesheet, and from the differential... NUCLEAR REGULATORY COMMISSION [NRC-2012-0125] Applications and Amendments to Facility Operating...

  7. Other best-estimate code and methodology applications in addition to licensing

    International Nuclear Information System (INIS)

    Tanarro, A.

    1999-01-01

    Along with their applications for licensing purposes, best-estimate thermalhydraulic codes allow for a wide scope of additional uses and applications, in which as realistic and realizable results as possible are necessary. Although many of these applications have been successfully developed nowadays, the use of best-estimate codes for applications other than those associated to licensing processes is not so well known among the nuclear community. This issue shows some of these applications, briefly describing their more significant and specific features. (Author)

  8. Organization and practices on regulatory review in the licensing process of nuclear power plants in Spain

    International Nuclear Information System (INIS)

    Trueba, P.

    1979-01-01

    The actual organisation, practices and experience of the JEN Nuclear Safety Department on the regulatory review in the licensing process of nuclear power plants in Spain, are presented. Topics to be covered are: The structure, organisation, staff and principal functional areas of the NSD, the academic qualifications and work experience of the NSD personnel, recruiting and training, the conduct of the regulatory review during the licensing process and working procedures, the manpower and coverage of the different technical areas, the principal problems and conclusions. (author)

  9. 77 FR 39521 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Science.gov (United States)

    2012-07-03

    ... primary- to-secondary leakage (including locked rotor and control rod ejection) has been shown to remain... Water Reactors with AREVA Topical Report ANP- 10307PA, Revision 0, ``AREVA MCPR Safety Limit Methodology for Boiling Water Reactors,'' in the list of analytical methods that have been reviewed and approved...

  10. 78 FR 77729 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-12-24

    ... existing batteries. Battery circuit coordination is not adversely affected by the addition of the new... Factors Engineering (HFE) Reports (prepared by Westinghouse and the NRC reviewed these reports as part of...: HFE Integrated System Validation (APP-OCS-GEH-320) (LAR 13-001) HFE Design Verification Plan (APP-OCS...

  11. Preparing to Submit a License Application for Yucca Mountain

    International Nuclear Information System (INIS)

    W.J. Arthur; M.D. Voegele

    2005-01-01

    In 1982, the U.S. Congress passed the Nuclear Waste Policy Act, a Federal law that established U.S. policy for the permanent disposal of spent nuclear fuel and high-level radioactive waste. Congress amended the Act in 1987, directing the Department of Energy to study only Yucca Mountain, Nevada as the site for a permanent geologic repository. As the law mandated, the Department evaluated Yucca Mountain to determine its suitability as the site for a permanent geologic repository. Decades of scientific studies demonstrated that Yucca Mountain would protect workers, the public, and the environment during the time that a repository would be operating and for tens of thousands of years after closure of the repository. A repository at this remote site would also: preserve the quality of the environment; allow the environmental cleanup of Cold War weapons facilities; provide the nation with additional protection from acts of terrorism; and support a sound energy policy. Throughout the scientific evaluation of Yucca Mountain, there has been no evidence to disqualify Yucca Mountain as a suitable site for the permanent disposal of spent nuclear fuel and high-level radioactive waste. Upon completion of site characterization, the Secretary of Energy considered the results and concluded that a repository at Yucca Mountain would perform in a manner that protects public health and safety. The Secretary recommended the site to the President in February 2002; the President agreed and recommended to Congress that the site be approved. The Governor of Nevada submitted a notice of disapproval, and both houses of Congress acted to override the disapproval. In July 2002, the President's approval allowed the Department to begin the process of submittal of a license application for Yucca Mountain as the site for the nation's first repository for spent nuclear fuel and high-level radioactive waste. Yucca Mountain is located on federal land in Nye County in southern Nevada, an arid region

  12. 77 FR 12830 - Pershing County Water Conservation District; Notice of Intent To File License Application, Filing...

    Science.gov (United States)

    2012-03-02

    ... Water Conservation District; Notice of Intent To File License Application, Filing of Pre-Application.... Submitted by: Pershing County Water Conservation District (Pershing County). e. Name of Project: Humboldt... the Commission's regulations. h. Potential Applicant Contact: Bennie Hodges, Pershing County Water...

  13. Application of IC Card License for Road Transportation in Commercial Vehicles Supervision and Service

    Directory of Open Access Journals (Sweden)

    Li Weiwei

    2016-01-01

    Full Text Available IC card electronic license for road transport includes the IC card commercial vehicle’s certificate and IC card practitioner’s qualification certificate. In China, the IC card electronic license for road transport is the electronic ID card which must be carried by each commercial vehicles and practitioners. This paper briefly introduces the basic situation, data format and security keys architecture of IC card electronic license for road transportation of China. In order to strengthen the supervision and service of commercial vehicles, this paper puts forward the overall application framework of IC card electronic license for road transport. The application examples of IC card license in the supervision of passenger station, dangerous goods transport management, governance overload and logistics park and port area management are discussed. The practical application results show that the application of IC card electronic license for road transport is an important technical means to improve the supervision ability and service quality of the road transportation industry.

  14. Regulatory analysis for amendments to regulations for the environmental review for renewal of nuclear power plant operating licenses. Final report

    International Nuclear Information System (INIS)

    1996-05-01

    This regulatory analysis provides the supporting information for a proposed rule that will amend the Nuclear Regulatory Commission's environmental review requirements for applications for renewal of nuclear power plant operating licenses. The objective of the proposed rulemaking is to improve regulatory efficiency by providing for the generic evaluation of certain environmental impacts associated with nuclear plant license renewal. After considering various options, the staff identified and analyzed two major alternatives. With Alternative A, the existing regulations would not be amended. This option requires that environmental reviews be performed under the existing regulations. Alternative B is to assess, on a generic basis, the environmental impacts of renewing the operating license of individual nuclear power plants, and define the issues that will need to be further analyzed on a case-by-case basis. In addition, Alternative B removes from NRC's review certain economics-related issues. The findings of this assessment are to be codified in 10 CFR 51. The staff has selected Alternative B as the preferred alternative

  15. 78 FR 54280 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-09-03

    ... the Commission's ``Agency Rules of Practice and Procedure'' in 10 CFR part 2. Interested person(s...-Filing system also distributes an email notice that provides access to the document to the NRC's Office... clarify language in the LSCS, Units 1 and 2, Technical Specifications (TS) applicable to the design...

  16. Nuclear plant license renewal

    International Nuclear Information System (INIS)

    Gazda, P.A.; Bhatt, P.C.

    1991-01-01

    During the next 10 years, nuclear plant license renewal is expected to become a significant issue. Recent Electric Power Research Institute (EPRI) studies have shown license renewal to be technically and economically feasible. Filing an application for license renewal with the Nuclear Regulatory Commission (NRC) entails verifying that the systems, structures, and components essential for safety will continue to perform their safety functions throughout the license renewal period. This paper discusses the current proposed requirements for this verification and the current industry knowledge regarding age-related degradation of structures. Elements of a license renewal program incorporating NRC requirements and industry knowledge including a schedule are presented. Degradation mechanisms for structural components, their significance to nuclear plant structures, and industry-suggested age-related degradation management options are also reviewed

  17. A review of electric cable aging effects and monitoring programs for plant license renewal

    International Nuclear Information System (INIS)

    Lofaro, R.J.

    1999-01-01

    As commercial nuclear power plants approach the end of their original license period, some utilities are considering the possibility of license renewal. The requirements for applying for license renewal are specified in the License Renewal Rule, which is in Title 10 of the Code of Federal Regulations, Part 54 (10 CFR54). Among the requirements specified in the rule is the performance of an Integrated Plant Assessment (IPA) which identifies and lists structures and components subject to an aging management review. The intent of this requirement is to ensure that aging degradation will not adversely affect plant safety during the license renewal period. The aging management review includes an identification of the aging effects and monitoring programs for components within the scope of the rule. Among the components within the scope are electric cables since they are passive, long-lived components that are not replaced on a periodic basis. This paper examines the aging causes and effects of electric cables, along with the programs that are typically used to ensure that proper aging management practices are in place to monitor and mitigate the effects of aging on electric cables

  18. 78 FR 13342 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-02-27

    .... Officers: Keith Phillips, Vice President (QI), Glenn Henderson, President. Application Type: New NVO & OFF.... Officers: Paul Pellitieri, President (QI), Virginia Pellitieri, Vice President. Application Type: New NVO...

  19. License renewal

    International Nuclear Information System (INIS)

    Newberry, S.

    1993-01-01

    This article gives an overview of the process of license renewal for nuclear power plants. It explains what is meant by license renewal, the significance of license renewal, and goes over key elements involved in the process of license renewal. Those key elements are NRC requirements embodied in 10 CFR Part 54 (Reactor Safety) and 10 CFR Part 51 (Environmental Issues). In addition Industry Reports must be developed and reviewed. License renewal is essentially the process of applying for a 20 year extension to the original 40 year operating license granted for the plant. This is a very long term process, which involves a lot of preparation, and compliance with regulatory rules and guidelines. In general it is a process which is expected to begin when plants reach an operating lifetime of 20 years. It has provisions for allowing the public to become involved in the review process

  20. 77 FR 73054 - Application for a License To Export Radioactive Waste

    Science.gov (United States)

    2012-12-07

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export Radioactive Waste Pursuant to 10 CFR 110.70(b) ``Public Notice of Receipt of an Application,'' please take notice that the Nuclear..., October 25, 2012, XW020, radioactive 1178 pounds disposal by the 11006061. waste in the (approximately...

  1. 77 FR 14445 - Application for a License To Export Steel Forging

    Science.gov (United States)

    2012-03-09

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export Steel Forging Pursuant to 10 CFR 110.70(b) ``Public Notice of Receipt of an Application,'' please take notice that the Nuclear... head steel February 7, 2012 forging. forging will be XR175 machined into the 11005983 finished vessel...

  2. 75 FR 15743 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2010-03-30

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export High-Enriched Uranium Pursuant to 10 CFR 110.70(c) ``Public notice of receipt of an application,'' please take notice that the...-Enriched 160.0 kilograms To fabricate fuel France. Complex, March 3, 2010. Uranium (93.35%). uranium (149...

  3. 75 FR 6223 - Application For a License To Export High-Enriched Uranium

    Science.gov (United States)

    2010-02-08

    ... NUCLEAR REGULATORY COMMISSION Application For a License To Export High-Enriched Uranium Pursuant to 10 CFR 110.70(c) ``Public notice of receipt of an application,'' please take notice that the..., Uranium (93.35%). uranium (16.3 targets for December 28, 2009, XSNM3623, kilograms U-235). irradiation in...

  4. 77 FR 1956 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2012-01-12

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export High-Enriched Uranium Pursuant to 10 CFR 110.70(b) ``Public Notice of Receipt of an Application,'' please take notice that the.... Security Complex. Uranium uranium (9.3 targets at December 21, 2011 (93.35%). kilograms U- CERCA AREVA...

  5. 75 FR 7525 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2010-02-19

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export High-Enriched Uranium Pursuant to 10 CFR 110.70(c) ``Public notice of receipt of an application,'' please take notice that the..., February 2, Uranium (93.35%). uranium (87.3 elements in 2010, February 2, 2010, kilograms U-235). France...

  6. 75 FR 71102 - White Mountain Hydroelectric Corp.; Notice of Application for Amendment of License, and...

    Science.gov (United States)

    2010-11-22

    ... Hydroelectric Corp.; Notice of Application for Amendment of License, and Soliciting Comments, Motions To Intervene, and Protests November 12, 2010. Take notice that the following hydroelectric application has been... Hydroelectric Corp. e. Name of Project: Apthorp Hydroelectric Project. f. Location: The project is located on...

  7. 76 FR 4417 - Liberty Natural Gas LLC, Liberty Liquefied Natural Gas (LNG) Deepwater Port License Application

    Science.gov (United States)

    2011-01-25

    ... DEPARTMENT OF TRANSPORTATION Maritime Administration [USCG-2010-0993] Liberty Natural Gas LLC, Liberty Liquefied Natural Gas (LNG) Deepwater Port License Application AGENCY: Maritime Administration... application describes an offshore natural gas deepwater port facility that would be located approximately 16.2...

  8. 77 FR 76483 - Ocean Transportation Intermediary License Applicants The Commission gives notice that the...

    Science.gov (United States)

    2012-12-28

    ... Transport Co., PAC International Logistics Company, & Book Express Network. Stealth Logistics LLC (NVO & OFF.... Application Type: QI Change. Efrinsa Global Logistics Inc. (NVO & OFF), 8441 NW 68th Street, Miami, FL 33166... (QI), Sheila E. Lawrence, President. Application Type: New OFF License. MMC Logistics, LLC (OFF), 2853...

  9. 75 FR 61474 - Juneau Hydropower, Inc.; Notice of Intent To File License Application, Filing of Pre-Application...

    Science.gov (United States)

    2010-10-05

    ... Hydropower, Inc.; Notice of Intent To File License Application, Filing of Pre-Application Document, and....: 13563-001. c. Dated Filed: July 28, 2010. d. Submitted By: Juneau Hydropower, Inc. e. Name of Project... Commission's regulations. h. Potential Applicant Contact: Duff W. Mitchell, Juneau Hydropower, Inc., P.O. Box...

  10. 78 FR 28845 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-05-16

    ..., President, Application Type: QI Change Contract Logistics, LLC (NVO), 4911 North Portland Avenue, Suite 200..., Application Type: Add Trade Name Smart Lines Worldwide Feiliks Global Logistics Corporation (NVO), 176-20 S..., Director, Application Type: QI Change Intermodal Tank Transport (USA), Inc. (NVO), 2537 S. Gessner, Suite...

  11. Information to be submitted in support of licensing applications for nuclear power plants

    International Nuclear Information System (INIS)

    1979-01-01

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Agency's Safety Series No.50-C-G, entitled ''Governmental Organization for the Regulation of Nuclear Power Plants: A Code of Practice''. It is concerned with the content of documents which should be submitted to the regulatory body by the applicant/licensee in support of licensing applications, with a possible method of classifying these documents and with the scheduling of their submission to the regulatory body at each major stage of the licensing process

  12. Use of annotated outlines to prepare guidance for license applications for the MRS and MGDS

    International Nuclear Information System (INIS)

    Roberts, J.; Griffin, W.R.

    1992-01-01

    This paper reports that the Office of Civilian Radioactive Waste Management (OCRWM) has embarked on an aggressive program to develop guidance for preparation of the License Applications for the Mined Geological Disposal System (MGDS) and Monitored Retrievable Storage (MRS). The endeavor is a team effort that will utilize personnel and funding from the Office of Systems and Compliance at DOE Headquarters, the MRS Project (i.e., DOE Office of Storage and Transportation) and the Yucca Mountain Project (i.e., DOE Office of Geologic Disposal). The endeavor was initiated in the Spring of 1991. It will continue via an iterative process until License Applications are completed for the MRS and MGDS projects

  13. 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...

  14. License renewal process

    International Nuclear Information System (INIS)

    Fable, D.; Prah, M.; Vrankic, K.; Lebegner, J.

    2004-01-01

    license renewal process in NPP's across the USA. List of NPP's with renewed license, or whose application is currently under review or whose applications are expected in near future, will be provided.(author)

  15. Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z., E-mail: jonatasfmata@yahoo.com.br, E-mail: vasconv@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

  16. Application of probabilistic risk assessment in nuclear and environmental licensing processes of nuclear reactors in Brazil

    International Nuclear Information System (INIS)

    Mata, Jonatas F.C. da; Vasconcelos, Vanderley de; Mesquita, Amir Z.

    2015-01-01

    The nuclear accident at Fukushima Daiichi, occurred in Japan in 2011, brought reflections, worldwide, on the management of nuclear and environmental licensing processes of existing nuclear reactors. One of the key lessons learned in this matter, is that the studies of Probabilistic Safety Assessment and Severe Accidents are becoming essential, even in the early stage of a nuclear development project. In Brazil, Brazilian Nuclear Energy Commission, CNEN, conducts the nuclear licensing. The organism responsible for the environmental licensing is Brazilian Institute of Environment and Renewable Natural Resources, IBAMA. In the scope of the licensing processes of these two institutions, the safety analysis is essentially deterministic, complemented by probabilistic studies. The Probabilistic Safety Assessment (PSA) is the study performed to evaluate the behavior of the nuclear reactor in a sequence of events that may lead to the melting of its core. It includes both probability and consequence estimation of these events, which are called Severe Accidents, allowing to obtain the risk assessment of the plant. Thus, the possible shortcomings in the design of systems are identified, providing basis for safety assessment and improving safety. During the environmental licensing, a Quantitative Risk Analysis (QRA), including probabilistic evaluations, is required in order to support the development of the Risk Analysis Study, the Risk Management Program and the Emergency Plan. This article aims to provide an overview of probabilistic risk assessment methodologies and their applications in nuclear and environmental licensing processes of nuclear reactors in Brazil. (author)

  17. 75 FR 32780 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-06-09

    .../Secretary, (Qualifying Individual), Bengt R. Anderson, President, Application Type: QI Change. Cargomar... Corp. (OFF & NVO), 6301 E. 10th Avenue, Hialeah, FL 33013, Officers: Marjorie E. Morales, Operation...

  18. Grant Application Development, Submission, Review, & Award

    Science.gov (United States)

    This infographic shows the National Cancer Institute general timeline progression through Grant Application Development, Submission, Review, and Award Infographic. In the first month, Applicant prepares and submits Grant Application to Grants.gov in response to FOA. In month two, The Center for Scientific Review (CSR) assigns applications that fall under the category of R01s, etc. to a Scientific Review Group (SRG) or the CSR assigns applications that fall under the category of Program Projects and Center Grants to NCI Division of Extramural Activities (DEA). Months four through five: First-level review by Scientific Review Group (SRG) for Scientific Merit: SRG assigns Impact Scores. Month five Summary Sstatements are prepared and are available to NCI Program staff and applicants. Month six, second-level review by National Cancer Advisory board (NCAB) for NCI Funding determination begins. NCAB makes recommendation to NCI Director, NCI develops funding plan, Applications selected for Funding, “Paylists” forwarded to Office of Grant Administration (OGA). Month ten, Award Negotiations and Issuance: Award issued, Award received by Institution, and Investigator begins work. www.cancer.gov Icons made by Freepik from http://www.flaticon.com is licensed by CC BY3.0

  19. 76 FR 19097 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-04-06

    ... Sachs, Partner/Logistics Manager (Qualifying Individual), Ali Ismailzada, Partner/CFO, Application Type... at (202) 523-5843 or by e-mail at [email protected] . Agility Logistics Corp. (OFF), 240 Commerce, Irvine... Avenue, Newark, NJ 07083, Officer: Hakeem K. Bisiolu, Member/Manager (Qualifying Individual), Application...

  20. 77 FR 23719 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-04-20

    ... Logistics, Inc. (NVO & OFF), 180 Champion Way, Northlake, IL 60164. Officers: David F. Gross, CEO (Qualifying Individual), Lance A. Lucibello, Vice President. Application Type: QI Change. CMA CGM Logistics... Fafoutis, General Manager (Qualifying Individual), Frank J. Baragona, Director. Application Type: New NVO...

  1. 75 FR 6398 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-02-09

    ... Forwarder Transportation Intermediary Applicants Best Way Logistics Corp., 901 SW. 98th Terrace, Pembroke..., Officers, Alessandro E. Bernardini, Sales Manager, (Qualifying Individual), Glenda Valdez, President... Intermediary Applicants (Cont'd): Vortex Worldwide Logistics Corp., 10125 NW. 116th Way, 10, Miami, FL 33178...

  2. 75 FR 66099 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-10-27

    ... Logistics, Inc. (NVO), 17890 Castleton Street, Suite 398, City of Industry, CA 91748, Officers: Jennifer X... (Qualifying Individual), Application Type: QI Change. Concert Group Logistics, Inc. (NVO & OFF), 1430 Branding... Individual), Daniel Para, CEO, Application Type: QI Change. De Well Logistics LLC dba De Well Logistics, dba...

  3. 75 FR 60124 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-09-29

    ... Individual), Sharlene Chesnes, EVP/COB/EVP/Secretary, Application Type: QI Change IAL Container Line (USA..., Vice President (Qualifying Individual), Arjun Menon, Director, Application Type: QI Change LTA Import & Export, Inc. (NVO & OFF), 14331 SW 120th Street, 203, Miami, FL 33186, Officers: Eric E. Diaz, Director...

  4. Licensing requirements for initial commissioning programs in Spain: Application to different PWR designs

    International Nuclear Information System (INIS)

    Munuera, A.; Conde, J.M.; Martinez, J.

    1991-01-01

    This paper describes the overall licensing process in Spain, focusing on the initial commissioning requirements. The significance of this part of the regulatory work is evident both from the licensing and the licensee's points of view. Licensing in Spain is ruled by different laws which determine the general requirements and fix the licensing frame. Being a nuclear technology importer country, the base of the regulatory work lies on the rules and regulations of the country of origin of the planet, with the addition of case specific requirements. The application of this methodology to plants designed in different countries produces licensing processes which are similar to the overall, but very different in its development. It also means a special technical effort on the part of the regulatory body to cope with the problems arising from the use of different technologies and safety standards. The start-up programs from fuel loading to full power of a Westinghouse plant (Vandellos 2) and a Siemens-KWU plant (Trillo 1) are compared from the technical point of view, enhancing the differences that can be relevant for the regulatory work. The difficulties arising from the application of both the German and US concepts are discussed. (orig.)

  5. Guide for the preparation of applications for licenses for the use of sealed sources in portable gauging devices

    International Nuclear Information System (INIS)

    1985-01-01

    The purpose of this regulatory guide is to provide assistance to applicants and licensees in preparing applications for new licenses, license amendments, and license renewals for the use of sealed sources in portable gauging devices. An example of a portable gauging device is a moisture-density gauge that contains a gamma-emitting sealed source, cesium-137, and a sealed neutron source, americium-242-beryllium

  6. 75 FR 52343 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-08-25

    ... Company, Inc. (NVO & OFF), 4529 Angeles Crest Highway, Suite 300, La Canada, CA 91011, Officers: Ernest V..., Application Type: QI Change. BestOcean Worldwide Logistics, Inc. (OFF & NVO), 1300 Valley Vista Drive, Suite...

  7. 76 FR 67188 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-10-31

    ... Liability Company, dba GlobalForwarding.com dba Forwardingservices.com dba Containerquote.com dba Global.../CEO/CFO, Application Type: QI Change. Unicorn Shipping, Inc. (NVO & OFF), 1225 W. 190th Street, Suite...

  8. 78 FR 30921 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-05-23

    .... (NVO & OFF), 2500 Wilcrest Drive, Suite 300, Houston, TX 77042, Officers: Myrian T. Morales, Vice..., FL 33178, Officer: Jose R. Gantus, President (QI), Application Type: QI Change XL Worldwide Corp...

  9. 76 FR 10593 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-02-25

    ... Individual), Steven L. Leturno, Director, Application Type: QI Change. Combined Freight System, Inc. (NVO...), 148-08 Guy R. Brewer Blvd., Jamaica, NY 11434, Officers: Wei Hu, Vice President, (Qualifying...

  10. 76 FR 71608 - Notice of Availability of Combined License Applications

    Science.gov (United States)

    2011-11-18

    ...://www.nrc.gov/reactors/new-reactors/col.html . FOR FURTHER INFORMATION CONTACT: Donald Habib, Office of..., email: Donald.Habib@nrc.gov . SUPPLEMENTARY INFORMATION: The following parties have filed applications...

  11. 76 FR 77021 - Notice of Availability of Combined License Applications

    Science.gov (United States)

    2011-12-09

    ...://www.nrc.gov/reactors/new-reactors/col.html . FOR FURTHER INFORMATION CONTACT: Donald Habib, Office of..., email: Donald.Habib@nrc.gov . SUPPLEMENTARY INFORMATION: The following parties have filed applications...

  12. 76 FR 72725 - Notice of Availability of Combined License Applications

    Science.gov (United States)

    2011-11-25

    ...://www.nrc.gov/reactors/new-reactors/col.html . FOR FURTHER INFORMATION CONTACT: Donald Habib, Office of..., email: Donald.Habib@nrc.gov . SUPPLEMENTARY INFORMATION: The following parties have filed applications...

  13. 78 FR 10173 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-02-13

    ... Road, Scituate, MA 02066, Officers: Stephen J. Zambo, Member (QI), Stephen A. Zambo, Member... 60007, Officers: Joshua H. Chau, President (QI), Bessie S. Chau, Secretary, Application Type: New NVO...

  14. 75 FR 28250 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-05-20

    ... Type: Add NVO Service and QI Change. Best Container Express, Inc. (NVO), 17238 S. Main Street, Gardena...). Peixin Li, President. Application Type: Add OFF Services. Project Rail, LLC dba Vectora Transportation...

  15. 76 FR 12962 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-03-09

    ... L. Li, President, Application Type: QI Change. EP-Team, Inc. dba EP-Team (NVO & OFF), 3700 Forums... Maritime Services USA (NVO), 425 West Main Street, Alhambra, CA 91801. Officers: Hans P. Hofmann, Assistant...

  16. 77 FR 32115 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-05-31

    ... Individual), Lar D. Westerberg, CEO, Application Type: Add NVO Service. Jo-Sak Shipping USA, Inc. (NVO & OFF... Service. Waterline International Logistics, Inc. (NVO & OFF), 24178 Alicia Parkway, Mission Viejo, CA...

  17. Pesticide Applicator Profiling: Using Polycom[R] Distance Delivery for Continuing Education and Characterizing Florida's Licensed Applicators

    Science.gov (United States)

    Fishel, Fred; Langeland, Ken

    2011-01-01

    The University of Florida offers continuing education units (CEUs) via distance technology using Polycom[R] to meet requirements for applicators of pesticides to renew their licenses. A large statewide event conducted in 2010 also included a needs assessment of this group concerning CEUs. Results indicate that these applicators strongly prefer…

  18. 77 FR 34030 - BOST1 Hydroelectric LLC; Notice of Intent To File License Application, Filing of Pre-Application...

    Science.gov (United States)

    2012-06-08

    ... Hydroelectric LLC; Notice of Intent To File License Application, Filing of Pre-Application Document, and.... Date Filed: March 21, 2012. d. Submitted By: BOST1 Hydroelectric LLC (BOST1). e. Name of Project: Coon Rapids Dam Hydroelectric Project. f. Location: Mississippi River in Hennepin and Anoka counties...

  19. 77 FR 6552 - Mahoning Hydropower, LLC; Notice of Intent To File License Application, Filing of Pre-Application...

    Science.gov (United States)

    2012-02-08

    ... Hydropower, LLC; Notice of Intent To File License Application, Filing of Pre-Application Document, and...: December 7, 2011. d. Submitted By: Mahoning Hydropower, LLC. e. Name of Project: Berlin Lake Hydroelectric... Hydropower, LLC, 11365 Normandy Lane, Chagrin Falls, OH 44023; (440) 804-6627; [email protected] i. FERC...

  20. Standard format and content of a license application for a low-level radioactive waste disposal facility: Safety analysis report

    International Nuclear Information System (INIS)

    1988-01-01

    This document discusses the information that should be provided in the Safety Analysis Report and establishes a uniform format for presenting the information necessary to fulfill the licensing requirements for land disposal of radioactive waste called for in 10 CFR 61. The uniform format will (1) help ensure that the Safety Analysis Report contains the information required by 10 CFR 61, (2) aid the applicant and NRC staff in ensuring that the information is complete, (3) help persons reading the Safety Analysis Report to locate information, and (4) contribute to shortening the time needed for the review process

  1. Standard format and content of a license application for a low-level radioactive waste disposal facility: Safety analysis report

    International Nuclear Information System (INIS)

    1987-01-01

    This document discusses the information that should be provided in the Safety Analysis Report and establishes a uniform format for presenting the information necessary to fulfill the licensing requirements for land disposal of radioactive waste called for in 10 CFR 61. The uniform format will (1) help ensure that the Safety Analysis Report contains the information required by 10 CFR 61, (2) aid the applicant and NRC staff in ensuring that the information is complete, (3) help persons reading the Safety Analysis Report to locate information, and (4) contribute to shortening the time needed for the review process

  2. 78 FR 45578 - Application For a License to Export Radioactive Waste

    Science.gov (United States)

    2013-07-29

    ... NUCLEAR REGULATORY COMMISSION Application For a License to Export Radioactive Waste Pursuant to 10..., 2013, radioactive waste authorized for disposal by the XW021, 11006101. as contaminated export will not original secondary waste exceed quantities generators, as resulting from imported in required or the...

  3. 77 FR 73056 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2012-12-07

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export High-Enriched Uranium Pursuant... Complex. Uranium (93.2%). uranium-235 at CERCA AREVA Romans October 10, 2012 contained in 6.2 in France and to October 12, 2012 kilograms irradiate targets at XSNM3729 uranium. the BR-2 Research 11006053...

  4. 77 FR 73055 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2012-12-07

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export High-Enriched Uranium Pursuant.... Security Complex. Uranium uranium-235 at CERCA AREVA October 10, 2012 (93.35%). contained in Romans in France October 12, 2012 10.1 kilograms and to irradiate XSNM3730 uranium. targets at the HFR 11006054...

  5. 77 FR 51579 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2012-08-24

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export High-Enriched Uranium Pursuant.... Complex, July 30, 2012, August Uranium (93.35%). uranium-235 high-enriched 1, 2012, XSNM3726, 11006037. contained in 7.5 uranium in the kilograms uranium. form of broken metal to the Atomic Energy of Canada...

  6. 78 FR 33448 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2013-06-04

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export High-Enriched Uranium Pursuant.... Security Complex, May 13, Uranium (93.35%). uranium-235 at the National 2013, May 21, 2013, XSNM3745, contained in 7.5 Research Universal 11006098. kilograms reactor in Canada for uranium. ultimate use in...

  7. 18 CFR 131.20 - Application for approval of transfer of license.

    Science.gov (United States)

    2010-04-01

    ... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Application for approval of transfer of license. 131.20 Section 131.20 Conservation of Power and Water Resources FEDERAL... a citizen of the United States of America. Subscribed and sworn to before me, a notary public of the...

  8. 75 FR 467 - Notice of Opportunity for Hearing, License Application Request of Powertech (USA) Inc. Dewey...

    Science.gov (United States)

    2010-01-05

    ... Hearing, License Application Request of Powertech (USA) Inc. Dewey-Burdock In Situ Uranium Recovery... Regulatory Commission (NRC) for the Dewey-Burdock In Situ Recovery Facility in Fall River and Custer Counties, South Dakota. The Dewey-Burdock facility would involve the recovery of uranium by in situ recovery (ISR...

  9. Shirley Basin Uranium Mill. Environmental report to accompany source material license application

    International Nuclear Information System (INIS)

    1975-12-01

    This document summarizes all of the environmental monitoring conducted by Utah. This Environmental Report consequently supplements and updates the information presented in the Source Material License application of August 18, 1970 and the Final Environmental Statement (FES) of December 1974. Water and air quality, liquid waste management, soil/vegetation monitoring, and reclamation are covered

  10. Standard format and content of license applications for plutonium processing and fuel fabrication plants

    International Nuclear Information System (INIS)

    1976-01-01

    The standard format suggested for use in applications for licenses to possess and use special nuclear materials in Pu processing and fuel fabrication plants is presented. It covers general description of the plant, summary safety assessment, site characteristics, principal design criteria, plant design, process systems, waste confinement and management, radiation protection, accident safety analysis, conduct of operations, operating controls and limits, and quality assurance

  11. NEP Nuclear Power Plant, Units 1 and 2. License application, general and financial information

    International Nuclear Information System (INIS)

    1976-01-01

    A license application is presented for 2 pressurized water reactors at a proposed location in Charlestown RI. Each reactor will have a net capacity of 1150 MW. Cooling water will be supplied by the Atlantic Ocean. NEP-1 is scheduled for operation in 1983 and NEP-2 in 1985

  12. 76 FR 71082 - Strata Energy, Inc., Ross Uranium Recovery Project; New Source Material License Application...

    Science.gov (United States)

    2011-11-16

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 40-9091; NRC-2011-0148] Strata Energy, Inc., Ross Uranium Recovery Project; New Source Material License Application; Notice of Intent To Prepare a... intent to prepare a supplemental environmental impact statement. SUMMARY: Strata Energy, Inc. (Strata...

  13. 78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

    Science.gov (United States)

    2013-07-05

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-298; NRC-2013-0139] Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving Proposed No Significant Hazards..., issued to Nebraska Public Power District (the licensee), for operation of the Cooper Nuclear Station (CNS...

  14. 78 FR 64493 - Juneau Hydropower, Inc.; Notice of Subsequent Draft License Application (DLA) and Draft...

    Science.gov (United States)

    2013-10-29

    ... Hydropower, Inc.; Notice of Subsequent Draft License Application (DLA) and Draft Preliminary Draft... Hydropower, Inc. e. Name of Project: Sweetheart Lake Hydroelectric Project. f. Location: At the confluence of..., Business Manager, Juneau Hydropower, Inc., P.O. Box 22775, Juneau, AK 99802; 907-789-2775, email: duff...

  15. 76 FR 52994 - Application for a License To Export Heavy Water

    Science.gov (United States)

    2011-08-24

    ... NUCLEAR REGULATORY COMMISSION Application for a License To Export Heavy Water Pursuant to 10 CFR... (liters). producing an active water). pharmaceutical ingredient known as CTP-499, which incorporates heavy water as the source of deuterium to achieve the hydrogen-deuterium exchange. November 30, 2010 December...

  16. 76 FR 53693 - Notice of Invitation To Participate; Coal Exploration License Application COC-74911, Colorado

    Science.gov (United States)

    2011-08-29

    ...] Notice of Invitation To Participate; Coal Exploration License Application COC-74911, Colorado AGENCY: Bureau of Land Management, Interior. ACTION: Notice. SUMMARY: Pursuant to the Mineral Leasing Act of 1920... America in lands located in Delta County, Colorado. DATES: This notice of invitation was published in the...

  17. Medical review licensing outcomes in drivers with visual field loss in Victoria, Australia

    Science.gov (United States)

    Muir, Carlyn; Charlton, Judith L; Odell, Morris; Keeffe, Jill; Wood, Joanne; Bohensky, Megan; Fildes, Brian; Oxley, Jennifer; Bentley, Sharon; Rizzo, Matthew

    2017-01-01

    Background Good vision is essential for safe driving and studies have associated visual impairment with an increased crash risk. Currently, there is little information about the medical review of drivers with visual field loss. This study examines the prevalence of visual field loss among drivers referred for medical review in one Australian jurisdiction and investigates factors associated with licence outcome in this group. Methods A random sample of 10,000 (31.25 per cent) medical review cases was extracted for analysis from the Victorian licensing authority. Files were screened for the presence of six visual field-related medical conditions. Data were captured on a range of variables, including referral source, age, gender, health status, crash history and licence outcome. Prevalence analyses were univariate and descriptive. Logistic regression was used to assess factors associated with licence outcomes in the visual field loss group. Results Approximately 1.9 per cent of the 10,000 medical review cases screened had a visual field loss condition identified (n=194). Among the visual field loss group, 57.2 per cent were permitted to continue driving (conditional/unconditional licence). Primary referral sources were the police, self-referrals and general medical practitioners. Key factors associated with licence test outcomes were visual field condition, age group, crash involvement and referral to the Driver Licensing Authority’s Medical Advisors. Those who were younger had a crash involvement triggering referral and those who were referred to the Medical Advisors were more likely to have a positive licensing outcome. Conclusion The evidence base for making licensing decisions is complicated by the variable causes, patterns, progressions and measuring technologies for visual field loss. This study highlighted that the involvement of an expert medical advisory service in Victoria resulted in an increased likelihood that drivers with visual field loss will be

  18. 76 FR 25690 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-05-05

    .... Capital Logistics CHB Corp. (NVO & OFF), 6000 NW 97th Avenue, 9-10, Miami, FL 33178, Officers: Manuel G..., San Diego, CA 92126, Officers: Alex O. De Guzman, President, (Qualifying Individual), Abraham B. Lanuzga, Vice President, Application Type: Business Structure Change. Embarque Bandera Shipping, Inc. (NVO...

  19. 10 CFR 40.31 - Application for specific licenses.

    Science.gov (United States)

    2010-01-01

    ... response organizations expected to respond in case of an accident 60 days to comment on the licensee's... environment shall be filed at least 9 months prior to commencement of construction of the plant or facility in... case of renewal applications submitted before July 27, 1990, this submittal may follow the renewal...

  20. 76 FR 9015 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-02-16

    ... Global Logistics, LLC (NVO & OFF), 53 Perimeter Center East, Suite 450, Atlanta, GA 30346. Officer: Chad... Street, Doral, FL 33126. Officers: Juan P. Constain, General Manager (Qualifying Individual), Santiago...). Application Type: Add NVO Service. CoscoEx (CGL), Inc. dba Citic Global Logistics dba Chimerica Global...

  1. 76 FR 71034 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-11-16

    ... at (202) 523-5843 or by email at [email protected] . AAB Global Logistics, LLC (NVO & OFF), 201 E. Dundee...), Robert E. Cleary, Manager. Application Type: Name Change. Abco International Freight (USA) Inc. dba Abco Logistics (NVO), 9420 Telstar Avenue, 203, El Monte, CA 91731. Officers: Shermin Kong, Treasurer (Qualifying...

  2. 78 FR 63475 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-10-24

    ... dba Fachel Shipping & Logistics (NVO & OFF), 6331 Belair Road, Baltimore, MD 21206, Officers: Chinyere W. Osasuyi, Chief Executive Manager (QI), Famous I. Osasuyi, Chief Executive Member. Application... Change. Perimeter International dba Perimeter Logistics (NVO & OFF), 2700 Story Road, Suite 150, Irving...

  3. Barnwell Nuclear Fuel Plant. License application, amendment 10

    International Nuclear Information System (INIS)

    1975-01-01

    Amendment No. 10 provides the applicant's responses to questions raised by the AEC in letters dated November 6 and December 5, 1974. Amendment No. 3, dated February 1975, to the BNFP Separations Facility Final Safety Analysis Report (FSAR) is included. The amendment consists of revision pages for volumes 1 through 5 of the FSAR along with a deletion and insertion guide. (U.S.)

  4. 7 CFR 46.4 - Application for license.

    Science.gov (United States)

    2010-01-01

    ... principal office. A limited liability company shall also furnish a copy of its articles of organization and... the trustee must be furnished. If the applicant is a limited liability company and a member or holder of more than 10 percent of the ownership stake is a partnership, another limited liability company...

  5. 75 FR 42446 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-07-21

    ... Transportation Intermediary (OTI) pursuant to section 19 of the Shipping Act of 1984 as amended (46 U.S.C... Shipping Limited (NVO), 1000 Corporate Center Drive, Suite 320, Monterey Park, CA 91754. Officers: Joey Tam, President/CEO (Qualifying Individual), Yu C. Lee, Secretary/Treasurer. Application Type: Name Change. Ever...

  6. 75 FR 63476 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2010-10-15

    .... David A. Knott dba DAK Logistics Services (NVO), 1010 Bluejay Drive, Suisun City, CA 94585. Officer... Office of Transportation Intermediaries, Federal Maritime Commission, Washington, DC 20573. ACS Logistics.... Application Type: QI Change. Archer Logistics USA LLC (NVO), 6051 Kennedy Boulevard East, PhB, West New York...

  7. 78 FR 23252 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-04-18

    .... Logistics, Inc. dba BE Logistics dba Belogistics dba Core Logistics (NVO), 12911 Simms Avenue, Hawthorn, CA... (QI), Kevin L. Miller, Secretary, Application Type: QI Change Triple Eagle Logistics Inc. dba Triple Eagle Logistic Canada Inc. (NVO & OFF), 17890 Castleton Street, Suite 367, City of Industry, CA 91748...

  8. 77 FR 9657 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-02-17

    ..., Owner, Application Type: Add OFF Service. Cargo Tours International, Inc. dba CTI Global Logistics (NVO.... Deckwell Sky (USA) Inc. dba Monarch Container Line (NVO & OFF), 14343 E. Don Julian Road, City of Industry.... Logistics, Inc. (NVO & OFF), 3905 West Albany Street, McHenry, IL 60050, Officers: Arthur N. Nutig, Chief...

  9. 78 FR 78956 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-12-27

    ... & OFF), 1515 Kona Drive, Compton, CA 90220, Officers: Won Rok (aka Steve) Choi, CFO (QI), Myeong H. Kim..., El Monte, CA 91731, Officers: Lynn H. Tran, Secretary (QI), Zheng Feng, CFO, Application Type: New.... 25th Street, Suite 107D, Miami, FL 33182, Officers: Sergio I. Lotero, President (QI), Stephen A. Blass...

  10. 78 FR 68444 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-11-14

    ... (America), Ltd. (NVO & OFF), 21061 S. Western Avenue, Suite 300, Torrance, CA 90501-1122, Officers: Mary M..., Officers: Kimberly A. Whisler Wagner, Member Manager (QI), Kara M. Norkus, Member Manager, Application Type..., Iselin, NJ 08830, Officers: Richard Kenyon, President (QI), Fernando Valenzuela, Global President...

  11. 77 FR 21559 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-04-10

    ... Individual). Luis Angel Rincon, Manager. Application Type: Business Structure Change and Add NVO Service. Dix.... Global Distribution & Logistics LLC (NVO & OFF), 7977 NW 21st Street, Miami, FL 33122. Officers: Jose L...: Edward J. Hathaway, Vice President-- Business Development (Qualifying Individual). Jeff Harvey, President...

  12. 78 FR 48435 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-08-08

    ..., Washington, DC 20573, by telephone at (202) 523-5843 or by email at [email protected] . A & J Cargo Logistics Inc... (QI), Application Type: Add Trade Name Arabia Cargo and OFF Service. CMX Global Logistics, LLC (NVO... Transport Co., Ltd. (NVO), 13101 Moore Street, Cerritos, CA 90703, Officers: Ki Hyeon Lee, CFO (QI), Seong...

  13. 78 FR 56229 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-09-12

    ..., Washington, DC 20573, by telephone at (202) 523-5843 or by email at [email protected] . ATS Logistics, LLC (NVO... Logistics Services, Inc. (NVO & OFF), One Cross Island Plaza, Suite 111, Rosedale, NY 11422, Officer: Jimmy..., Secretary, Application Type: QI Change World Link Transport, Inc. (NVO & OFF), 1220 Kona Drive, Compton, CA...

  14. 76 FR 31962 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-06-02

    .... International First Service USA, Inc. dba Global Wine Logistics, Inc. (NVO & OFF), 197 Route 18 South, Suite..., President, Application Type: Add NVO Service. Nano Express Corp. (NVO,) 5765 N. Lincoln Avenue, Suite 17... Zai Ocean Services dba Zai Container Line (NVO & OFF), 6324 NW 97th Avenue, Doral, FL 33178, Officer...

  15. 77 FR 35079 - License Renewal Application for Seabrook Station, Unit 1 ; NextEra Energy Seabrook, LLC

    Science.gov (United States)

    2012-06-12

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-443; NRC-2010-0206] License Renewal Application for Seabrook Station, Unit 1 ; NextEra Energy Seabrook, LLC AGENCY: Nuclear Regulatory Commission. ACTION: License renewal application; intent to prepare supplement to draft [[Page 35080

  16. A study for the review of export license through the NSG denial notification

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Sun Do; Yang, Seung Hyo [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2012-10-15

    All NSG participating members that have rejected applications of export licenses for nuclear export control items within their respective countries must give notice of this to the point of contact at NSG. This is referred to as the Denial Notification, and each of the participating members must respect the denial notifications of the other member nations. When participating members seek to obtain approval for an export license that is essentially identical to the denial notification of other member nations, they must necessarily go through the process of prior discussion with the nation that gave the denial notification. Also, it is regulated that the export license must not be approved without the sufficient exchange of information. Thus, these records of denial notifications must be constantly checked and maintained as the latest updated information and these records must be utilized in related approval examinations. This study analyzes the denial notifications that have been recorded in the past 20 years and it describes the areas that must be mainly examined at the export and import licensing.

  17. 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

  18. Safety case for license application for a final repository: The French example

    International Nuclear Information System (INIS)

    Boissier, Fabrice; Voinis, Sylvie

    2014-01-01

    The reversible repository in a deep geological formation is the French reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste (HLW and ILW). Twenty years of R and D work and conceptual and basic studies since the first French Act of 1991 led, in particular, to a feasibility demonstration in 2005. According to the French Act on Radioactive Waste of 28 of June 2006, Andra shall design a reversible repository in order to apply for license in 2015. In response to this demand, Andra developed the industrial project known as 'Cigeo', a reversible geological disposal facility for HLW and ILW located in Meuse/Haute-Marne. Two years before applying for authorisation, Andra's project is now focusing on three main targets: developing Cigeo's industrial design, preparing the authorisation process through increased exchanges with stakeholders and the preparation of a safety case to support authorisation application. The latter draws on the previous safety cases of 2005 and 2009, which give a sound basis to assess Cigeo's safety, both for the operational and post-closure periods. In this new stage of the project, the challenging issues for the preparation of the safety case are the following: - to identify the various regulatory frameworks (nuclear and non-nuclear) and guides applicable to the facility; - to ensure that the industrial design complies in particular with the safety requirements as presented in the safety case and its supporting safety assessment; - to identify crucial inputs (R and D, tests,...) needed to support the authorisation application, in particular, to bring convincing arguments to assess the technical feasibility of the design and when appropriate its ability to meet the safety requirements; - to ensure that all the requirements from previous regulatory and peer reviews (national and international?) are taken into account. (authors)

  19. Standard format and content for a license application to store spent fuel and high-level radioactive waste

    International Nuclear Information System (INIS)

    1989-09-01

    Subpart B, ''License Application, Form, and Contents,'' of 10 CFR Part 72, ''Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste,'' specifies the information to be covered in an application for a license to store spent fuel in an independent spent fuel storage installation (ISFSI) or to store spent fuel and high-level radioactive waste in a monitored retrievable storage facility (MRS). However, Part 72 does not specify the format to be followed in the license application. This regulatory guide suggests a format acceptable to the NRC staff for submitting the information specified in Part 72 for license application to store spent fuel in an ISFSI or to store spent fuel and high-level radioactive waste in an MRS

  20. Licensing an assured isolation facility for low-level radioactive waste. Volume 1: Licensing strategy and issues

    International Nuclear Information System (INIS)

    Silverman, D.J.; Bauser, M.A.; Baird, R.D.

    1998-07-01

    This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application

  1. Palo Verde Generating Station, Units 4 and 5. License application, general information

    International Nuclear Information System (INIS)

    1978-01-01

    A license application for two more Palo Verde reactors, Units 4 and 5, is presented. The two PWR reactors have a nominal net generating power each of 1,270 MW(e). Containments are steel-lined prestressed cylindrical structures with hemispherical domes. The reactors are replicas of Palo Verde 1, 2 and 3 (see DOCKETS 50528, 50529 and 50530) using the standard Combustion Engineering System 80 (see DOCKET-STN-50470)

  2. 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

  3. Dealing with the current permissibility application for constructing a spent fuel DGR in Sweden. SKB's license applications for a spent fuel repository

    International Nuclear Information System (INIS)

    Olsson, Olle

    2014-01-01

    The nuclear power utilities in Sweden were in 1976 obliged to demonstrate a safe method for final disposal of spent fuel in order to start operation of new reactors. This initiated a comprehensive research, development and demonstration programme and the development of the KBS-method for final disposal. A new Nuclear Activities Act in 1984 gave the reactor owners full technical and financial responsibility for the waste. They gave in turn SKB the responsibility for all nuclear waste management. Reprocessing was no longer required and direct disposal of the spent fuel has, since then, been the main alternative. Alternative methods for final disposal have been evaluated and compared to the KBS-3-method but it has remained the preferred alternative. A comprehensive research, development and demonstration programme to strengthen the scientific basis and to refine the KBS-3-method has been operated by SKB since then. The site selection process for the final repository for spent nuclear fuel was initiated in 1992. The work included general siting studies at the national and the municipal level and in 2002, SKB initiated site investigations for siting of a final repository on two sites: the Simpevarp and Laxemar areas and the Forsmark area. At the same time, the work on preparing license applications to construct and operate an encapsulation plant and a final repository for spent fuel was started. In June 2009, SKB announced Forsmark as the selected site for the final repository. This paper reviews the applicable legislation and describes the license application, the licensing review and the preparations for implementation

  4. Regulatory guidance for license renewal

    International Nuclear Information System (INIS)

    Thoma, John A.

    1991-01-01

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

  5. Review of nuclear air treatment system related License Event Reports for the period 1985 - 1987

    International Nuclear Information System (INIS)

    Jacox, J.W.

    1989-01-01

    This paper will continue the review of HVAC/NATS related LERS presented at past Air Cleaning Conferences by Dr. D. W. Moeller and his associates. The general approach and format are similar. LER abstracts from mid 1985 through 1987 were reviewed and those related to HVAC/NATS classified and analyzed. The categories were jointly developed by Dr. Moeller, Dr. Casper Sun and myself. In appropriate cases both primary and secondary categories fora problem are given. A basic listing by category and brief statistical review are presented. Additionally a number of categories are discussed in some detail. The categories chosen for specific review are intended to highlight particular problem areas. NUREG/CR-2000 License Event Report (LER) Compilation is the basis for the initial review and coding. In essentially all cases where an LER is classified as of interest the complete LER was obtained and reviewed in full. The intent of this paper is to provide a basis for the industry to document and analyze problem areas that require additional attention. It appears that about 15% of all LERS in the subject period are HVAC/NATS related. This figure is generally consistent with those reported at the 17th DOE Nuclear Air Cleaning Conference. It is hoped that such attention will allow additional resources to be allocated to upgrade systems, procedures and training as well as in some cases government regulation

  6. Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-term operating license applications

    International Nuclear Information System (INIS)

    1980-01-01

    The results are presented of a generic evaluation of feedwater transients, small-break loss-of-coolant accidents (LOCAs), and other TMI-2-related events for General Electric Company (GE)-designed operating plants and near-term operating license applications to confirm or establish the bases for the continued safe operation of the operating plants. The results of this evaluation are presented in this report in the form of a set of findings and recommendations in each of the principal review areas. Additional review of the accident is continuing and further information is being obtained and evaluated. Any new information will be reviewed and modifications will be made as appropriate

  7. NUMARC view of license renewal criteria

    International Nuclear Information System (INIS)

    Edwards, D.W.

    1989-01-01

    The Atomic Energy Act and the implementing regulations of the US Nuclear Regulatory Commission (NRC) permit the renewal of nuclear plant operating licenses upon expiration of their 40-year license term. However, the regulatory process by which license renewal may be accomplished and the requirements for the scope and content of renewal applications are yet to be established. On August 29, 1988, the NRC published an Advanced Notice of Proposed Rulemaking regarding the subject of license renewal. This Advanced Notice and the NUREG which it references, NUREG-1317, Regulatory Options for Nuclear Plant License Renewal, provide the most recent regulatory thought on this issue. The basic issue addressed by NUREG-1317 is the definition of an adequate licensing basis for the renewal of a plant license. The report contemplates three alternatives in this regard. This paper discusses each of these three proposals. The NUMARC NUPLEX Working Group endorses a license renewal process based on a plant's current licensing basis along with an evaluation of the pertinent components, systems, and structures affected by age-related degradation. The NUMARC NUPLEX Working group believes that an appropriate scope for NRC review of the license renewal application should focus on those safety-significant structures systems, and components subject to significant age-related degradation that are not subject to existing recognized effective replacement, refurbishment, or inspection programs. The paper also briefly discusses NUMARC's view of the role of the Backfit Rule in the license renewal process

  8. Development, assessment, licensing, and application of RELAP5YA at Yankee Atomic Electric Company

    International Nuclear Information System (INIS)

    Husain, A.

    1984-01-01

    Since 1975, Yankee Atomic Electric Company (YAEC) has been licensed to perform LOCA analyses (large and small breaks) for PWRs. The methods are based upon the WREM package, comprised of RELAP4-MOD 3, RELAP4-FLOOD, and TOODEE-2EM. Significant efforts were expended to compare WREM models against Appendix K criteria, and to incorporate changes for compliance with the criteria and for improved representation of LOCA phenomena. /SUP 2,3,4/ This internalized capability has been used extensively for licensing the Yankee and Maine Yankee plants, and for timely resolution of LOCA issues which frequently arose. The value of this internalized analysis capability was well recognized by the Yankee management. In 1979, Yankee embarked upon another LOCA Methods Development Program. One objective was to remove extra conservatisms inherent in older codes to provide additional operational flexibility for our plants. Also, we needed a code which could be used in a production mode to provide realistic response for off-normal conditions to be used in operator training and emergency guideline assessment. This program resulted in the development of RELAP5YA. The development, assessment, licensing, and application of RELAP5YA at YAEC is briefly described in this paper

  9. Licensing and advanced fuel designs

    International Nuclear Information System (INIS)

    Davidson, S.L.; Novendstern, E.H.

    1991-01-01

    For the past 15 years, Westinghouse has been actively involved in the development and licensing of fuel designs that contain major advanced features. These designs include the optimized fuel assembly, The VANTAGE 5 fuel assembly, the VANTAGE 5H, and most recently the VANTAGE+ fuel assembly. Each of these designs was supported by extensive experimental data, safety evaluations, and design efforts and required intensive interaction with the US Nuclear Regulatory Commission (NRC) during the review and approval process. This paper presents a description of the licensing approach and how it was utilized by the utilities to facilitate the licensing applications of the advanced fuel designs for their plants. The licensing approach described in this paper has been successfully applied to four major advanced fuel design changes ∼40 plant-specific applications, and >350 cycle-specific reloads in the past 15 years

  10. Application of ASP Technology to Realize the Online Administrative License of the earthquake in Hunan Province

    Science.gov (United States)

    Tang, Hongliang; Kang, Chengxu; Tian, Youping

    2018-01-01

    Realizing the online handling of administrative approval of earthquakes is an important measure to improve work efficiency and facilitate people’s convenience. Based on the analysis of the characteristics and processes of the administrative licensing in the earthquake industry, this paper proposes an online processing model based on ASP technology and an online processing system based on B/S architecture. This paper presents the design and implementation methods. The application of the system shows that the system is simple in design and full in function, and can be used on mobile platforms such as computers and mobile phones, and has good practicability and forward-lookingness.

  11. 77 FR 23241 - Lock+ Hydro Friends Fund XXX, LLC; Notice of Intent To File License Application, Filing of Pre...

    Science.gov (United States)

    2012-04-18

    ... Friends Fund XXX, LLC; Notice of Intent To File License Application, Filing of Pre-Application Document.... Date Filed: February 20, 2012. d. Submitted By: Lock+ Hydro Friends Fund XXX, LLC. e. Name of Project... Applicant Contact: Mr. Mark R. Stover, Lock+\\TM\\ Hydro Friends Fund XXX, c/o Hydro Green Energy, LLC, 900...

  12. 47 CFR 25.137 - Application requirements for earth stations operating with non-U.S. licensed space stations.

    Science.gov (United States)

    2010-10-01

    ... space stations. (a) Earth station applicants or entities filing a “letter of intent” or “Petition for... Union. (d) Earth station applicants requesting authority to operate with a non-U.S.-licensed space... 47 Telecommunication 2 2010-10-01 2010-10-01 false Application requirements for earth stations...

  13. The Monticello license renewal project

    International Nuclear Information System (INIS)

    Clauss, J.M.; Harrison, D.L.; Pickens, T.A.

    1993-01-01

    Today, 111 nuclear power plants provide over 20 percent of the electrical energy generated in the United States. The operating license of the oldest operating plant will expire in 2003, one-third of the existing operating licenses will expire by 2010 and the newest plant's operating license will expire in 2033. The National Energy Strategy (NES) prepared by the Department of Energy (DOE) assumes that 70 percent of the current operating plants will continue to operate beyond their current license expiration. Power from current operating plants can assist in ensuring an adequate, diverse, and environmentally acceptable energy supply for economic growth and improved U.S. competitiveness. In order to preserve this energy resource, three major tasks must be successfully completed: (1) establishment of regulations, technical standards, and procedures for the preparation and review of License Renewal Applications (LRAs); (2) development of technical criteria and bases for monitoring, refurbishing or replacing plant equipment; and (3) demonstration of the regulatory process by a plant obtaining a renewed license. Since 1986, the DOE has been working with the nuclear industry and the Nuclear Regulatory Commission (NRC) to establish and demonstrate the option to extend the life of a nuclear power plant by renewing the operating license. The Monticello Lead Plant demonstration project was initiated in September 1988, following the Pilot Plant studies. This paper is primarily focused on the status and insights gained from the Northern States Power Company (NSP) Monticello Lead Plant demonstration project. The following information is included: (1) Current Status - Monticello License Renewal Application; (2) Economic Analysis; (3) License Renewal Regulatory Uncertainty Issues; (4) Key Decisions; (5) Management Structure; (6) Technical and Licensing Perspective; (7) NRC Interactions; (8) Summary

  14. Overview of the Yucca Mountain Licensing Process

    International Nuclear Information System (INIS)

    M. Wisenburg

    2004-01-01

    This paper presents an overview of the licensing process for a Yucca Mountain repository for high-level radioactive waste and spent nuclear fuel. The paper discusses the steps in the licensing proceeding, the roles of the participants, the licensing and hearing requirements contained in the Code of Federal Regulations. A description of the Nuclear Regulatory Commission (NRC) staff acceptance and compliance reviews of the Department of Energy (DOE) application for a construction authorization and a license to receive and possess high-level radioactive waste and spent nuclear fuel is provided. The paper also includes a detailed description of the hearing process

  15. 18 CFR 16.10 - Information to be provided by an applicant for new license: Filing requirements.

    Science.gov (United States)

    2010-04-01

    ... FEDERAL POWER ACT PROCEDURES RELATING TO TAKEOVER AND RELICENSING OF LICENSED PROJECTS Applications for... redistribution of power flows on line loading (with respect to applicable thermal, voltage, or stability limits... governmental agencies and subdivisions likely to be interested in or affected by the proposed expansion. (11...

  16. 76 FR 40905 - Turnagain Arm Tidal Electric Energy Project; Notice of Intent To File License Application, Filing...

    Science.gov (United States)

    2011-07-12

    ... Tidal Electric Energy Project; Notice of Intent To File License Application, Filing of Pre-Application....: 13509-001. c. Dated Filed: May 11, 2011. d. Submitted By: Turnagain Arm Tidal Energy Corporation. e. Name of Project: Turnagain Arm Tidal Electric Energy Project. f. Location: Of the Upper Cook Inlet off...

  17. 77 FR 58370 - Pennamaquan Tidal Power LLC; Notice of Intent To File License Application, Filing of Pre...

    Science.gov (United States)

    2012-09-20

    ... Tidal Power LLC; Notice of Intent To File License Application, Filing of Pre-Application Document (PAD... Filed: July 19, 2012. d. Submitted By: Pennamaquan Tidal Power LLC (Pennamaquan Power). e. Name of Project: Pennamaquan Tidal Power Plant Project. f. Location: On the Pennamaquan River at the entrance to...

  18. 76 FR 81992 - PPL Bell Bend, LLC; Combined License Application for Bell Bend Nuclear Power Plant; Exemption

    Science.gov (United States)

    2011-12-29

    ... License Application for Bell Bend Nuclear Power Plant; Exemption 1.0 Background PPL Bell Bend, LLC... for Nuclear Power Plants.'' This reactor is to be identified as Bell Bend Nuclear Power Plant (BBNPP... based upon the U.S. EPR reference COL (RCOL) application for UniStar's Calvert Cliffs Nuclear Power...

  19. 75 FR 51451 - Erie Boulevard Hydropower, L.P.; Notice of Intent To File License Application, Filing of Pre...

    Science.gov (United States)

    2010-08-20

    ... Hydropower, L.P.; Notice of Intent To File License Application, Filing of Pre-Application Document, and.... Project No.: 7320-040. c. Dated Filed: June 29, 2010. d. Submitted By: Erie Boulevard Hydropower, L.P. e...: John Mudre at (202) 502-8902; or e-mail at [email protected] . j. Erie Boulevard Hydropower, L.P...

  20. Gibbs and Hill Standard Safety Analysis Report, GIBBSSAR. License application, volume 1: chapters 1--3 (section 7)

    International Nuclear Information System (INIS)

    1977-01-01

    License application for the GIBBSSAR Standard Plant is presented. The reactor used with the GIBBSSAR balance-of-plant system is the Westinghouse 3800 MW(t) PWR. This portion of the application includes a general plant description; site characteristics; and design of structures, components, equipment and systems

  1. Dry spent fuel storage licensing

    International Nuclear Information System (INIS)

    Sturz, F.C.

    1995-01-01

    In the US, at-reactor-site dry spent fuel storage in independent spent fuel storage installations (ISFSI) has become the principal option for utilities needing storage capacity outside of the reactor spent fuel pools. Delays in the geologic repository operational date at or beyond 2010, and the increasing uncertainty of the US Department of Energy's (DOE) being able to site and license a Monitored Retrievable Storage (MRS) facility by 1998 make at-reactor-site dry storage of spent nuclear fuel increasingly desirable to utilities and DOE to meet the need for additional spent fuel storage capacity until disposal, in a repository, is available. The past year has been another busy year for dry spent fuel storage licensing. The licensing staff has been reviewing 7 applications and 12 amendment requests, as well as participating in inspection-related activities. The authors have licensed, on a site-specific basis, a variety of dry technologies (cask, module, and vault). By using certified designs, site-specific licensing is no longer required. Another new cask has been certified. They have received one new application for cask certification and two amendments to a certified cask design. As they stand on the brink of receiving multiple applications from DOE for the MPC, they are preparing to meet the needs of this national program. With the range of technical and licensing options available to utilities, the authors believe that utilities can meet their need for additional spent fuel storage capacity for essentially all reactor sites through the next decade

  2. Integration of MGDS design into the licensing process

    International Nuclear Information System (INIS)

    1997-12-01

    This paper presents an overview of how the Mined Geologic Disposal System (MGDS) design for a potential repository is integrated into the licensing process. The integration process employs a two-told approach: (1) ensure that the MGDS design complies with applicable Nuclear Regulatory Commission (NRC) licensing requirements, and (2) ensure that the MGDS design is appropriately reflected in a license application that is acceptable to the NRC for performing acceptance and compliance reviews

  3. Screening Analysis of Criticality Features, Events, and Processes for License Application

    International Nuclear Information System (INIS)

    J.A. McClure

    2004-01-01

    This report documents the screening analysis of postclosure criticality features, events, and processes. It addresses the probability of criticality events resulting from degradation processes as well as disruptive events (i.e., seismic, rock fall, and igneous). Probability evaluations are performed utilizing the configuration generator described in ''Configuration Generator Model'', a component of the methodology from ''Disposal Criticality Analysis Methodology Topical Report''. The total probability per package of criticality is compared against the regulatory probability criterion for inclusion of events established in 10 CFR 63.114(d) (consider only events that have at least one chance in 10,000 of occurring over 10,000 years). The total probability of criticality accounts for the evaluation of identified potential critical configurations of all baselined commercial and U.S. Department of Energy spent nuclear fuel waste form and waste package combinations, both internal and external to the waste packages. This criticality screening analysis utilizes available information for the 21-Pressurized Water Reactor Absorber Plate, 12-Pressurized Water Reactor Absorber Plate, 44-Boiling Water Reactor Absorber Plate, 24-Boiling Water Reactor Absorber Plate, and the 5-Defense High-Level Radioactive Waste/U.S. Department of Energy Short waste package types. Where defensible, assumptions have been made for the evaluation of the following waste package types in order to perform a complete criticality screening analysis: 21-Pressurized Water Reactor Control Rod, 5-Defense High-Level Radioactive Waste/U.S. Department of Energy Long, and 2-Multi-Canister Overpack/2-Defense High-Level Radioactive Waste package types. The inputs used to establish probabilities for this analysis report are based on information and data generated for the Total System Performance Assessment for the License Application, where available. This analysis report determines whether criticality is to be

  4. [Radiation protection in medical research : Licensing requirement for the use of radiation and advice for the application procedure].

    Science.gov (United States)

    Minkov, V; Klammer, H; Brix, G

    2017-07-01

    In Germany, persons who are to be exposed to radiation for medical research purposes are protected by a licensing requirement. However, there are considerable uncertainties on the part of the applicants as to whether licensing by the competent Federal Office for Radiation Protection is necessary, and regarding the choice of application procedure. The article provides explanatory notes and practical assistance for applicants and an outlook on the forthcoming new regulations concerning the law on radiation protection of persons in the field of medical research. Questions and typical mistakes in the application process were identified and evaluated. The qualified physicians involved in a study are responsible for deciding whether a license is required for the intended application of radiation. The decision can be guided by answering the key question whether the study participants would undergo the same exposures regarding type and extent if they had not taken part in the study. When physicians are still unsure about their decision, they can seek the advisory service provided by the professional medical societies. Certain groups of people are particularly protected through the prohibition or restriction of radiation exposure. A simplified licensing procedure is used for a proportion of diagnostic procedures involving radiation when all related requirements are met; otherwise, the regular licensing procedure should be used. The new radiation protection law, which will enter into force on the 31st of december 2018, provides a notification procedure in addition to deadlines for both the notification and the licensing procedures. In the article, the authors consider how eligible studies involving applications of radiation that are legally not admissible at present may be feasible in the future, while still ensuring a high protection level for study participants.

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

    Science.gov (United States)

    2014-01-01

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

  6. Current regulatory and licensing status for byproduct sources, facilities and applications

    International Nuclear Information System (INIS)

    Tingey, G.L.; Jensen, G.A.; Hazelton, R.F.

    1985-02-01

    Public use of nuclear byproducts, especially radioactive isotopes, will require approval by various regulatory agencies. Use of cesium-137 as an irradiation source for sterilizing medical products will require US Nuclear Regulatory Commission (NRC) approval. Two applications have been filed with NRC, and approval is expected soon. Widespread use of irradiation for food products depends on a favorable ruling by the Food and Drug Administration (FDA). A ruling is pending that would permit irradiation of fruits and vegetables up to 100 krad. NRC also controls the use of isotopes in remote power generators, but little regulatory action has been required in recent years. Recent development of radioluminescent (RL) lighting for runway lights has led to interest by commercial manufacturers. At the present time, a license has been issued to at least one manufacturer for sale of tritium-powered runway lights. 28 refs., 1 fig

  7. 78 FR 37281 - Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating Licenses

    Science.gov (United States)

    2013-06-20

    ... factors: (1) License renewal will involve nuclear power plants for which the environmental impacts of...) Changes in the environment around nuclear power plants are gradual and predictable. The 1996 GEIS improved... environmental impacts that may occur from renewing commercial nuclear power plant operating licenses; (2...

  8. Nuclear relevant installations licensing methodology in the Argentine Republic

    International Nuclear Information System (INIS)

    Paganini, C.E.

    1986-01-01

    A review of the requeriments of the Nuclear Installations Advisory Committee on Licensing (CALIN) from the nuclear security point of view, is presented. The methodology applied by the CALIN for the licensing in the Argentine Republic is included as well as codes, standards of applications and the interaction between the licensing Authority and the Responsible Entity during the whole process. Finally, the Atucha II nuclear power plant's licensing, in construction at present, is explained and the standard, of the licensing schedule, is presented graphically. (author) [es

  9. Safety and licensing of MOX versus UO2 for BWRs and PWRs: Aspects applicable for civilian and weapons grade Pu

    International Nuclear Information System (INIS)

    Goldstein, L.; Malone, J.

    2000-01-01

    This paper reviews the safety and licensing differences between MOX and UO 2 BWR and PWR cores. MOX produced from the normal recycle route and from weapons grade material are considered. Reload quantities of recycle MOX assemblies have been licensed and continue to operate safely in European LWRs. In general, the European MOX assemblies in a reload are 2 . These studies indicated that no important technical or safety related issues have evolved from these studies. The general specifications used by fuel vendors for recycled MOX fuel and core designs are as follows: MOX assemblies should be designed to minimize or eliminate local power peaking mismatches with co-resident and adjacently loaded UO 2 assemblies. Power peaking at the interfaces arises from different neutronic behavior between UO 2 and MOX assemblies. A MOX core (MOX and UO 2 or all-MOX assemblies) should provide cycle energy equivalent to that of an all-UO 2 core. This applies, in particular, to recycle MOX applications. An important consideration when burning weapons grade material is rapid disposition which may not necessarily allow for cycle energy equivalence. The reactivity coefficients, kinetics data, power peaking, and the worth of shutdown systems with MOX fuel and cores must be such to meet the design criteria and fulfill requirements for safe reactor operation. Both recycle and weapons grade plutonium are considered, and positive and negative impacts are given. The paper contrasts MOX versus UO 2 with respect to safety evaluations. The consequences of some transients/accidents are compared for both types of MOX and UO 2 fuel. (author)

  10. The United States nuclear regulatory commission license renewal process

    International Nuclear Information System (INIS)

    Holian, B.E.

    2009-01-01

    The United States (U.S.) Nuclear Regulatory Commission (NRC) license renewal process establishes the technical and administrative requirements for the renewal of operating power plant licenses. Reactor ope-rating licenses were originally issued for 40 years and are allowed to be renewed. The review process for license renewal applications (L.R.A.) provides continued assurance that the level of safety provided by an applicant's current licensing basis is maintained for the period of extended operation. The license renewal review focuses on passive, long-lived structures and components of the plant that are subject to the effects of aging. The applicant must demonstrate that programs are in place to manage those aging effects. The review also verifies that analyses based on the current operating term have been evaluated and shown to be valid for the period of extended operation. The NRC has renewed the licenses for 52 reactors at 30 plant sites. Each applicant requested, and was granted, an extension of 20 years. Applications to renew the licenses of 20 additional reactors at 13 plant sites are under review. As license renewal is voluntary, the decision to seek license renewal and the timing of the application is made by the licensee. However, the NRC expects that, over time, essentially all U.S. operating reactors will request license renewal. In 2009, the U.S. has 4 plants that enter their 41. year of ope-ration. The U.S. Nuclear Industry has expressed interest in 'life beyond 60', that is, requesting approval of a second renewal period. U.S. regulations allow for subsequent license renewals. The NRC is working with the U.S. Department of Energy (DOE) on research related to light water reactor sustainability. (author)

  11. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    1987-05-01

    The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes

  12. Applicability of IBAMA normative instruction 146-2007 to pipeline environmental licensing

    Energy Technology Data Exchange (ETDEWEB)

    Basbaum, Marcos A.; Fonseca, Renata A.A. [Servicos de Engenharia Emilio Baumgart Ltda. (SEEBLA), Rio de Janeiro, RJ(Brazil)], e-mail: mbasbaum.seebla@petrobras.com.br, e-mail: renataamorim.seebla@petrobras.com.br; Torggler, Bianca F.; Fernandes, Renato; Guimaraes, Ricardo Z.P. [Petroleo do Brasil S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil)], e-mail: torggler@petrobras.com.br, e-mail: renatofer@petrobras.com.br, e-mail: rzaluar@petrobras.com.br

    2009-07-01

    PETROBRAS has been conducting several wildlife programs in response to environmental licensing requirements from IBAMA (Brazilian environmental agency). Since 2007, IBAMA has been requiring the application of the Normative Instruction n. 146 (NI), which establishes criteria for wildlife management in the influence areas of new enterprises. However, experience from PETROBRAS has shown that many of the NI articles are not applicable to pipelines. Thus, a critical analysis of this NI was done based on data from company's wildlife programs. Our analysis indicated that the main NI items that do not apply to pipelines are: 1 - Animal rescue programs in deforested areas and selection of release areas, 2 - More than two fauna monitoring campaigns a year, 3 - Monitoring programs involving all groups of terrestrial vertebrates and also invertebrate classes. The non-applicability of these items is due to: 1 - The majority of pipelines are built in areas without significant native vegetation or with small fragments only, which are usually in secondary stage of ecological succession. Most pipelines scarcely involve removal of primary vegetation, 2 - Pipelines have an influence area restricted to a range of 800 m and the construction directly affects only strips from 20 m to 30 m, 3 - The most relevant impacts associated with pipelines are temporary, and do not persist during their operation. (author)

  13. 14 CFR 415.57 - Payload review.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Payload review. 415.57 Section 415.57... TRANSPORTATION LICENSING LAUNCH LICENSE Payload Review and Determination § 415.57 Payload review. (a) Timing. A payload review may be conducted as part of a license application review or may be requested by a payload...

  14. Licensing issues

    International Nuclear Information System (INIS)

    Roberts, J.P.; Desell, L.J.; Birch, M.L.; Berkowitz, L.; Bader, J.F.

    1992-01-01

    To provide guidance for the Department of Energy's (DOE) Civilian Radioactive Waste Management Program, the Nuclear Regulatory Commission (NRC) has issued a draft regulatory guide on the Format and Content for the License Application for the High-Level Waste Repository (FCRG). To facilitate the development of the FCRG, NRC suggested that DOE use the draft guide as the basis for preparing an annotated outline for a license application. DOE is doing so using an iterative process called the Annotated Outline Initiative. DOE;s use of the Initiative will assist in achieving the desired incorporation of actual experience in the FCRG, contribute to the development of shared interpretation and understanding of NRC regulations, and provide other important programmatic benefits described in this paper

  15. 78 FR 30914 - Grand River Dam Authority Notice of Application for Temporary Variance of License and Soliciting...

    Science.gov (United States)

    2013-05-23

    .... Description of Request: Grand River Dam Authority (GRDA) requests a temporary variance, for the year 2013, to... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 1494-416] Grand River Dam Authority Notice of Application for Temporary Variance of License and Soliciting Comments, Motions To...

  16. 77 FR 39675 - Applications for Licensing as a Non-Leveraged Rural Business Investment Company Under the Rural...

    Science.gov (United States)

    2012-07-05

    ... large 3-ring binder. Label the binders with the RBIC's name. Submit one complete and unbound one-sided hard copy of the MAQ and Exhibits suitable for photocopying (i.e., no hole punches, staples, paper clips, tabs or binders). Applicants must enclose in their submission a nonrefundable licensing fee of...

  17. 78 FR 4467 - UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3...

    Science.gov (United States)

    2013-01-22

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3, Exemption 1.0 Background UniStar Nuclear Energy (UNE), on behalf of Calvert Cliffs Nuclear Project, LLC and UniStar Nuclear Operating Services...

  18. 76 FR 81994 - UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit...

    Science.gov (United States)

    2011-12-29

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit 3; Exemption 1.0 Background: UniStar Nuclear Energy (UNE) submitted to the U.S. Nuclear Regulatory Commission (NRC or the Commission ) a...

  19. 76 FR 11522 - In the Matter of Progress Energy Florida, Inc. (Combined License Application, Levy County Nuclear...

    Science.gov (United States)

    2011-03-02

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 52-029-COL, 52-030-COL] In the Matter of Progress Energy Florida, Inc. (Combined License Application, Levy County Nuclear Power Plant, Units 1 and 2... by the Nuclear Regulatory Commission staff in this case. Mr. Dehmel has not previously performed any...

  20. 75 FR 69063 - Port Bailey Wild Enterprises, LLC; PB Energy, Inc.; Notice of Application for Transfer of License...

    Science.gov (United States)

    2010-11-10

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 1432-010] Port Bailey Wild... Motions To Intervene November 3, 2010. On October 22, 2010, Port Bailey Wild Enterprises, LLC (transferor) and PB Energy, Inc. (transferee) filed a joint application for transfer of license for the Dry Spruce...

  1. 78 FR 61984 - Copper Valley Electric Association, Inc.; Notice of Application To Amend License and Accepted for...

    Science.gov (United States)

    2013-10-09

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13124-005] Copper Valley...: Amendment to License. b. Project No: 13124-005. c. Date Filed: September 27, 2013. d. Applicant: Copper..., Copper Valley Electric Association, Inc., P.O. Box 45, Mile 187 Glenn Highway, Glennallen, AK 99588, (907...

  2. 78 FR 14528 - Mayo Hydropower, LLC, Avalon Hydropower, LLC; Notice of Application for Transfer of License, and...

    Science.gov (United States)

    2013-03-06

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 11169-029] Mayo Hydropower, LLC, Avalon Hydropower, LLC; Notice of Application for Transfer of License, and Soliciting Comments and Motions To Intervene On November 20, 2012, Mayo Hydropower, LLC (transferor) and Avalon Hydropower...

  3. 78 FR 5196 - Notice of Invitation To Participate; Exploration for Coal in Colorado License Application COC-75642

    Science.gov (United States)

    2013-01-24

    ...] Notice of Invitation To Participate; Exploration for Coal in Colorado License Application COC-75642... Mineral Leasing Act of 1920, as amended by the Federal Coal Leasing Amendments Act of 1976, and to Bureau..., Colorado. DATES: Any party electing to participate in this exploration program must send written notice to...

  4. 76 FR 55701 - Notice of Invitation to Participate; Exploration for Coal in Colorado License Application COC-74895

    Science.gov (United States)

    2011-09-08

    ...] Notice of Invitation to Participate; Exploration for Coal in Colorado License Application COC-74895... Mineral Leasing Act of 1920, as amended by the Federal Coal Leasing Amendments Act of 1976, and to Bureau... coal deposits owned by the United States of America in lands located in Routt County, Colorado. DATES...

  5. 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.

  6. 47 CFR 97.21 - Application for a modified or renewed license grant.

    Science.gov (United States)

    2010-10-01

    ... name, club name, license trustee name or license custodian name in accordance with § 1.913 of this... form to a Club Station Call Sign Administrator who must submit the information thereon to the FCC in an electronic batch file. The Club Station Call Sign Administrator must retain the collected information for at...

  7. Lessons learned from the licensing process and the operational performance of the important to safety digital application implemented at the Mexican nuclear facilities

    International Nuclear Information System (INIS)

    Ledesma-Carrion, R.

    1998-01-01

    This paper describes the main concerns detected during the licensing processes performed by the Mexican Nuclear Regulatory Commission (CNSNS) for the NUMAC-PRNM, the Integrated Computer Systems at the Laguna Verde Nuclear Power Station (LVNPS) and for the Digital Control Console of the Triga Mark III Research Reactor (TMRR). The review and approval process was performed following the guidelines of the US Nuclear Regulatory Commission (USNRC); the regulatory frame applied includes the Code of Federal Regulation (10CFR50), some Regulatory Guides, such as: RG 1.152, RG 1.153, some Industrial Standards, for example: IEEE-279, IEEE-603, IEEE-7.4.3-2. Also, based on the operational experience taken from the LVNPS License Event Report (LER) reported under the 10CFR50.72 and 10CFR50.73 USNRC rules, and from the Report of Events to be Analyzed (REA) issued for a CNSNS agreement with the utility stated by the necessity to determine failure rates of digital equipment, some case studies and a preliminary failure cause classification is shown. The Event Report evaluation covered topics related to the software, hardware and firmware issues. Finally, the lessons learned from the licensing assessments and from the operational experience of the digital applications implemented are presented. It will also give the regulatory activities related to an IAEA international cooperation project on I and C digital upgrade concerns. (author)

  8. Current status of the PBMR licensing project

    International Nuclear Information System (INIS)

    Mysen, A.; Clapisson, G.A.; Metcalf, P.E.

    2000-01-01

    The CNS is currently reviewing the PBMR conceptual design from a licensibility point of view. The PBMR concept is based on a High Temperature Gas Cooled Reactor - pebble bed reactor type. It is anticipated that the PBMR design will rely on inherent safety characteristics to contain fission products within fuel over the full range of design basis events. This feature combined with the high temperature integrity of the fuel and structural graphite, allows the safe use of a high coolant temperature, which allows consideration of the future development of this reactor for non-electrical applications of nuclear heat for industrial use. The CNS licensing approach requires that the licensing and design basis of the plant should respect prevailing international norms and practices and that a quantitative risk assessment should demonstrate compliance with the CNS fundamental safety standards. The first stage of the licensing process is now ongoing; this is a pre-application phase, which will result in a statement on licensibility being issued. Identification of the specific documentation requirements and information needed is required across every step of the licensing process. Top level regulatory requirements have been established for the PBMR. They include the CNS fundamental safety standard and basic licensing criteria, which describes requirements on licensees of nuclear installations regarding risk assessment and compliance with the safety criteria and define classification of licensing basis events. (author)

  9. 75 FR 32983 - Commercial Driver's License (CDL) Standards: Exemption

    Science.gov (United States)

    2010-06-10

    ...-28480] Commercial Driver's License (CDL) Standards: Exemption AGENCY: Federal Motor Carrier Safety... commercial driver's license (CDL) as required by current regulations. FMCSA reviewed NAAA's application for... demonstrate alternatives its members would employ to ensure that their commercial motor vehicle (CMV) drivers...

  10. Open data used in water sciences - Review of access, licenses and understandability

    Science.gov (United States)

    Falkenroth, Esa; Lagerbäck Adolphi, Emma; Arheimer, Berit

    2016-04-01

    . Understandability of the data sets: 13 major formats were found, but the major issues encountered were due to incomplete documentation or metadata and problems with decoding binary formats. Ideally, open data sets should be represented in well-known formats and they should be accompanied with sufficient documentation so the data set can be understood. The development efforts on Water ML and NETCDF and other standards could improve understandability of data sets over time but in this review, only a few data sets were provided in these formats. Instead, the majority of datasets were stored in various text-based or binary formats or even document-oriented formats such as PDF. Other disciplines such as meteorology have long-standing traditions of operational data exchange format whereas hydrology research is still quite fragmented and the data exchange is usually done on a case-by-case basis. With the increased sharing of open data there is a good chance the situation will improve for data sets used also in water sciences. License issue: Only 3% of the data is completely free to use, while 57% can be used for non-commercial purposes or research. A high number of datasets did not have a clear statement on terms of use and limitation for access. In most cases the provider could be contacted regarding licensing issues.

  11. Qualification of the coupled RELAP5/PANTHER/COBRA code package for licensing applications

    International Nuclear Information System (INIS)

    Schneidesch, C.R.; Zhang Jinzhao

    2004-01-01

    A coupled thermal hydraulics-neutronics code package has been developed at Tractebel Engineering (TE), in which the best-estimate thermal-hydraulic system code, RELAP5/mod2.5, is coupled with the full three-dimensional reactor core kinetics code, PANTHER, via the dynamic data exchange interface, TALINK. The Departure from Nucleate Boiling Ratio (DNBR) is calculated by the sub-channel thermal-hydraulic analysis code COBRA-3C. The package provides the capability to accurately simulate the key physical phenomena in nuclear power plant accidents with strong asymmetric behaviours and system-core interactions. This paper presents the TE coupled code package and focuses on the methodology followed for qualifying it for licensing applications. The qualification of the coupling demonstrated the robustness achieved by the combined 3-D neutron kinetics/system T-H code package for transient simulations. The coupled TE code package has been qualified and will be used at Tractebel Engineering (TE) for analyzing asymmetric PWR accidents with strong core-system interactions

  12. Some inspirations drawn from the SKB license-application report for the construction of the final repository for spent nuclear fuel in Sweden

    International Nuclear Information System (INIS)

    Xu Guoqing

    2014-01-01

    The following problems are described in this paper: the current state of nuclear energy and spent fuel in Sweden, the brief process of repository site selection and the concise geological settings of candidate site Forsmark, the option of repository design, the data presented in license-application report on repository, construction, the review work presented by OECD/NEA international peer review team (IRT) and some considerations noted by the author: 1) Why the design of underground engineering, also known as 5 shafts + l ramp, is adopted? 2) Why the timescale for the assessment is one million years? 3) Why the computer codes used in performance assessment at Forsmark candidate repository site are different from those used at Yucca Mountain candidate repository site? 4) How to carry out the public involvement, support from local government and volumtary siting in China? 5) What is the most important in the R and D program of HLW disposal? 6) What shall we do for the future license-application report for the construction of the final repository in China? (author)

  13. 75 FR 23808 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-05-04

    ... most adverse moderation conditions feasible by unborated water. By meeting this criteria, the removal... Risk Assessment in Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis,'' and RG 1...

  14. 76 FR 77565 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-12-13

    ... intervene shall be filed in accordance with the Commission's ''Rules of Practice for Domestic Licensing...- conservative emergency diesel generator fuel oil supply volumes, incorporate portions of Technical... of the associated Technical Specifications to require an adequate emergency diesel generator and...

  15. Perspective about the US license Renewal for NNPP's

    International Nuclear Information System (INIS)

    Lehnert, D. F.

    2004-01-01

    This article provides and overview of the US License Renewal Rule, 10 CFR 54, and its implementation in the US leading to the preparation and review of a license renewal application. The key regulatory documents and the industry's methodology and guidance for successfully implementing the Rule are discussed. While the process still undergoes change and optimization, it has become predictable and reliable, such that utilities can establish realistic schedules and budgets to complete the license renewal process. Nearly 60% of the US operating units have either received and extended operating license, have submitted their application for review, or have committed to submit an application in the next few years. The article concludes with a discussion of lessons learned from this wealth of experience and some emerging issues that may affect license renewal process. (Author)

  16. Trends in nuclear licensing

    International Nuclear Information System (INIS)

    Dalton, N.W.

    1990-01-01

    The development of nuclear safety and licensing is briefly reviewed in four stages namely: The Formative Period (1946-1959), The Expansive Period (1960-1969), The Mature Period (1970-1979) and the Apprehensive Period (1980-1989). Particular safety issues in the respective periods are highlighted to indicate the changing emphasis of nuclear licensing over the past thirty years or so. Against this background, nuclear licensing. (author)

  17. Trends in nuclear licensing

    Energy Technology Data Exchange (ETDEWEB)

    Dalton, N W [Council for Nuclear Safety, Hennopsmeer, Pretoria (South Africa)

    1990-06-01

    The development of nuclear safety and licensing is briefly reviewed in four stages namely: The Formative Period (1946-1959), The Expansive Period (1960-1969), The Mature Period (1970-1979) and the Apprehensive Period (1980-1989). Particular safety issues in the respective periods are highlighted to indicate the changing emphasis of nuclear licensing over the past thirty years or so. Against this background, nuclear licensing. (author)

  18. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    1993-01-01

    The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining licensees and applicants for reactor operator and senior reactor operator licenses at power reactor facilities pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). The Examiner Standards are intended to assist NRC examiners and facility licensees to better understand the initial and requalification examination processes and to ensure the equitable and consistent administration of examinations to all applicants. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator licensing policy changes

  19. 75 FR 54330 - Intent To Grant an Exclusive Field of Use License of a U.S. Government-Owned Patent Application

    Science.gov (United States)

    2010-09-07

    ... DEPARTMENT OF DEFENSE Department of the Army Intent To Grant an Exclusive Field of Use License of a U.S. Government-Owned Patent Application AGENCY: Department of the Army, DoD. ACTION: Notice... intent to grant an exclusive, revocable license for the field of use in the research reagent market to...

  20. 75 FR 39668 - Intent To Grant a Field of Use Exclusive License of a U.S. Government-Owned Patent Application

    Science.gov (United States)

    2010-07-12

    ... DEPARTMENT OF DEFENSE Department of the Army Intent To Grant a Field of Use Exclusive License of a U.S. Government-Owned Patent Application AGENCY: Department of the Army, DoD. ACTION: Notice... intent to grant a field of use exclusive, revocable license for the field of shigella vaccine development...

  1. Review of access, licenses and understandability of open datasets used in hydrology research

    Science.gov (United States)

    Falkenroth, Esa; Arheimer, Berit; Lagerbäck Adolphi, Emma

    2015-04-01

    could be that many data sets have been assembled by research project that no longer are funded. Hence, their server infrastructure would be less maintained compared to large-scale operational services. Regarding understandability of the data sets, the issues encountered were mainly due to incomplete documentation or metadata and problems with decoding binary formats. Ideally, open data sets should be represented in well-known formats and they should be accompanied with sufficient documentation so the data set can be understood. Furthermore, machine-readable format would be preferrable. Here, the development efforts on Water ML and NETCDF and other standards should improve understandability of data sets over time but in this review, only a few data sets were provided in these wellknown formats. Instead, the majority of datasets were stored in various text-based or binary formats or even document-oriented formats such as PDF. For some binary formats, we could not find information on what software was necessary to decipher the files. Other domains such as meteorology have long-standing traditions of operational data exchange format whereas hydrology research is still quite fragmented and the data exchange is usually done on a case-by-case basis. With the increased sharing of open data there is a good chance the situation will improve for data sets used in hydrology research. Finally, regarding licensce issue, a high number of data sets did not have a clear statement on terms of use and limitation for access. In most cases the provider could be contacted regarding licensing issues.

  2. NPP License Renewal and Aging Management: Revised Guidance

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  3. NPP License Renewal and Aging Management: Revised Guidance

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  4. Applicability of Item Response Theory to the Korean Nurses' Licensing Examination

    Directory of Open Access Journals (Sweden)

    Geum-Hee Jeong

    2005-06-01

    Full Text Available To test the applicability of item response theory (IRT to the Korean Nurses' Licensing Examination (KNLE, item analysis was performed after testing the unidimensionality and goodness-of-fit. The results were compared with those based on classical test theory. The results of the 330-item KNLE administered to 12,024 examinees in January 2004 were analyzed. Unidimensionality was tested using DETECT and the goodness-of-fit was tested using WINSTEPS for the Rasch model and Bilog-MG for the two-parameter logistic model. Item analysis and ability estimation were done using WINSTEPS. Using DETECT, Dmax ranged from 0.1 to 0.23 for each subject. The mean square value of the infit and outfit values of all items using WINSTEPS ranged from 0.1 to 1.5, except for one item in pediatric nursing, which scored 1.53. Of the 330 items, 218 (42.7% were misfit using the two-parameter logistic model of Bilog-MG. The correlation coefficients between the difficulty parameter using the Rasch model and the difficulty index from classical test theory ranged from 0.9039 to 0.9699. The correlation between the ability parameter using the Rasch model and the total score from classical test theory ranged from 0.9776 to 0.9984. Therefore, the results of the KNLE fit unidimensionality and goodness-of-fit for the Rasch model. The KNLE should be a good sample for analysis according to the IRT Rasch model, so further research using IRT is possible.

  5. Selected review of regulatory standards and licensing issues for nuclear power plants

    International Nuclear Information System (INIS)

    Stevenson, J.D.; Thomas, F.A.

    1982-11-01

    This report presents a compilation and description of current foreign regulatory standards and licensing issues in the areas of interest associated with Siting, Structural Engineering, Metallurgy and Materials, and Mechanical Engineering. In addition, summary comparisons of the requirements of both the US and foreign nuclear power plant regulatory standards are provided. The selected foreign countries surveyed include Canada, France, Japan, Sweden, United Kingdom of Great Britain and Northern Ireland, and the Federal Republic of Germany

  6. IRIS Licensing Status

    International Nuclear Information System (INIS)

    Kling, Charles L.; Carelli, Mario D.

    2006-01-01

    The International Reactor Innovative and Secure (IRIS) nuclear power plant is well into the pre-application review process with the US NRC and has accomplished its first near term goal of obtaining US NRC feedback on the long term testing program. To date, the IRIS team has submitted to the US NRC a number of documents patterned after the Evaluation Model Development and Assessment Process (EMDAP) outlined in Regulatory Guide 1,203. They have covered a detailed description of IRIS, initial safety analysis results, PIRT development for limiting transients, scaling analysis and a description of the test program. The IRIS Safety-by-Desing TM intrinsically eliminates and/or significantly reduces the consequences of traditional LWR accidents. In addition, the fewer passive safety systems are similar in principle to those of the US NRC approved AP1000 design. For these reasons, the IRIS testing program only needs to include those features unique to the IRIS design. NRC feedback was that the planned test program appeared to be complete and could generate sufficient information to support a Design Certification (DC) submittal. The US NRC has also stated that a DC application must include complete information regarding the test program. On this basis the IRIS team has initiated an aggressive program to conduct IRIS testing to support a DC submittal by the end of 2008. Subsequent US NRC review should be expeditious because of the AP1000 precedent, allowing IRIS to obtain its Final Design Approval (FDA) in 2012; thereby, maintaining its goal of deployment in the 2015-2017 time frame. The next steps in the pre-application review process will be to provide the US NRC with a road map of the anticipated IRIS licensing process, a review of current licensing requirements showing that IRIS meets or exceeds all current criteria and information to support the long term goal of redefining the Emergency Planning Zone (EPZ)

  7. 15 CFR 747.5 - SIRL application review process.

    Science.gov (United States)

    2010-01-01

    ... establish the reliability of the proposed parties to the application, it may deny the application, or modify... potential impact of the proposed transaction on the security situation in Iraq; and (v) The reliability of... BIS approval: (i) License holder address, contact information, or license value; or (ii) Removing...

  8. Guide for the preparation of applications for special nuclear material licenses of less than critical mass quantities - July 1976

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    This guide describes the type of information needed to evaluate an application for a specific license for receipt, possession, use, and transfer of special nuclear material. It is intended for applicants requesting authorization to possess and use up to 2000 grams of plutonium, total, in the form of sealed plutonium-beryllium neutron sources, and any special nuclear material in quantities and forms not sufficient to form a critical mass. The latter quantities are considered to be 350 grams of contained uranium-235, 200 grams of uranium-233, 200 grams of plutonium (in any form other than plutonium-beryllium neutron sources) or any combination of them

  9. 76 FR 52699 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-08-23

    ... proposes to credit the automatic trip of the main turbine upon the initiation of a manual reactor trip for... credited manual reactor trip action that is part of the current licensing basis. Considerable defense-in... more robust AREVA Advanced W17 high thermal performance (HTP) fuel at Sequoyah Nuclear Plant (SQN...

  10. 75 FR 61521 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-10-05

    ... revises the charcoal testing criteria in Technical Specification 5.5.9, ``Ventilation Filter Testing... staffing from two to four, allow in-plant protective actions to be performed by personnel assigned to other functions, and replace a Mechanical Maintenance person with a Non-Licensed Operator. Date of issuance...

  11. Guidance for the licensing procedure concerning the application of radiographic equipment

    International Nuclear Information System (INIS)

    1987-01-01

    According to article 4 of the Ordinance on the Implementation of Atomic Safety and Radiation Protection dated 11 October 1984 the operation of radiographic equipment has to be licensed. The personnel and material requirements that are to be fulfilled by a licensee prior to commissioning X-ray or gamma equipment, are discussed in detail

  12. 76 FR 73727 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-11-29

    ..., Donald C. Cook Nuclear Plant, Unit 2 (DCCNP-2), Berrien County, Michigan; Date of amendment request... Counsel, Indiana Michigan Power Company, One Cook Place, Bridgman, MI 49106. NRC Acting Branch Chief: Thomas J. Wengert. Notice of Issuance of Amendments to Facility Operating Licenses During the period...

  13. 76 FR 61391 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-10-04

    ... ''Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR part 2. Interested person(s) should... to be operable in MODES 1, 2, and 3, as well as in MODE 4 when a steam generator (SG) is relied upon... stored diesel fuel oil inventory will require that a 7 day supply be available for each diesel generator...

  14. 76 FR 39136 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-07-05

    ... the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR part 2. Interested... Generator (SG) Program,'' to exclude a portion of the tubes below the top of the steam generator tubesheet from periodic steam generator tube inspections during Refueling Outage 14 and the subsequent operating...

  15. 75 FR 37471 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-06-29

    ... accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2... Specifications (TSs) to extend the allowed outage time (AOT) for the ``A'' and ``B'' emergency diesel generators... emergency diesel generators are safety related components which provide backup electrical power supply to...

  16. 75 FR 48370 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-08-10

    ... ensures the timely transfer of plant safety system loads to the Emergency Diesel Generators in the event a... a margin of safety. The basis for this proposed determination for each amendment request is shown... Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2. Interested person(s...

  17. 47 CFR 74.113 - Supplementary reports with application for renewal of license.

    Science.gov (United States)

    2010-10-01

    ... renewal of license. 74.113 Section 74.113 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED... covered. (4) Power employed, field intensity measurements and visual and aural observations and the types... respective types of transmissions. (5) Estimated degree of public participation in reception and the results...

  18. 75 FR 52039 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-08-24

    ... the design earthquake, the double design earthquake, the Hosgri earthquake, and the loss-of-coolant... by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the....m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the...

  19. 75 FR 13786 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-03-23

    ... earthquake (DE), double design earthquake (DDE), Hosgri earthquake (HE), and loss of coolant accident (LOCA... Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition...-Filing system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the...

  20. Guide for the preparation of applications for licenses for the use of self-contained dry source-storage irradiators. Second proposed Revision 1

    International Nuclear Information System (INIS)

    Bassin, N.

    1984-10-01

    The purpose of this regulatory guide is to provide assistance to applicants and licensees in preparing applications for new licenses, license amendments, and license renewals for the use of self-contained dry source-storage irradiators. These irradiators are constructed so that the sealed sources and the material being irradiated are contained in a shielded volume and there is no external radiation beam during the use of the irradiator. The radioisotopes most commonly used for these irradiators are cobalt-60 and cesium-137

  1. Assessment report: Application from OKG AB for a license according to the Act on Nuclear Activities concerning a shallow land burial/landfill for low-level nuclear waste in Simpevarp in the Oskarshamn municipality

    International Nuclear Information System (INIS)

    Lindbom, G.; Wiebert, A.; Norden, M.; Larsson, Carl-Magnus; Loefgren, T.; Lumpus, J.

    2000-10-01

    OKG AB has to SSI submitted an application for a license according to the Act on Nuclear Activities (1984:3) concerning a shallow land burial/landfill for low-level nuclear waste in Simpevarp in the Oskarshamn municipality. The application for a license covers permission to build, possess and operate a shallow land burial/landfill for low-level nuclear waste. Attached to the application is an environmental impact statement. An application for a license according to the Environmental Act (1998:808) has been submitted to the Environmental Court in Vaexjoe. SSI has circulated the application for consideration to the Swedish Nuclear Power Inspectorate, the Swedish Environmental Protection Agency, the County Government Board of Kalmar and the Oskarshamn municipality. SSI has informed the European Commission about the application in accordance with the EURATOM Treaty, article 37. This assessment report constitutes the base for the decision by SSI 2000-09-18 for approval and radiation protection conditions. In the report, earlier permissions for shallow land burials/landfills at the Swedish nuclear installations are described. This report shows the development of the legal system during the last years, the premises for the assessment of the application, and SSI's review of OKG's plans, consequence analysis and environmental impact statement

  2. Facilities license application record data as of April 1, 1981. Tri-annual report 30 Nov 80-1 Apr 81

    International Nuclear Information System (INIS)

    1981-06-01

    The FLAR is divided into three parts as follows: Part I - The first part is a listing of all operating licenses, authorizations and construction permits in effect plus applications pending; Part II - The second part is a listing of applications that have been withdrawn or denied, and licenses and construction permits terminated or revoked; and Part III - The third part is a listing of research, test and power reactors for export

  3. Driving licences and medical screening in old age: Review of literature and European licensing policies

    DEFF Research Database (Denmark)

    Siren, Anu Kristiina; Haustein, Sonja

    2015-01-01

    Chronological age, per se, seems to be, in the case of mature drivers, only a weak predictor of safe driving performance. However, screening policies based on chronological age are widely used. Nevertheless, lately, more evidence-based policies have been called for. In this paper we first......, investigate the evidence for and against having an age-based driver screening policy in place; second, we map and compare the current driving licensing policies in European Union (EU) member states in order to examine the variation; and third, we draw conclusions based on the literature and the policy mapping...... are likely to limit the mobility and potentially worsen the safety of older persons....

  4. Licensing process in Finland

    International Nuclear Information System (INIS)

    Tiippana, Petteri

    2011-01-01

    In accordance with the Nuclear Energy Act, the use of nuclear energy constitutes operations subject to license. The licensing process and conditions for granting a license is defined in the legislation. The licenses are applied from and granted by the Government. This paper discusses briefly the licensing process in Finland and also the roles and responsibilities of main stakeholders in licensing. Licensing of a nuclear power plant in Finland has three steps. The first step is the Decision in Principle (DiP). Goal of DiP is to decide whether using nuclear power is for the overall good for the Finnish society. The second step is Construction License (CL) and the goal of CL phase is to determine whether the design of the proposed plant is safe and that the participating organisations are capable of constructing the plant to meet safety goals. The third step is the Operating License (OL) and the goal of the OL phase is to determine whether the plant operates safely and licensee is capable to operate the plant safely. Main stakeholders in the licensing process in Finland are the utility (licensee) interested in using nuclear power in Finland, Ministry of Employment and the Economy (MEE), Government, Parliament, STUK, the municipality siting the plant and the general public. Government grants all licenses, and Parliament has to ratify Government's Decision in Principle. STUK has to assess the safety of the license applications in each step and give statement to the Ministry. Municipality has to agree to site the plant. Both STUK and the municipality have a veto right in the licensing process

  5. ITER licensing

    International Nuclear Information System (INIS)

    Gordon, C.W.

    2005-01-01

    ITER was fortunate to have four countries interested in ITER siting to the point where licensing discussions were initiated. This experience uncovered the challenges of licensing a first of a kind, fusion machine under different licensing regimes and helped prepare the way for the site specific licensing process. These initial steps in licensing ITER have allowed for refining the safety case and provide confidence that the design and safety approach will be licensable. With site-specific licensing underway, the necessary regulatory submissions have been defined and are well on the way to being completed. Of course, there is still work to be done and details to be sorted out. However, the informal international discussions to bring both the proponent and regulatory authority up to a common level of understanding have laid the foundation for a licensing process that should proceed smoothly. This paper provides observations from the perspective of the International Team. (author)

  6. 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)

  7. Advanced CANDU reactor pre-licensing progress

    International Nuclear Information System (INIS)

    Popov, N.K.; West, J.; Snell, V.G.; Ion, R.; Archinoff, G.; Xu, C.

    2005-01-01

    The Advanced CANDU Reactor (ACR) is an evolutionary advancement of the current CANDU 6 reactor, aimed at producing electrical power for a capital cost and at a unit-energy cost significantly less than that of the current reactor designs. The Canadian Nuclear Safety Commission (CNSC) staff are currently reviewing the ACR design to determine whether, in their opinion, there are any fundamental barriers that would prevent the licensing of the design in Canada. This CNSC licensability review will not constitute a licence, but is expected to reduce regulatory risk. The CNSC pre-licensing review started in September 2003, and was focused on identifying topics and issues for ACR-700 that will require a more detailed review. CNSC staff reviewed about 120 reports, and issued to AECL 65 packages of questions and comments. Currently CNSC staff is reviewing AECL responses to all packages of comments. AECL has recently refocused the design efforts to the ACR-1000, which is a larger version of the ACR design. During the remainder of the pre-licensing review, the CNSC review will be focused on the ACR-1000. AECL Technologies Inc. (AECLT), a wholly-owned US subsidiary of AECL, is engaged in a pre-application process for the ACR-700 with the US Nuclear Regulatory Commission (USNRC) to identify and resolve major issues prior to entering a formal process to obtain standard design certification. To date, the USNRC has produced a Pre-Application Safety Assessment Report (PASAR), which contains their reviews of key focus topics. During the remainder of the pre-application phase, AECLT will address the issues identified in the PASAR. Pursuant to the bilateral agreement between AECL and the Chinese nuclear regulator, the National Nuclear Safety Administration (NNSA) and its Nuclear Safety Center (NSC), NNSA/NSC are reviewing the ACR in seven focus areas. The review started in September 2004, and will take three years. The main objective of the review is to determine how the ACR complies

  8. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    1983-10-01

    The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining and licensing of applicants for NRC operator licenses pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). They are intended to assist NRC examiners and facility licensees to understand the examination process better and to provide for equitable and consistent administration of examinations to all applicants by NRC examiners. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator examination licensing policy changes. As appropriate, these standards will be revised periodically to accommodate comments and reflect new information or experience

  9. Licensing topical report: application of probabilistic risk assessment in the selection of design basis accidents

    International Nuclear Information System (INIS)

    Houghton, W.J.

    1980-06-01

    A probabilistic risk assessment (PRA) approach is proposed to be used to scrutinize selection of accident sequences. A technique is described in this Licensing Topical Report to identify candidates for Design Basis Accidents (DBAs) utilizing the risk assessment results. As a part of this technique, it is proposed that events with frequencies below a specified limit would not be candidates. The use of the methodology described is supplementary to the traditional, deterministic approach and may result, in some cases, in the selection of multiple failure sequences as DBAs; it may also provide a basis for not considering some traditionally postulated events as being DBAs. A process is then described for selecting a list of DBAs based on the candidates from PRA as supplementary to knowledge and judgments from past licensing practice. These DBAs would be the events considered in Chapter 15 of Safety Analysis Reports of high-temperature gas-cooled reactors

  10. 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

  11. Evaluation of Terminated Nuclear Material Licenses

    International Nuclear Information System (INIS)

    Spencer, K.M.; Zeighami, E.A.

    1999-01-01

    This report presents the results of a six-year project that reviewed material licenses that had been terminated during the period from inception of licensing until approximately late-1994. The material licenses covered in the review project were Part 30, byproduct material licenses; Part 40, source material licenses; and Part 70, special nuclear material licenses. This report describes the methodology developed for the project, summarizes the findings of the license file inventory process, and describes the findings of the reviews or evaluations of the license files. The evaluation identified nuclear material use sites that need review of the licensing material or more direct follow-up of some type. The review process also identified licenses authorized to possess sealed sources for which there was incomplete or missing documentation of the fate of the sources

  12. Pesticide use and risk of end-stage renal disease among licensed pesticide applicators in the Agricultural Health Study.

    Science.gov (United States)

    Lebov, Jill F; Engel, Lawrence S; Richardson, David; Hogan, Susan L; Hoppin, Jane A; Sandler, Dale P

    2016-01-01

    Experimental studies suggest a relationship between pesticide exposure and renal impairment, but epidemiological evidence is limited. We evaluated the association between exposure to 39 specific pesticides and end-stage renal disease (ESRD) incidence in the Agricultural Health Study, a prospective cohort study of licensed pesticide applicators in Iowa and North Carolina. Via linkage to the US Renal Data System, we identified 320 ESRD cases diagnosed between enrolment (1993-1997) and December 2011 among 55 580 male licensed pesticide applicators. Participants provided information on use of pesticides via self-administered questionnaires. Lifetime pesticide use was defined as the product of duration and frequency of use and then modified by an intensity factor to account for differences in pesticide application practices. Cox proportional hazards models, adjusted for age and state, were used to estimate associations between ESRD and: (1) ordinal categories of intensity-weighted lifetime use of 39 pesticides, (2) poisoning and high-level pesticide exposures and (3) pesticide exposure resulting in a medical visit or hospitalisation. Positive exposure-response trends were observed for the herbicides alachlor, atrazine, metolachlor, paraquat, and pendimethalin, and the insecticide permethrin. More than one medical visit due to pesticide use (HR=2.13; 95% CI 1.17 to 3.89) and hospitalisation due to pesticide use (HR=3.05; 95% CI 1.67 to 5.58) were significantly associated with ESRD. Our findings support an association between ESRD and chronic exposure to specific pesticides, and suggest pesticide exposures resulting in medical visits may increase the risk of ESRD. Clinicaltrials.gov NCT00352924. 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/

  13. Viability Assessment of a Repository at Yucca Mountain. Volume 4: License Application Plan and Costs

    Energy Technology Data Exchange (ETDEWEB)

    None

    1998-12-01

    defensible LA. Volume 4 is divided into seven sections. Section 2 presents a rationale and summary for the technical work to be done to develop the preclosure and postclosure safety cases that will support the compliance evaluations required for the evaluation of site suitability and for licensing. Section 2 also describes other necessary technical work, including that needed to support design decisions and development of the necessary design information. Section 3 presents a more detailed description of the technical work required to address the issues identified in Section 2. Section 3 also describes activities that will continue after submittal of the site recommendation and the LA. Examples include the drift scale heater test in the Exploratory Studies Facility (Section 3.1.4.3) and long-term waste package corrosion testing (Section 3.2.2.9). Section 4 discusses the statutory and regulatory framework for site recommendation and submittal of an LA, and describes the activities and documentation that must be completed to achieve these milestones, including the development of an EIS. Section 5 describes the numerous activities required to support program milestones, including support for completing the testing program, continuing tests as part of the performance confirmation program, and managing information and records to support regulatory and legal review. Sections 6 and 7 provide cost and schedule information for the activities planned.

  14. Parameter Selection for Department of Energy Spent Nuclear Fuel to be Used in the Yucca Mountain License Application

    Energy Technology Data Exchange (ETDEWEB)

    D. L. Fillmore

    2003-10-01

    This report contains the chemical, physical, and radiological parameters that were chosen to represent the U.S. Department of Energy spent nuclear fuel in the Yucca Mountain license application. It also contains the selected packaging requirements for the various fuel types and the criticality controls that were used. The data are reported for representative fuels and bounding fuels in groups of fuels that were selected for the analysis. The justification for the selection of each parameter is given. The data reported were not generated under any quality assurance program.

  15. Biomedical applications of nanodiamond (Review)

    Science.gov (United States)

    Turcheniuk, K.; Mochalin, Vadym N.

    2017-06-01

    The interest in nanodiamond applications in biology and medicine is on the rise over recent years. This is due to the unique combination of properties that nanodiamond provides. Small size (∼5 nm), low cost, scalable production, negligible toxicity, chemical inertness of diamond core and rich chemistry of nanodiamond surface, as well as bright and robust fluorescence resistant to photobleaching are the distinct parameters that render nanodiamond superior to any other nanomaterial when it comes to biomedical applications. The most exciting recent results have been related to the use of nanodiamonds for drug delivery and diagnostics—two components of a quickly growing area of biomedical research dubbed theranostics. However, nanodiamond offers much more in addition: it can be used to produce biodegradable bone surgery devices, tissue engineering scaffolds, kill drug resistant microbes, help us to fight viruses, and deliver genetic material into cell nucleus. All these exciting opportunities require an in-depth understanding of nanodiamond. This review covers the recent progress as well as general trends in biomedical applications of nanodiamond, and underlines the importance of purification, characterization, and rational modification of this nanomaterial when designing nanodiamond based theranostic platforms.

  16. Integrated ground-water monitoring strategy for NRC-licensed facilities and sites: Case study applications

    Science.gov (United States)

    Price, V.; Temples, T.; Hodges, R.; Dai, Z.; Watkins, D.; Imrich, J.

    2007-01-01

    This document discusses results of applying the Integrated Ground-Water Monitoring Strategy (the Strategy) to actual waste sites using existing field characterization and monitoring data. The Strategy is a systematic approach to dealing with complex sites. Application of such a systematic approach will reduce uncertainty associated with site analysis, and therefore uncertainty associated with management decisions about a site. The Strategy can be used to guide the development of a ground-water monitoring program or to review an existing one. The sites selected for study fall within a wide range of geologic and climatic settings, waste compositions, and site design characteristics and represent realistic cases that might be encountered by the NRC. No one case study illustrates a comprehensive application of the Strategy using all available site data. Rather, within each case study we focus on certain aspects of the Strategy, to illustrate concepts that can be applied generically to all sites. The test sites selected include:Charleston, South Carolina, Naval Weapons Station,Brookhaven National Laboratory on Long Island, New York,The USGS Amargosa Desert Research Site in Nevada,Rocky Flats in Colorado,C-Area at the Savannah River Site in South Carolina, andThe Hanford 300 Area.A Data Analysis section provides examples of detailed data analysis of monitoring data.

  17. Postulated licensing schedule for an independent spent-fuel-storage installation

    International Nuclear Information System (INIS)

    Ludwick, J.D.

    1982-11-01

    A review of licensing requirements, processes, and anticipated actions for independent spent fuel storage installations (ISFSIs) was conducted in order to develop an estimated schedule and sequence of events for licensing a new ISFSI. This estimate will be useful to potential ISFSI owners in planning for the licensing of their facilities. It is concluded that, although many uncertainties exist with respect to such things as legal appeals, about 29 months are estimated to elapse between license application and license issuance for an ISFSI. This estimate is in reasonable agreement with a previous time estimate for licensing an ISFSI, and, taking into account the special circumstances involved, with the actual licensing schedule for the GE-Morris ISFSI. However, individual portions of the licensing schedule from each case studied sometimes vary significantly

  18. 43 CFR 36.5 - Application review.

    Science.gov (United States)

    2010-10-01

    ... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false Application review. 36.5 Section 36.5... ACROSS, AND ACCESS INTO, CONSERVATION SYSTEM UNITS IN ALASKA § 36.5 Application review. (a) When there is... the purpose of coordinating appropriate Federal agency actions in the review and processing of the SF...

  19. The pre-licensing of a multi-purpose hybrid research reactor for high-tech applications 'MYRRHA'

    International Nuclear Information System (INIS)

    Hakimi, N.; Dams, C.; Wertelaers, A.; Nys, V.; Schrauben, M.; Dresselaers, R.

    2013-01-01

    The Belgian Nuclear Research Centre in Mol has been working for several years on the design of a multi-purpose flexible irradiation facility in order to replace the ageing BR2, a multipurpose materials testing reactor (MTR), in operation since 1962. MYRRHA, a flexible fast spectrum research reactor is conceived as an accelerator driven system (ADS), able to operate in sub-critical and critical modes. It contains a proton accelerator of 600 MeV, a spallation target and a multiplying medium with MOX fuel, cooled by liquid lead-bismuth (Pb-Bi). Since February 2011, the Belgian Nuclear Research Centre has engaged in a 'pre-licensing' process with the regulatory authority for an estimated period up to mid 2014. The paper presents on the one hand the objectives of the pre-licensing phase as well as its implementation process and on the other hand, 2 implementing instruments which have been developed by the regulatory authority providing guidance to the designer of MYRRHA in order to meet the pre-licensing phase objectives. The first instrument is a strategic note for the design and operation of MYRRHA where as the second instrument is a guidance document for the format and content of a design options and provisions file (DOPF). Both instruments have been developed taking into account that MYRRHA is an irradiation facility using a Generation IV nuclear power system's type technology (liquid metal cooled fast neutron reactor). The strategic note overview aims to cover the safety approach as well as the security requirements and safeguards obligation applicable to MYRRHA. In particular, in the strategic note, a specific attention has been paid in order to ensure that a safety, security and safeguards integrated approach will drive the development of the MYRRHA design. The safety approach focuses on the safety goals and the minimum safety objectives set by the regulatory authority for this innovative design. The DOPF overview presents its objectives and structure resuming

  20. Density and Proximity of Licensed Tobacco Retailers and Adolescent Smoking: A Narrative Review

    Science.gov (United States)

    Gwon, Seok Hyun; DeGuzman, Pamela B.; Kulbok, Pamela A.; Jeong, Suyong

    2017-01-01

    Adolescent smoking prevention is an important issue in health care. This literature review describes the theoretical concept of ecological model for adolescent smoking and tobacco retailers and summarizes previous studies on the association between the density and proximity of tobacco retailers and adolescent smoking. We reviewed nine studies on…

  1. Licensing the ACR-700 in the USA

    International Nuclear Information System (INIS)

    Langman, V.; Ion, R.; Reid, C.; Snell, V.

    2003-01-01

    Atomic Energy of Canada Ltd. (AECL), via its 100% owned US subsidiary AECL Technologies Inc., is performing a pre-application review of the Advanced CANDU Reactor (ACR) with the US Nuclear Regulatory Commission (USNRC). Completion of this pre-application review by mid-2004, is in support of an application to the USNRC for Standard Design Certification that is targeted for the fall of 2004. The intent of the pre-application review is to deal up-front with potential issues associated with the CANDU reactor genealogy of the ACR that are different from the Light Water Reactor (LWR) and Boiling Water Reactor (BWR) regulatory framework in the USA. The focus of the paper will be to describe the pre-application review process currently underway with the NRC staff. In the context of the pre-application review this paper will provide an overview of the licensing approach being used to introduce the ACR-700 to the USA. (author)

  2. Licensing the ACR-700 in the USA

    Energy Technology Data Exchange (ETDEWEB)

    Langman, V.; Ion, R. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Reid, C. [Bechtel Power Corporation, San Fransisco, California (United States); Snell, V. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)

    2003-07-01

    Atomic Energy of Canada Ltd. (AECL), via its 100% owned US subsidiary AECL Technologies Inc., is performing a pre-application review of the Advanced CANDU Reactor (ACR) with the US Nuclear Regulatory Commission (USNRC). Completion of this pre-application review by mid-2004, is in support of an application to the USNRC for Standard Design Certification that is targeted for the fall of 2004. The intent of the pre-application review is to deal up-front with potential issues associated with the CANDU reactor genealogy of the ACR that are different from the Light Water Reactor (LWR) and Boiling Water Reactor (BWR) regulatory framework in the USA. The focus of the paper will be to describe the pre-application review process currently underway with the NRC staff. In the context of the pre-application review this paper will provide an overview of the licensing approach being used to introduce the ACR-700 to the USA. (author)

  3. Development and application of a deterministic-realistic hybrid methodology for LOCA licensing analysis

    International Nuclear Information System (INIS)

    Liang, Thomas K.S.; Chou, Ling-Yao; Zhang, Zhongwei; Hsueh, Hsiang-Yu; Lee, Min

    2011-01-01

    Highlights: → A new LOCA licensing methodology (DRHM, deterministic-realistic hybrid methodology) was developed. → DRHM involves conservative Appendix K physical models and statistical treatment of plant status uncertainties. → DRHM can generate 50-100 K PCT margin as compared to a traditional Appendix K methodology. - Abstract: It is well recognized that a realistic LOCA analysis with uncertainty quantification can generate greater safety margin as compared with classical conservative LOCA analysis using Appendix K evaluation models. The associated margin can be more than 200 K. To quantify uncertainty in BELOCA analysis, generally there are two kinds of uncertainties required to be identified and quantified, which involve model uncertainties and plant status uncertainties. Particularly, it will take huge effort to systematically quantify individual model uncertainty of a best estimate LOCA code, such as RELAP5 and TRAC. Instead of applying a full ranged BELOCA methodology to cover both model and plant status uncertainties, a deterministic-realistic hybrid methodology (DRHM) was developed to support LOCA licensing analysis. Regarding the DRHM methodology, Appendix K deterministic evaluation models are adopted to ensure model conservatism, while CSAU methodology is applied to quantify the effect of plant status uncertainty on PCT calculation. Generally, DRHM methodology can generate about 80-100 K margin on PCT as compared to Appendix K bounding state LOCA analysis.

  4. Use of modeling in repository licensing

    International Nuclear Information System (INIS)

    McGarry, J.M. III; Echols, F.S.

    1995-01-01

    A review of the regulatory history of the Nuclear Regulatory Commission (NRC) regulations applicable to the licensing of a geologic repository, as well as a review of NRC administrative (licensing) decisions and federal case law, support the NRC's use of simplified models, in appropriate circumstances, which provide well-documented and reasonably conservative bounding assumptions, together with the use of expert judgement, natural analogues, and other aids to supplement available information, in reaching its reasonable assurance determination whether the public health and safety will be adequately protected if the Yucca Mountain, Nevada site should be licensed for development as a geologic repository. Specific examples are provided to assist the reader to better understand how such qualitative concepts as open-quote reasonable assurance close-quote, open-quote reasonably conservative close-quote, and open-quote adequate close-quote protection are used in an administrative context to resolve technical issues

  5. A BWR licensing experience in the USA

    International Nuclear Information System (INIS)

    Powers, J.; Ogura, C.; Arai, K.; Thomas, S.; Mookhoek, B.

    2015-09-01

    The US-Advanced Boiling Water Reactor (A BWR), certified by the United States Nuclear Regulatory Commission (US NRC), is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The STP3-4 project has finished the US NRC technical review of the Cola through the final meeting of the Advisory Committee on Reactor Safeguards (ACRS), and the Final Safety Evaluation Report (FSER) is scheduled to be issued by the US NRC in the middle of 2015. The next steps are to support the Mandatory Hearing process, and voting by the NRC commissioners on the motion to grant the Combined License, which is scheduled beginning of 2016 according to US NRC schedule as of March 30, 2015. This paper summarizes the history and progress of the US-A BWR licensing, including the experiences of the Licensee, Nina, and Toshiba as the Epc team worked through the Code of Federal Regulations Title 10 (10-Cfr) Part 52 process, and provides some perspectives on how the related licensing material would also be of value within a 10-Cfr Part 50, two-step process to minimize schedule and financial risks which could arise from ongoing technical developments and regulatory reviews. (Author)

  6. A BWR licensing experience in the USA

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J.; Ogura, C. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Arai, K. [Toshiba Corporation, Yokohama, Kanagawa (Japan); Thomas, S.; Mookhoek, B., E-mail: jim.powers@toshiba.com [Nuclear Innovation North America, Lake Jackson, Texas (United States)

    2015-09-15

    The US-Advanced Boiling Water Reactor (A BWR), certified by the United States Nuclear Regulatory Commission (US NRC), is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The STP3-4 project has finished the US NRC technical review of the Cola through the final meeting of the Advisory Committee on Reactor Safeguards (ACRS), and the Final Safety Evaluation Report (FSER) is scheduled to be issued by the US NRC in the middle of 2015. The next steps are to support the Mandatory Hearing process, and voting by the NRC commissioners on the motion to grant the Combined License, which is scheduled beginning of 2016 according to US NRC schedule as of March 30, 2015. This paper summarizes the history and progress of the US-A BWR licensing, including the experiences of the Licensee, Nina, and Toshiba as the Epc team worked through the Code of Federal Regulations Title 10 (10-Cfr) Part 52 process, and provides some perspectives on how the related licensing material would also be of value within a 10-Cfr Part 50, two-step process to minimize schedule and financial risks which could arise from ongoing technical developments and regulatory reviews. (Author)

  7. 48 CFR 519.7011 - Application review.

    Science.gov (United States)

    2010-10-01

    ... SOCIOECONOMIC PROGRAMS SMALL BUSINESS PROGRAMS GSA Mentor-Protégé Program 519.7011 Application review. (a) The... of the application. The contracting officer must provide feedback to the Program Manager no later...

  8. Medical review practices for driver licensing : Volume 1 : a case study of guidelines and processes in seven U.S. States.

    Science.gov (United States)

    2016-10-01

    This report is the first of three examining driver medical review practices in the United States and how they fulfilled the basic functions of identifying, assessing, and rendering licensing decisions on medically at-risk drivers. The aim was not to ...

  9. Contestable Licensing

    OpenAIRE

    Zvika Neeman; Gerhard O. Orosel

    2000-01-01

    We analyze a model of repeated franchise bidding for natural monopoly with contestable licensing - a franchisee halds an (exclusive) license to operate a franchise until another rm offers to pay more for it. In a world where quality is observable but not veri able, the simple regulatory scheme we describe combines market-like incentives with regulatory oversight to generate efficient outcomes.

  10. Radiopharmaceutical licensing

    International Nuclear Information System (INIS)

    Mather, S.J.

    1992-01-01

    Recent health service legislation, and especially the loss of crown immunity has once again focussed attention on the arrangements for licensing of radiopharmaceuticals. The aim of the article is to describe in general terms the UK licensing system and in particular to provide guidance to those responsible for the supply of radiopharmaceuticals in hospitals. (author)

  11. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  12. Essays on the economics of licensing nuclear power plants

    International Nuclear Information System (INIS)

    Cohen, L.R.

    1979-01-01

    Regulation and licensing of nuclear power plants by the United States Atomic Energy Commission and the United States Nuclear Regulatory Commission are discussed. Chapter 1 overviews the licensing process and issues raised in licensing cases. Based on a sample of plants licensed between 1967 and 1978, a statistical study of the impact of public participation in licensing is performed. The study concludes that public participation has had a major impact on licensing and power-plant costs. The impact is due to a fundamental weakness of the Commissions: their inability to resolve certain issues related to acceptable social risk. The study has important policy implications for reforming the Federal licensing process. Chapter 2 contains an analysis of the Price-Anderson Act, a Federal program for compensating victims of large nuclear accidents. The Price-Anderson Act is placed within the context of generalized federal disaster relief. A model is developed that allows an evaluation programs on the basis of moral hazard and equity principles. Chapter 3 analyzes the Nuclear Regulatory Commission's treatment of its mandatory antitrust review of applicants for nuclear power plants. The main conclusion of the chapter is that the reviews have not addressed the central economic issues of antitrust that are relevant to nuclear power. Instead, the reviews contribute to further cartelization of the electric utility industry. While politically expedient, the reviews are counter-productive to the development of an optimal industry structure

  13. 77 FR 73060 - Standard Review Plan for Review of Fuel Cycle Facility License Applications

    Science.gov (United States)

    2012-12-07

    ... Management System (ADAMS) under Accession No. ML12284A033. The NRC staff is seeking to engage stakeholders during the early stages of the SRP revision process by soliciting comments on which SRP areas should be... (ISG) to provide guidance on Integrated Safety Analysis (ISA) implementation issues consistent with the...

  14. Social Licensing in uranium mining: Experiences from the IAEA review of the planned Mukju River Uranium Project, Tanzania

    International Nuclear Information System (INIS)

    Schnell, H.; Hilton, J.; Saint-Pierre, S.; Baldry, K.; Fan, Z.; Tulsidas, H.

    2014-01-01

    The IAEA Uranium Production Site Appraisal Team (UPSAT) programme is designed to assist Member States to enhance the operational performance and the occupational, public and environmental health and safety of uranium mining and processing facilities across all phases of the uranium production cycle. The scope of the appraisal process includes exploration, resource assessment, planning, environmental and social impact assessment, mining, processing, waste management, site management, remediation, and final closure. An UPSAT review was requested in 2010 by the United Republic of Tanzania (URT) to address the challenges the country is currently facing in developing its uranium mining and processing capability for the first time. The review that was carried out from 27 May to 5 June, 2013 had the objective to to appraise URT’s preparedness for overseeing the Uranium Production Cycle in general, at the same time focusing on the planned Mkuju River Project (MRP) in the south of the country in particular. The UPSAT team was tasked to report its findings according to five primary areas: 1. Regulatory system; 2. Sustainable uranium production life cycle; 3. Health, Safety and Environment (HSE); 4. Social licensing; 5. Capacity building. The paper will discuss the key findings and suggestions that were provided to governmental stakeholders and the operater to improve the planned operations. (author)

  15. 14 CFR 415.23 - Policy review.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Policy review. 415.23 Section 415.23... TRANSPORTATION LICENSING LAUNCH LICENSE Policy Review and Approval § 415.23 Policy review. (a) The FAA reviews a... raised during a policy review that would impede issuance of a policy approval. The applicant may respond...

  16. 17 CFR 3.40 - Temporary licensing of applicants for associated person, floor broker or floor trader registration.

    Science.gov (United States)

    2010-04-01

    ... has been granted trading privileges by a contract market or derivatives transaction execution facility... officer with respect to the review of an applicant's employment, credit and other history in connection...

  17. Export Controls: Controls Over the Export Licensing Process for Chemical and Biological Items

    National Research Council Canada - National Science Library

    2005-01-01

    .... foreign policy should read this report. The report discusses the effectiveness of the DoD review process for export license applications and updates to Federal export regulations to prevent the proliferation of items that could pose...

  18. The Licensing of New Nuclear Power Plants in Europe

    International Nuclear Information System (INIS)

    Raetzke, C.

    2008-01-01

    After an introduction dealing with the nuclear Renaissance in Europe and the specific situation of Germany and of Italy, the article focuses on the question of licensing processes for new reactors. New nuclear power plant projects involve a substantial investment and electric utilities will only take this decision if the licensing and regulatory risk can be adequately managed. Licensing processes should be predictable and efficient in order to give sufficient assurance to applicants. The article discusses best practice in licensing by giving some examples of suitable licensing processes of other countries. It also highlights international initiatives aimed at harmonizing safety requirements for new reactors and a multinational cooperation in reactor design review. These issues should be carefully considered by any country wanting to get new nuclear started. [it

  19. 22 CFR 96.30 - State licensing.

    Science.gov (United States)

    2010-04-01

    ... Licensing and Corporate Governance § 96.30 State licensing. (a) The agency or person is properly licensed or... person follows applicable State licensing and regulatory requirements in all jurisdictions in which it provides adoption services. (c) If it provides adoption services in a State in which it is not itself...

  20. Application of PLUTO Test Facility for U. S. NRC Licensing of a Fuel Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Dongseok; Shin, Changhwan; Lee, Kanghee; Kang, Heungseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    The fuel assembly of the PLUS-7 loaded in the APR-1400 follows the same schedule. Meanwhile, In July 1998, the U.S. NRC adopted a research plan to address the effects of high burnup from a Loss of Coolant Accident (LOCA). From these programs, several important technical findings for rule revision were obtained. Based on the technical findings, the U. S. NRC has amended the 10 CFR 50.46 which will be proclaimed sooner or later. Through the amendment, a LOCA analysis on the fuel assembly has to show the safety at both a fresh and End of Life (EOL) state. The U. S. NRC has already required EOL effects on seismic/LOCA performance for a fuel assembly since 1998. To obtain U.S NRC licensing of a fuel assembly, based on the amendment of 10CFR50.46, a LOCA analysis of the fuel assembly has to show safety both fresh and EOL states. The proper damping factor of the fuel assembly measured at the hydraulic test loop for a dynamic model in a LOCA and a seismic analysis code are at least required. In this paper, we have examined the damping technologies and compared the test facility of PLUTO with others in terms of performance. PLUTO has a better performance on the operating conditions than any others.

  1. Prevention of firearm-related injuries with restrictive licensing and concealed carry laws: An Eastern Association for the Surgery of Trauma systematic review.

    Science.gov (United States)

    Crandall, Marie; Eastman, Alexander; Violano, Pina; Greene, Wendy; Allen, Steven; Block, Ernest; Christmas, Ashley Britton; Dennis, Andrew; Duncan, Thomas; Foster, Shannon; Goldberg, Stephanie; Hirsh, Michael; Joseph, D'Andrea; Lommel, Karen; Pappas, Peter; Shillinglaw, William

    2016-11-01

    In the past decade, more than 300,000 people in the United States have died from firearm injuries. Our goal was to assess the effectiveness of two particular prevention strategies, restrictive licensing of firearms and concealed carry laws, on firearm-related injuries in the US Restrictive Licensing was defined to include denials of ownership for various offenses, such as performing background checks for domestic violence and felony convictions. Concealed carry laws allow licensed individuals to carry concealed weapons. A comprehensive review of the literature was performed. We used Grading of Recommendations Assessment, Development, and Evaluation methodology to assess the breadth and quality of the data specific to our Population, Intervention, Comparator, Outcomes (PICO) questions. A total of 4673 studies were initially identified, then seven more added after two subsequent, additional literature reviews. Of these, 3,623 remained after removing duplicates; 225 case reports, case series, and reviews were excluded, and 3,379 studies were removed because they did not focus on prevention or did not address our comparators of interest. This left a total of 14 studies which merited inclusion for PICO 1 and 13 studies which merited inclusion for PICO 2. PICO 1: We recommend the use of restrictive licensing to reduce firearm-related injuries.PICO 2: We recommend against the use of concealed carry laws to reduce firearm-related injuries.This committee found an association between more restrictive licensing and lower firearm injury rates. All 14 studies were population-based, longitudinal, used modeling to control for covariates, and 11 of the 14 were multi-state. Twelve of the studies reported reductions in firearm injuries, from 7% to 40%. We found no consistent effect of concealed carry laws. Of note, the varied quality of the available data demonstrates a significant information gap, and this committee recommends that we as a society foster a nurturing and encouraging

  2. 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.

  3. 76 FR 1462 - Notice Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2011-01-10

    ... thickness, the calculated total amount of hydrogen generated from a chemical reaction of the cladding with... conditions defined by the Technical Specifications. The engineering reviews performed for the constant...

  4. 78 FR 29391 - Luminant Generation Company, LLC; Combined License Application for Comanche Peak Nuclear Power...

    Science.gov (United States)

    2013-05-20

    ... only temporary relief from the applicable regulation and the licensee has made good faith efforts to... only temporary relief from the regulations of 10 CFR 50.71(e)(3)(iii). Luminant has made good faith... applicable regulation and the licensee has made good faith efforts to comply with the regulation'' (10 CFR 50...

  5. 78 FR 36014 - Deepwater Port License Application: Liberty Natural Gas, LLC, Port Ambrose Deepwater Port

    Science.gov (United States)

    2013-06-14

    ... timeline for processing an application. When MarAd and USCG determine that an application contains the... that Port Ambrose falls within the proposed area of interest for the New York Power Authority Long Island-New York City Offshore Wind Project. This project will be acknowledged and considered in the...

  6. 75 FR 32450 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2010-06-08

    .... Name of Project: C.J. Strike Hydroelectric Project. f. Location: The project is located on the Snake... Snake River. l. Locations of the Application: A copy of the application is available for inspection and reproduction at the Commission's Public Reference Room, located at 888 First Street, NE., Room 2A, Washington...

  7. 75 FR 57266 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2010-09-20

    ...) is located on the Snake River in Gooding, Twin Falls and Elmore Counties, Idaho. The Lower Salmon Falls Project (P-2061) is located on the Snake River in Gooding and Twin Falls Counties, Idaho. Both.... Locations of the Application: A copy of the application is available for inspection and reproduction at the...

  8. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    1994-06-01

    The Operator Licensing Examiner Standards provide policy and guidance to NRC examiners and establish the procedures and practices for examining licensees and applicants for reactor operator and senior reactor operator licenses at power reactor facilities pursuant to Part 55 of Title 10 of the Code of Federal Regulations (10 CFR 55). The Examiner Standards are intended to assist NRC examiners and facility licensees to better understand the initial and requalification examination processes and to ensure the equitable and consistent administration of examinations to all applicants. These standards are not a substitute for the operator licensing regulations and are subject to revision or other internal operator licensing policy changes. Revision 7 was published in January 1993 and became effective in August 1993. Supplement 1 is being issued primarily to implement administrative changes to the requalification examination program resulting from the amendment to 10 CFR 55 that eliminated the requirement for every licensed operator to pass an NRC-conducted requalification examination as a condition for license renewal. The supplement does not substantially alter either the initial or requalification examination processes and will become effective 30 days after its publication is noticed in the Federal Register. The corporate notification letters issued after the effective date will provide facility licensees with at least 90 days notice that the examinations will be administered in accordance with the revised procedures

  9. 76 FR 67723 - CRD Hydroelectric, LLC; Notice of Application To Amend License and Accepted for Filing...

    Science.gov (United States)

    2011-11-02

    ... two turbine/generator units rather than the previously approved three units. The applicant does not propose any change to the authorized installed capacity or maximum hydraulic capacity. l. Locations of the...

  10. Standard review plan on antitrust reviews. Final report

    International Nuclear Information System (INIS)

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

    1997-12-01

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

  11. 77 FR 15387 - Notice of Invitation To Participate; Coal Exploration License Application WYW180710, Wyoming

    Science.gov (United States)

    2012-03-15

    ... exploration plan are available for review during normal business hours in the following offices (case file... notice should be sent to the following addresses: Antelope Coal LLC, c/o Cloud Peak Energy, Attn: Mark... during normal business hours. The FIRS is available 24 hours a day, 7 days a week, to leave a message or...

  12. 77 FR 32665 - Notice of Invitation To Participate; Coal Exploration License Application WYW180763, Wyoming

    Science.gov (United States)

    2012-06-01

    ... available for review during normal business hours in the following offices (case file number WYW180763): BLM... following addresses: Cordero Mining LLC, c/o Cloud Peak Energy, Attn: Mark Arambel, Caller Box 3009... Information Relay Service (FIRS) at 1-800- 877-8339 to contact the above individual during normal business...

  13. 75 FR 458 - Notice; Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2010-01-05

    ... Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non... procedures described below. To comply with the procedural requirements of E-Filing, at least ten (10) days... equipment lineup, accident scenario, or interaction mode not reviewed and approved as part of the design and...

  14. 78 FR 7803 - Agency Information Collection Activities: Application-Permit-Special License Unlading-Lading...

    Science.gov (United States)

    2013-02-04

    ... request to the Office of Management and Budget (OMB) for review and approval in accordance with the... collection to the Office of Information and Regulatory Affairs, Office of Management and Budget. Comments... supplies, ship's stores, sea stores, or equipment not to be reladen. CBP Form 3171 is authorized by 19 U.S...

  15. 77 FR 13684 - Commercial Driver's License Standards: Application for Exemption; Daimler Trucks North America...

    Science.gov (United States)

    2012-03-07

    ... requirements and to promote the development of technology advancements in vehicle safety systems and emissions... environmental regulatory requirements and to promote the development of technology advancements in vehicle... association, business, labor union, etc.). You may review the U.S. Department of Transportation's online...

  16. Licensing of New Nuclear Power Plants in Canada

    International Nuclear Information System (INIS)

    Schwarz, Garry; Miller, Doug

    2011-01-01

    The regulatory process for new power plant licensing in Canada, from receipt of the initial application to commercial operation, can be divided into three phases: - Environmental Assessment (EA) and License to Prepare Site; - License to Construct; and - License to Operate. The Nuclear Safety and Control Act (NSCA) does not have provisions for combined licenses for site preparation, construction, or operation. Separate licenses must, therefore, be granted for each phase, and would be issued in sequence. However, applications to prepare a site, to construct and to operate a new nuclear power plant could be assessed in parallel. The total duration from the application for the License to Prepare Site to the issuance of the License to Operate (which is a prerequisite for first fuel load) has been established as 9 years subject to certain factors. To help facilitate this timeline, the CNSC has undertaken an aggressive program of documenting regulatory practices, requirements and guidance to assist applicants in submitting complete applications. Working level procedures to assist CNSC staff in their review of submissions are also under development. Extensive program and project management has been introduced to ensure that timelines will be achieved. In parallel with the above activities, regulatory oversight measures to be employed during site preparation activities and plant construction and commissioning are also being developed. On the international front, the CNSC is participating in the MDEP program to leverage the resources and knowledge of other national regulatory authorities in reviews the CNSC is undertaking. The CNSC also participates in IAEA and other international activities to utilize/adapt international practices as appropriate in Canada. (authors)

  17. 75 FR 3217 - J&T Hydro Company; H. Dean Brooks and W. Bruce Cox; Notice of Application for Transfer of License...

    Science.gov (United States)

    2010-01-20

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 11392-009] J&T Hydro Company; H. Dean Brooks and W. Bruce Cox; Notice of Application for Transfer of License and Soliciting Comments and Motions To Intervene January 12, 2010. On October 30, 2009, J&T Hydro Company (transferor) and...

  18. 75 FR 15419 - Notice of Intent To Grant Exclusive License of U.S. Patent Application No. 12/432,842 Filed April...

    Science.gov (United States)

    2010-03-29

    ... Exclusive License of U.S. Patent Application No. 12/432,842 Filed April 30, 2009 Entitled: ``A Soil Stabilization Soil Comprising Same, and a Method of Stabilizing Soil'' AGENCY: Department of the Army, U.S. Army... climates with sandy, gravelly soils where emulsions and hydraulic cements will not effectively cure. If...

  19. Nuclear licensing in Slovenia

    International Nuclear Information System (INIS)

    Prah, M.; Spiler, J.; Vojnovic, D.; Pristavec, M.

    1998-01-01

    The article presents the approach to nuclear licensing in Slovenia. The paper describes, the initialization, internal authorization and review process in the Krsko NPP. The overall process includes preparation, internal independent evaluation, the Krsko Operating Committee and the Krsko Safety Committee review and internal approval. In addition, the continuation of the licensing process is discussed which includes independent evaluation by an authorized institution and a regulatory body approval process. This regulatory body approval process includes official hearing of the licensee, communication with the licensee, and final issuance of a license amendment. The internal evaluation, which follows the methodology of US NRC (defined in 10 CFR 50.59 and NUMARC 125) is described. This concept is partially implemented in domestic legislation.(author)

  20. NEA/CNRA Report of the Survey on the Review of New Reactor Applications

    International Nuclear Information System (INIS)

    Gibson, Steve

    2013-01-01

    This presentation treats of the NEA/CNRA report of the survey on the review of new reactor application. It indicates that licensing is state specific and that timelines vary from 6 months to 4 years. In addition, review effort and documentation is significant and most states have explicit guidance for the reviews. All states include some form of public participation and regulatory oversight. Next steps include two reports, one on design reviews and another on the construction phase. The author also presented on licensing experience in the United Kingdom. He highlighted the importance of several practices for ensuring a successful project, including: early engagement and communication between applicant and regulatory, sharing of plans between applicant and regulator, establishing and monitoring good metrics on progress and quality for both the applicant and the regulator, identifying 'work streams' and monitoring those streams closely, identifying and addressing risks, ensuring high quality interactions between applicant and regulator, and using dashboards as a way to maintain openness, transparency and trust. He also emphasized the need for engagement at different levels within the organization, including management as necessary

  1. Applications of Entropy in Finance: A Review

    Directory of Open Access Journals (Sweden)

    Guanqun Tong

    2013-11-01

    Full Text Available Although the concept of entropy is originated from thermodynamics, its concepts and relevant principles, especially the principles of maximum entropy and minimum cross-entropy, have been extensively applied in finance. In this paper, we review the concepts and principles of entropy, as well as their applications in the field of finance, especially in portfolio selection and asset pricing. Furthermore, we review the effects of the applications of entropy and compare them with other traditional and new methods.

  2. 77 FR 9998 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2012-02-21

    ... more conservative values that incorporate measurement uncertainty. Additionally, one of the operating..., in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to... purpose of the adjudicatory filings and would constitute a Fair Use application, participants are...

  3. 77 FR 10491 - Progress Energy Carolinas, Inc.; Notice of Application for Amendment of License and Soliciting...

    Science.gov (United States)

    2012-02-22

    ... ensuring the continued safe and reliable production of hydroelectric power at the project. Among other... Intervene, and Protests Take notice that the following hydroelectric application has been filed with the.... Name of Project: Yadkin-Pee Dee Hydroelectric Project. f. Location: Lake Tillery in Montgomery and...

  4. 77 FR 28372 - South Carolina Public Service Authority; Notice of Application for Amendment of License and...

    Science.gov (United States)

    2012-05-14

    ... documents may be filed electronically via the Internet. See, 18 CFR 385.2001(a)(1)(iii) and the instructions... marina, fuel and sewage pump-out services, restrooms, parking, shops, restaurant, swimming pool, rental cottages, boardwalk, wooden deck, and remote parking for boat trailers. l. Locations of the Application: A...

  5. 77 FR 38618 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2012-06-28

    ... Hydroelectric Project. f. Location: The project is located in south-western Idaho on the Snake River from river... application is available for inspection and reproduction at the Commission's Public Reference Room, located at... available for inspection and reproduction at the address in item (h) above. m. Individuals desiring to be...

  6. 76 FR 51016 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2011-08-17

    .... Name of Project: Twin Falls Hydroelectric Project. f. Location: This project is located on the Snake... application is available for inspection and reproduction at the Commission's Public Reference Room, located at... available for inspection and reproduction at the address in item (h) above. m. Individuals desiring to be...

  7. 78 FR 51753 - AUC, LLC Reno Creek, In Situ Project, New Source Material License Application

    Science.gov (United States)

    2013-08-21

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 040-09092; [NRC-2013-0164] AUC, LLC Reno Creek, In Situ..., AUC, LLC (AUC) submitted to the U.S. Nuclear Regulatory Commission (NRC) an application for a new... and operation, and decommissioning of AUC's proposed in-situ uranium recovery (ISR, also known as in...

  8. 76 FR 3927 - Ameren Missouri; Combined License Application for Callaway Plant Unit 2; Exemption

    Science.gov (United States)

    2011-01-21

    ... public health or safety, and are consistent with the common defense and security; and (2) special... only temporary relief from the applicable regulation and the licensee has made good faith efforts to... good faith efforts to comply with 10 CFR 50.71(e)(3)(iii) by submitting Revision 1 to the COL...

  9. 77 FR 76539 - Ameren Missouri; Combined License Application For Callaway Plant, Unit 2; Exemption

    Science.gov (United States)

    2012-12-28

    ... present an undue risk to public health or safety, and are consistent with the common defense and security... regulation and the licensee or applicant has made good faith efforts to comply with the regulation'' (10 CFR... good faith efforts to comply with 10 CFR 50.71(e)(3)(iii) by submitting Revision 1 to the COL...

  10. 77 FR 63301 - Juneau Hydropower, Inc.; Notice of Draft License Application and Preliminary Draft Environmental...

    Science.gov (United States)

    2012-10-16

    .... 791(a)-825(r). h. Applicant Contact: Duff Mitchell, Business Manager, Juneau Hydropower, Inc., P.O... information at the end of your comments. For assistance, please contact FERC Online Support at FERCOnline... access the document. For assistance, contact FERC Online Support. You may also register online at http...

  11. 76 FR 18801 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-04-05

    ... request: The proposed change would revise the application of Risk-Managed Technical Specifications (RMTS) to Technical Specification (TS) 3.7.7, ``Control Room Makeup and Cleanup Filtration System.'' This... change allows the Configuration Risk Management Program (CRMP) to be applied to Technical Specification...

  12. Pulse Holography: Review Of Applications

    Science.gov (United States)

    Smigielski, Paul

    1990-04-01

    Pulse Holography includes studies concerning time-varying phase objects as well as time-varying reflective objects involving the use of pulse ruby- and YAG-lasers. The paper is divided in two parts. One part concerns the direct use of 3-1) images reconstructed from holograms, i.e. applications to particle size analysis, 3-I) velocity measurements, 3-I) cinematography ... The second part describes applications using holographic interferometry in laboratory or in an industrial environment, i.e. applications to fluid mechanics, vibration analysis, non-destructive testing ... Recent developments including interferornetric cineholography, fiber optics, measurement of non-interferometric displacements ... , are also described. The future of holography depends to a great extent on data processing and interpretation of informations contained in holograms or holographic intericrograms. Therefore, we give the state of art in this field in Europe illustrated with some industrial applications.

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

    International Nuclear Information System (INIS)

    1996-11-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

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

  15. Flexible licensing

    Directory of Open Access Journals (Sweden)

    Martyn Jansen

    2012-07-01

    Full Text Available The case is presented for a more flexible approach to licensing online library resources. Today's distributed education environment creates pressure for UK higher and further education institutions (HEI/FEIs to form partnerships and to develop educational products and roll them out across the globe. Online library resources are a key component of distributed education and yet existing licensing agreements struggle to keep pace with the increasing range of users and purposes for which they are required. This article describes the process of developing a flexible approach to licensing and proposes a new model licence for online library resources which has the adaptability needed in this new global educational landscape. These ideas have been presented and discussed at various workshops across Eduserv's and JISC Collections' higher education and publisher communities, and further consultation is ongoing.

  16. Marble Hill Nuclear Generating Station, Units 1 and 2. License application, PSAR, general information

    International Nuclear Information System (INIS)

    1975-01-01

    An application is presented for two PWR reactors to be constructed in Salud Township, Jefferson County, Indiana, about six miles northeast of New Washington on the Ohio River. Each unit will have a rated core power level of 3411 MW(t) with a corresponding electrical output of 1130 MW(e). Mechanical draft cooling towers will be provided. The facility, which will replicate the Byron facility will be employed for the generation of electricity for transmission, sale for resale, and distribution

  17. Black Fox Station, Units 1 and 2. Application for construction permits and operating licenses

    International Nuclear Information System (INIS)

    1975-01-01

    An application to construct and operate Black Fox Station, Units 1 and 2, is presented. The two BWR type reactors will have a rated core thermal power of 3579 MW(t) and a net electrical power of approximately 1150 MW(e). The facility will be located in Inola Township, 23 miles east of Tulsa on the east side of the Verdigris River in Rogers County, Oklahoma

  18. Edwin I. Hatch Nuclear Plant, Unit 2. License application, general information

    International Nuclear Information System (INIS)

    1975-01-01

    An application for a direct cycle BWR is presented. The reactor will be located about 11 miles north of Baxley, Ga., near the south bank of the Ultamaha River in Appling County close to Hatch-1 Reactor. The core thermal power level will be 2537 MW(t) and the electrical power level will be 795 MW(e). Mechanical cooling towers will be utilized

  19. Review of magnetohydrodynamic pump applications

    Directory of Open Access Journals (Sweden)

    O.M. Al-Habahbeh

    2016-06-01

    Full Text Available Magneto-hydrodynamic (MHD principle is an important interdisciplinary field. One of the most important applications of this effect is pumping of materials that are hard to pump using conventional pumps. In this work, the progress achieved in this field is surveyed and organized according to the type of application. The literature of the past 27 years is searched for the major developments of MHD applications. MHD seawater thrusters are promising for a variety of applications requiring high flow rates and velocity. MHD molten metal pump is important replacement to conventional pumps because their moving parts cannot stand the molten metal temperature. MHD molten salt pump is used for nuclear reactor coolants due to its no-moving-parts feature. Nanofluid MHD pumping is a promising technology especially for bioapplications. Advantages of MHD include silence due to no-moving-parts propulsion. Much progress has been made, but with MHD pump still not suitable for wider applications, this remains a fertile area for future research.

  20. Licensing in BE system code calculations. Applications and uncertainty evaluation by CIAU method

    International Nuclear Information System (INIS)

    Petruzzi, Alessandro; D'Auria, Francesco

    2007-01-01

    The evaluation of uncertainty constitutes the necessary supplement of Best Estimate (BE) calculations performed to understand accident scenarios in water cooled nuclear reactors. The needs come from the imperfection of computational tools on the one side and from the interest in using such tool to get more precise evaluation of safety margins. In the present paper the approaches to uncertainty are outlined and the CIAU (Code with capability of Internal Assessment of Uncertainty) method proposed by the University of Pisa is described including ideas at the basis and results from applications. Two approaches are distinguished that are characterized as 'propagation of code input uncertainty' and 'propagation of code output errors'. For both methods, the thermal-hydraulic code is at the centre of the process of uncertainty evaluation: in the former case the code itself is adopted to compute the error bands and to propagate the input errors, in the latter case the errors in code application to relevant measurements are used to derive the error bands. The CIAU method exploits the idea of the 'status approach' for identifying the thermal-hydraulic conditions of an accident in any Nuclear Power Plant (NPP). Errors in predicting such status are derived from the comparison between predicted and measured quantities and, in the stage of the application of the method, are used to compute the uncertainty. (author)

  1. International assistance. Licensing assistance project

    International Nuclear Information System (INIS)

    Aleev, A.

    1999-01-01

    Description of licensing assistance project for VATESI is presented. In licensing of unit No.1 of INPP VATESI is supported by many western countries. Experts from regulatory bodies or scientific organizations of those countries assist VATESI staff in reviewing documentation presented by INPP. Among bilateral cooperation support is provided by European Commission through Phare programme

  2. Introduction to Technology Export License of Nuclear Facility

    International Nuclear Information System (INIS)

    Seo, Hana; Lee, Chansuh; Shin, Donghoon

    2014-01-01

    In this regime, the Nuclear Safety and Security Commission (NSSC) has authority on final decision making. And the Korea Institute of Nuclear nonproliferation and Control (KINAC) has missions to review the classification and export licensing technically. In principle, classification and export licensing are applied and reviewed individually. However, the number of application for classification and licensing has increased geometrically in the last three years. This is largely a due to the contract that the Republic of Korea (ROK) has finalized to build the UAE Barakah Nuclear Power Plant (BNPP) and Jordan Research and Training Reactor (JRTR). This circumstance brought an administrative burden for the government and related institutes as well as stakeholders. This article introduces the law related to the 'Technology Export License of Nuclear Facility' which was developed and legislated to improve the efficiency and effectiveness of commodities classification and export licensing. This system could significantly reduce the licensing burden for transferring the technologies. However, the classification and license on this system are still requested when transferring the goods. Therefore, KINAC will continue to figure out the needs for the stakeholders and keep searching for solutions to problems inherent in the industry

  3. Introduction to Technology Export License of Nuclear Facility

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Hana; Lee, Chansuh; Shin, Donghoon [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2014-05-15

    In this regime, the Nuclear Safety and Security Commission (NSSC) has authority on final decision making. And the Korea Institute of Nuclear nonproliferation and Control (KINAC) has missions to review the classification and export licensing technically. In principle, classification and export licensing are applied and reviewed individually. However, the number of application for classification and licensing has increased geometrically in the last three years. This is largely a due to the contract that the Republic of Korea (ROK) has finalized to build the UAE Barakah Nuclear Power Plant (BNPP) and Jordan Research and Training Reactor (JRTR). This circumstance brought an administrative burden for the government and related institutes as well as stakeholders. This article introduces the law related to the 'Technology Export License of Nuclear Facility' which was developed and legislated to improve the efficiency and effectiveness of commodities classification and export licensing. This system could significantly reduce the licensing burden for transferring the technologies. However, the classification and license on this system are still requested when transferring the goods. Therefore, KINAC will continue to figure out the needs for the stakeholders and keep searching for solutions to problems inherent in the industry.

  4. ITER Safety and Licensing

    International Nuclear Information System (INIS)

    Girard, J-.P; Taylor, N.; Garin, P.; Uzan-Elbez, J.; GULDEN, W.; Rodriguez-Rodrigo, L.

    2006-01-01

    The site for the construction of ITER has been chosen in June 2005. The facility will be implemented in Europe, south of France close to Marseille. The generic safety scheme is now under revision to adapt the design to the host country regulation. Even though ITER will be an international organization, it will have to comply with the French requirements in the fields of public and occupational health and safety, nuclear safety, radiation protection, licensing, nuclear substances and environmental protection. The organization of the central team together with its partners organized in domestic agencies for the in-kind procurement of components is a key issue for the success of the experimentation. ITER is the first facility that will achieve sustained nuclear fusion. It is both important for the experimental one-of-a-kind device, ITER itself, and for the future of fusion power plants to well understand the key safety issues of this potential new source of energy production. The main safety concern is confinement of the tritium, activated dust in the vacuum vessel and activated corrosion products in the coolant of the plasma-facing components. This is achieved in the design through multiple confinement barriers to implement the defence in depth approach. It will be demonstrated in documents submitted to the French regulator that these barriers maintain their function in all postulated incident and accident conditions. The licensing process started by examination of the safety options. This step has been performed by Europe during the candidature phase in 2002. In parallel to the final design, and taking into account the local regulations, the Preliminary Safety Report (RPrS) will be drafted with support of the European partner and others in the framework of ITER Task Agreements. Together with the license application, the RPrS will be forwarded to the regulatory bodies, which will launch public hearings and a safety review. Both processes must succeed in order to

  5. Licensing of ANSTO's Replacement Research Reactor

    International Nuclear Information System (INIS)

    Summerfield, M.W.; Garea, V.

    2003-01-01

    This paper presents a general description of the licensing of the 20 MW Pool-type Replacement Research Reactor (RRR) currently being built by the Australian Nuclear Science and Technology Organisation (ANSTO) at their Lucas Heights site. The following aspects will be addressed: 1) The influence of ARPANSA's (the Australian regulator) Regulatory Assessment Principles and Design Criteria on the design of the RRR. 2) The Site Licence Application, including the EIS and the supporting siting documentation. 3) The Construction Licence Application, including the PSAR and associated documentation. 4) The review process, including the IAEA Peer Review and the Public Submissions as well as ARPANSA's own review. 5) The interface between ANSTO, INVAP and ARPANSA in relation to the ongoing compliance with ARPANS Regulation 51 and 54. 6) The future Operating Licence Application, including the draft FSAR and associated documentation. These aspects are all addressed from the point of view of the licensee ANSTO and the RRR Project. Particular emphasis will be given to the way in which the licensing process is integrated into the overall project program and how the licensing and regulatory regime within Australia influenced the design of the RRR. In particular, the safety design features that have been incorporated as a result of the specific requirements of ANSTO and the Australian regulator will be briefly described. The paper will close with a description of how the RRR meets, and in many aspects exceeds the requirements of ANSTO and the Australian regulator. (author)

  6. AP1000R licensing and deployment in the United States

    International Nuclear Information System (INIS)

    Jordan, R. P.; Russ, P. A.; Filiak, P. P.; Castiglione, L. L.

    2012-01-01

    In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two new nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing actions directed

  7. Guide to request license for teletherapy practice

    International Nuclear Information System (INIS)

    2000-01-01

    In this work the steps to request license for teletherapy practice are described , among these steps they it continued it plows to request the qualified personnel's yams, the operation authorization, application purpose, license type

  8. 75 FR 4571 - Government-Owned Inventions; Availability for Licensing

    Science.gov (United States)

    2010-01-28

    .... Applications: Therapies for tumors associated with NF1 (including brain and peripheral nervous system tumors...-US-01). Licensing Status: Available for licensing. Licensing Contact: Patrick P. McCue, Ph.D.; 301...

  9. 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

  10. Multiscale Model Simulations of Temperature and Relative Humidity for the License Application of the Proposed Yucca Mountain Repository

    Science.gov (United States)

    Buscheck, T.; Glascoe, L.; Sun, Y.; Gansemer, J.; Lee, K.

    2003-12-01

    ; these variables are determined every 20 m for each emplacement drift in the repository. The MSTHM accounts for 3-D drift-scale and mountain-scale heat flow and captures the influence of the key engineering-design variables and natural-system factors affecting TH conditions in the emplacement drifts and adjoining host rock. Presented is a synopsis of recent MSTHM calculations conducted to support the Total System Performance Assessment for the License Application (TSPA-LA). This work was performed under the auspices of the U.S. Department of Energy by University of California Lawrence Livermore National Laboratory under contract No. W-7405-Eng-48.

  11. Clinch River Breeder Reactor Plant. License application, statement of general information

    International Nuclear Information System (INIS)

    1975-01-01

    Application is made for a reactor facility consisting of a liquid metal cooled reactor and steam generator system, a steam turbine driven electric generating system, electrical switchyard, and related auxiliaries and supporting structures. The primary system is located in an inert atmosphere in shielded vaults within a containment structure. Sodium coolant is used to remove heat from the core and radial blanket. Heat from the primary sodium is transferred in heat exchangers to non radioactive sodium which is used to convert feed-water into steam which is superheated to drive a tandem-compound generator. A single shaft multi-stage turbine generator produces 380 MW(e) with steam conditions of 1450 psig at 900 0 F. Fuel is sintered ceramic pellets of mixed uranium-plutonium oxides encapsulated in stainless steel. There are 198 fuel assemblies with each assembly consisting of 217 fuel rods placed in a hexagonal channel. Plutonium enrichment ranges from 1817 to 32.0 percent by weight. Axial blanket sections contain depleted UO 2 with 99.8 percent 238 U and 0.2 percent 235 U by weight. The proposed location of the plant is within the corporate limits of the city of Oak Ridge in Roane County, Tennessee. (U.S.)

  12. Clinical application analysis of andrographolide total ester sulfonate injection, a traditional Chinese medicine licensed in China.

    Science.gov (United States)

    Zhao, Ying; Huang, Pu; Chen, Zhe; Zheng, Si-Wei; Yu, Jin-Yang; Shi, Chen

    2017-04-01

    Andrographolide total ester sulfonate (ATES) injection is one of the products of traditional Chinese medicine (TCM) currently used against viral infection in China. ATES injection was approved for manufacturing and marketing in January 2002. It is indicated for acute respiratory infections, tonsillitis, chronic obstructive pulmonary disease, influenza, foot and mouth disease, bronchiolitis, herpangina, mumps, infectious mononucleosis and psychosis. However, its usage also carries risk. We investigated the use of ATES at the Wuhan Union Hospital from January 2014 to December 2014 and evaluated its real-world clinical application using the hospital centralized monitoring method. A total of 848 cases were enrolled in this study. In these cases, it was mainly used for postoperative anti-inflammation and treating upper respiratory infection, pneumonia and bronchitis. Among them, 39.86% were contraindicated. Irregular medication of adults and children accounted for 1.91% and 23.38%, respectively. Improper choice of solvent accounted for 3.18%. The choice of intravenous drip versus aerosol inhalation was reasonable. A case of adverse events (AEs) was observed in the monitoring period, and the incidence of adverse drug reaction (ADR) of ATES injection was 0.12%. ATES injection in our hospital is relatively safe with a low incidence of adverse reactions. The study assesses the clinical usage and adverse reactions of ATES injection, and provides suggestions for rational use in clinical practice.

  13. Licensing safety critical software

    International Nuclear Information System (INIS)

    Archinoff, G.H.; Brown, R.A.

    1990-01-01

    Licensing difficulties with the shutdown system software at the Darlington Nuclear Generating Station contributed to delays in starting up the station. Even though the station has now been given approval by the Atomic Energy Control Board (AECB) to operate, the software issue has not disappeared - Ontario Hydro has been instructed by the AECB to redesign the software. This article attempts to explain why software based shutdown systems were chosen for Darlington, why there was so much difficulty licensing them, and what the implications are for other safety related software based applications

  14. 29 Has the licensing ACT 2003 affected levels of violence in England and Wales? A systematic review of hospital and police studies.

    Science.gov (United States)

    Callan, Caitríona; Boyle, Adrian

    2017-12-01

    Population-level legislation has been implemented in many countries to try and address alcohol misuse and related harms, including assault. Most violent incidents in the UK are alcohol-related, with alcohol misuse accounting for a substantial proportion of Accident and Emergency Department attendances. The Licensing Act 2003 aimed to reduce alcohol-related crime and disorder by abolishing set closing times and giving local authorities control over premises licensing in England and Wales. Concerns were raised, however, that greater availability of alcohol would lead to increased consumption and violence. This review examines primary research from hospital and police settings to evaluate whether the implementation of the Act in 2005 reduced or increased violence rates in England and Wales. We performed an inclusive systematic review of the major biomedical databases. We included original research that evaluated changes in violence rates before and after the implementation of the Licensing Act, including hospital- and police- defined measures for this primary outcome. Our secondary outcome was whether there was change in temporal distribution of violent incidents after implementation of the Act. We identified 184 studies. 15 studies were included. The evidence was of overall poor quality, with the majority of included studies being uncontrolled before-after studies. 8 of these studies were conducted in the hospital setting, and 7 were from the police setting. Overall, 7 studies found reduced violence rates after implementation of the Licensing Act, 3 found increased rates, and 5 found no significant change. A subset of 9 papers analysed temporal distribution of violent incidents, 8 finding evidence of temporal displacement of assaults further into the early hours of the morning. This is the most complete analysis to date of the effects of the Licensing Act on violence. There is no evidence for the Act having a significant or consistent effect on community violence

  15. U.S. licensing process and ABWR certification

    International Nuclear Information System (INIS)

    Quirk, J.F.; Williams, W.A.

    1996-01-01

    Part 50 of Title 10 of the Code of Federal Regulation (CFR) establishes a two-step licensing process by which the U.S. Nuclear Regulatory Committee (NRC) authorizes nuclear reactor plant construction through issuance of a construction permit and authorizes operation by issuance of an operating license. At each stage, the NRC Staff conducts technical reviews and there is potential for public hearings. In 1989, the NRC issued a new, simplified licensing process: Part 52. The purpose of the Part 52 licensing process is to provide a regulatory framework that brings about earlier resolution of licensing issues. Because issues are not resolved early in the Part 50 licensing process, approval of an operating license is not assured until after a significant investment has been made in the plant. Part 52 increases the stability and certainty of the licensing process by providing for the early resolution of safety and environmental issues. The Part 52 licensing process features (1) early site permits, (2) design certification, and (3) combined construction permit and operating licenses. As part of the U.S. Advanced Light Water Reactor (ALWR) Program to revitalize the nuclear option through the integration of government/utility/industry efforts, GE undertook the role of applying for certification for its latest product line, the Advanced Boiling Water Reactor (ABWR), under the U.S. ABWR certification program. The ABWR design is an essentially complete plant. Initial application for design certification was in 1987 under Part 50. GE reapplied in late 1991 under the newly promulgated Part 52. Following seven years of intensive interactions with the NRC and ACRS, GE was awarded the first Final Design Approval (FDA) under Part 52. The Commission initiated rulemaking by publishing the proposed ABWR Certification Rule in the Federal Register in early 1995. Certification is anticipated mid-1996. (J.P.N.)

  16. Software licenses: Stay honest!

    CERN Multimedia

    Computer Security Team

    2012-01-01

    Do you recall our article about copyright violation in the last issue of the CERN Bulletin, “Music, videos and the risk for CERN”? Now let’s be more precise. “Violating copyright” not only means the illegal download of music and videos, it also applies to software packages and applications.   Users must respect proprietary rights in compliance with the CERN Computing Rules (OC5). Not having legitimately obtained a program or the required licenses to run that software is not a minor offense. It violates CERN rules and puts the Organization at risk! Vendors deserve credit and compensation. Therefore, make sure that you have the right to use their software. In other words, you have bought the software via legitimate channels and use a valid and honestly obtained license. This also applies to “Shareware” and software under open licenses, which might also come with a cost. Usually, only “Freeware” is complete...

  17. Presentation summary, safety design aspects and U.S. licensing challenges of the pebble bed modular reactor

    International Nuclear Information System (INIS)

    Sproat, Ward; Slabber, Johan

    2001-01-01

    This presentation consists of three sections: An overview of the status of the PBMR project in South Africa, a review of the design features and philosophy being utilized to design the PBMR, and a summary of the key licensing issues that Exelon has identified in assessing the licensability of the PBMR for application in this country

  18. The Texas concurrent characterization, licensing, and development process

    Energy Technology Data Exchange (ETDEWEB)

    Avant, R.V. Jr. [Texas Low-Level Radioactive Waste Disposal Authority, Austin, TX (United States)

    1993-03-01

    The 72nd Texas Legislature specifically delineated a 400-square-mile area in southeast Hudspeth County where siting activities would be limited. The Authority was given unprecedented powers of property access and eminent domain and expanded budget authority to conduct site selection, characterization, and licensing. In the summer of 1991, the Authority identified five general siting areas in the prescribed region, and in the fall of 1991, the Authority narrowed the siting area to one large ranch composed of about 16,000 acres--called the Faskin Ranch. Site characterization began in 1991 and will be complete by September 1993. In September 1991, Authority staff began preparing the license application and included all available information on the Faskin Ranch. At its February meeting, the Authority`s board directed staff to submit the license application to the Texas Water Commission (the new Texas radiation control agency). The license application was submitted on March 2, 1992, and on April 15, 1992, the Commission determined that the application was sufficiently complete to begin review. Discrete technical packages such as groundwater hydrology, surface water hydrology, design, etc., will be submitted to the agency for review on the completion of each package. A schedule has been developed to allow the regulators the maximum time possible to review critical technical areas while minimizing the total review period.

  19. Reactor licensing process: a status report

    International Nuclear Information System (INIS)

    Long, J.A.

    1977-01-01

    The Nuclear Regulatory Commission (NRC), in its review of applications for licenses to construct and operate nuclear power plants, is required to consider those measures necessary to ensure the protection of the health and safety of the public and the environment. The article discusses the NRC staff procedures and policies for conducting the detailed safety, environmental, and antitrust reviews that provide the basis for these assurances. Included is a discussion of the improvements to the licensing process currently being proposed or implemented to enhance its stability and predictability for the benefit of all involved with the regulation of nuclear power. The views and opinions expressed in the article are those of the author alone and do not represent positions of the NRC

  20. Licensing the California low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Dressen, A.L.; Serie, P.J.; Junkert, R.

    1992-01-01

    California has made significant progress toward the issuance of a license to construct and operate the Southwestern Compact's low-level radioactive waste disposal facility. However, obstacles to completing construction and preparing to receive waste still exist. This paper will describe the technical licensing issues, EIR/S process, political events, and public interactions that have impacted on California regulators' ability to complete the license application review and reach a decision on issuing a license. Issues associated with safely and liability evaluations, finalization of the environmental impact report, and land transfer processes involving multiple state, federal, and local agencies will be identified. Major issues upon which public and political opposition is focusing will also be described. (author)

  1. Regulatory Review of Early Site Permit Applications

    International Nuclear Information System (INIS)

    Scott, Michael L.

    2004-01-01

    The U.S. Nuclear Regulatory Commission (NRC) has received and is reviewing three applications for early site permits (ESPs). The ESP process allows early resolution of site-related issues affecting possible construction and operation of a new nuclear power plant. The nuclear industry views a successful and predictable ESP process as an important step in assessing whether to seek authorization to construct and operate a new generation of nuclear power reactors in the United States. Because consideration of ESP applications is a first-of-a-kind activity, a number of issues have emerged prior to and during the reviews of the first three applications. Issues have included the need for design information at the ESP stage, accident analyses, quality assurance, and seismic analyses. The NRC has been working to resolve identified issues to support a Commission decision on whether to issue an ESP approximately 33-37 months after receipt of each ESP application. (authors)

  2. Ceramics for Dental Applications: A Review

    Directory of Open Access Journals (Sweden)

    Julie A. Holloway

    2010-01-01

    Full Text Available Over the past forty years, the technological evolution of ceramics for dental applications has been remarkable, as new materials and processing techniques are steadily being introduced. The improvement in both strength and toughness has made it possible to expand the range of indications to long-span fixed partial prostheses, implant abutments and implants. The present review provides a state of the art of ceramics for dental applications.

  3. Establishment of regulatory framework for the development reactor licensing

    International Nuclear Information System (INIS)

    Jo, Jong C.; Yune, Young G.; Kim, Woong S.; Ahn, Sang K.; Kim, In G.; Kim, Hho J.

    2003-01-01

    With a trend that various types of advanced reactor designs are currently under development worldwide, the Korea Atomic Energy Research Institute has been developing an advanced reactor called ' System-integrated Modular Advanced Reactor (SMART)', which is a small sized integral type pressurized water reactor with a rated thermal power of 330 MW. To demonstrate the safety and the performance of the SMART reactor design, the SMART Research and Development Center has embarked to build a scaled-down pilot plant of SMART, called 'SMART-P' with a rated thermal power of 65 MW. In preparation for the forthcoming applications for both construction permit and operating license of SMART-P in the near future, the Korea Institute of Nuclear Safety is developing a new regulatory framework for licensing review of such a development reactor, which covers establishment of licensing process, identification and resolution of technical and safety issues, development of regulatory evaluation or verification-purpose computer codes and analytical methods, and establishment of design-specific, general design and operating criteria, regulations, and associated regulatory guides. This paper presents the current activities for establishing a regulatory framework for the licensing of a research and development reactor. Discussions are made on the SMART-P development program, the current Korean regulatory framework for reactor licensing, the SMART-P licensing-related issues, and the approach and strategy for developing an effective regulatory framework for the SMART-P licensing

  4. The safety case in support of the license application of the surface repository of low-level waste in Dessel, Belgium

    International Nuclear Information System (INIS)

    Wacquier, William; Cool, Wim

    2014-01-01

    The modern concept of the safety case, developed by the OECD/NEA for geological repositories of high- and medium-level waste has been successfully applied by ONDRAF/ NIRAS for a surface repository for Category A waste (i.e. low-level waste) in Belgium in the current project phase 2006-2012. This resulted in the submission on 31 January 2013 by ONDRAF/NIRAS of an application for a 'construction and operation license' to the safety authorities. The benefits of using the notion of the safety case have been that: i) safety has been incorporated in an integrated manner within all assessment basis, design and safety assessment activities; ii) the process of development of the license application has gained in clarity and traceability; iii) the documentation of the license application contains multiple lines of argumentation for safety rather than argumentation based only on quantitative radiological impact calculations. To offer a comprehensive view on the safety argumentation and its development, it has been found useful to develop the argumentation not only along a safety statements structure but also along the safety report structure. (authors)

  5. License plate recognition (phase B).

    Science.gov (United States)

    2010-06-01

    License Plate Recognition (LPR) technology has been used for off-line automobile enforcement purposes. The technology has seen mixed success with correct reading rate as high as 60 to 80% depending on the specific application and environment. This li...

  6. DOE Patents Available for Licensing

    International Nuclear Information System (INIS)

    Stuber, C.

    1981-01-01

    DOE Patents Available for Licensing (DOE PAL) provides abstracting and indexing coverage of the DOE patent literature, including patent applications, that concerns any apsect of energy production, conservation, and utilization. The citations are arranged by subject category. DOE is prepared to grant exclusive or nonexclusive, revocable licenses under DOE-owned US patents and patent applications in accordance with the provisions of 10CFR781

  7. Challenges of SMR licensing practices

    Energy Technology Data Exchange (ETDEWEB)

    Soderholm, K., E-mail: kristiina.soderholm@fortum.com [Fortum Power, Espoo (Finland)

    2012-12-15

    This paper aims to increase the understanding of high level Nuclear Power Plant (NPP) licensing processes in Finland, France, the UK, Canada and the USA. These countries have been selected for this study because of their different licensing processes and recent actions in new NPP construction. After discussing their similarities and differences, suitable features for Small Modular Reactor licensing can be emphasized and suggested. Some of the studied licensing processes have elements that are already quite well suited for application to SMRs, but all of these different national processes can benefit from studying and implementing lessons learned from SMR specific licensing needs. The main SMR features to take into account in licensing are standardization of the design, modularity, mass production and serial construction. Modularity can be divided into two different categories: the first category is simply a single unit facility constructed of independently engineered modules (e.g., construction process for Westinghouse AP-1000 NPP) and the second is a facility structure composed of many reactor modules where modules are manufactured in factories and installed into the facility as needed (e.g., NuScale Power SMR design). Short construction schedules will not be fully benefited from if the long licensing process prolongs the commissioning and approach to full-power operation. The focus area of this study is to better understand the possibility of SMR deployment in small nuclear countries, such as Finland, which currently has four operating NPPs. The licensing process needs to be simple and clear to make SMR deployment feasible from an economical point of view. This paper uses public information and interviews with experts to establish the overview of the different licensing processes and their main steps. A high-level comparison of the licensing steps has been carried out. Certain aspects of the aviation industry licensing process have also been studied and certain

  8. Application of the New Decommissioning Regulation to the Nuclear Licensed Facilities (NLF) at Fontenay-aux-Roses's Nuclear Center (CEA)

    International Nuclear Information System (INIS)

    Sauret, Josiane; Piketty, Laurence; Jeanjacques, Michel

    2008-01-01

    This abstract describes the application of the new decommissioning regulation on all Nuclear Licensed Facilities (NLF is to say INB in French) at Fontenay-aux-Roses's Center (CEA/FAR). The decommissioning process has been applied in six buildings which are out of the new nuclear perimeter proposed (buildings no 7, no 40, no 94, no 39, no 52/1 and no 32) and three buildings have been reorganized (no 54, no 91 and no 53 instead of no 40 and no 94) in order to increase the space for temporary nuclear waste disposal and to reduce the internal transports of nuclear waste on the site. The advantages are the safety and radioprotection improvements and a lower operating cost. A global safety file was written in 2002 and 2003 and was sent to the French Nuclear Authority on November 2003. The list of documents required is given in the paragraph I of this paper. The main goals were two ministerial decrees (one decree for each NLF) getting the authorization to modify the NLF perimeter and to carry out cleaning and dismantling activities leading to the whole decommissioning of all NLF. Some specific authorizations were necessary to carry out the dismantling program during the decommissioning procedure. They were delivered by the French Nuclear Safety Authority (FNSA) or with limited delegation by the General Executive Director (GED) on the CEA Fontenay-aux-Roses's Center, called internal authorization. Some partial dismantling or decontamination examples are given below: - evaporator for the radioactive liquid waste treatment station (building no 53): FNSA authorization: phase realised in 2002/2003. - disposal tanks for the radioactive liquid waste treatment station (building no 53) FNSA authorization: phase realised in 2004, - incinerator for the radioactive solid waste treatment station (building no 07): FNSA authorization: operation realised in 2004, - research equipments in the building no. 54 and building no. 91: internal authorization ; realised in 2005, - sample

  9. Westinghouse AP1000 licensing maturity

    International Nuclear Information System (INIS)

    Schulz, T.; Vijuk, R.P.

    2005-01-01

    The Westinghouse AP1000 Program is aimed at making available a nuclear power plant that is economical in the U.S deregulated electrical power industry in the near-term. The AP1000 is two-loop 1000 MWe pressurizer water reactor (PWR). It is an up rated version of the AP600. The AP1000 uses passive safety systems to provide significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. The AP1000 uses proven technology, which builds on over 35 years of operating PWR experience. The AP1000 received Final Design Approval by the United States Nuclear Regulatory Commission (U.S. NRC) in September 2004. The AP1000 meets the US utility requirements. The AP1000 and its sister plant the AP600 have gone through a very through and complete licensing review. This paper describes the U.S. NRC review efforts of both the AP600 and the AP1000. The detail of the review and the independent calculations, evaluations and testing is discussed. The AP600 licensing documentation was submitted in 1992. The U.S. NRC granted Final Design Approval in 1999. During the intervening 7 years, the U.S. NRC asked thousands of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. For the AP1000 Westinghouse first engaged the U.S. NRC in pre-certification discussions to define the extent of the review required, since the design is so similar to the AP600. The AP1000 licensing documentation was submitted in March 2002. The U.S. NRC granted Final Design Approval in September 2004. During the intervening 2 1/2 years, the U.S. NRC asked hundreds of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. The implications of this review and approval on AP1000 applications in

  10. Licensing process of the digital application: Nuclear measurement analysis and control power range neutron monitor (NUMAC-PRNM) system for their implementation in the Laguna Verde NPP unit 2

    International Nuclear Information System (INIS)

    Ledesma-Carrion, R.; Hernandez-Cortes, A.

    1998-01-01

    This paper describe the licensing process performed by the Mexican Regulatory Commission (CNSNS) for the NUclear Measurement Analysis and Control-Power Range Neutron Monitor (NUMAC-PRNM) system, which sends trip signals to the Reactor Protection System (RPS), and has been implemented in the Laguna Verde Nuclear Power Plant Unit (LVNPP-U2) before its first fuel loading. The review and approval process was performed with the advise role of the United States of America Nuclear Regulatory Commission (USNRC): the regulatory frame applied includes the Code of Federal Regulation, some Regulatory Guides and some Industrial Standards. The evaluation covered topics related with the software, hardware and firmware specifications, design, tests, training, maintenance and operational experience. After the revision of these topics, the NUMAC-PRNM was approved through the CNSNS Safety Evaluation Report (SER) and then installed in the LVNPP-U2. This paper include a description of the regulatory requirements to this digital application, the safety concerns involved, the compliance to these requirements by the utility and the results of the CNSNS evaluation, mentioning the experience acquired during the process and the method used to perform the evaluation. Additionally, the interface between the designer-vendor, the utility and the regulatory body during the licensing process is commented. Finally, the conclusion is presented, taking into account the operational experience of the NUMAC applications implemented in the LVNPP. It also gives the future regulatory tasks related to the assessment of digital performance equipment and upgrades. (author)

  11. Application of the NEI 95-10 methodology in the Rcic system of the Unit-1, to implement the criterions of the license renovation rule; (10 Cfr-54)

    International Nuclear Information System (INIS)

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

    2012-10-01

    In December of 1991, the US National Regulatory Commission (US NRC) published the 10 Cfr-54, to establish the procedures, criterions and necessary requirements for the license renovation of a nuclear power station. In 1994 the US NRC proposed an amendment to these requirements that basically were centered in the effects of the aging in structures and passive components of long life and in the inclusion of Time Limited Aging Analyses (TLAAs). In a general way, is established that the requester should show to the regulator body that the effects of the aging in structures, systems and components are and will be appropriately negotiated or that the TLAAs has been evaluated for the operation extended period. The NEI 95-10 is a guide document developed by the Nuclear Energy Institute (NEI), to provide a focus accepted to cover the requirements of 10 Cfr-54, offering an efficient process that allows to any requester to complete in a practical way the requirements of the License Renovation Rule and to supplement their solicitude. This work presents the application of this guide to the Reactor Core Insulation Cooling (Rcic) of the Unit 1 of the nuclear power plant of Laguna Verde, elect as pilot system to carry out the application of the 10 Cfr-54 following the recommended methodology by the Industrial Guide for the implementation of the License Renovation Rule. (Author)

  12. Microcomputer applications for NSSS data package review

    International Nuclear Information System (INIS)

    Eng, D.J.; Smith, F.M.

    1984-01-01

    Associated with each component of a Nuclear Steam Supply System are the necessary supporting documents which demonstrate compliance with applicable codes, specifications and design criteria. The documents are grouped into individual data packages, and may exceed 800 in number for a major installation. A complete review, initiated by a utility in response to federal code regulations (10 CFR 50), can involve a tremendous number of review transactions. A data management system to assist the reviewer in the tracking and resolution of discrepancy items is currently under development and use. The system uses microcomputer-based relational database management software and provides complete and flexible capabilities to process database components and attributes based on user specified criteria. The completed database is a ''portable'' system, and can be utilized on an as-needed basis after the review is completed. A discrepancy analysis is performed to identify relations between manufacturer and discrepancy occurrence, part type vs. discrepancy type, etc. These results may prove useful in subsequent reviews or application to existing QA procedures

  13. 76 FR 7847 - Glenn A. Baxter, Application To Renew License for Amateur Radio Service Station K1MAN

    Science.gov (United States)

    2011-02-11

    ... Renew License for Amateur Radio Service Station K1MAN AGENCY: Federal Communications Commission. ACTION... Service Station K1MAN filed by Glenn A. Baxter should be granted. DATES: The document was mailed to the... Amateur Radio Station K1MAN should be granted. As discussed below, the record before us indicates that...

  14. 77 FR 16278 - License Renewal Application for Indian Point Nuclear Generating Units 2 and 3; Entergy Nuclear...

    Science.gov (United States)

    2012-03-20

    ... contacting the NRC about the availability of information regarding this document. You may access information... the Village of Buchanan, New York. The current operating licenses for IP2 and IP3 expire on September... units of measure; (2) a new thermal study that characterizes the thermal plume of cooling water...

  15. Physician input and licensing of at-risk drivers: a review of all-inclusive medical evaluation forms in the US and Canada.

    Science.gov (United States)

    Meuser, Thomas M; Berg-Weger, Marla; Niewoehner, Patricia M; Harmon, Annie C; Kuenzie, Jill C; Carr, David B; Barco, Peggy P

    2012-05-01

    This article details a systematic review of medical evaluation forms in support of licensing decisions for medically at-risk drivers. Comparisons were made between all-inclusive forms utilized by 52 State and Provincial Departments of Motor Vehicles (DMVs) in the US and Canada. Comparisons focused on length, format, content, instructional quality, medical coverage, ease of use, and other qualitative characteristics. Median page length was 2 (range 1-10), and mean word count was 1083 (494-3884). Common response options included open-ended (98%), forced choice (87%), and check box (81%). While the majority of forms (77%) required driver consent, only 24% requested information from the driver. Less than half (46%) included text on confidentiality protection. While all forms requested general medical information, just over half included specific sections for vision (54%) and cognitive/neurological conditions (56%). Most forms (81%) required that a judgment be made concerning driver safety, and half prompted for possible license restrictions. Criterion-based quality ratings were assigned on a five-point Likert scale by group consensus. One third of forms were rated as marginal or poor in comprehensiveness and utility, and just two garnered an excellent overall rating. Findings are discussed relative to current research on driver fitness and elements of a proposed model form. Best practice recommendations include a page length limitation, emphasis on in-person evaluation (i.e., as opposed to a records-only review), prompts to collect crash and other driving history information, clear instructions and stepwise format, content prompts across relevant medical categories, documentation of functional status and impairment levels, options for driving with restrictions in lieu of de-licensing, and emphasis on relative (vs. absolute) clinical judgments of overall driver safety. Copyright © 2011 Elsevier Ltd. All rights reserved.

  16. A Review of State Licensing Regulations to Determine Alignment with Best Practices to Prevent Human Norovirus Infections in Child-Care Centers.

    Science.gov (United States)

    Leone, Cortney M; Jaykus, Lee-Ann; Cates, Sheryl M; Fraser, Angela M

    2016-01-01

    Close, frequent contact between children and care providers in child-care centers presents many opportunities to spread human noroviruses. We compared state licensing regulations for child-care centers with national guidelines written to prevent human noroviruses. We reviewed child-care licensing regulations for all 50 U.S. states and the District of Columbia in effect in June 2015 to determine if these regulations fully, partially, or did not address 14 prevention practices in four topic areas: (1) hand hygiene, (2) exclusion of ill people, (3) environmental sanitation, and (4) diapering. Approximately two-thirds (8.9) of the 14 practices across all state regulations were partially or fully addressed, with few (2.6) fully addressed. Practices related to exclusion of ill people and diapering were fully addressed most often, while practices related to hand hygiene and environmental sanitation were fully addressed least often. Regulations based on guidelines for best practices are one way to prevent the spread of human noroviruses in child-care facilities, if the regulations are enforced. Our findings show that, in mid-2015, many state child-care regulations did not fully address these guidelines, suggesting the need to review these regulations to be sure they are based on best practices.

  17. Medical imaging technology reviews and computational applications

    CERN Document Server

    Dewi, Dyah

    2015-01-01

    This book presents the latest research findings and reviews in the field of medical imaging technology, covering ultrasound diagnostics approaches for detecting osteoarthritis, breast carcinoma and cardiovascular conditions, image guided biopsy and segmentation techniques for detecting lung cancer, image fusion, and simulating fluid flows for cardiovascular applications. It offers a useful guide for students, lecturers and professional researchers in the fields of biomedical engineering and image processing.

  18. Health related smartphone applications: a literature review

    Directory of Open Access Journals (Sweden)

    Pantelis Stergiannis

    2015-09-01

    Full Text Available The rapid evolution of technology, has offered access to a variety of applications and technologies to healthcare professionals. New operating systems developed in the field of mobile devices revolutionized the way in which they are used. One of the main features offered by advanced software of a smartphone is the user’s access to a wealth of new, impressive applications across several operating systems for smartphones. The health related applications provided through smartphones, promote more active involvement of patients and healthcare professionals to provided care and are a new tool for improving health. The purpose of this abstract paper or article was to refer to applications currently used in the health sector, indicating specific capabilities they offer through review of electronic literature, focusing on scientific articles published in databases (PubMed, Scopus, etc. referring to the potentials they offer. It seems that several health related applications have been developed, that can be classified into two main categories. One category comprises applications that are informative, i.e. provide information to the user about health issues, allowing a person to read, gather resources to make decisions, but also to introduce its own data. These applications are mostly used by health care professionals. The second major category of applications refers to those related to help with the diagnosis, treatment and decision-making on various health related issues and in some cases take the form of consultancy, substituting the health care professional. As technology advances, the development of new health related applications is expected, specialized, with new features. Finally, the use of such applications by health care professionals is essential.

  19. 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

  20. Future superconductivity applications in space - A review

    Science.gov (United States)

    Krishen, Kumar; Ignatiev, Alex

    High temperature superconductor (HISC) materials and devices can provide immediate applications for many space missions. The in-space thermal environment provides an opportunity to develop, test, and apply this technology to enhance performance and reliability for many applications of crucial importance to NASA. Specifically, the technology development areas include: (1) high current power transmission, (2) microwave components, devices, and antennas, (3) microwave, optical, and infrared sensors, (4) signal processors, (5) submillimeter wave components and systems, (6) ultra stable space clocks, (7) electromagnetic launch systems, and (8) accelerometers and position sensors for flight operations. HTSC is expected to impact NASA's Lunar Bases, Mars exploration, Mission to Earth, and Planetary exploration programs providing enabling and cost-effect technology. A review of the space applications of the HTSC technology is presented. Problem areas in technology development needing special attention are identified.