WorldWideScience

Sample records for license application project

  1. 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)

  2. 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

  3. 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...

  4. 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.

  5. 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)

  6. 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...

  7. Licensing and Environmental Issues of Wave Energy Projects

    DEFF Research Database (Denmark)

    Neumann, Frank; Tedd, James; Prado, Miguel

    2006-01-01

    a special standing or facilitated access to operating licenses due to their experimental character, the move of wave energy projects towards commercial applications implies complex procedures for obtaining licenses both with respect to the construction and deployment and operation phases, as well......The major non-technical barrier for large-scale wave energy implementation is the wide range of licensing issues and potential environmental concerns, in addition to significant National/regional differences in licensing procedures and permit requirements. Whereas some pilot plants have had...... as concerning ocean space use and environmental concerns. Despite recent efforts to streamline European EIA (Environmental Impact Assessment) in general, potential project developers are far from having a clear view of present and future requirements concerning these barriers on a trans-national level...

  8. 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...

  9. Licensing plan for UMTRA project disposal sites

    International Nuclear Information System (INIS)

    1993-09-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project Office developed a plan to define UMTRA Project licensing program objectives and establish a process enabling the DOE to document completion of remedial actions in compliance with 40 CFR 1 92 and the requirements of the NRC general license. This document supersedes the January 1987 Project Licensing Plan (DOE, 1987). The plan summarizes the legislative and regulatory basis for licensing, identifies participating agencies and their roles and responsibilities, defines key activities and milestones in the licensing process, and details the coordination of these activities. This plan provides an overview of the UMTRA Project from the end of remedial actions through the NRC's acceptance of a disposal site under the general license. The licensing process integrates large phases of the UMTRA Project. Other programmatic UMTRA Project documents listed in Section 6.0 provide supporting information

  10. Licensing aspects regarding the RBMN project

    International Nuclear Information System (INIS)

    Cuccia, Valeria; Sacramento, Arivaldo M.; Aleixo, Bruna L.; Ferreira, Vinicius V.M.

    2013-01-01

    The licensing process of a waste disposal facility is a complex and demanding undertaking. It proceeds in phases, starting with the site selection and ending many decades later, when the radionuclides decayed and no longer offer possible hazard. That is one of the reasons why the licensing process for the Brazilian repository for low and intermediate level radioactive waste (RBMN Project) is a challenge for all the technicians involved. Besides that, the only national experience associated to this subject arose after a radiological accident in the State of Goias, in 1987. Two different institutions are involved in this licensing process: IBAMA, for environmental licensing, and CNEN, for nuclear licensing. Both of them will evaluate the possible impacts caused by the waste disposal, so it is essential to avoid conflicts and duplications of activities. The RBMN project has different teams for each main activity, and one of them is the Licensing group. This team has been planning the licensing activities for the repository, studying the legal framework and estimating costs and execution time for each step. This paper presents the status of the licensing activities regarding to the RBMN project done by the CNEN staff. (author)

  11. 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...

  12. 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

  13. 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

  14. Status report on the HFR conversion and re-licensing project

    International Nuclear Information System (INIS)

    Wijtsma, F.G.

    2003-01-01

    In 1999 the HFR license holder (JRC, Petten, the Netherlands) initiated a project to study the conversion of the HFR from HEU to LEU. The first phase of this project consisted of a parametric study to determine the optimum fuel element and control rod design within given boundary conditions such as geometry, density, performance and cycle length. Results of this study are a 22 plates fuel element (550 g 235 U) at a density of 4.8 g.cm -3 and a 17 plates control rod (440 g 235 U). The second phase contains all aspects related to the conversion including a full-scale test irradiation of a prototype LEU element. The actual conversion of the HFR requires a new license. For this reason the re-licensing project has started in 2001. In this context many studies have been performed e.g. Risk Scoping Study, Safety Analyses, TOPA (Technical, Operational, Personnel and Administrative) evaluation. The license application will be based on a new Safety Report and an Environmental Impact Statement and will be submitted to the competent Authorities at the end of October 2003. (author)

  15. Environmental impact studies of projects be licensed under the Atomic Law

    International Nuclear Information System (INIS)

    Heuel-Fabianek, Burkhard; Lennartz, Reinhard

    2009-01-01

    The German Law on Environmental Impact Assessment (UVPG) defines projects to be licensed under the Atomic Law that require an environmental impact study (EIS). Since the project concepts as defined in the UVPG are often not the same as those defined in the Atomic Law (AtG), the licensing authority has to decide which project should be subjected to an EIA. Additionally, Article 37 of the EURATOM Treaty obliges every Member State to communicate certain data relating to the impact of emissions of radioactive substances to the Commission. This is independent of the EIA. A licence may only be granted by the competent authorities if an opinion has been received from the Commission pursuant to Article 37. In either case, the licensing authority is the first point of contact for the applicant if the question arises of whether a project has to be subjected to an EIA. A ''voluntary'' EIA should be regarded with caution because of the complexity of such a procedure within the licensing process requiring considerable resources of time and manpower, and the danger of a loss of credibility of the EIA. (orig.)

  16. 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

  17. PBMR-SA licensing project organization

    International Nuclear Information System (INIS)

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

    2001-01-01

    The South African nuclear regulatory authority, the Council for Nuclear Safety (CNS), is beginning the safety review of the Pebble Bed Modular Reactor (PBMR) design under development by the South African National Electrical Utility, Eskom. This paper describes the CNS licensing process, including the establishment of basic licensing criteria, general design criteria, and specific design rules, as well the safety assessment to be conducted in accordance with the established structure. It also summarises the CNS PBMR review project activities, including the overall organisational arrangements, licensing basis, safety and risk assessment, general operating rules and plant design engineering, and pre-operational testing. (author)

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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)

  4. 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

  5. Public participation in the licensing of large-scale projects with environmental impact

    International Nuclear Information System (INIS)

    1989-01-01

    As a rule, public participation in licensing and planning procedures for large-scale projects with environmental impact is as controversial as the projects themselves. Against this background, an interdisciplinary examination of several 'cases' of public participation in administrative procedures with varying legal forms is being conducted in a joint research project run by the Department for Applied Systems Analysis (Karlsruher Nuclear Centre) and the Research Institute for Public Administration at the College for Administrative Sciences in Speyer. The actual course of events and the practical experience of the groups involved (authorities, applicants, objectors, experts) are related to the applicable legal arrangements for public participation. The question to be answered is: which expected and unexpected functions do the procedures actually fulfill and which not. Proposals for the amendment of legal policy could be developed upon the foundation of such a diagnosis. The report contains the results of the 'pilot study' on public participation in the licensing of the nuclear power plant GKN-2 in Neckarwestheim and further contributions on the issue of 'public participation', presented within the framework of a research colloquium at the School for Nuclear Technology/Karlsruhe Nuclear Research Centre. (orig.) [de

  6. 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...

  7. 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...

  8. Licensing Process for International Projects

    International Nuclear Information System (INIS)

    Raetzke, Christan

    2014-01-01

    Christan Raetzke, lawyer, then outlined why nuclear constructions were always international projects and in which cases it would make sense to also make the licensing process be international. His law consulting firm CONLAR focuses specifically on design review so he could adequately present why an international process would make a lot of sense without being a loss of sovereignty

  9. 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

  10. Licensing Status of New and Expanding In-Situ Recovery Uranium Projects in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Catchpole, G.; Thomas, M., E-mail: gccatchpole@uranerz.com [Uranerz Energy Corporation (URZ), Casper, WY (United States)

    2014-05-15

    The authors investigated the licensing status of new in-situ recovery (“ISR”) uranium projects, as well as the expansion of existing projects, within the United States (“US”). Specific emphasis and analysis is placed on those projects within the states of Texas and Wyoming. Of note, information used to prepare this paper was obtained from public sources that included company web sites, the US Securities and Exchange Commission, the US Nuclear Regulatory Commission (“NRC”), the US Energy Information Agency (“EIA”), and the relevant state regulatory agencies. The renewed interest in the production of natural uranium has been motivated, in part, by the increased sale price of yellowcake beginning around 2003 resulting in numerous new and existing natural resources companies acquiring mineral rights in the United States. Because of the economic favorability in terms of both operating and capital costs of ISR mines versus conventional mines in the US (with its relatively low grade of uranium ore), the model for most companies was to acquire mineral properties that had the potential for being mined using the ISR method. There were, however, exceptions to this model. The Uravan mineral district in southwest Colorado and southeast Utah, where relatively high-grade, shallow uranium deposits have the potential to be mined using underground methods, is one such exception. However, the focus of this paper will be on ISR projects. In Wyoming, which has been the top producer of natural uranium among the 50 states for the past seven years, there is one producing ISR mine (Bill Smith — Highland), one ISR mine on standby (Christensen Ranch), and two ISR uranium projects licensed but not yet built (Gas Hills and North Butte). Cameco Resources is planning to develop two ISR projects in Wyoming that have been licensed but not yet constructed. Additionally, three new uranium companies (Ur-Energy, Uranerz and Uranium One) have filed applications with the federal and

  11. 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

  12. 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.

  13. 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...

  14. 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

  15. Legal aspects of public participation in the planning/licensing of environmentally related large-scale projects

    International Nuclear Information System (INIS)

    Kurz, A.

    1991-01-01

    A variety of legal problems arise in the planning/licensing of environmentally related large-scale projects associated with the control and evaluation of technical conditions and the ramifications in social and legal policy of the acceptance of, and resistance to, such projects. On the basis of a number of partial studies e.g. of the licensing procedure of a nuclear power plant (Neckar-2 reactor) the author examines the legal aspects of public participation in the administrative procedures of licensing/plans approval. The dichotomy of law and technology is covered, and public participation in administrative procedures is derived legally from the basic constitutional rights and the principle of fair hearing. After an outline of specific administrative procedures, public participation as part of administrative procedures is included in the broad legal framework of licensing/plans approval of environmentally related large-scale projects. The author concludes that public participation, within the framework of the basic decisions established by legislature, is not a tool to be used in deciding basic political conflicts. Instead, public participations in the application of law serves to protect the rights of the individual by ensuring fair proceedings paying attention to the subjective rights of the individual. As it is unable to decide political conflicts, it is also an unsuitable means of establishing of basic societal consensus, or of seeking acceptance of large-scale projects. (orig./HP) [de

  16. 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...

  17. 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)

  18. Project licensing plan for UMTRA [Uranium Mill Tailings Remedial Action] sites

    International Nuclear Information System (INIS)

    1984-07-01

    The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Project Licensing Plan is to establish how a disposal site will be licensed, and to provide responsibilities of participatory agencies as legislated by the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 (Public Law 95-604). This Plan has been developed to ensure that the objectives of licensing are met by identifying the necessary institutional controls, participatory agency responsibilities, and key milestones in the licensing process. The Plan contains the legislative basis for and a description of the licensing process (''Process'') for UMTRA sites. This is followed by a discussion of agency responsibilities, and milestones in the Process. The Plan concludes with a generic timeline of this Process. As discussed in Section 2.1, a custodial maintenance and surveillance plan will constitute the basis for a site license. The details of maintenance and surveillance are discussed in the Project Maintenance and Surveillance Plan (AL-350124.0000). 5 refs., 4 figs

  19. 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...

  20. 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...

  1. 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.

  2. Legal aspects of public participation in the planning/licensing of environmentally related large-scale projects

    International Nuclear Information System (INIS)

    Kurz, A.

    1992-02-01

    A variety of legal problems arise in the planning/licensing of environmentally related large-scale projects associated with the control and evaluation of technical conditions and the ramifications in social and legal policy of the acceptance of, and resistance to, such projects. On the basis of a number of partial studies e.g. of the licensing procedure of a nuclear power plant (Neckar-2 reactor), the author examines the legal aspects of public participation in the administrative procedure of licensing/plans approval. The dichotomy of law and technology is covered, and public participation in administrative procedures is derived legally from the basic constitutional rights and the principle of fair hearing. After an outline of specific administrative procedures, public participation as part of administrative procedures is included in the broad legal framework of licensing/plans approval of environmentally related large-scale projects. The author concludes that public participation, within the framework of the basic decisions established by legislature, is not a tool to be used in deciding basic political conflicts. Instead, public participations in the application of law serves to protect the rights of the individual by ensuring fair proceedings paying attention to the subjective rights of the individual. As it is unable to decide political conflicts, it is also an unsuitable means of establishing of basic societal consensus, or of seeking acceptance of large-scale projects. This is reflected also in studies of the legal functions of public participation, according to which the lawfulness of procedures is observed without, however, the legitimacy of the project being achieved. (orig./HP) [de

  3. 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)

  4. 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...

  5. 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

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. 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...

  12. IRIS project update: status of the design and licensing activities

    International Nuclear Information System (INIS)

    Petrovic, B.; Carelli, M.

    2004-01-01

    This paper presents an overview of the current status of the IRIS (International Reactor Innovative and Secure) project, focusing on the design and licensing activities. An update relative to the previous presentation at the 4th HND Conference is provided, highlighting some of the main accomplishments over the past two years. After successfully completing the conceptual design phase, IRIS is now finalizing the preliminary design as well. The pre-application licensing review with the U.S. NRC has been initiated in October of 2002. The safety-by-design approach and PRA-guided design open the possibility to aim for licensing not requiring off-site emergency response planning. Multiple single-unit and twin-unit site layouts have been developed within the ESP (Early Site Permit) program currently pursued by three U.S. power utilities. Desalination and district heating options have recently been added to the base design. Staggered construction schedules of multiple units may be applied to optimize cash-flow and minimize the required investment, making IRIS a financially attractive option, even for economies with limited investment capabilities. Because of its modularity, compatibility with smaller/medium grids, and enabling gradual build of new generating capacity matching the needs, IRIS has a large potential in the worldwide market.(author)

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. License - Budding yeast cDNA sequencing project | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us Budding yeast cDNA sequencing project License to Use This Database Last updated : 2010/02/15 You may use this databas...ional License described below. The Standard License specifies the license terms regarding the use of this database... and the requirements you must follow in using this database. The Additiona...n the Standard License. Standard License The Standard License for this database is the license specified in ...the Creative Commons Attribution-Share Alike 2.1 Japan . If you use data from this database

  6. Licensing of away-from-reactor (AFR) installations

    International Nuclear Information System (INIS)

    Gray, P.L.

    1980-01-01

    Storage of spent fuel at Away-From-Reactor (AFR) installations will allow reactors to continue to operate until reprocessing or other fuel disposal means are available. AFR installations must be licensed by the Nuclear Regulatory Commission (NRC). Although wide experience in licensing reactors exists, the licensing of an AFR installation is a relatively new activity. Only one has been licensed to date. This paper delineates the requirements for licensing an AFR installation and projects a licensing schedule. Because the NRC is developing specific AFR requirements, this schedule is based primarily on draft NRC documents. The major documents needed for an AFR license application are similar to those for a reactor. They include: a Safety Analysis Report (SAR), and Environmental Report (ER), safeguards and security plans, decommissioning plans, proposed technical specifications, and others. However, the licensing effort has one major difference in that for AFR installations it will be a one-step effort, with follow-up, rather than the two-step process used for reactors. The projected licensing schedule shows that the elapsed time between filing an application and issuance of a license will be about 32 months, assuming intervention. The legal procedural steps will determine the time schedule and will override considerations of technical complexity. A license could be issued in about 14 months in the absence of intervention

  7. 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...

  8. 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...

  9. 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

  10. 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...

  11. 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...

  12. Mock Site Licensing Demonstration Project. Final report

    International Nuclear Information System (INIS)

    Roop, R.D.

    1986-06-01

    The Mock Site Licensing Demonstration Project developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This report describes the development, contant, and usefulness of the siting simulation. The simulation was designed by Harvard University's Program on Negotiation; it can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions. In the first, participants negotiate the selection of siting criteria, and in the second, a preferred site for a facility is chosen from three candidate sites. The project sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation was conducted for persons involved in planning for LLW. It is concluded that the siting simulation can be useful in three ways: (1) as a tool for information dissemination, (2) as a vehicle that can foste communication among parties in conflict, and (3) as a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

  13. 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...

  14. 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

  15. 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...

  16. 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

  17. 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...

  18. 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...

  19. 18 CFR 4.106 - Standard terms and conditions of case-specific exemption from licensing.

    Science.gov (United States)

    2010-04-01

    ... LICENSES, PERMITS, EXEMPTIONS, AND DETERMINATION OF PROJECT COSTS Exemption of Small Hydroelectric Power... licensing. Any case-specific exemption from licensing granted for a small hydroelectric power project is... falsehoods were made by or on behalf of the applicant. (h) Article 8. Any exempted small hydroelectric power...

  20. Licensing aspects of the NPP Temelin IandC replacement project

    International Nuclear Information System (INIS)

    Karpeta, C.

    1997-01-01

    The objections raised against the original design of the instrumentation and control system of the Temelin nuclear power plant are summarized. The nuclear regulatory environment of the Czech Republic is described; the activities of the State Office for Nuclear Safety (SONS) are highlighted. The requirements underlying the licensing of the Temelin IandC replacement project are discussed in some detail. The licensing process adopted by SONS is to a certain degree computer-aided. A database has been developed by SONS; the three-layer structure of the database is described. (A.K.)

  1. 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...

  2. 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...

  3. 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...

  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. Outline for embedded topical license renewal industry perspective

    International Nuclear Information System (INIS)

    Gilchrist, Jacqueline

    1991-01-01

    This presentation describes the history of the project, selection of the Lead plant; project management, and project implementation, License renewal application contains: implementation plan; technical specifications and program changes; updated safety analysis report supplement; plant specific exemptions; environmental report update

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. Federal/State cooperation in the licensing of a nuclear power project. A joint licensing process between the US Nuclear Regulatory Commission and the Washington State Energy Facility Site Evaluation Council

    International Nuclear Information System (INIS)

    1984-05-01

    This report summarizes and documents a joint environmental review and licensing process established between the US Nuclear Regulatory Commission (NRC) and the Washington State Energy Facility Site Evaluation Council (EFSEC) in 1980-1983 for the Skagit/Hanford Nuclear Project (S/HNP). It documents the agreements made between the agencies to prepare a joint environmental impact statement responsive to the requirements of the National Environmental Policy Act of 1969 (NEPA) and the Washington State Environmental Policy Act. These agreements also established protocol to conduct joint public evidentiary hearings on matters of mutual jurisdiction, thereby reducing the duplication of effort and increasing the efficiency of the use of resources of federal and state governments and other entities involved in the process. This report may provide guidance and rationale to licensing bodies that may wish to adopt some of the procedures discussed in the report in the event that they become involved in the licensing of a nuclear power plant project. The history of the S/HNP and of the agreement processes are discussed. Discussions are provided on implementing the joint review process. A separate section is included which presents independent evaluations of the process by the applicant, NRC, and EFSEC

  12. 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...

  13. 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)

  14. 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)

  15. 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)

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. Unique Regulatory Approach for Licensing the Port Hope Remediation Project in Canada - 13315

    International Nuclear Information System (INIS)

    Kostova, M.; Howard, D.; Elder, P.

    2013-01-01

    The Port Hope remediation project is a part of a larger initiative of the Canadian Federal Government the Port Hope Area Initiative (PHAI) which is based upon a community proposal. The Government of Canada, through Natural Resources Canada (NRCan) is investing $1.28 billion over 10 years to clean up historic low-level radioactive waste in the Port Hope Area and to provide long-term safe management of the low-level radioactive wastes in the Port Hope Area. These wastes arose from the activities of a former Federal Crown Corporation (Eldorado Nuclear) and its private sector predecessors. In Canada, historic waste are defined as low-level radioactive waste that was managed in a manner no longer considered acceptable, but for which the original producer cannot reasonably be held responsible or no longer exists and for which the Federal Government has accepted responsibility. In Canada, under the current regulatory framework, the environmental remediation is not considered as a distinct phase of the nuclear cycle. The regulatory approach for dealing with existing sites contaminated with radioactive residues is defined on the basis of risk and application of existing regulations. A unique regulatory approach was taken by the Canadian Nuclear Safety Commission (CNSC) to address the various licensing issues and to set out the requirements for licensing of the Port Hope Project within the current regulatory framework. (authors)

  1. Unique Regulatory Approach for Licensing the Port Hope Remediation Project in Canada - 13315

    Energy Technology Data Exchange (ETDEWEB)

    Kostova, M.; Howard, D.; Elder, P. [Directorate of Nuclear Cycle and Facilities Regulation, Canadian Nuclear Safety Commission, 280, Slater Street, Ottawa, Ontario K1P 5S9 (Canada)

    2013-07-01

    The Port Hope remediation project is a part of a larger initiative of the Canadian Federal Government the Port Hope Area Initiative (PHAI) which is based upon a community proposal. The Government of Canada, through Natural Resources Canada (NRCan) is investing $1.28 billion over 10 years to clean up historic low-level radioactive waste in the Port Hope Area and to provide long-term safe management of the low-level radioactive wastes in the Port Hope Area. These wastes arose from the activities of a former Federal Crown Corporation (Eldorado Nuclear) and its private sector predecessors. In Canada, historic waste are defined as low-level radioactive waste that was managed in a manner no longer considered acceptable, but for which the original producer cannot reasonably be held responsible or no longer exists and for which the Federal Government has accepted responsibility. In Canada, under the current regulatory framework, the environmental remediation is not considered as a distinct phase of the nuclear cycle. The regulatory approach for dealing with existing sites contaminated with radioactive residues is defined on the basis of risk and application of existing regulations. A unique regulatory approach was taken by the Canadian Nuclear Safety Commission (CNSC) to address the various licensing issues and to set out the requirements for licensing of the Port Hope Project within the current regulatory framework. (authors)

  2. 33 CFR Appendix - List of FPC Standard Articles Forms Used in Permits and Licenses for Hydroelectric Projects

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 3 2010-07-01 2010-07-01 false List of FPC Standard Articles Forms Used in Permits and Licenses for Hydroelectric Projects Navigation and Navigable Waters CORPS OF... Forms Used in Permits and Licenses for Hydroelectric Projects The following FPC standard articles Forms...

  3. 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...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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...

  9. 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...

  10. 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...

  11. 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.

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. Technical Specifications, South Texas Project, Unit No. 1 (Docket No. 50-498): Appendix ''A'' to License No. NPF-76

    International Nuclear Information System (INIS)

    1988-03-01

    The South Texas Project, Unit No. 1, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public. This report is Appendix A to License No. NPF-76

  7. 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...

  8. 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...

  9. Systems engineering and the licensing of Small Modular Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kulesa, T., E-mail: tkulesa@us.ibm.com [IBM, Philidelphia, Pennsylvania (United States); Soderholm, K., E-mail: Kristiina.Soderholm@fortum.com [Fortum Power (Finland); Fechtelkotter, P., E-mail: pfech@us.ibm.com [IBM, Boston, Massacheusets (United States)

    2014-07-01

    Both global warming and the need for dependable sources of energy continue to make nuclear power generation an appealing option. But a history of cost overruns, project delays, and environmental disaster has pushed the industry to innovate and design a more flexible, scalable, and safe source of nuclear energy - the small modular reactor. Innovation in generation technology creates disruption in already complex licensing and regulatory processes. This paper discusses how the application of systems engineering and requirements management can help combat confusion, rework, and efficiency problems across the engineering and compliance life cycle. The paper is based on the PhD Dissertation 'Licensing Model Development for Small Modular Reactors (SMRs) - Focusing on Finnish Regulatory Framework', approved in 2013. The result of the study gives recommendations and tools to develop and optimize the licensing process for SMRs. The most important SMR-specific feature, in terms of licensing, is the modularity of the design. Here the modularity indicates multi-module SMR designs, which creates new challenges in the licensing process. Another feature impacting licensing feasibility is the plan to build many standardized power plants in series and use factory-fabricated modules to optimize the construction costs. SMR licensing challenges are under discussion in many international forums, such as World Nuclear Association Cooperation in Reactor Design Evaluation and Licensing Small Modular Reactor group (WNA CORDEL SMR) group and IAEA INPRO regulators' forum. This paper also presents an application of the new licensing process using Systems Engineering, Requirements Management, and Project Management practices and tools. (author)

  10. Systems engineering and the licensing of Small Modular Reactors

    International Nuclear Information System (INIS)

    Kulesa, T.; Soderholm, K.; Fechtelkotter, P.

    2014-01-01

    Both global warming and the need for dependable sources of energy continue to make nuclear power generation an appealing option. But a history of cost overruns, project delays, and environmental disaster has pushed the industry to innovate and design a more flexible, scalable, and safe source of nuclear energy - the small modular reactor. Innovation in generation technology creates disruption in already complex licensing and regulatory processes. This paper discusses how the application of systems engineering and requirements management can help combat confusion, rework, and efficiency problems across the engineering and compliance life cycle. The paper is based on the PhD Dissertation 'Licensing Model Development for Small Modular Reactors (SMRs) - Focusing on Finnish Regulatory Framework', approved in 2013. The result of the study gives recommendations and tools to develop and optimize the licensing process for SMRs. The most important SMR-specific feature, in terms of licensing, is the modularity of the design. Here the modularity indicates multi-module SMR designs, which creates new challenges in the licensing process. Another feature impacting licensing feasibility is the plan to build many standardized power plants in series and use factory-fabricated modules to optimize the construction costs. SMR licensing challenges are under discussion in many international forums, such as World Nuclear Association Cooperation in Reactor Design Evaluation and Licensing Small Modular Reactor group (WNA CORDEL SMR) group and IAEA INPRO regulators' forum. This paper also presents an application of the new licensing process using Systems Engineering, Requirements Management, and Project Management practices and tools. (author)

  11. 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...

  12. 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

  13. 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)

  14. 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)

  15. 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.

  16. 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...

  17. Nursing Manpower Licensed in Kentucky, 1979-1981. Kentucky Nursing Education Project.

    Science.gov (United States)

    Kentucky State Council on Higher Education, Frankfort.

    Data on nurses licensed in Kentucky for 1979-1981 are presented, as part of the Kentucky Nursing Education Project. Information is provided on: licensure status, home state/district/county, employment status, employment state/district/county, field of employment in nursing, position, highest educational level attained, age, sex, marital status,…

  18. 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

  19. Licensing schedule for away-from-reactor (AFR) spent fuel storage facilities

    International Nuclear Information System (INIS)

    Gray, P.L.

    1981-08-01

    The Nuclear Regulatory Commission has authority to issue licenses for Away-From-Reactor (AFR) installations for the storage of spent nuclear fuel. This report presents a detailed estimate of the time required to prosecute a licensing action. The projected licensing schedule shows that the elapsed time between filing an application and issuance of a license will be about 32 months, assuming intervention. The legal procedural steps will determine the time schedule and will override considerations of technical complexity. A license could be issued in about 14 months in the absence of intervention

  20. Optimized application of systems engineering to nuclear waste repository projects

    International Nuclear Information System (INIS)

    Miskimin, P.A.; Shepard, M.

    1986-01-01

    The purpose of this presentation is to describe a fully optimized application of systems engineering methods and philosophy to the management of a large nuclear waste repository project. Knowledge gained from actual experience with the use of the systems approach on two repository projects is incorporated in the material presented. The projects are currently evaluating the isolation performance of different geologic settings and are in different phases of maturity. Systems engineering methods were applied by the principal author at the Waste Isolation Pilot Plant (WIPP) in the form of a functional analysis. At the Basalt Waste Isolation Project (BWIP), the authors assisted the intergrating contractor with the development and application of systems engineering methods. Based on this experience and that acquired from other waste management projects, an optimized plan for applying systems engineering techniques was developed. The plan encompasses the following aspects: project organization, developing and defining requirements, assigning work responsibilities, evaluating system performance, quality assurance, controlling changes, enhancing licensability, optimizing project performance, and addressing regulatory issues. This information is presented in the form of a roadmap for the practical application of system engineering principles to a nuclear waste repository project

  1. 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...

  2. 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.)

  3. NRC Licensing Status Summary Report for NGNP

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-11-01

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

  4. 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...

  5. 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...

  6. Technology neutral licensing requirements: have we been successful?

    International Nuclear Information System (INIS)

    Jamieson, T.

    2009-01-01

    The Canadian Nuclear Safety Commission (CNSC) is Canada's nuclear regulator. In preparation for the licensing of the next generation of nuclear reactors in Canada, the CNSC has made major changes in its processes and procedures associated with all aspects of the licensing life cycle. These include: development of key regulatory documents outlining the CNSC expectations for the design and siting of new reactors; creation of applicant guidelines for completing licensing applications; creation of a comprehensive set of review guides, specifying how topics in applications are to be reviewed; performing pre-project design reviews for proposed new reactor technologies; and streamlining processes wherever possible, such as performing the environmental assessment and license to prepare site activities in parallel. The predicted workload associated with the nuclear renaissance in Canada is real. The CNSC is currently performing: 4 pre-project design reviews (for AECL's ACR-1000 and EC-6, Areva's EPR and Westinghouse's AP-1000), has received applications for 4 new builds (at Darlington, Bruce, Nanticoke and in Alberta) and is in the midst of performing the combined environmental assessment and license to prepare site phases for these sites. This is in addition to the work associated with: the licensing of new uranium mines; oversight of the existing reactor fleet; refurbishments at Bruce/Gentilly/Point Lepreau; license renewal for the NRU reactor; and oversight of our general client base of over 5000 licensees. In this presentation, experience to date with these new processes and procedures will be discussed, including: status of the current new build projects; anticipated new activities; lessons learned, especially the technology neutral approach; application to our other licensed activities, including non-power reactors; and work underway to further develop CNSC methods. Qualifications Needed to Design, Construct and Manufacture Nuclear Systems and Equipment, C. Voutsinos

  7. 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)

  8. 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)

  9. 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...

  10. 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...

  11. 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...

  12. 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...

  13. 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.

  14. 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

  15. 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...

  16. 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

  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 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...

  19. 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...

  20. 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.

  1. 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

  2. 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)

  3. 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

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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

  9. 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

  10. 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...

  11. 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...

  12. 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...

  13. 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.

  14. Project 2019 of Garona Nuclear power plant. First project to licensing renew more than 40 years in Spain

    International Nuclear Information System (INIS)

    Fernandez, R. A.; Torralbo, J. R.

    2004-01-01

    NUCLENOR has been developing lifetime management and modernisation activities at Santa Maria de Garona NPP since the end of the 80's and the plant is now in optimum technical conditions to continue in operation beyond its original lifetime planned in the design (40 years). In the USA, the country of origin of the project, a good number of power plants with a similar design, age and history to SMG are in the process of obtaining or have already obtained, a licensing extension of up to 60 years from the NRC. In Spain, the activities required for requesting a long-term operating licensing extension include the Ageing Assessment and Management of the plant systems, structures and components, in accordance with the american regulation 10CFR54, a Radiological Impact Study for the new operating period, and an Analysis of New Legislation, not included in the licensing bases and considered to be important to safety by the CSN. With a view to obtaining a renewal of the current operating permit for the period 2009-2019, NUCLENOR has launched the Proyecto 2019, which extends to technical and licensing aspects, as it involves all the company's personnel. (Author)

  15. 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...

  16. 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...

  17. 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

  18. 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)

  19. 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...

  20. 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

  1. 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.''

  2. 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...

  3. 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...

  4. 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...

  5. 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

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

    International Nuclear Information System (INIS)

    DiSalvo, R.; Zielenbach, W.

    1987-01-01

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

  7. 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

  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. Finnish experiences on licensing and using of programmable digital systems in nuclear power plants

    International Nuclear Information System (INIS)

    Haapanen, P.; Maskuniitty, M.; Heimburger, H.; Hall, L.E.; Manninen, T.

    1993-01-01

    Finnish utility companies, Imatran Voima Oy (IVO) and Teollisuuden Voima (TVO), and the licensing authority, the Finnish Centre for Radiation and Nuclear Safety (STUK), are preparing for a new nuclear power plant in Finland. Plant vendors are proposing programmable digital automation systems for both the safety-related and the operational I and C (instrumentation and control) systems in this new unit. Also in existing plant units the replacement of certain old analog systems with state-of-the-art digital ones will become necessary in the years to come. Licensing of programmable systems for safety critical applications requires a new approach due to the special properties and failure modes of these systems. The major difficulties seem to be in the assessment and quantification of software reliability. The Technical Research Centre of Finland has in co-operation with the authority and the utilities conducted a project (AJA) to develop domestically applicable licensing requirements, guidelines and practices. International standards, guidelines and licensing practices have been analyzed in order to specify national licensing requirements. The paper describes and discusses the findings and experiences of the AJA project so far. The experience in introducing advanced programmable digital control and computer systems in the operating nuclear power plants will be covered briefly. Although these systems are not safety-related but systems of more general interest regarding nuclear safety, some routines regarding the licensing of safety- related systems have been followed. In these backfitting and replacement projects some experience have been gained in how to license safety-related programmable systems. (Author) 31 refs., 2 figs

  10. 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

  11. 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.

  12. 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

  13. Project Surveillance and Maintenance Plan

    International Nuclear Information System (INIS)

    1985-09-01

    The Project Surveillance and Maintenance Plan (PSMP) describes the procedures that will be used by the US Department of Energy (DOE), or other agency as designated by the President to verify that inactive uranium tailings disposal facilities remain in compliance with licensing requirements and US Environmental Protection Agency (EPA) standards for remedial actions. The PSMP will be used as a guide for the development of individual Site Surveillance and Maintenance Plans (part of a license application) for each of the UMTRA Project sites. The PSMP is not intended to provide minimum requirements but rather to provide guidance in the selection of surveillance measures. For example, the plan acknowledges that ground-water monitoring may or may not be required and provides the [guidance] to make this decision. The Site Surveillance and Maintenance Plans (SSMPs) will form the basis for the licensing of the long-term surveillance and maintenance of each UMTRA Project site by the NRC. Therefore, the PSMP is a key milestone in the licensing process of all UMTRA Project sites. The Project Licensing Plan (DOE, 1984a) describes the licensing process. 11 refs., 22 figs., 8 tabs

  14. 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

  15. 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...

  16. 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

  17. 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...

  18. 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...

  19. Online driver's license renewal.

    Science.gov (United States)

    2015-09-01

    The Kentucky Department of Vehicle Regulation is exploring the possibility of developing and implementing online : drivers license renewal. The objective of this project was to: 1) evaluate online drivers license and REAL ID renewal : programs ...

  20. 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)

  1. 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.)

  2. Nebraska withdraws its intent to deny site license

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The state of Nebraska has withdrawn its notice of intent to deny the US Ecology (USE) license application for the proposed low-level radioactive waste disposal site in Boyd County, near Butte, Neb. On October 4, after review of USE's August 27 submittal of a revision to the boundaries of the proposed site, a letter from the state's Department of Health (DOH) and Department of Environmental Quality (DEQ) to John. H. DeOld, the USE project manager for the Central Interstate Compact's proposed LLW site, noted that open-quotes...we are hereby withdrawing the Notice of Intent to Deny License as a moot, and will conduct a substantive review of the reconfigured site for compliance with the applicable regulations.close quotes

  3. 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

  4. 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.

  5. 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.)

  6. Licensing of the OPAL reactor during construction and commissioning

    International Nuclear Information System (INIS)

    Summerfield, M.

    2007-01-01

    This paper presents a description of the licensing activities associated with the construction and commissioning of the Australian Nuclear Science and Technology Organisation's (ANSTO) OPAL reactor. It addresses the Construction Licence, the interface between ANSTO, INVAP (the contractor with responsibility for design and construction of the facility) and the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA, the Australian nuclear regulator) during the construction of OPAL, specific licensing issues that have arisen during the construction and commissioning process, and the Operating Licence Application. Particular emphasis will be given to the way in which the licensing process is integrated into the overall project program and the lessons learnt that may be of benefit to other licensees and regulators

  7. License renewal process

    International Nuclear Information System (INIS)

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

    2004-01-01

    The purpose of this paper is to provide information about license renewal process, as defined by Nuclear Regulatory Commission (NRC). The Atomic Energy Act and NRC regulations limit commercial power reactor licenses to an initial 40 years but also permit such licenses to be renewed. This original 40-year term for reactor licenses was based on economic and antitrust considerations not on limitations of nuclear technology. Due to this selected time period; however, some structures and components may have been engineered on the basis of an expected 40-year service life. The NRC has established a timely license renewal process and clear requirements codified in 10 CFR Part 51 and 10 CFR Part 54, that are needed to assure safe plant operation for extended plant life. The timely renewal of licenses for an additional 20 years, where appropriate to renew them, may be important to ensuring an adequate energy supply during the first half of the 21st Century. License renewal rests on the determination that currently operating plants continue to maintain adequate levels of safety, and over the plant's life, this level has been enhanced through maintenance of the licensing bases, with appropriate adjustments to address new information from industry operating experience. Additionally, NRC activities have provided ongoing assurance that the licensing bases will continue to provide an acceptable level of safety. This paper provides additional discussion of license renewal costs, as one of key elements in evaluation of license renewal justifiability. Including structure of costs, approximately value and two different approaches, conservative and typical. Current status and position of Nuclear Power Plant Krsko, related to license renewal process, will be briefly presented in this paper. NPP Krsko is designed based on NRC Regulations, so requirements from 10 CFR 51, and 10 CFR 54, are applicable to NPP Krsko, as well. Finally, this paper will give an overview of current status of

  8. 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)

  9. 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

  10. 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

  11. 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…

  12. 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

  13. 76 FR 57729 - Boundary Hydroelectric Project; Sullivan Creek Project; Notice of Availability of the Final...

    Science.gov (United States)

    2011-09-16

    ...-015] Boundary Hydroelectric Project; Sullivan Creek Project; Notice of Availability of the Final Environmental Impact Statement for the Relicensing of the Boundary Hydroelectric Project and the Surrender of... reviewed the applications for license for the Boundary Hydroelectric Project (FERC No. 2144-38), and the...

  14. 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

  15. ACR-1000TM Project - Licensing Opportunities and Challenges

    International Nuclear Information System (INIS)

    Popov, N.; Doerffer, S.; Ion, R.; Hopwood, J.

    2011-01-01

    Atomic Energy of Canada Limited (AECL) has developed the Advanced CANDU Reactor TM 1 1000 (ACR-1000 TM ) as an evolutionary advancement of the current CANDU 6 reactor. The ACR-1000 design has evolved from AECL's in-depth knowledge of CANDU TM systems, components, and materials, as well as the experience and feedback received from owners and operators of CANDU plants. The ACR design retains the proven strengths and features of CANDU reactors, while incorporating innovations and state-of-the-art technology. It also features major improvements in economics, inherent safety characteristics, and performance, while retaining the proven benefits of the CANDU family of nuclear power plants. To ensure that the ACR design is compliant with Canadian and international requirements, regulatory pre-project reviews of the ACR-1000 (and ACR-700 TM 1 with lower output) were conducted early in the design work. The regulatory feedback from these pre-project regulatory reviews helped AECL to better understand regulatory expectations in Canada, US and the UK, and to make further advancements and improvements in the ACR design to meet the Canadian and international regulatory requirements. This paper provides an overview of the key design features of the ACR-1000 reactor design, and summary of the pre-project reviews by those above-mentioned regulatory bodies, demonstrating opportunities and challenges in licensing process of and pointing to the importance of efficient vendor-regulator interaction. (author)

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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

  1. 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

  2. Estimation of expenses for low and intermediate level radioactive waste repository project in Croatia up to site license acquisition

    International Nuclear Information System (INIS)

    Schaller, A.; Lokner, V.; Subasic, D.

    2003-01-01

    The expenses needed for development of low- and intermediate level radioactive waste (LILW) repository project in Croatia include: (a) preliminary activities, (b) preparatory activities, and (c) preparing of environmental impact study. The first group of expenses are referring to the project leading activities, project plan updating, build-up of required infrastructure, preparing of licensing documentation, site investigations, data acquisition programme, pre-operational radio-ecological monitoring, modelling, safety analysis (first iteration) and public related activities. Preparatory activities are referring to purchasing of land for repository and preparatory activities for carrying out of on-site investigations, while third group of expenses are related to preparation and validation of Environmental impact study. It was found out that about 50 % of total expenses refer to build-up of infrastructure. Additional 25 % finances are related to radio-ecological monitoring, site investigations and development of calculations and models, while remaining 25 % of total estimated sum is expected to be spent for repository safety assessment, public relations, purchasing and preparing the on-site terrain for construction, etc. It was calculated 607 EUR per m3 of LILW to be needed up to site license acquisition. According to the world-wide practice, by extrapolating of additional expenses necessary for construction of the repository and acquisition of operational license, it comes out the cost of 1.723 EUR per m3 of LILW for shallow-ground and 2.412 EUR per m3 of LILW for tunnel repository. The estimated expenses for Croatia are within the span of expenses for the same purpose in the countries considered. Expected duration of the project performance up to acquisition of the site license is 4 years and 3 months. (author)

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

    Science.gov (United States)

    2012-04-10

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

  4. 76 FR 41308 - Strata Energy, Inc., Ross In Situ Recovery Uranium Project, Crook County, WY; Notice of Materials...

    Science.gov (United States)

    2011-07-13

    ..., Inc., Ross In Situ Recovery Uranium Project, Crook County, WY; Notice of Materials License Application...-4737, or by e-mail to [email protected] . The Ross In Situ Recovery Uranium Project License... source and byproduct materials license at its Ross In Situ Recovery Uranium Project site located in Crook...

  5. 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

  6. Impact of 2D/3D-project on LOCA-licensing analysis and reactor safety of PWRs

    International Nuclear Information System (INIS)

    Winkler, F.; Krebs, W.D.

    1989-01-01

    In the past LOCA-licensing analysis has included large conservatisms to compensate for the lack of detailed two phase flow and full scale experimental data. The 2D/3D-project was established to improve the data base in order to minimize the conservatisms required. The significant results and findings of the full scale Upper Plenum Test Facility (UPTF) and from the electrically heated Slab Core Test Facility (SCTF) were particularly useful for understanding the multidimensional phenomena in the primary system and in the core of a PWR. UPTF results were used to verify the TRAC-PF1 analysis of a PWR with combined ECC-Injection during the reflood phase of a large break-LOCA. Comparison of these results with results from classic licensing calculations quantifies the large safety margin in earlier licensing procedures and in reactor systems. (orig.)

  7. Current status of construction license of PEFP

    International Nuclear Information System (INIS)

    Kim, J. Y.; Cho, J. S.; Min, Y. S.; Nam, J. M.; Jeon, G. P.; Park, S. S.; Jo, J. H.; Song, I. T.

    2012-01-01

    Since 2010 August, PEFP(Proton Engineering Frontier Project)'s Proton Accelerator Research Center has been under construction so far. Generally, in advance of construction startup, many kinds of licenses should be acquired along with the types of construction works. To acquire a license in time, each item should meet the standard by the related regulation, including not only procedural but also content aspect. In the advent of internet era, electronic government system has been adopted in many governmental functions: So is the national construction license acquisition system. Owing to the system, both approval and documentation functions in licensing are integrated in online computer network which provide us simplification in process and easy accessibility to license data. However, aside from these construction licenses, other types of licenses still remain separately managed: Machinery, electric facilities, and so on. Moreover, all the licenses have the priority order and take legal term in processing. So, to avoid any time delay in license acquisition, we organized license hierarchy and found out the priority among them. Thereafter, according to their legal term in approval and acquisition, whole license acquisition schedule was arranged and we completed all the necessary licenses acquisition in time In this study, we summarize the current status of license acquisition on Proton Accelerator Research Center Construction, and manifest how they have been and will be managed systematically

  8. 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...

  9. 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...

  10. 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.

  11. 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

  12. 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

  13. The dispute over the social license for mining projects in La Rioja, Argentina

    Directory of Open Access Journals (Sweden)

    Mariana Sola Álvarez

    2013-11-01

    Full Text Available Since the beginning of this century, projects of transnational corporations design to extract -in a mega scale- gold, silver, copper, and molybdenum are back to interrogate Famatina Valley, located in the northwest of Argentina, in the province of La Rioja. The dispute that is generated around the "social license" of mining projects highlights features of policy matrix and local government backing for extractive activities. At the same time illustrates the content and the potentiality of social resistance. The power of veto from a network of neighbors assemblies and a highly mobilized community in critical moments of the conflict is framed in a process of resistance to mercantilization of commons that travels through Latin America.

  14. [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.

  15. 78 FR 17450 - Notice of Issuance of Materials License Renewal, Operating License SUA-1341, Uranium One USA, Inc...

    Science.gov (United States)

    2013-03-21

    ... License Renewal, Operating License SUA-1341, Uranium One USA, Inc., Willow Creek Uranium In Situ Recovery.... SUA- 1341 to Uranium One USA, Inc. (Uranium One) for its Willow Creek Uranium In Situ Recovery (ISR... Commission License No. SUA-1341 For Uranium One USA, Inc., Irigaray and Christensen Ranch Projects (Willow...

  16. 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...

  17. Regulatory systems-based licensing guidance documentation

    International Nuclear Information System (INIS)

    Delligatti, M.S.

    1991-01-01

    The US Nuclear Regulatory Commission (NRC) has developed a series of licensing guidance documents based on the regulatory requirements in Part 60 of Title 10 of the Code of Federal Regulations (10 CFR Part 60). This regulatory systems-based approach to licensing guidance documentation relies on the definition of the high-level waste repository in 10 CFR Part 60. A document which is important for the frame-work it gives to other programmatic licensing guidance is the Draft Regulatory Guide open-quotes Format and Content for the License Application for the High-Level Waste Repositoryclose quotes (FCRG). The FCRG describes a format and content acceptable to NRC for a high-level waste repository license application pursuant to the requirements of 10 CFR Part 60. Other licensing guidance documents will be compatible with the FCRG

  18. 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...

  19. 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

  20. 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.

  1. 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...

  2. 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

  3. Modern methods of project handling - lean management during the deconstruction of nuclear facilities as illustrated by the vitrification plant VEK

    International Nuclear Information System (INIS)

    Freund, Christina; Gentes, Sascha; Dux, Joachim; Reinelt, Joachim

    2011-01-01

    The authors describe the positive experiences from the project handling during the WAK deconstruction process including the implementation of the so called lean management that is supposed to optimize the timing and cost specific approaches. The practical application includes the planning, the licensing application and in case of licensing the realization of the project. Enhancement of transparency and information flow are reached by periodic last planner sessions. Time management and exact scheduling are central parts of the project handling. The contract partners, authorities and consultants are involved at an early state of the project. After shutdown of the vitrification plant VEK the planning for the deconstruction licensing application according to the atomic law have been started.

  4. 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...

  5. Considerations about the licensing process of special nuclear industrial facilities

    Energy Technology Data Exchange (ETDEWEB)

    Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2015-07-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  6. Considerations about the licensing process of special nuclear industrial facilities

    International Nuclear Information System (INIS)

    Talarico, M.A.; Melo, P.F. Frutuoso e

    2015-01-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  7. 76 FR 78628 - Copper Valley Electric Association, Inc.; Notice of Application and Applicant-Prepared EA...

    Science.gov (United States)

    2011-12-19

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13124-003] Copper Valley... Application: Major License. b. Project No.: P-13124-003. c. Date filed: August 30, 2011. d. Applicant: Copper.... 791 (a)-825(r). h. Applicant Contact: Robert A. Wilkinson, CEO, Copper Valley Electric Association...

  8. 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...

  9. 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...

  10. 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...

  11. 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...

  12. Licensing of ANSTO'S OPAL reactor during construction and commissioning

    International Nuclear Information System (INIS)

    Summerfield, M.W.; Ordonez, J.P.

    2006-01-01

    Full text: This paper presents a general description of the ongoing licensing activities associated with the construction and commissioning of the Australian Nuclear Science and Technology Organisation's (ANSTO) Open Pool Australian Light-water (OPAL) Reactor at their Lucas Heights site. It addresses the following aspects: The Construction Licence - what it is and what impact it had on the construction of the OPAL Reactor, specifically the various Construction Licence Conditions; The interface between ANSTO, INVAP and ARPANSA during the construction of the OPAL Reactor, particularly in relation to ARPANS Regulation 54; Specific licensing issues that have arisen during the construction and commissioning process and how they have been resolved; The Operating Licence Application - what it is and how it interfaces with the construction and commissioning of the OPAL Reactor. 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 the lessons learnt that may be of benefit to other licensees and regulators. Note that this paper is an update of a presentation given at IGORR10 and follows on from a paper previously presented at PNBC12 in October 2002

  13. Trends in CANDU licensing

    International Nuclear Information System (INIS)

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

    1997-01-01

    Modern utilities view nuclear power more and more as a commodity - it must compete 'today' with current alternatives to attract their investment. With its long construction times and large capital investment, nuclear plants are vulnerable to delays once they have been committed. There are two related issues. Where the purchaser and the regulator are experienced in CANDU, the thrust is a very practical one: to identify and resolve major licensing risks at a very early stage in the project. Thus for a Canadian project, the designer (AECL) and the prospective purchaser would deal directly with the AECB. However CANDU has also been successfully licensed in other countries, including Korea, Romania, Argentina, India and Pakistan. Each of these countries has its own regulatory agency responsible for licensing the plant. In addition, however, the foreign customer and regulator may seek input from the AECB, up to and including a statement of licensability in Canada; this is not normally needed for a ''repeat'' plant and/or if the customer is experienced in CANDU, but can be requested if the plant configuration has been modified significantly from an already-operating CANDU. It is thus the responsibility of the designer to initiate early discussions with the AECB so the foreign CANDU meets the expectations of its customers

  14. 18 CFR 4.101 - Applicability.

    Science.gov (United States)

    2010-04-01

    ... PROJECT COSTS Exemption of Small Hydroelectric Power Projects of 5 Megawatts or Less § 4.101 Applicability... the Federal Power Act (Act), including licensing, for small hydroelectric power projects as defined in... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Applicability. 4.101...

  15. 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

  16. The licensing practice on nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Moon, S. P.

    1994-01-01

    The evolution of Korean regulatory system has tightly coupled with development ot Korean nuclear power program. The nuclear power plant licensing has become a major regulatory function of the government when the construction of the Kori NPP Unit 1 started in early 1970s. During this period, domestic laws and regulations applicable to the licensing of NPP were not yet fully developed. Therefore the vendor countries' laws and regulations were applied as mandatory requirement. Beginning in the early 19808, component approach was used and contracts were awarded separately for major components of the plants, thus enabling more domestic industries to participate in the projects. The two-step licensing system was incorporated into the law. In the third phase from 1987, major efforts have been concentrated on the maximum participation of local industries. The overriding priority for selecting suppliers was the condition of higher nuclear technology transfer to Korea. The Korea Institute of Nuclear Safety (KINS) was established in 1990 as an independent regulatory expert organization

  17. 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)

  18. Managing the high level waste nuclear regulatory commission licensing process

    International Nuclear Information System (INIS)

    Baskin, K.P.

    1992-01-01

    This paper reports that the process for obtaining Nuclear Regulatory Commission permits for the high level waste storage facility is basically the same process commercial nuclear power plants followed to obtain construction permits and operating licenses for their facilities. Therefore, the experience from licensing commercial reactors can be applied to the high level waste facility. Proper management of the licensing process will be the key to the successful project. The management of the licensing process was categorized into four areas as follows: responsibility, organization, communication and documentation. Drawing on experience from nuclear power plant licensing and basic management principles, the management requirement for successfully accomplishing the project goals are discussed

  19. 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

  20. 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

  1. 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

  2. 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

  3. License renewal in the United States

    International Nuclear Information System (INIS)

    Brons, Jack

    2002-01-01

    Full text: Nuclear plants in the United States are licensed for 40 years, a length specified in the Atomic Energy Act of 1954, which laid out much of the regulatory basis for the commercial nuclear industry. The Act, however, made provision for license renewal. The original 40-year license period was chosen arbitrarily by the U.S. Congress because it was the typical period over which utilities recovered their investment in electricity generating plants. Nuclear plants, however, are subject to a rigorous program of Nuclear Regulatory Commission oversight, maintenance and equipment replacement. In effect, they must be in the same operating condition on the last day of their licenses as they were on the first. As the industry matured, it became apparent that there was no physical limitation on the continued operation of nuclear plants past 40 years. The industry turned its attention toward license renewal. When the issue was first raised, the NRC considered stringent process equivalent to seeking a new operating license for each plant. The complexity, length and cost of the process made it unlikely that many nuclear plants would seek license renewal. The nuclear industry worked successfully with NRC on the application of generic principles to license renewal, however, and in 1995, the NRC issued an efficient, tightly-focused rule that made license renewal a safe, viable option. To extend the operating license for a reactor, a company must demonstrate to the NRC that aging effects will be adequately managed during the renewal terms, thus ensuring equipment functionality. The rule allows licensees to apply for extensions of up to 20 years. The first license renewal application was filed in 1998 by the owner of the two-unit Calvert Cliffs plant. Shortly thereafter, an application was filed for the three-unit Oconee Nuclear Station. The NRC renewed the licenses for all five units in 2000, and since then, five more licenses have been renewed. The NRC has received 37

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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...

  10. 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)

  11. Environmental licensing issues for cogeneration plants

    International Nuclear Information System (INIS)

    Lipka, G.S.; Bibbo, R.V.

    1990-01-01

    The siting and licensing of cogeneration and independent power production (IPP) facilities is a complex process involving a number of interrelated engineering, economic, and environmental impact considerations. Important considerations for the siting and licensing of such facilities include air quality control and air quality impacts, water supply and wastewater disposal, and applicable noise criteria and noise impact considerations. Air quality control and air quality impact considerations for power generation facilities are commonly reviewed in the public forum, and most project developers are generally aware of the key air quality licensing issues. These issues include Best Available Control Technology (BACT) demonstration requirements, and air quality modeling requirements. BACT is a case-by-case determination, which causes uncertainty, in that developers have difficulty in projecting the cost of required control systems. Continuing developments in control technology may cause this problem to continue in the 1990's. Air quality modeling can be a problem in hilly terrain or within or near an urban environment, which could delay or preclude permitting of a new cogeneration or IPP facility in such locations. This paper discusses several environmental issues which are less frequently addressed than air quality issues, namely water/wastewater and noise. The design features of typical cogeneration and IPP facilities that affect water supply requirements, wastewater volumes, and noise emissions are discussed. Then, the site selection and impact review process are examined to identify typical constraints and trade-offs that can develop relative to water, wastewater, and noise issues. Trends in permit review requirements for water, wastewater, and noise are examined. Finally, innovative approaches that can be used to resolve potential development constraints for water, wastewater, and noise issues are discussed

  12. 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...

  13. Licensing of the Ignalina NPP

    International Nuclear Information System (INIS)

    Kutas, S.

    1999-01-01

    Since 1991 State Nuclear Power Safety Inspectorate (VATESI) has regulated Ignalina NPP operation by issuing annual operating permits. Those have been issued following submission of specified documents by the Ignalina NPP that have been reviewed by VATESI. However, according to to the procedures that are now established in the Law on Nuclear Energy and subordinate regulations the use of nuclear energy in the Republic of Lithuania is subject to strict licensing. Therefore a decision about the licence for continued operation of unit 1 should be taken. Licence would be granted by VATESI in cooperation with the Ministry of Health, Ministry of Environment and the institutions of local authorities. Ignalina NPP presented to the VATESI safety analysis report (SAR) with other documents. SAR was made mainly by foreign experts and financed by European Bank for Reconstruction and Development (EBRD). VATESI in this process is supported by western regulators. A special project LAP - Licensing Assistance Project was launched to help VATESI perform licensing according western practices

  14. Non-Power Reactor Operator Licensing Examiner Standards

    International Nuclear Information System (INIS)

    1994-06-01

    The Non-Power Reactor 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 Part 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, this standard will be revised periodically to accommodate comments and reflect new information or experience

  15. Small modular reactors: current status, economic aspects and licensing

    International Nuclear Information System (INIS)

    Zimbron E, E.; Puente E, F.

    2014-10-01

    Interest for nuclear energy had resurgence since the beginning of the new century. This was a consequence of the new world conditions and needs: increasing energy demands (mainly from developing countries), awareness of the importance of energetic security and the necessity of limiting carbon emissions. In this nuclear boom, Small Modular Reactors (SMRs) develop and start to consolidate as a viable option for the present energy market. Their modular characteristics, lower initial capital cost, passive safety features and their niche applications, situate them as a technology with various advantages. The following study will present and analysis that will help to comprehend the SMRs present status. Information will show planned reactors, reactors in construction and in operation, advantages and challenges of their implementation, relevant economic aspects and important licensing factors that need to be highlighted. The analysis showed that the SMR technology is still in an initial stage that could reach and important development point in the next ten years. In this period, many of the reactors that are in design stage or that are through their licensing process might be constructed and could be getting ready for a commercial status. On the other hand, it has been observed that there are two main economic factors that need to be considered for any SMRs implementation project. First, the costs (initial, operation, maintenance, fuel and decommissioning) and second their possible niche market applications. Additionally, it has been noted that the licensing process is one of the greatest challenges for SMR general development. Licensing is mainly related to topic such as Emergency Planning Zone, first-of-a-kind engineering, passive safety features, proliferation resistance, multiple module designs and staffing. Previous information will serve as a base for carrying out a feasibility assessment analysis for SMR in Mexico. This part will be the last section of the project

  16. Small modular reactors: current status, economic aspects and licensing

    Energy Technology Data Exchange (ETDEWEB)

    Zimbron E, E. [Instituto Tecnologico de Estudios Superiores de Monterrey, Campus Santa Fe, Av. Carlos Lazo No. 100, Santa Fe, 01389 Mexico D. F. (Mexico); Puente E, F., E-mail: erick.zimbron@gmail.com [ININ, Direccion de Investigacion Cientifica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    Interest for nuclear energy had resurgence since the beginning of the new century. This was a consequence of the new world conditions and needs: increasing energy demands (mainly from developing countries), awareness of the importance of energetic security and the necessity of limiting carbon emissions. In this nuclear boom, Small Modular Reactors (SMRs) develop and start to consolidate as a viable option for the present energy market. Their modular characteristics, lower initial capital cost, passive safety features and their niche applications, situate them as a technology with various advantages. The following study will present and analysis that will help to comprehend the SMRs present status. Information will show planned reactors, reactors in construction and in operation, advantages and challenges of their implementation, relevant economic aspects and important licensing factors that need to be highlighted. The analysis showed that the SMR technology is still in an initial stage that could reach and important development point in the next ten years. In this period, many of the reactors that are in design stage or that are through their licensing process might be constructed and could be getting ready for a commercial status. On the other hand, it has been observed that there are two main economic factors that need to be considered for any SMRs implementation project. First, the costs (initial, operation, maintenance, fuel and decommissioning) and second their possible niche market applications. Additionally, it has been noted that the licensing process is one of the greatest challenges for SMR general development. Licensing is mainly related to topic such as Emergency Planning Zone, first-of-a-kind engineering, passive safety features, proliferation resistance, multiple module designs and staffing. Previous information will serve as a base for carrying out a feasibility assessment analysis for SMR in Mexico. This part will be the last section of the project

  17. 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...

  18. 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

  19. 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...

  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. Licensing process for safety-critical software-based systems

    Energy Technology Data Exchange (ETDEWEB)

    Haapanen, P. [VTT Automation, Espoo (Finland); Korhonen, J. [VTT Electronics, Espoo (Finland); Pulkkinen, U. [VTT Automation, Espoo (Finland)

    2000-12-01

    System vendors nowadays propose software-based technology even for the most critical safety functions in nuclear power plants. Due to the nature of software faults and the way they cause system failures new methods are needed for the safety and reliability evaluation of these systems. In the research project 'Programmable automation systems in nuclear power plants (OHA)', financed together by the Radiation and Nuclear Safety Authority (STUK), the Ministry of Trade and Industry (KTM) and the Technical Research Centre of Finland (VTT), various safety assessment methods and tools for software based systems are developed and evaluated. As a part of the OHA-work a reference model for the licensing process for software-based safety automation systems is defined. The licensing process is defined as the set of interrelated activities whose purpose is to produce and assess evidence concerning the safety and reliability of the system/application to be licensed and to make the decision about the granting the construction and operation permissions based on this evidence. The parties of the licensing process are the authority, the licensee (the utility company), system vendors and their subcontractors and possible external independent assessors. The responsibility about the production of the evidence in first place lies at the licensee who in most cases rests heavily on the vendor expertise. The evaluation and gauging of the evidence is carried out by the authority (possibly using external experts), who also can acquire additional evidence by using their own (independent) methods and tools. Central issue in the licensing process is to combine the quality evidence about the system development process with the information acquired through tests, analyses and operational experience. The purpose of the licensing process described in this report is to act as a reference model both for the authority and the licensee when planning the licensing of individual applications

  2. Licensing process for safety-critical software-based systems

    International Nuclear Information System (INIS)

    Haapanen, P.; Korhonen, J.; Pulkkinen, U.

    2000-12-01

    System vendors nowadays propose software-based technology even for the most critical safety functions in nuclear power plants. Due to the nature of software faults and the way they cause system failures new methods are needed for the safety and reliability evaluation of these systems. In the research project 'Programmable automation systems in nuclear power plants (OHA)', financed together by the Radiation and Nuclear Safety Authority (STUK), the Ministry of Trade and Industry (KTM) and the Technical Research Centre of Finland (VTT), various safety assessment methods and tools for software based systems are developed and evaluated. As a part of the OHA-work a reference model for the licensing process for software-based safety automation systems is defined. The licensing process is defined as the set of interrelated activities whose purpose is to produce and assess evidence concerning the safety and reliability of the system/application to be licensed and to make the decision about the granting the construction and operation permissions based on this evidence. The parties of the licensing process are the authority, the licensee (the utility company), system vendors and their subcontractors and possible external independent assessors. The responsibility about the production of the evidence in first place lies at the licensee who in most cases rests heavily on the vendor expertise. The evaluation and gauging of the evidence is carried out by the authority (possibly using external experts), who also can acquire additional evidence by using their own (independent) methods and tools. Central issue in the licensing process is to combine the quality evidence about the system development process with the information acquired through tests, analyses and operational experience. The purpose of the licensing process described in this report is to act as a reference model both for the authority and the licensee when planning the licensing of individual applications. Many of the

  3. 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

  4. Use of the Legal-Institutional Analysis Model to assess hydropower licensing negotiations

    Science.gov (United States)

    Burkardt, N.; Lamb, B.L.; Lamb, B.L.; Garcia de Jalon, D.; Sabaton, C.; Souchon, Y.; Tamai, N.; Robinette, H.R.; Waddle, T.J.; Brinson, A.

    2003-01-01

    In the United States, the Federal Energy Regulatory Commission (FERC) is responsible for issuing or renewing licenses for hydropower projects owned and operated by power companies. During the licensing process, these companies are required to consult with agencies and other parties that are affected by project operating regimes. Typical participants include state and federal fish and wildlife agencies, environmental interest groups, and the FERC. One of the most difficult tasks facing participants is to reach agreement about what kinds of environmental conditions should be placed on license. Researchers at the United States Geological Survey developed a model to analyze the institutional context of natural resource disputes. The Legal-Institutional Analysis Model (LIAM) is a computerized model that allows an analyst to determine the likely behavior of each organization in a conflict. The model also analyzes the types and levels of negotiating power held by each organization. Researchers at the USGS have used the model in several cases involving hydropower license applications. To use the model, they facilitate workshops for stakeholder groups in order to develop a shared understanding of the likely obstacles and opportunities for successful resolution of the issues. This allows a systematic workshop analyses to develop strategies for successful negotiations, because they are able to better understand the negotiation problem and work more effectively with both their allies and their competitors.

  5. The licensing practice on nuclear power plants in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Moon, S P

    1994-12-31

    The evolution of Korean regulatory system has tightly coupled with development ot Korean nuclear power program. The nuclear power plant licensing has become a major regulatory function of the government when the construction of the Kori NPP Unit 1 started in early 1970s. During this period, domestic laws and regulations applicable to the licensing of NPP were not yet fully developed. Therefore the vendor countries` laws and regulations were applied as mandatory requirement. Beginning in the early 19808, component approach was used and contracts were awarded separately for major components of the plants, thus enabling more domestic industries to participate in the projects. The two-step licensing system was incorporated into the law. In the third phase from 1987, major efforts have been concentrated on the maximum participation of local industries. The overriding priority for selecting suppliers was the condition of higher nuclear technology transfer to Korea. The Korea Institute of Nuclear Safety (KINS) was established in 1990 as an independent regulatory expert organization. 1 tab., 4 figs.

  6. 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...

  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. Nuclear Regulatory Commission staff development of the license application review plan for a high-level radioactive waste repository

    International Nuclear Information System (INIS)

    Johnson, R.L.; Holonich, J.J.; Lee, M.P.; Delligatti, M.S.

    1993-01-01

    The Nuclear Regulatory Commission staff has recently started a new initiative to develop the License Application Review Plan (LARP) which the staff will use in its reviews of the U.S. Department of Energy's (DOE's) license application (LA) for a geologic repository for the disposal of high-level radioactive waste (HLW). This paper describes the staff's approach for developing the LARP, the development schedule and current status, the organization and content of the LARP, and the staff's LA review strategy. Therefore, it gives a preview of the draft LARP which will be made available in late 1993. It also describes how the LARP will be used as guidance to the staff in conducting reviews of regulatory and technical issues important to the licensing of a geologic repository. Finally, the benefits to the NRC staff, DOE, and other parties are discussed

  9. 47 CFR 25.117 - Modification of station license.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Modification of station license. 25.117 Section 25.117 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Applications and Licenses General Application Filing Requirements § 25.117...

  10. 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

  11. 9 CFR 2.6 - Annual license fees.

    Science.gov (United States)

    2010-01-01

    ... method used to calculate the license fee. All initial license and changed class of license fees must be... research facilities, dealers, exhibitors, retail pet stores, and persons for use as pets, directly or through an auction sale, by the dealer or applicant during his or her preceding business year (calendar or...

  12. 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

  13. Economics of license renewal in the U.S. - entergy's perspective

    International Nuclear Information System (INIS)

    Young, Garry G.

    2003-01-01

    License renewal of operating nuclear plants in the United States has become one of the most successful U.S. nuclear regulatory activities in the past few years. In 1995, the U.S. Nuclear Regulatory Commission (NRC) published a revised rule in 10 CFR Part 54 that provided the requirements for an operating nuclear plant to seek license renewal. At that time, many people believed that only a select few operating nuclear plants would pursue license renewal and that most plants would operate for no more than 40 years. By mid-2003, the owners of approximately 52% of the U.S. nuclear fleet of 103 operating nuclear plants have decided to pursue license renewal and more are expected to follow. This change in direction since 1995 can be attributed to the improving economics of U.S. nuclear power plant operation and to the improved regulatory process resulting from the 1995 revision to 10 CFR Part 54. In 2000, Entergy submitted a license renewal application for Arkansas Nuclear One, Unit 1 (ANO-1). This application was the third to be submitted to the NRC at a time when it was still unclear how successful the regulatory process might be. However, less than 17 months later, in June 2001, the NRC granted a renewed operating license for ANO-1 at a total cost of approximately $11 million. Due in part to the ANO-1 license renewal success, Entergy now has tentative plans to pursue license renewal for the entire fleet of operating nuclear power plants. Without license renewal, Entergy's current nuclear fleet capacity of approximately 9,000 MW(e) would begin to decline in 2012. With license renewal, Entergy's nuclear fleet capacity can remain in place until 2032. This projection does not include the expected improvements in capacity due to power uprate that is currently planned. The combination of power uprate and license renewal will add significant economic value to Entergy's nuclear fleet. One of the major factors in strong performance is capacity factor. In 1990, the average

  14. Current status of construction license of PEFP

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. Y.; Cho, J. S.; Min, Y. S.; Nam, J. M.; Jeon, G. P.; Park, S. S.; Jo, J. H.; Song, I. T. [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    Since 2010 August, PEFP(Proton Engineering Frontier Project)'s Proton Accelerator Research Center has been under construction so far. Generally, in advance of construction startup, many kinds of licenses should be acquired along with the types of construction works. To acquire a license in time, each item should meet the standard by the related regulation, including not only procedural but also content aspect. In the advent of internet era, electronic government system has been adopted in many governmental functions: So is the national construction license acquisition system. Owing to the system, both approval and documentation functions in licensing are integrated in online computer network which provide us simplification in process and easy accessibility to license data. However, aside from these construction licenses, other types of licenses still remain separately managed: Machinery, electric facilities, and so on. Moreover, all the licenses have the priority order and take legal term in processing. So, to avoid any time delay in license acquisition, we organized license hierarchy and found out the priority among them. Thereafter, according to their legal term in approval and acquisition, whole license acquisition schedule was arranged and we completed all the necessary licenses acquisition in time In this study, we summarize the current status of license acquisition on Proton Accelerator Research Center Construction, and manifest how they have been and will be managed systematically.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-05-01

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

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

    International Nuclear Information System (INIS)

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

    1997-05-01

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

  17. 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,...

  18. 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...

  19. 10 CFR 34.13 - Specific license for industrial radiography.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Specific license for industrial radiography. 34.13 Section 34.13 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION SAFETY... industrial radiography. An application for a specific license for the use of licensed material in industrial...

  20. 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

  1. 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

  2. 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)

  3. 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

  4. 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

  5. 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)

  6. 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)

  7. 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...

  8. 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...

  9. 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

  10. USNRC licensing process as related to nuclear criticality safety

    International Nuclear Information System (INIS)

    Ketzlach, N.

    1987-01-01

    The U.S. Code of Federal Regulations establishes procedures and criteria for the issuance of licenses to receive title to, own, acquire, deliver, receive, possess, use, and initially transfer special nuclear material; and establishes and provides for the terms and conditions upon which the Nuclear Regulatory Commission (NRC) will issue such licenses. Section 70.22 of the regulations, ''Contents of Applications'', requires that applications for licenses contain proposed procedures to avoid accidental conditions of criticality. These procedures are elements of a nuclear criticality safety program for operations with fissionable materials at fuels and materials facilities (i.e., fuel cycle facilities other than nuclear reactors) in which there exists a potential for criticality accidents. To assist the applicant in providing specific information needed for a nuclear criticality safety program in a license application, the NRC has issued regulatory guides. The NRC requirements for nuclear criticality safety include organizational, administrative, and technical requirements. For purely technical matters on nuclear criticality safety these guides endorse national standards. Others provide guidance on the standard format and content of license applications, guidance on evaluating radiological consequences of criticality accidents, or guidance for dealing with other radiation safety issues. (author)

  11. 78 FR 34090 - Lois Von Morganroth; Shiloh Warm Springs Ranch, LLC; Notice of Application for Transfer of...

    Science.gov (United States)

    2013-06-06

    ... Springs Ranch, LLC (transferee) filed an application for the transfer of license for the L & M Angus Ranch..., Idaho. Applicants seek Commission approval to transfer the license for the L & M Angus Ranch Project...

  12. 78 FR 29393 - University of Missouri-Columbia Facility Operating License No. R-103

    Science.gov (United States)

    2013-05-20

    ... Facility Operating License No. R-103 AGENCY: Nuclear Regulatory Commission. ACTION: License renewal... the renewal of Facility Operating License No. R-103 (``Application''), which currently authorizes the... application for the renewal of Facility Operating License No. R-103, which, currently authorizes the licensee...

  13. 47 CFR 25.113 - Station licenses and launch authority.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Station licenses and launch authority. 25.113 Section 25.113 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Applications and Licenses General Application Filing Requirements § 25.113 Station...

  14. LIRA - License Renewal Assistant an expert system advisor for system and component screening

    International Nuclear Information System (INIS)

    Wood, R.M.; DeLuke, R.J.; Lu, Yi; Catron, S.R.

    1992-01-01

    In developing a license renewal application for a nuclear power plant, it is necessary to identify those systems and components for which age-related degradation must be evaluated and addressed in detail. One approach, used in the Monticello Lead Plant project, is to screen all plant systems and components, based on criteria developed by the Nuclear Utility Management and Resources Council (NUMARC). This paper describes an expert system developed as an assistant in the application of the screening methodology. 4 refs., 5 figs., 1 tab

  15. TMI-related requirements for new operating licenses. Technical report

    International Nuclear Information System (INIS)

    1980-06-01

    There are four types of TMI-related requirements and actions approved by the Commission for new operating licenses: (1) those required to be completed by a license applicant prior to receiving a fuel-loading and low-power testing license, (2) those required to be completed by a license applicant prior to receiving a license to operate at appreciable power levels up to full power, (3) those the NRC will take prior to issuing a fuel-loading and low-power testing or a full-power operating license, and (4) those required to be completed by a licensee prior to a specified date. In this report, only those dated requirements that have already been issued are of interest. Other dated requirements are expected to be issued in the future as work progresses in accordance with the TMI Action Plan. This report summarizes the several parts of the list of TMI-related requirements approved by the Commission for new operating licenses

  16. 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...

  17. 75 FR 70226 - Mackay Bar Corporation; Notice of Authorization for Continued Project Operation

    Science.gov (United States)

    2010-11-17

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 3041-004] Mackay Bar... Mackay Bar Corporation, licensee for the Hettinger Hydroelectric Project, filed an Application to..., notice is hereby given that an annual license for Project No. 3041 is issued to the Mackay Bar...

  18. Non-Power Reactor Operator Licensing Examiner Standards. Revision 1

    International Nuclear Information System (INIS)

    1995-06-01

    The Non-Power Reactor 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

  19. Non-Power Reactor Operator Licensing Examiner Standards. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Non-Power Reactor 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.

  20. 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...

  1. 15 CFR 732.4 - Steps regarding License Exceptions.

    Science.gov (United States)

    2010-01-01

    ... General Prohibition Six (Embargo), consult part 746 of the EAR for applicable License Exceptions. (b... export or reexport is subject to General Prohibition Six (Embargo) for embargoed destinations, License...

  2. 48 CFR 1852.227-86 - Commercial computer software-Licensing.

    Science.gov (United States)

    2010-10-01

    .../contractor proposes its standard commercial software license, those applicable portions thereof consistent... its standard commercial software license until after this purchase order/contract has been issued, or at or after the time the computer software is delivered, such license shall nevertheless be deemed...

  3. Project Portfolio Management Applications Testing

    OpenAIRE

    Paul POCATILU

    2006-01-01

    Many IT companies are running project simultaneously. In order to achieve the best results, they have to group to the project in portfolios, and to use specific software that helps to manage them. Project portfolio management applications have a high degree of complexity and they are very important for the companies that are using it. This paper focuses on some characteristics of the testing process for project portfolio management applications

  4. Investment issues in nuclear plant license renewal

    International Nuclear Information System (INIS)

    Eynon, R.T.

    1999-01-01

    A method that determines the operating lives for existing nuclear power plants is discussed. These assumptions are the basis for projections of electricity supply through 2020 reported in the Energy Information Administration's (EIA's) Annual Energy Outlook 1999. To determine if plants will seek license renewal, one must first determine if they will be operating to the end of their current licenses. This determination is based on an economic test that assumes an investment of $150/kW will be required after 30 yr of operation for plants with older designs. This expenditure is intended to be equivalent to the cost that would be associated with any of several needs such as a one0time investment to replace aging equipment (steam generators), a series of investments to fix age-related degradation, increases in operating costs, or costs associated with decreased performance. This investment is compared with the cost of building and operating the lowest-cost new plant over the same 10-yr period. If a plant fails this test, it is assumed to be retired after 30 yr of service. All other plants are then considered candidates for license renewal. The method used to determine if it is economic to apply for license renewal and operate plants for an additional 20 yr is to assume that plants face an investment of $250 million after 40 yr of operation to refurbish aging components. This investment is compared with the lowest-cost new plant alternative evaluated over the same 20 yr that the nuclear plant would operate. If the nuclear plant is the lowest cost option, it is projected to continue to operate. EIA projects that it would be economic to extend the operating licenses for 3.7 GW of capacity (6 units)

  5. 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)

  6. Project Portfolio Management Applications Testing

    Directory of Open Access Journals (Sweden)

    Paul POCATILU

    2006-01-01

    Full Text Available Many IT companies are running project simultaneously. In order to achieve the best results, they have to group to the project in portfolios, and to use specific software that helps to manage them. Project portfolio management applications have a high degree of complexity and they are very important for the companies that are using it. This paper focuses on some characteristics of the testing process for project portfolio management applications

  7. Motorcycle Training for California Driver Licensing Personnel. Final Report.

    Science.gov (United States)

    California State Dept. of Motor Vehicles, Sacramento.

    The development of a 6-hour motorcycle course of instruction for personnel responsible for motorcycle licensing is described in this project report. The primary goals are stated and include (1) training driver licensing personnel in motorcycle safety and principles of operation, and (2) purchasing and installing appropriate motorcycle skill…

  8. 77 FR 48130 - Prospective Grant of Exclusive Patent License

    Science.gov (United States)

    2012-08-13

    ... Exclusive Patent License AGENCY: National Institute of Standards and Technology, Commerce. ACTION: Notice of prospective grant of exclusive patent license. SUMMARY: This is a notice in accordance with 35 U.S.C. 209(e... Provisional Application for Patent Application No. 61,638,362 titled ``Flow Cytometer Systems and Associated...

  9. 77 FR 47619 - Alcoa Power Generating Inc.; Brookfield Smoky Mountain Hydropower LLC; Notice of Application for...

    Science.gov (United States)

    2012-08-09

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2169-104] Alcoa Power Generating Inc.; Brookfield Smoky Mountain Hydropower LLC; Notice of Application for Transfer of License, and... Brookfield Smoky Mountain Hydropower LLC (transferee) filed an application for the transfer of license for...

  10. 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...

  11. 76 FR 67178 - Wells Hydroelectric Project; Notice of Availability of the Final Environmental Impact Statement...

    Science.gov (United States)

    2011-10-31

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2149-152] Wells Hydroelectric Project; Notice of Availability of the Final Environmental Impact Statement for the Wells... application for license for the Wells Hydroelectric Project (FERC No. 2149), located on the Columbia River in...

  12. 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

  13. 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)

  14. The permissibility of power plants and other large-scale projects outside densely populated areas from the point of view of planning legislation

    International Nuclear Information System (INIS)

    Hoppe, W.

    1978-01-01

    For the licensing of power plants, nuclear power plants and other industrial large projects, the question of the building law admissibility gains more and more importance in the licensing procedure. According to paragraph 6 of the Fed. Immission Protection, it is not only necessary that immission protection duties of the operator of plants which are subject to licensing are fulfilled, but other public law regulations must be in correspondance with the construction and operation of the plant. In this connection, the planning law admissibility of the project must also be examined. This is also valid for nuclear power plants. In the practical application of licensing such plants are treated in different ways, as far as terms of building planning are concerned. Some licensing authorities regard them as priviledged outskirts projects, others demand a zoning plan of the community. The author pleads for such large projects to be licensed only on the basis of a zoning plan set up by the community. (orig.) [de

  15. 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

  16. Class I structures license renewal industry report; revision 1. Final report

    International Nuclear Information System (INIS)

    Deng, D.; Renfro, J.; Statton, J.

    1994-07-01

    The U.S. nuclear power industry, through coordination by the Nuclear Management and Resources Council (NUMARC), and sponsorship by the U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), has evaluated age-related degradation effects for a number of major plant systems, structures, and components, in the license renewal technical Industry Reports (IRs). License renewal applicants may choose to reference these IRs in support of their plant-specific license renewal applications, as an equivalent to the integrated plant assessment provisions of the license renewal rule (10 CFR Part 54). This IR provides the technical basis for license renewal for U.S. nuclear power plant Class I structures, with the IR evaluating which structures are Class I. Seventeen structures are explicitly described and evaluated in this IR. These structures are not necessarily classified as Class I at all plants, therefore the license renewal applicant should consult this IR for correct identification

  17. 46 CFR 515.14 - Issuance and use of license.

    Science.gov (United States)

    2010-10-01

    ... will issue a license only in the name of the applicant, whether the applicant is a sole proprietorship, a partnership, or a corporation. A license issued to a sole proprietor doing business under a trade name shall be in the name of the sole proprietor, indicating the trade name under which the licensee...

  18. 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

  19. Capital Projects Application (CPA)

    Data.gov (United States)

    General Services Administration — Capital Projects application (CPA) provides users with the ability to maintain project related financial data for Budget Activity (BA) 51, 55, 64, 01, 02, 03, 04....

  20. 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

  1. 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

  2. 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

  3. 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

  4. May compact storage facilities be licensed

    International Nuclear Information System (INIS)

    Gleim, A.; Winter, G.

    1980-01-01

    The authors examine as potential statements fo fact for licensing so-called compact storage facilities for spent fuel elements Sec. 6 to 9c of the German Atomic Energy Act and Sec. 4 of the German Radiation Protection Ordinance. They find that none of these provisions were applicable to compact stroage facilities. In particular, the storage of spent fuel elements was no storage of nuclear fuels licensable under Sec. 6 of the Atomic Energy Act, because Sec. 6 did not cover spent fuel elements. Also in the other wording of the Atomic Energy Act there was no provision, which could be used as a statement of fact for licensing compact storage facilities. Such facilities could not be licensed and, for that reason, were not permitted. (IVR) [de

  5. 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

  6. 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

  7. Cost and risk reduction using upfront licensing in Canada. Annex 15

    International Nuclear Information System (INIS)

    Snell, V.G.

    2002-01-01

    The paper summarizes the use of 'up-front' licensing in Canada - how licensing requirements are defined, and met - in advance of a project commitment. The approach to licensing in Canada has allowed flexibility in development of new designs. Since licensing was originally risk-based, and current regulatory policy allows cost-benefit considerations as part of the decision making, risk can be and should be used in novel circumstances as a licensing tool. Since the licensing framework is non-prescriptive, innovative approaches to design can be introduced and dispositioned without changing the legal structure. This flexibility has been used in several up-front licensing reviews: a small urban heating reactor, repeat CANDU 6 generating station units, and the single unit CANDU 9 generating station. In the future we expect to apply it to advanced designs, as an essential part of risk reduction and customer confidence in the product. The important lessons learned in Canada include: Up-front licensing is essential to reduce the risk of licensing-related delays once a project has been committed. It requires a significant investment in time and effort from both the designer and the regulator; The most effective scope for up-front licensing is for the regulator to thoroughly assess novel concepts, test the design against changed domestic requirements, and follow-up on known difficult areas; and for the designer to ensure foreign requirements are incorporated. There is little benefit in certifying the design in detail; Although it would be satisfying to have legally-binding certification, in the end there can be no legal obligation on the regulator, and agreement is pursued on the basis of good faith that the regulator will not make arbitrary decisions and that the designer will meet agreed targets or requirements; In almost all circumstances, issues will arise that are beyond the current 'rules', however expressed. Rather than rushing to create new rules, one reaches a

  8. NRC licensing requirements: DOD options

    International Nuclear Information System (INIS)

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

    1982-09-01

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

  9. 45 CFR 1321.75 - Licenses and safety.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 4 2010-10-01 2010-10-01 false Licenses and safety. 1321.75 Section 1321.75... AND COMMUNITY PROGRAMS ON AGING Service Requirements § 1321.75 Licenses and safety. The State shall... that the facility complies with all applicable State and local health, fire, safety, building, zoning...

  10. 76 FR 57720 - Intent To Grant an Exclusive Patent License

    Science.gov (United States)

    2011-09-16

    ... DEPARTMENT OF DEFENSE Department of the Air Force Intent To Grant an Exclusive Patent License... in: U.S. Patent Application No. 12/932,341, filed on February 23, 2011, entitled ``Resin-Based... INFORMATION CONTACT: An exclusive license for the invention described in this patent application will be...

  11. MEX04/058 supporting the license renewal of the LVNPP

    International Nuclear Information System (INIS)

    Diaz, A.; Arganis, C.; Viais, J.; Mendoza, G.; Lucatero, M. A.; Contreras, A.

    2010-10-01

    Nuclear power plants in the United States are authorized to operate for 40 years. However, this 40-year period was chosen based on economic considerations and not on technological restrictions or safety aspects. In general, the operation of equipment, systems and components in a nuclear power plant is subject to rigorous maintenance and inspection monitoring under strict surveillance programs throughout their life. In fact, according to the Nuclear Energy Institute, in December 2009, 59 nuclear power plants in the United States had already reached the 40 years of the original operating license and carried out their renewal process, extending their operation for up to 20 more years. These 59 nuclear power plants carried out their renewal process, basing their operation mainly on safety reviews that validated the good working order of systems, structures and components, meeting the technical specifications required, as well as complying with the specific safety provisions for prolonging the use of a operating license. The owner is responsible for showing the Regulatory Agency that it is capable of effectively managing the aging of the systems, structures and components,guaranteeing their good working order during the renewal period. In the specific case of Mexico, Unit 1 of the Laguna Verde Nuclear Power Plant (LVNPP) has an original 30-year license, with almost 20 years of proper operation, for which, in order to request a license extension, it is necessary to begin management activities, which allow for constituting and submitting the license renewal application to the Regulatory Agency in order to continue its commercial operation. This paper presents some of most important activities carried out by Instituto Nacional de Investigaciones Nucleares and LVNPP in the international project MEX04/058, related to Plant Life Management as a support of the beginning of plant license renewal process. (Author)

  12. 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...

  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. 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

  15. Nuclear Power 2010 Program Dominion Virginia Power Cooperative Project U.S. Department of Energy Cooperative Agreement DE-FC07-05ID14635 Construction and Operating License Demonstration Project Final Report

    International Nuclear Information System (INIS)

    Grecheck, Eugene S.; Batalo, David P.

    2010-01-01

    This report serves to summarize the major activities completed as part of Virginia Electric and Power Company's North Anna construction and operating license demonstration project with DOE. Project successes, lessons learned, and suggestions for improvement are discussed. Objectives of the North Anna COL project included preparation and submittal of a COLA to the USNRC incorporating ESBWR technology for a third unit a the North Anna Power Station site, support for the NRC review process and mandatory hearing, obtaining NRC approval of the COLA and issuance of a COL, and development of a business case necessary to support a decision on building a new nuclear power plant at the North Anna site.

  16. 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

  17. 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

  18. Licensing experience of the HTR-10 test reactor

    International Nuclear Information System (INIS)

    Sun, Y.; Xu, Y.

    1996-01-01

    A 10MW high temperature gas-cooled test reactor (HTR-10) is now being projected by the Institute of Nuclear Energy Technology within China's National High Technology Programme. The Construction Permit of HTR-10 was issued by the Chinese nuclear licensing authority around the end of 1994 after a period of about one year of safety review of the reactor design. HTR-10 is the first high temperature gas-cooled reactor (HTGR) to be constructed in China. The purpose of this test reactor project is to test and demonstrate the technology and safety features of the advanced modular high temperature reactor design. The reactor uses spherical fuel elements with coated fuel particles. The reactor unit and the steam generator unit are arranged in a ''side-by-side'' way. Maximum fuel temperature under the accident condition of a complete loss of coolant is limited to values much lower than the safety limit set for the fuel element. Since the philosophy of the technical and safety design of HTR-10 comes from the high temperature modular reactor design, the reactor is also called the Test Module. HTR-10 represents among others also a licensing challenge. On the one side, it is the first helium reactor in China, and there are less licensing experiences both for the regulator and for the designer. On the other side, the reactor design incorporates many advanced design features in the direction of passive or inherent safety, and it is presently a world-wide issue how to treat properly the passive or inherent safety design features in the licensing safety review. In this presentation, the licensing criteria of HTR-10 are discussed. The organization and activities of the safety review for the construction permit licensing are described. Some of the main safety issues in the licensing procedure are addressed. Among these are, for example, fuel element behaviour, source term, safety classification of systems and components, containment design. The licensing experiences of HTR-10 are of

  19. The DIALOGUE project: The right decision? A sociological evaluation of the project

    International Nuclear Information System (INIS)

    Sundqvist, G.

    1993-11-01

    The DIALOGUE project has been conducted by the Swedish Nuclear Power Inspectorate (SKI) since 1990. The aim of the project was to stimulate a dialogue between different interest groups within Sweden. The purpose of this dialogue was to establish a licensing process, prior to a future licensing of a repository for spent nuclear waste, in which several of the parties involved are reasonably confident. The DIALOGUE project was carried out with the participation of other government agencies, municipalities and environmental groups and was headed by the former chairman of the National Licensing Board for Environmental Protection

  20. Licensing activities for the partial decommissioning of IRT-2000 research reactor in Sofia

    International Nuclear Information System (INIS)

    Apostolov, T.; Ilieva, Kr.; Papukchiev, A.; Kalchev, B.

    2001-01-01

    The project for refurbishment of IRT-2000 research reactor in Sofia into low-power reactor (200 kW) is based on the retention of some IRT-2000 buildings, facilities and equipment. The activities, which determine the partial decommissioning should be realized in accordance with preliminary developed licensing documents as General Plan, Safety Analysis Report and Environment Impact assessment Report. The goal of these documents is to provide and guarantee safe and effective activities with radioactive materials, to define strictly the dismantling procedures, and in the same time to minimize their influence on the environment. The Technical Tasks for General Plan, Safety Analysis Report and Environment Impact Assessment Report have been prepared and will be presented as preliminary licensing documents to the National Regulatory Body for approval before their application. A Quality Management system is being developed nowadays at INRNE. After its certification some requirements of the regulatory body will be completed. This certified QA system is a major part of the licensing procedure for the reconstruction of IRT-2000 research reactor. (author)

  1. Application of the graded management approach to Battelle's nuclear project

    International Nuclear Information System (INIS)

    Voth, C.B.

    1996-01-01

    Battelle's graded management approach provides an effective and efficient method to perform the Battelle Columbus Laboratories Decommissioning Project (BCLDP). The project is managed by Battelle under their US Nuclear Regulatory Commission (NRC) license but is partially funded by the US Department of Energy (DOE) on a cost-shared basis. Battelle's graded management approach adheres to the regulations and orders governing the BCLDP by the interaction of various plans, procedures, permits, and work instructions. By independent assessment, quality control, and worker training, Battelle has been able to establish a cost-effective approach to performing work and, at the same time, have a controlled checks and balance system to assure the proper safety considerations and project particulars are taken into account

  2. Advanced Engineering Environment FY09/10 pilot project.

    Energy Technology Data Exchange (ETDEWEB)

    Lamph, Jane Ann; Kiba, Grant W.; Pomplun, Alan R.; Dutra, Edward G.; Sego, Abraham L.

    2010-06-01

    The Advanced Engineering Environment (AEE) project identifies emerging engineering environment tools and assesses their value to Sandia National Laboratories and our partners in the Nuclear Security Enterprise (NSE) by testing them in our design environment. This project accomplished several pilot activities, including: the preliminary definition of an engineering bill of materials (BOM) based product structure in the Windchill PDMLink 9.0 application; an evaluation of Mentor Graphics Data Management System (DMS) application for electrical computer-aided design (ECAD) library administration; and implementation and documentation of a Windchill 9.1 application upgrade. The project also supported the migration of legacy data from existing corporate product lifecycle management systems into new classified and unclassified Windchill PDMLink 9.0 systems. The project included two infrastructure modernization efforts: the replacement of two aging AEE development servers for reliable platforms for ongoing AEE project work; and the replacement of four critical application and license servers that support design and engineering work at the Sandia National Laboratories/California site.

  3. 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...

  4. 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...

  5. Nuclear Power 2010 Program Dominion Virginia Power Cooperative Project U.S. Department of Energy Cooperative Agreement DE-FC07-05ID14635 Construction and Operating License Demonstration Project Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Eugene S. Grecheck

    2010-11-30

    This report serves to summarize the major activities completed as part of Virginia Electric and Power Company's North Anna construction and operating license demonstration project with DOE. Project successes, lessons learned, and suggestions for improvement are discussed. Objectives of the North Anna COL project included preparation and submittal of a COLA to the USNRC incorporating ESBWR technology for a third unit a the North Anna Power Station site, support for the NRC review process and mandatory hearing, obtaining NRC approval of the COLA and issuance of a COL, and development of a business case necessary to support a decision on building a new nuclear power plant at the North Anna site.

  6. Licensing of HTGRs in the United States

    International Nuclear Information System (INIS)

    Fisher, C.R.; Orvis, D.D.

    1981-01-01

    The licensing history of the high-temperature gas-cooled reactor (HTGR) in the United States is given historical perspective. The experience began with the licensing of the Peach Bottom Atomic Power Station and extends to the continuing experience at the Fort St. Vrain Nuclear Generating Station. Additional experience was obtained from the licensing reviews in the mid-1970s of the large HTGR plants that were to be built by Philadelphia Electric Company and Delmarva Power and Light. Also, information was provided by the licensing review of the General Atomic standard plant by the U.S. Nuclear Regulatory Commission (NRC) at about the same time. These experiences are summarized in terms of the principal design criteria that were required by the regulatory authority for each project. These criteria include specification of the design basis accidents that were postulated for the plant safety analysis. Several technical issues raised by the NRC during their review of the large HTGR are presented. (author)

  7. Licensing of HTGRs in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Fisher, C. R.; Orvis, D. D. [General Atomic Co., San Diego, CA (USA)

    1981-01-15

    The licensing history of the high-temperature gas-cooled reactor (HTGR) in the United States is given historical perspective. The experience began with the licensing of the Peach Bottom Atomic Power Station and extends to the continuing experience at the Fort St. Vrain Nuclear Generating Station. Additional experience was obtained from the licensing reviews in the mid-1970s of the large HTGR plants that were to be built by Philadelphia Electric Company and Delmarva Power and Light. Also, information was provided by the licensing review of the General Atomic standard plant by the U.S. Nuclear Regulatory Commission (NRC) at about the same time. These experiences are summarized in terms of the principal design criteria that were required by the regulatory authority for each project. These criteria include specification of the design basis accidents that were postulated for the plant safety analysis. Several technical issues raised by the NRC during their review of the large HTGR are presented.

  8. Roundtable discussion: Materials management issues supporting licensing renewal

    International Nuclear Information System (INIS)

    1991-01-01

    The purpose of this technical session is to discussion the relationships between nuclear materials management/procurement engineering and plant license renewal. The basis for the discussion is DG-1009 'Standard format and content of technical information for applications to renew nuclear power plant operating licenses', dated 12/90

  9. 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.

  10. 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

  11. 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

  12. Analyses for licensing of new fuel types at Paks NPP

    International Nuclear Information System (INIS)

    Kereszturi, A.; Bogatyr, S.; Miko, S.; Nemes, I.

    2003-01-01

    In the last years Paks NPP initiated several projects aiming at the introduction of new fuel types and resulting in more economic fuel cycles. The motivations, the reasons, and the economic consequences of the above modifications are detailed. The application of a new fuel type requires the renewal of the relevant chapters of the Safety Analysis Report. The fulfilment of fuel design basis requirements, to be summarised briefly also in the paper, must be investigated during normal and accidental conditions. The characteristics of the different codes, the data transfer between them are detailed. After, the cases of the Normal Operation, Anticipated Operation Occurrence, and the Postulated Accidents, judged as the most relevant ones in case of fuel modifications, are overviewed. In the last part, selected examples of the licensing calculations, performed by the above tools are presented. In conclusion, modifications of the WWER fuel, namely increased enrichment, application of burnable fuel pins, modified geometry make more economic fuel cycles (larger discharge burnup, power up-rate, reduced pressure vessel fluence) are possible. The further step (increased enrichment, burnable poison) of the fuel modernisation at NPP Paks is necessary for more economic fuel cycles and fuel consuming. A sound basis of licensing methodology, safety analysis, and necessary computer codes for the WWER fuel modernisation is available

  13. 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)

  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. 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...

  16. 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...

  17. 78 FR 41390 - Pershing County Water Conservation District; Notice of Application Tendered for Filing with the...

    Science.gov (United States)

    2013-07-10

    ... Water Conservation District; Notice of Application Tendered for Filing with the Commission and... License. b. Project No.: 14327-000. c. Date filed: June 26, 2013. d. Applicant: Pershing County Water Conservation District. e. Name of Project: Humboldt River Hydro Power Project. f. Location: At the existing U.S...

  18. 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

  19. Improving the effectiveness of impact assessment pertaining to Indigenous peoples in the Brazilian environmental licensing procedure

    International Nuclear Information System (INIS)

    Hanna, Philippe; Vanclay, Frank; Langdon, Esther Jean; Arts, Jos

    2014-01-01

    The number of environmental licence applications for projects affecting Indigenous peoples in Brazil has increased since the implementation of a major infrastructure program (Programa de Aceleração do Crescimento) in 2007. This increase has caused problems for Brazilian agencies involved in environmental licensing procedures (IBAMA, FUNAI and others). We analyze the Brazilian environmental licensing procedure for situations involving Indigenous peoples, Maroons (Quilombolas) or other traditional communities in order to identify potential improvements for Brazil and potentially other countries. Although Brazilian procedures are consistent with international best practice in environmental licensing, in practice social impacts are inadequately addressed, mitigation measures are poorly implemented, and there is a lack of enforcement and compliance. The paper is based on document analysis and interviews with key actors in governmental and non-governmental organizations and Indigenous leaders. We suggest that Free, Prior and Informed Consent (FPIC) processes need to be conducted at the earliest stages of project planning, and that Indigenous peoples should actively participate in impact assessment, monitoring and evaluation processes. In order to achieve a social licence to operate, there needs to be full recognition of traditional knowledge and acceptance of Indigenous values and concepts. We also recommend increased involvement of social experts and mediators as well as improved accountability, enforcement and grievance mechanisms in the licensing process. - Highlights: • The Brazilian environmental licensing system needs to address social impacts better. • Communities need to be consulted at the earliest stage possible. • Indigenous peoples need to be invited to participate in impact assessment teams. • Independent Indigenous committees to monitor implementation of mitigation measures. • Accountability, enforcement and grievance mechanisms need to be

  20. Improving the effectiveness of impact assessment pertaining to Indigenous peoples in the Brazilian environmental licensing procedure

    Energy Technology Data Exchange (ETDEWEB)

    Hanna, Philippe [Department of Cultural Geography, Faculty of Spatial Sciences, University of Groningen, PO Box 800, 9700 AV Groningen (Netherlands); Vanclay, Frank, E-mail: frank.vanclay@rug.nl [Department of Cultural Geography, Faculty of Spatial Sciences, University of Groningen, PO Box 800, 9700 AV Groningen (Netherlands); Langdon, Esther Jean [Department of Anthropology, Center for Philosophy and Human Sciences, Federal University of Santa Catarina PO Box 5104, 88040-970, Florianópolis, SC (Brazil); Arts, Jos [Department of Planning, Faculty of Spatial Sciences, University of Groningen, PO Box 800, 9700 AV Groningen (Netherlands)

    2014-04-01

    The number of environmental licence applications for projects affecting Indigenous peoples in Brazil has increased since the implementation of a major infrastructure program (Programa de Aceleração do Crescimento) in 2007. This increase has caused problems for Brazilian agencies involved in environmental licensing procedures (IBAMA, FUNAI and others). We analyze the Brazilian environmental licensing procedure for situations involving Indigenous peoples, Maroons (Quilombolas) or other traditional communities in order to identify potential improvements for Brazil and potentially other countries. Although Brazilian procedures are consistent with international best practice in environmental licensing, in practice social impacts are inadequately addressed, mitigation measures are poorly implemented, and there is a lack of enforcement and compliance. The paper is based on document analysis and interviews with key actors in governmental and non-governmental organizations and Indigenous leaders. We suggest that Free, Prior and Informed Consent (FPIC) processes need to be conducted at the earliest stages of project planning, and that Indigenous peoples should actively participate in impact assessment, monitoring and evaluation processes. In order to achieve a social licence to operate, there needs to be full recognition of traditional knowledge and acceptance of Indigenous values and concepts. We also recommend increased involvement of social experts and mediators as well as improved accountability, enforcement and grievance mechanisms in the licensing process. - Highlights: • The Brazilian environmental licensing system needs to address social impacts better. • Communities need to be consulted at the earliest stage possible. • Indigenous peoples need to be invited to participate in impact assessment teams. • Independent Indigenous committees to monitor implementation of mitigation measures. • Accountability, enforcement and grievance mechanisms need to be

  1. 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...

  2. 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...

  3. 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...

  4. 30 CFR 402.10 - Research-project applications.

    Science.gov (United States)

    2010-07-01

    ... project title, project objectives, background information, research tasks, methodology to conduct the... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Research-project applications. 402.10 Section... PROGRAM AND THE WATER-RESOURCES TECHNOLOGY DEVELOPMENT PROGRAM Application, Evaluation, and Management...

  5. 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)

  6. 10 CFR 780.45 - Criteria for decision to issue a license.

    Science.gov (United States)

    2010-01-01

    .... A license shall issue to the applicant to use the invention covered by the patent for the purposes stated in the application upon a final decision that: (a) The invention or discovery covered by the... energy; (b) The licensing of such invention or discovery is of primary importance to the conduct of the...

  7. Guide to request license for industrial X-rays practices

    International Nuclear Information System (INIS)

    2000-05-01

    In this work the instructions it plows described to request license for practices it of industrial x-ray it continued. The instructions but important: they plows license type, purpose of the application, source and equipment, location of local the, program of radiological protection and security

  8. 77 FR 38771 - Prospective Grant of Exclusive Patent License

    Science.gov (United States)

    2012-06-29

    ... Exclusive Patent License AGENCY: National Institute of Standards and Technology, Department of Commerce. ACTION: Notice of prospective grant of exclusive patent license. SUMMARY: This is a notice in accordance... embodied in U.S. Patent Application No. 13/346,999 titled ``Chirped-Pulse Terahertz Spectroscopy for...

  9. 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)

  10. 77 FR 2057 - Aquamac Corporation; Notice of Termination of License by Implied Surrender and Soliciting...

    Science.gov (United States)

    2012-01-13

    ... Corporation; Notice of Termination of License by Implied Surrender and Soliciting Comments and Motions To.... Type of Proceeding: Termination of License by Implied Surrender. b. Project No.: 2927-006. c. Date... authorized, the licensee is in violation of the terms and conditions of the license. l. This notice is...

  11. An Organizational-Technical Concept to Deal with Open Source Software License Terms

    Directory of Open Access Journals (Sweden)

    Sergius Dyck

    2016-06-01

    Full Text Available Open source software (OSS released under various license terms is widely used as third party libraries in today's software projects. To ensure open source compliance within an organization, a strategic approach to OSS management is needed. As basis for such an approach, we introduce an organizational-technical concept for dealing with the various OSS licenses by using procedural instructions and build automation software. The concept includes the careful consideration of OSS license conditions. The results obtained from this consideration and additional necessary commitments are documented in a so-called license playbook. We introduce procedure instructions enabling a consistent approach for software development using OSS libraries. The procedure instructions are described in a way such that they can be implemented for example for Java projects using the popular build automation tool Apache Maven and the software repository tool Nexus. We give guidance on how to realize such an implementation on basis of automation tools in practice.

  12. AP1000{sup R} licensing and deployment in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, R. P.; Russ, P. A.; Filiak, P. P.; Castiglione, L. L. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01

    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

  13. 10 CFR 40.33 - Issuance of a license for a uranium enrichment facility.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Issuance of a license for a uranium enrichment facility... License Applications § 40.33 Issuance of a license for a uranium enrichment facility. (a) The Commission... the licensing of the construction and operation of a uranium enrichment facility. The Commission will...

  14. 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...

  15. 47 CFR 74.787 - Digital licensing.

    Science.gov (United States)

    2010-10-01

    ..., AUXILIARY, SPECIAL BROADCAST AND OTHER PROGRAM DISTRIBUTIONAL SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.787 Digital licensing. (a) Applications for digital low power television and... channels may be filed at any time. Such applications shall be filed on FCC Form 346 and will be treated as...

  16. The Design Options and Provision File and the Role of Defence in Depth Within the Pre-Licensing of the MYRRHA Project

    Energy Technology Data Exchange (ETDEWEB)

    Fiorini, G. L.; Hakimi, N., E-mail: Gian-Luigi.fiorini@fanc.fgov.be [FANC (Belgium); Tombuyses, B.; Dams, C.; Wertelaers, A.; Schrauben, M.; Dresselaers, R. [Federal Agency for Nuclear Control (FANC), Bruxelles (Belgium)

    2014-10-15

    The Belgian Federal Agency for Nuclear Control (FANC) is engaged in a process of pre-licensing for the experimental reactor MYRRHA. The regulatory framework applicable for the implementation of the MYRRHA project and the expected safety, security and safeguards philosophy are described by FANC in a Strategic Note. This document presents a logical flow chart which defines the steps required to design a basic nuclear installation and ensure compliance with the requirements of nuclear safety, security and safeguards. Using this flow chart, the content of a set of volumes (Design Options and Provision File - DOPF) is defined; the DOPF will serve as a basis for the evaluation of the concept with the acceptability of the selected design options. Defence in depth (DiD) and its fundamental principles remain the foundation of the whole process. The paper summarizes the contents of the Strategic Note and the DOPF and focuses more specifically on aspects relating to changes in the concept of defence in depth and on practices for their integration in the process of design / assessment of the MYRRHA reactor. (author)

  17. Expert system application education project

    Science.gov (United States)

    Gonzelez, Avelino J.; Ragusa, James M.

    1988-01-01

    Artificial intelligence (AI) technology, and in particular expert systems, has shown potential applicability in many areas of operation at the Kennedy Space Center (KSC). In an era of limited resources, the early identification of good expert system applications, and their segregation from inappropriate ones can result in a more efficient use of available NASA resources. On the other hand, the education of students in a highly technical area such as AI requires an extensive hands-on effort. The nature of expert systems is such that proper sample applications for the educational process are difficult to find. A pilot project between NASA-KSC and the University of Central Florida which was designed to simultaneously address the needs of both institutions at a minimum cost. This project, referred to as Expert Systems Prototype Training Project (ESPTP), provided NASA with relatively inexpensive development of initial prototype versions of certain applications. University students likewise benefit by having expertise on a non-trivial problem accessible to them at no cost. Such expertise is indispensible in a hands-on training approach to developing expert systems.

  18. Local licensers and recovering in VP ellipsis

    Directory of Open Access Journals (Sweden)

    Sonia Cyrino

    2005-12-01

    Full Text Available The core properties of VP ellipsis in English and Portuguese may be captured assuming that the elliptical constituent is licensed under local c-command by a verbal element in a sentence functional head. However, the lack of VP ellipsis in most Romance languages and in German, despite the existence of verb movement to sentence functional projections in these languages, suggests that a parameter is involved. Empirical evidence indicates that this parametric variation should not be attributed to a specific functional head because the functional head occupied by the verbal licenser may vary across languages and language varieties. So we will claim that the existence vs. absence of VP ellipsis in the languages considered in this study is due to the features of the functional head that intervenes between the verbal licenser and the elliptical vP phase.

  19. 77 FR 3273 - Government-Owned Inventions; Availability for Licensing

    Science.gov (United States)

    2012-01-23

    ... Technology: Available for licensing is a novel method using short-term treatment with a glucocorticoid...: Licensing information and copies of the U.S. patent applications listed below may be obtained by writing to... into memory cells and terminally differentiated plasma cells. Moreover, IL-21 has anti-tumor activity...

  20. 77 FR 65673 - Prospective Grant of Exclusive Patent License

    Science.gov (United States)

    2012-10-30

    ... Exclusive Patent License AGENCY: National Institute of Standards and Technology, Commerce. ACTION: Notice of prospective grant of exclusive patent license. SUMMARY: This is a notice in accordance with 35 U.S.C. 209(e.... Patent Application No. 61/625,511 titled ``UV-Assisted Alcohol Sensing with Zinc Oxide Functionalized...

  1. 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

  2. Sodium Fast Reactor Safety and Licensing Research Plan

    International Nuclear Information System (INIS)

    Denman, Matthew; Lachance, Jeff; Sofu, Tanju; Wigeland, Roald; Flanagan, George; Bari, Robert

    2013-01-01

    Conclusions: The Sodium Fast Reactor Safety and Licensing Research Plan reports conclude a multi-year expert elicitation process. All information included in the studies are publicly available and the reports are UUR. These reports are intended to guide SFR researchers in the safety and licensing arena to important and outstanding issues Two (and a half) projects have been funded based on the recommendations in this report: • Modernization of SAS4A; • Incorporation of Contain/LMR with MELCOR; • (Data recovery at INL and PNNL)

  3. Decontamination and decommissioning project status of the TRIGA Mark II and III in Korea

    International Nuclear Information System (INIS)

    Paik, S.T.; Park, S.K.; Chung, K.W.; Chung, U.S.; Jung, K.J.

    1999-01-01

    TRIGA Mark-II, the first research reactor in Korea, has operated since 1962, and the second one, TRIGA Mark-III since 1972. Both of them had their operation phased out in 1995 due to their lives and operation of the new research reactor, HANARO (High-flux Advanced Neutron Application Reactor) at the Korea Atomic Energy Institute (KAERI) in Taejon. Decontamination and decommissioning (D and D) project of TRIGA Mark-II and Mark-III was started in January 1997 and will be completed in December 2002. The first year of the project, work was performed in preparation of the decommissioning plan, start of the environmental impact assessment and setup licensing procedure and documentation for the project with cooperation of Korea Institute of Nuclear Safety (KINS). Hyundai Engineering Company (HEC) is the main contractor to do design and licensing documentation for the D and D of both reactors. British Nuclear Fuels plc (BNFL) is the technical assisting partner of HEC. The decommissioning plan document was submitted to the Ministry of Since and Technology (MOST) for the decommissioning license in December 1998, and it expecting to be issued a license in mid 1999. The goal of this project is to release the reactor site and buildings as an unrestricted area. This paper summarizes current status and future plan for the D and D project. (author)

  4. Final environmental statement related to the operation of the Teton Uranium ISL Project (Docket No). 40-8781

    International Nuclear Information System (INIS)

    1983-08-01

    This Final Environmental Impact Statement is issued by the US Nuclear Regulatory Commission in response to the request by Teton Exploration Drilling, Inc. for the issuance of an NRC Source and Byproduct Material License authorizing operation of the proposed Teton Project to mine uranium in situ by injecting a carbonate/bicarbonate lixiviant into the ore body. The statement considers: (1) alternative of no licensing action, (2) alternative energy sources, and (3) alternatives if uranium ore is mined and refined on the site. The proposed action is to grant a Source and Byproduct Material License to the applicant subject to the stipulated license condition

  5. Anticipating impacts of climate change on fish habitat to support decisionmaking in hydropower licensing: a climate risk study for the Hiram Dam, Saco River, ME

    Science.gov (United States)

    Lagron, C. S.; Ray, A. J.; Barsugli, J. J.

    2016-12-01

    The Federal Energy Regulatory Commission (FERC) issues licenses for non-federal hydropower projects through its Integrated Licensing Process (ILP). Through this multi-stage, multi-year decision process, NOAA National Marine Fisheries Service (NMFS) can request studies needed to prescribe license conditions to mitigate dams' effects on trust resources, e.g. fish passages and flow requirements. NMFS must understand the combined effects of hydropower projects and climate change to fulfill its mandates to maintain fisheries and protected species. Although 30-50 year hydropower licenses and renewals are within the time frame of anticipated risks from changing climate, FERC has consistently rejected NMFS' climate study requests, stating climate science is "too uncertain," and therefore not actionable. The ILP is an opportunity to incorporate climate change risks in this decision process, and to make decisions now to avoid failures later in the system regarding both hydropower reliability (the concern of FERC and the applicant) and ecosystem health (NMFS's concern). NMFS has partnered with climate scientists at the ESRL Physical Sciences Division to co-produce a climate study request for the relicensing of the Hiram Project on the Saco River in Southern Maine. The Saco hosts Atlantic salmon (Salmo salar) runs which are not currently self-sustaining. This presentation will describe basin-to-basin variability in both historic river analyses (Hydro-Climate Data Network, HCDN) and projected hydrologic responses of New England rivers to climate forcings using statewide Precipitation-Runoff Modeling System (PRMS) demonstrate the need to develop Saco-specific watershed models. Furthermore, although methods for projecting fishery-relevant metrics (heat waves, flood annual exceedance probabilities) have been proven in nearby basins, this modeling has not been conducted at fishery-relevant thresholds. Climate study requests are an example of bridging between science and

  6. Bavarian liquid hydrogen bus demonstration project - safety, licensing and acceptability aspects

    Energy Technology Data Exchange (ETDEWEB)

    Wurster, R.; Knorr, H.; Pruemm, W.

    1999-07-01

    A regular 12 m city bus of the MAN SL 202 type with an internal combustion engine adapted to hydrogen operation and auxiliary gasoline operation was demonstrated in the Bavarian cities of Erlangen and Munich between April 1996 and August 1998. Three bus operators, Erlanger Stadtwerke, Stadtwerke Muenchen and Autobus Oberbayern were testing the bus in three different operating schemes. In order to be able to perform this worldwide first public demonstration of a liquid hydrogen (LH{sub 2}) city bus in regular service, several requirements with respect to safety, licensing, training and acceptability had to be fulfilled. These activities were focusing mainly on the hydrogen specific issues such as (a) integration of onboard LH{sub 2} storage vessels, piping and instrumentation, (b) implementation of storage and refueling infrastructure in the operators' yards, (c) adaptation of the maintenance garages, (d) training of operating and maintenance personnel. During phase II of the demonstration activity a poll was performed on passengers traveling onboard the hydrogen-powered city bus in order to determined the level of acceptance among the users of the bus. The bus was designed and manufactured by MAN Nutzfahrzeuge Aktiengesellschaft. The cryogenic fuel storage and the refueling equipment were designed and manufactured by Linde AG. The realization of the hardware was financially supported by the European Commission (EC) within the Euro-Quebec Hydro-Hydrogen Pilot Project. The demonstration phase was financially supported by EC and the Bavarian State Government. Ludwig-Boelkow-Systemtechnik performed project monitoring for both funding organizations. The presentation will summarize the most important results of this demonstration phase and will address the measures undertaken in order to get the bus, the refueling infrastructure and the maintenance and operating procedures approved by the relevant authorities.

  7. Puget Sound Tidal Energy In-Water Testing and Development Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Collar, Craig W

    2012-11-16

    others. All required permit and license applications were completed and submitted under this award, including a Final License Application for a pilot hydrokinetic license from the Federal Energy Regulatory Commission. The tasks described above have brought the project through all necessary requirements to construct a tidal pilot project in Admiralty Inlet with the exception of final permit and license approvals, and the selection of a general contractor to perform project construction.

  8. 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...

  9. 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...

  10. Project mobilisation

    International Nuclear Information System (INIS)

    Clark, J.; Limbrick, A.

    1996-01-01

    This paper identifies and reviews the issues to be addressed and the procedures to be followed during the mobilisation of projects using LFG as an energy source. Knowledge of the procedures involved in project mobilisation, their sequence and probable timescales, is essential for efficient project management. It is assumed that the majority of projects will be situated on existing, licensed landfill sites and, in addition to complying with the relevant conditions of the waste management licence and original planning consent, any proposed developments on the site will require a separate planning consent. Experience in the UK indicates that obtaining planning permission rarely constitutes a barrier to the development of schemes for the utilisation of LFG. Even so, an appreciation of the applicable environmental and planning legislation is essential as this will enable the developer to recognise the main concerns of the relevant planning authority at an early stage of the project, resulting in the preparation of an informed and well-structured application for planning permission. For a LFG utilisation scheme on an existing landfill site, the need to carry out an environmental assessment (EA) as part of the application for planning permission will, in vitually all cases, be discretionary. Even if not deemed necessary by the planning authority, an EA is a useful tool at the planning application stage, to identify and address potential problems and to support discussions with bodies such as the Environment Agency, from whom consents or authorisations may be required. Carrying out an EA can thus provide for more cost-effective project development and enhanced environmental protection. Typically, the principal contractual arrangements, such as the purchase of gas or the sale of electricity, will have been established before the project mobilisation phase. However, there are many other contractural arrangements that must be established, and consents and permits that may be

  11. 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.

  12. 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

  13. Advanced Turbine Technology Applications Project (ATTAP)

    Science.gov (United States)

    1994-01-01

    Reports technical effort by AlliedSignal Engines in sixth year of DOE/NASA funded project. Topics include: gas turbine engine design modifications of production APU to incorporate ceramic components; fabrication and processing of silicon nitride blades and nozzles; component and engine testing; and refinement and development of critical ceramics technologies, including: hot corrosion testing and environmental life predictive model; advanced NDE methods for internal flaws in ceramic components; and improved carbon pulverization modeling during impact. ATTAP project is oriented toward developing high-risk technology of ceramic structural component design and fabrication to carry forward to commercial production by 'bridging the gap' between structural ceramics in the laboratory and near-term commercial heat engine application. Current ATTAP project goal is to support accelerated commercialization of advanced, high-temperature engines for hybrid vehicles and other applications. Project objectives are to provide essential and substantial early field experience demonstrating ceramic component reliability and durability in modified, available, gas turbine engine applications; and to scale-up and improve manufacturing processes of ceramic turbine engine components and demonstrate application of these processes in the production environment.

  14. Why trash don't pass? pharmaceutical licensing and safety performance of drugs.

    Science.gov (United States)

    Banerjee, Tannista; Nayak, Arnab

    2017-01-01

    This paper examines how asymmetric information in pharmaceutical licensing affects the safety standards of licensed drugs. Pharmaceutical companies often license potential drug molecules at different stages of drug development from other pharmaceutical or biotechnology companies and complete the remaining of research stages before submitting the new drug application(NDA) to the food and drug administration. The asymmetric information associated with the quality of licensed molecules might result in the molecules which are less likely to succeed to be licensed out, while those with greater potential of success being held internally for development. We identify the NDAs submitted between 1993 and 2004 where new molecular entities were acquired through licensing. Controlling for other drug area specific and applicant firm specific factors, we investigate whether drugs developed with licensed molecules face higher probability of safety based recall and ultimate withdrawal from the market than drugs developed internally. Results suggest the opposite of Akerlof's (Q J Econ 84:488-500, 1970) lemons problem. Licensed molecules rather have less probability of facing safety based recalls and ultimate withdrawal from the market comparing to internally developed drug molecules. This suggests that biotechnology and small pharmaceutical firms specializing in pharmaceutical research are more efficient in developing good potential molecules because of their concentrated research. Biotechnology firms license out good potential molecules because it increases their market value and reputation. In addition, results suggest that both the number of previous approved drugs in the disease area, and also the applicant firms' total number of previous approvals in all disease areas reduce the probability that an additional approved drug in the same drug area will potentially be harmful.

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. The DIALOGUE project. Report of the Gaming group on the structure and content of the project

    International Nuclear Information System (INIS)

    Andersson, Johan; Hallencreutz, M.; Andersson, Kjell; Wene, C.O.; Westerlund, S.

    1993-11-01

    The DIALOGUE project has been conducted by the Swedish Nuclear Power Inspectorate (SKI) since 1990. The aim of the project was to stimulate a dialogue between different interest groups within Sweden. The purpose of this dialogue was to establish a licensing process, prior to a future licensing of a repository for spent nuclear waste, in which several of the parties involved are reasonably confident. The DIALOGUE project was carried out with the participation of other government agencies, municipalities and environmental groups and was headed by the former chairman of the National Licensing Board for Environmental Protection

  20. Siting Practices and Site Licensing Process for New Reactors in Canada

    International Nuclear Information System (INIS)

    Vos, Marcel de

    2011-01-01

    'Siting' in Canada is composed of Site Evaluation and Site Selection. As outlined in CNSC Regulatory Document RD-346 Site Evaluation for New Nuclear Power Plants (based on IAEA NS-R-3), prior to the triggering of the Environmental Assessment (EA) and licensing processes, the proponent is expected to use a robust process to characterize proposed sites over the full life cycle of the facility, and then develop a fully documented defense of the site selection case. This case forms the backbone for submissions in support of the EA and the application for a License to Prepare Site which will be reviewed by the CNSC and other applicable federal authorities. The Environmental Assessment process and License to Prepare Site in Canada do not require a proponent to select a specific design; however, CNSC does not accept a 'black box' approach to siting. CNSC balances the level of design information required with the extent of safety assurance desired for any designs being contemplated for the proposed site. Nevertheless, the design information submitted must be sufficient to justify the site as suitable for all future licensing stages. The depth of plant design information contributes significantly to the credibility of the applicant's case for both the EA and application for License to Prepare Site. The review process utilizes an assessment plan with defined review stages and timelines. The outcome of these reviews is a series of recommendations to a federal government appointed Joint Review Panel (which also serves as a panel of the 'Commission') which, following public hearings, renders a decision regarding the EA, and subsequently, the application for a License to Prepare Site. (author)

  1. 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...

  2. Licensing procedures for Low-Level Waste disposal facilities

    International Nuclear Information System (INIS)

    Roop, R.D.; Van Dyke, J.W.

    1985-09-01

    This report describes the procedures applicable to siting and licensing of disposal facilities for low-level radioactive wastes. Primary emphasis is placed on those procedures which are required by regulations, but to the extent possible, non-mandatory activities which will facilitate siting and licensing are also considered. The report provides an overview of how the procedural and technical requirements for a low-level waste (LLW) disposal facility (as defined by the Nuclear Regulatory Commission's Rules 10 CFR Parts 2, 51, and 61) may be integrated with activities to reduce and resolve conflict generated by the proposed siting of a facility. General procedures are described for site screening and selection, site characterization, site evaluation, and preparation of the license application; specific procedures for several individual states are discussed. The report also examines the steps involved in the formal licensing process, including docketing and initial processing, preparation of an environmental impact statement, technical review, hearings, and decisions. It is concluded that development of effective communication between parties in conflict and the utilization of techniques to manage and resolve conflicts represent perhaps the most significant challenge for the people involved in LLW disposal in the next decade. 18 refs., 6 figs

  3. Licensing procedure and requirements in the FRG

    International Nuclear Information System (INIS)

    Brosche, D.

    1981-01-01

    The investigations of the different dynamic stresses of pressure suppression systems after the Wuergassen incident in 1972 and their theoretical and experimental solutions required an extraordinary effort from all participants of the licensing procedures. As a consequence of these new problems a lot of mathematical models and computer codes had been developed and a lot of experimental work had been performed. Numerous highly qualified scientists and engineers had been involved for a long time in the licensing procedures and innumerable discussions had been necessary. These investigations and discussions had a great influence on the licensing procedures and on the project running. Too pessimistic assumptions and wrong interpretations of experiments led to fictitious problems and a lot of time and money was necessary to overcome these difficulties. Finally at 1977 it could be proved that the construction was able to control stresses so that additional investigations were not necessary. (orig./HP)

  4. 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.)

  5. 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...

  6. Participation of the public in licensing procedures under the Atomic Energy Act and the Federal Emission Control Act

    International Nuclear Information System (INIS)

    Hett, F.T.

    1994-01-01

    Section 7 of the Atomic Energy Act (AtG), section 4 of the Federal Emission Control Act (BImSchG), the Nuclear Installations Licensing Ordinance (AtVfV), and the Ninth Ordinance on the Implementation of the BImSchG (Principles of the licensing procedure) require participation of the public in the procedure before administrative provisions or decisions are issued. The book presents the legally prescribed steps at which participation of the public is mandatory, for the simple case (only one license on the agenda), and for the multi-stage licensing procedure: preliminary negotiations / filling of applications for a license and filing of documents / public announcement of projects / access to files / objections / preclusion of delayed objections / public hearing and other expert discussions / termination of procedure, decision-making by the authorities / decisions on subdivision of procedure into defined stages / modification of the procedure. The analysis of the functions of participation of the public examines the following goals: information / representation of interests / reconciliation of interests / legitimation / control / protection of rights / support. Finally, the book explains the principles of the Constitution demanding participation of the public: human dignity / democracy / rule of law / anticipated effects of the right to have recourse to the courts / civil rights. (orig./HP) [de

  7. Librarian Certification and Licensing: A Brief Accounting.

    Science.gov (United States)

    Kaatrude, Peter B.

    1992-01-01

    Examines certification and licensing of librarians in the United States and Canada from the perspective of differences between the two concepts and through historical analysis of applications of each. A contextual framework for studying applications of these concepts to other professions is provided. (nine references) (MES)

  8. Status of the Monticello nuclear generating plant lead plant license renewal program

    International Nuclear Information System (INIS)

    Pickens, T.A.

    1992-01-01

    In 1988, the Monticello nuclear generating plant was chosen by the US Department of Energy through Sandia National Laboratories and the Electric Power Research Institute to serve as the lead boiling water reactor in the lead plant license renewal program. The purpose of the lead plant license renewal program is to provide insights during the development of and to demonstrate the license renewal regulatory process with the US Nuclear Regulatory Commission (NRC). The work being performed in three phases: (1) preparation of the technical basis for license renewal; (2) development of the technical basis into a formal license renewal application; and (3) review of the application by the NRC. This paper discusses the systems and structures identified as important to license renewal in accordance with 10CFR54 as well as the plant documents and programs that were used in going through the identification process. The systems and structures important to license renewal will then provide insights into how structures and components were identified that are required to be evaluated for aging, the elements of the aging evaluations, and the effective programs used to manage potentially significant aging

  9. Project Integration Architecture: Inter-Application Propagation of Information

    Science.gov (United States)

    Jones, William Henry

    2005-01-01

    A principal goal of the Project Integration Architecture (PIA) is to facilitate the meaningful inter-application transfer of application-value-added information. Such exchanging applications may be largely unrelated to each other except through their applicability to an overall project; however, the PIA effort recognizes as fundamental the need to make such applications cooperate despite wide disparaties either in the fidelity of the analyses carried out, or even the disciplines of the analysis. This paper discusses the approach and techniques applied and anticipated by the PIA project in treating this need.

  10. Resource communication: ApkFor©, an Android Open-Source Project for research and technology transfer in forest management

    Directory of Open Access Journals (Sweden)

    Fernando Pérez-Rodríguez

    2018-01-01

    Full Text Available Aim of the study: To introduce and describe ApkFor©, an Android Open-Source Project to generate basic mobile applications to transfer forest growth and yield models for even-aged stands. Material and methods: ApkFor© was developed in Android Studio using Java and XML languages integrating  transition functions for dominant height and basal area, equations of tree and stand volume and structural models. The project was applied and validated for Pinus pinaster Ait. stands in Northeastern Portugal. Main results: ApkFor© is an Open-Source project freely available from the Source Force repository: https://sourceforge.net/projects/apkfor/, licensed under the GNU General Public License version 3.0 (GPLv3. Research highlights: This project has been designed and created to provide the code and promote its re-use and modification to develop simple growth and yield mobile applications in Android, and with it to transfer research results of forest modelling to forest managers. Moreover, an example of application of the compiled code is provided using the models of Pinus pinaster Ait. previously validated for the Northeastern Region of Portugal.

  11. 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)

  12. 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

  13. 77 FR 68155 - The Armed Forces Radiobiology Research Institute TRIGA Reactor: Facility Operating License No. R-84

    Science.gov (United States)

    2012-11-15

    ... Research Institute TRIGA Reactor: Facility Operating License No. R-84 AGENCY: Nuclear Regulatory Commission... considering an application for the renewal of Facility Operating License No. R-84 (Application), which... the renewal of Facility Operating License No. R-84, which currently authorizes the licensee to operate...

  14. 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/

  15. 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...

  16. 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.

  17. 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

  18. 47 CFR 22.228 - Cellular rural service area licenses subject to competitive bidding.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Cellular rural service area licenses subject to... Procedures § 22.228 Cellular rural service area licenses subject to competitive bidding. Mutually exclusive initial applications for Cellular Rural Service Area licenses are subject to competitive bidding. The...

  19. BWR containments license renewal industry report; revision 1. Final report

    International Nuclear Information System (INIS)

    Smith, S.; Gregor, F.

    1994-07-01

    The U.S. nuclear power industry, through coordination by the Nuclear Management and Resources Council (NUMARC), and sponsorship by the U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), has evaluated age-related degradation effects for a number of major plant systems, structures, and components, in the license renewal technical Industry Reports (IR's). License renewal applicants may choose to reference these IR's in support of their plant-specific license renewal applications as an equivalent to the integrated plant assessment provisions of the license renewal rule (IOCFR54). The scope of the IR provides the technical basis for license renewal for U.S. Boiling Water Reactor (BWR) containments. The scope of the report includes containments constructed of reinforced or prestressed concrete with steel liners and freestanding stell containments. Those domestic BWR containments designated as Mark I, Mark II or Mark III are covered, but no containments are addressed before these designs. The report includes those items within the jurisdictional boundaries for metal and concrete containments defined by Section III of the ASME Boiler and Pressure Vessel Code, Division 1, Subsection NE (Class MC) and Division 2 (Class CC) and their supports, but excluding snubbers

  20. 10 CFR 780.34 - Criteria for decision to issue a license.

    Science.gov (United States)

    2010-01-01

    ... license. A license shall issue to the applicant to use the invention covered by the patent declared to be affected with the public interest pursuant to subsection 153b(2) of the Act upon a final decision that: (a...

  1. Site characterization activities at Stripa and other Swedish projects

    International Nuclear Information System (INIS)

    Ahlstroehm, P.E.

    1991-01-01

    The Swedish research programme concerning spent nuclear fuel disposal aims for submitting a siting license application around the year 2000. An important step towards that goal will be the detailed characterization of at least two potential sites in late 1990s. In preparation for such characterization several research projects are conducted. One is the international Stripa Project that includes a site characterization and validation project for a small size granite rock body. The Stripa work also includes further development of instrumentation and measurement techniques. Another project is the Finnsjoen Fracture Zone Project, which is characterizing a subhorizontal zone at depths from 100 to 350 meters. The third project is the new Swedish Hard Rock Laboratory planned at the site of the Oskarshamn nuclear power plant. The preinvestigations and construction of this laboratory include major efforts in development, application and validation of site characterization methodology. (author) 6 figs., 9 refs

  2. Economic implications of nuclear plant license renewal in the U.S

    International Nuclear Information System (INIS)

    Smith, L.J.

    2001-01-01

    The NRC and the nuclear industry struggled for many years with the development of a viable license renewal rule. Now that a workable rule appears to have been developed, and the first license renewal applicants have received renewed licenses, the floodgates have opened and a large number of nuclear utilities have announced intentions to seek renewed NRC operating licenses. In this time when profound changes are being experienced in the electric generation markets in the United States, nuclear plant license renewal can have several economic effects that should be considered by utilities prior to the pursuit of an NRC license renewal. This paper examines some of the factors that may be affected by the prospect of an additional 20-year operating life of a nuclear plant. (author)

  3. 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...

  4. Validation, acceptance and licensing

    International Nuclear Information System (INIS)

    Wene, C.O.

    1992-01-01

    The licensing process requires communication of complex scientific and technical information. In this paper transfer of such information is discussed using concepts and ideas from systems analysis, cybernetics and argumentation theory. A simple model for the decision process is developed. The analysis stresses the need for careful design of the communication channels between the three systems involved: the political system, the judicial-regulatory system and the scientific-technical community. The Dialogue - Scenario project initiated by the Swedish nuclear Inspectorate is briefly presented

  5. The use of on-site Project Officers by a nuclear regulatory body

    International Nuclear Information System (INIS)

    Beare, J.W.

    1977-01-01

    In Canada consideration of applications for licensing nuclear installations is entrusted to the Reactor Safety Advisory Committee within the Atomic Energy Control Board (AECB). The licensing procedure is conducted in three stages (site approval, construction licence, operating licence). In order to control construction and operation of nuclear installations Project Officers are assigned to each particular installation. The policy of AECB is to send these officers on site several months before the reactor reaches criticality; and during reactor operation. This system clearly provides great practical advantages. (NEA) [fr

  6. A new license plate extraction framework based on fast mean shift

    Science.gov (United States)

    Pan, Luning; Li, Shuguang

    2010-08-01

    License plate extraction is considered to be the most crucial step of Automatic license plate recognition (ALPR) system. In this paper, a region-based license plate hybrid detection method is proposed to solve practical problems under complex background in which existing large quantity of disturbing information. In this method, coarse license plate location is carried out firstly to get the head part of a vehicle. Then a new Fast Mean Shift method based on random sampling of Kernel Density Estimate (KDE) is adopted to segment the color vehicle images, in order to get candidate license plate regions. The remarkable speed-up it brings makes Mean Shift segmentation more suitable for this application. Feature extraction and classification is used to accurately separate license plate from other candidate regions. At last, tilted license plate regulation is used for future recognition steps.

  7. Conditions for licensing workers exposed to ionizing radiation

    International Nuclear Information System (INIS)

    2007-01-01

    This entrance speaking on conditions of license workers in the areas of employment ionizing radiation addresses two aspects, the first aspect: industrial applications: speak for the workers in this area by a supervisor to portray industrial and industrial photographer and a supervisor sounding wells and a Nuclear Gauges Supervisor and the previous and subsequent Practices of the law The second aspect: about the medical applications and describes the general conditions of the licenses in this area and those working in this area of professional diagnostic radiology and nuclear medicine technician and technician treatment of radiotherapy and radiation protection officers at large and small institutions

  8. 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)

  9. Licensing systems and inspection of nuclear installations in NEA Member countries. Part 1, Description of licensing systems

    International Nuclear Information System (INIS)

    1977-01-01

    This study provides an assessment of the legislative and regulatory provisions applicable and of the practices followed in the countries concerned and is divided into two separate sections. This document is the first part only. It contains the description of national licensing and inspection systems for nuclear installations in the twenty OECD countries which have specific regulations in this field. Each analysis has been presented following a plan which is as standardised as possible so as to facilitate comparison between the national systems. Part II, which is not included in this document, contains the diagrams illustrating the steps in the licensing procedure and the duties of the bodies involved as well as certain additional documents. It also includes a table showing the sequence of the main steps in the licensing process in the countries covered by this Study

  10. Spatial service delivery system for smart licensing & enforcement management

    Science.gov (United States)

    Wahap, N. A.; Ismail, N. M.; Nor, N. M.; Ahmad, N.; Omar, M. F.; Termizi, A. A. A.; Zainal, D.; Noordin, N. M.; Mansor, S.

    2016-06-01

    Spatial information has introduced a new sense of urgency for a better understanding of the public needs in term of what, when and where they need services and through which devices, platform or physical locations they need them. The objective of this project is to value- add existing license management process for business premises which comes under the responsibility of Local Authority (PBT). Manipulation of geospatial and tracing technology via mobile platform allows enforcement officers to work in real-time, use a standardized system, improve service delivery, and optimize operation management. This paper will augment the scope and capabilities of proposed concept namely, Smart Licensing/Enforcement Management (SLEm). It will review the current licensing and enforcement practice of selected PBT in comparison to the enhanced method. As a result, the new enhanced system is expected to offer a total solution for licensing/enforcement management whilst increasing efficiency and transparency for smart city management and governance.

  11. Generic data sources for the update of an environmental report in support of license renewal

    International Nuclear Information System (INIS)

    Mauro, John J.

    1991-01-01

    Over the past 2 years, our organization has been providing assistance to the NUMARC PLEX working group in matters pertaining to the environmental impacts of license renewal. Part of this support was the identification of data sets and publications that may be useful to the NRC in the preparation of their Environment Report Supplements (ERSs). The following presents a strategy for preparing an ERS, along with references and data sets pertinent to each ER topic. Each section of the ERS should present the following information: (1) Updated information on plant design and operating experience, along with projections of the plant impacts through the end of its currently licensed period of operation. These impacts are used as a baseline against which to compare the projected impacts for the period of license renewal. In addition, the baseline impacts may be compared to the impacts projected in the plant's original Environmental Report and Environmental Impact Statement. (2) Projections of how the impacts may change during the period of license renewal. The purpose of this information will be to determine the degree to which the projected impacts differ significantly from the impacts presented in the original ER and those that have actually occurred during the period of plant operation. We believe that the ERS will reveal that (1) the actual impacts that have occurred during the period of plant operation are comparable to, or less than, those predicted in the original ER, (2) many impacts have been decreasing with time, such as routine radioactive emissions, and (3) the impacts predicted for the period of license renewal will be comparable to, or less than, the baseline impacts. (author)

  12. 77 FR 34392 - Government-Owned Inventions; Availability for Licensing

    Science.gov (United States)

    2012-06-11

    ... pneumonia viruses, and other viral infections. Potential Commercial Applications: Prevention and treatment... of federally-funded research and development. Foreign patent applications are filed on selected... INFORMATION: Licensing information and copies of the U.S. patent applications listed below may be obtained by...

  13. Licensing procedures for Low-Level Waste disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Roop, R.D.; Van Dyke, J.W.

    1985-09-01

    This report describes the procedures applicable to siting and licensing of disposal facilities for low-level radioactive wastes. Primary emphasis is placed on those procedures which are required by regulations, but to the extent possible, non-mandatory activities which will facilitate siting and licensing are also considered. The report provides an overview of how the procedural and technical requirements for a low-level waste (LLW) disposal facility (as defined by the Nuclear Regulatory Commission's Rules 10 CFR Parts 2, 51, and 61) may be integrated with activities to reduce and resolve conflict generated by the proposed siting of a facility. General procedures are described for site screening and selection, site characterization, site evaluation, and preparation of the license application; specific procedures for several individual states are discussed. The report also examines the steps involved in the formal licensing process, including docketing and initial processing, preparation of an environmental impact statement, technical review, hearings, and decisions. It is concluded that development of effective communication between parties in conflict and the utilization of techniques to manage and resolve conflicts represent perhaps the most significant challenge for the people involved in LLW disposal in the next decade. 18 refs., 6 figs.

  14. 75 FR 21286 - Bowersock Mills and Power Company; Notice of Application Accepted for Filing, Soliciting Motions...

    Science.gov (United States)

    2010-04-23

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13526-002] Bowersock Mills... License. b. Project No.: 13526-002. c. Date Filed: February 8, 2010. d. Applicant: Bowersock Mills Power Company (Bowersock). e. Name of Project: Bowersock Mills and Power Company Expanded Kansas River...

  15. 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)

  16. Intervention in independent spent fuel storage facility license application proceedings for storage on the power plant site

    International Nuclear Information System (INIS)

    Jordan, J.

    1992-01-01

    This presentation summarizes the intervention in the Nuclear Regulatory Commission (NRC) licensing process for currently operating Independent Spent fuel Storage Installation (ISFSI) projects at Carolina Power and Light's Company's H.B. Robinson, Duke Power Company's Oconee, and Virginia Power Company's Surry. In addition, intervention at dry storage facilities that are currently under development are also described. The utilities and reactors include Baltimore Gas and Electric Company's Calvert Cliffs, Public Service Company of Colorado's Fort St. Vrain plant, Northern States Power Company's Prairie Island, Wisconsin Electric Power Company's Point Beach, and Consumers Power Company's Palisades

  17. The PRINCE Project and its Applications (clone)

    OpenAIRE

    Bescos, Sylvie; Bisière, Christophe; Gailly, Pierre-Joseph; Krautter, Wolfgang

    1992-01-01

    The Esprit project Prince aims at development of an industrial Constraint Logic Programing environment based on the Prolog III language. In parallel, the current technology is being validated within the project on representative real-world examples. This paper describes the current status of the three application domains which were Selected to demonstrate the applicability and usefulness of CLP. These applications deal with industrial systems engineering, medium term banking planning and jobs...

  18. Licensing requirements for nuclear merchant ships in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Schafstall, H.-G.

    1978-01-01

    The procedure of approval in the Federal Republic of Germany will be discussed, referring to the participated authorities and organizations. Rules and guidelines relevant for licensing are mentioned in the frame of legal positions. After presentation of general aspects of basic licensing requirements more detailed information is given relative to their accomplishment demonstrated on the German Nuclear Contained Ship NCS-80-Project

  19. The state and profile of open source software projects in health and medical informatics.

    Science.gov (United States)

    Janamanchi, Balaji; Katsamakas, Evangelos; Raghupathi, Wullianallur; Gao, Wei

    2009-07-01

    Little has been published about the application profiles and development patterns of open source software (OSS) in health and medical informatics. This study explores these issues with an analysis of health and medical informatics related OSS projects on SourceForge, a large repository of open source projects. A search was conducted on the SourceForge website during the period from May 1 to 15, 2007, to identify health and medical informatics OSS projects. This search resulted in a sample of 174 projects. A Java-based parser was written to extract data for several of the key variables of each project. Several visually descriptive statistics were generated to analyze the profiles of the OSS projects. Many of the projects have sponsors, implying a growing interest in OSS among organizations. Sponsorship, we discovered, has a significant impact on project success metrics. Nearly two-thirds of the projects have a restrictive license type. Restrictive licensing may indicate tighter control over the development process. Our sample includes a wide range of projects that are at various stages of development (status). Projects targeted towards the advanced end user are primarily focused on bio-informatics, data formats, database and medical science applications. We conclude that there exists an active and thriving OSS development community that is focusing on health and medical informatics. A wide range of OSS applications are in development, from bio-informatics to hospital information systems. A profile of OSS in health and medical informatics emerges that is distinct and unique to the health care field. Future research can focus on OSS acceptance and diffusion and impact on cost, efficiency and quality of health care.

  20. 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

  1. Demonstrating safety during license renewal should not be a large task

    International Nuclear Information System (INIS)

    Berto, D.S.

    1993-01-01

    The principal regulatory goal related to nuclear power plant operation is to ensure the health and safety of the public. The principal goal of extended plant operation via the license renewal process is also to ensure the health and safety of the public. The license renewal documentation issued by the Nuclear Regulatory Commission (NRC) provides guidance on what will be acceptable to the NRC in a license renewal application to demonstrate that this goal will be met. Application of this guidance is currently open to wide interpretation, with many of the current approaches proving to be extremely costly, complex, and uncertain of acceptability. This paper evaluates the requirements necessary to ensure the continued health and safety of the public during any license renewal term. This evaluation is based on the stated goals of the License Renewal Rule and on the published bases for the Rule. An approach to License Renewal is recommended that: (1) meets the stated goals of the NRC; (2) is consistent with current regulatory practices; and (3) will continue to ensure the health and safety of the public. This recommended approach is also much less costly than other current approaches, and can be easily agreed to by all participants. This approach will meet regulatory goals, while removing the cost and uncertainty obstacles currently being confronted by utilities. Providing a viable approach to license renewal will allow the renewal process to be pursued by utilities. Without such an approach, safe and reliable nuclear power plants will be permanently shut down at the arbitrary 40 year license limit

  2. Projecting Thailand physician supplies between 2012 and 2030: application of cohort approaches

    Directory of Open Access Journals (Sweden)

    Suphanchaimat Rapeepong

    2013-02-01

    Full Text Available Abstract Background This study forecasts physician supply between 2012 and 2030 using cohort analysis, based on future production capacity and losses from the profession, and assesses if, and by when, the projected numbers of physicians would meet the targets of one doctor per 1,500 population, as proposed by the 7th National Conference on Medical Education in 2001, and one per 1,800, proposed by the Ministry of Public Health (MoPH in 2004. Methods We estimated the annual loss rate that best reflected the dynamics of existing practising doctors, then applied this rate to the existing physicians, plus the newly licensed physicians flowing into the pool over the next two decades (from 2012 to 2030. Finally, the remaining practising physicians, after adjustment for losses, were verified against demand projections in order to identify supply gaps. Results Thailand has been experiencing an expansion in the total number of physicians, with an annual loss rate of 1%. Considering future plans for admission of medical students, the number of licensed physicians flowing into the pool should reach 2,592 per annum, and 2,661 per annum, by 2019 and 2030 respectively. By applying the 1% loss rate to the existing, and future newly licensed, physicians, there are forecast to be around 40,000 physicians in active clinical service by 2016, and in excess of 60,000 by 2028. Conclusion This supply forecast, given various assumptions, would meet the targets outlined above, of one doctor per 1,800 population, and one per 1,500 population, by 2016 and 2020 respectively. However, rapid changes in the contextual environment, e.g. economic demand, physician demographics, and disease burden, may mean that the annual loss rate of 1% used in this projection is not accurate in the future. To ensure population health needs are met, parallel policies on physician production encompassing both qualitative and quantitative aspects should be in place. Improved, up

  3. A model record of technologies for use in a compatible projects for environmental licensing of wind farms; Um modelo de registro das tecnologias para uso na compatibilizacao de projetos para licenciamento ambiental de parques eolicos

    Energy Technology Data Exchange (ETDEWEB)

    Tavares Junior, Wandemberg; Oliveira, Lucia Maria Barbosa [Universidade de Fortaleza (UNIFOR), CE (Brazil)

    2008-07-01

    This article presents the development of a model for survey and registration of technologies that can be inserted in the process of reconciliation of the subjects of the project for environmental licensing of wind farms. It was used a basis for the theoretical model of the Simultaneous Engineering and Failure Mode and Effect Analysis - FMEA. Given the importance that the wind has for the pursuit of sustainable development, this work had as its main objective to contribute to the reduction of negative indices, proposing improvements to the process of project for environmental licensing of wind farms. (author)

  4. Project 2019 of Garona Nuclear power plant. First project to licensing renew more than 40 years in Spain; Proyecto 2019 de Cn Garona. El primer proyecto para la renovacion de licencia mas alla de 40 anos en Espana

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, R. A.; Torralbo, J. R.

    2004-07-01

    NUCLENOR has been developing lifetime management and modernisation activities at Santa Maria de Garona NPP since the end of the 80's and the plant is now in optimum technical conditions to continue in operation beyond its original lifetime planned in the design (40 years). In the USA, the country of origin of the project, a good number of power plants with a similar design, age and history to SMG are in the process of obtaining or have already obtained, a licensing extension of up to 60 years from the NRC. In Spain, the activities required for requesting a long-term operating licensing extension include the Ageing Assessment and Management of the plant systems, structures and components, in accordance with the american regulation 10CFR54, a Radiological Impact Study for the new operating period, and an Analysis of New Legislation, not included in the licensing bases and considered to be important to safety by the CSN. With a view to obtaining a renewal of the current operating permit for the period 2009-2019, NUCLENOR has launched the Proyecto 2019, which extends to technical and licensing aspects, as it involves all the company's personnel. (Author)

  5. 77 FR 64973 - Don W. Gilbert Hydro Power, LLC; Notice of Application Accepted for Filing With the Commission...

    Science.gov (United States)

    2012-10-24

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 14367-001] Don W. Gilbert...: Original Minor License. b. Project No.: 14367-001. c. Date filed: May 30, 2012. d. Applicant: Don W...(a)-825(r). (2006). h. Applicant Contact: Don W. Gilbert and DeAnn G. Somonich, Don W. Gilbert Hydro...

  6. 75 FR 6371 - Jordan Hydroelectric Limited Partnership; Notice of Application Accepted for Filing and...

    Science.gov (United States)

    2010-02-09

    ... Hydroelectric Limited Partnership; Notice of Application Accepted for Filing and Soliciting Motions To Intervene and Protests February 2, 2010. Take notice that the following hydroelectric application has been filed... License b. Project No.: P-12740-003 c. Date filed: July 13, 2009 d. Applicant: Jordan Hydroelectric...

  7. Applying human factors engineering program to the modernization project of NPP Control Room in accordance with U.S.NRC and KTA regulations

    International Nuclear Information System (INIS)

    Avellar, Renato Koga de; Schirru, Roberto

    2017-01-01

    Application of Human Factors Engineering (HFE) in the design and implementation of such a project is essential to ensure that the new man-machine interface outcoming from the modernization does not have any negative impacts on human performance and plant safety. This paper analyzes the applicability of the Human Factors Engineering Program in the licensing and certification of Konvoi Nucleoelectric Power Plant Control Room Modernization Project using digital instrumentation and control in accordance with U.S.NRC and KTA regulations. The results of the analyses show that although regulatory bodies adopt different methodology in the process of licensing the modernization of control rooms, the engineering aspects are being developed based on the principles of engineering. (author)

  8. Applying human factors engineering program to the modernization project of NPP Control Room in accordance with U.S.NRC and KTA regulations

    Energy Technology Data Exchange (ETDEWEB)

    Avellar, Renato Koga de, E-mail: rkoga@eletronuclear.gov.br [Eletrobrás Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). Assessoria de Licenciamento Nuclear e Ambiental; Schirru, Roberto, E-mail: schirru@lmp.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2017-07-01

    Application of Human Factors Engineering (HFE) in the design and implementation of such a project is essential to ensure that the new man-machine interface outcoming from the modernization does not have any negative impacts on human performance and plant safety. This paper analyzes the applicability of the Human Factors Engineering Program in the licensing and certification of Konvoi Nucleoelectric Power Plant Control Room Modernization Project using digital instrumentation and control in accordance with U.S.NRC and KTA regulations. The results of the analyses show that although regulatory bodies adopt different methodology in the process of licensing the modernization of control rooms, the engineering aspects are being developed based on the principles of engineering. (author)

  9. 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...

  10. 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

  11. The end game must end before license renewal begins

    International Nuclear Information System (INIS)

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

    1995-01-01

    The quest for a process and strategy to achieve license renewal was begun in the mid-1980s with the view that renewal was an imperative. A major portion of the nation's future electric supply seemed to be at stake. For plants who were becoming noncompetitive because of annual capital recovery, license renewal also appeared as the means of survival. These two perceptions led to a third: License renewal should be sought immediately upon completion of the first 20 yr of operation. Although the basic engineering premise of license renewal remains sound, the perceptions regarding timing of an application may be incorrect. This paper suggests that a gauntlet of uncertainty exists for all plants. Further, it is most severe between the 20th and 30th years of operation. Thus, the competitive viability of the plant must be sustained for most of the initial term before license renewal can become a serious option

  12. NRC licensing of uranium enrichment plants

    International Nuclear Information System (INIS)

    Moran, B.W.

    1991-01-01

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

  13. The Atomic Energy Control Board requirements for the radioisotope licensing of a radiopharmaceutical facility

    International Nuclear Information System (INIS)

    Kennedy, P.

    1980-01-01

    Items that must be addressed by an applicant for a radioisotope license in Canada are described. Site, design and operating conditions, safety assessment, organization, emergency procedures and operating policies and procedures must be described to the Atomic Energy Control Board (AECB), in support of any license application. All information submitted in support of the application is subject to AECB's policy on public access to that information. (OT)

  14. 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

  15. Prototype Rail Crossing Violation Warning Application Project Report.

    Science.gov (United States)

    2017-09-05

    This report is the Project Report for the Rail Crossing Violation Warning (RCVW) safety application developed for the project on Rail Crossing Violation Warning Application and Infrastructure Connection, providing a means for equipped connected vehic...

  16. Safety and licensing analyses for the Fort St. Vrain HTGR

    International Nuclear Information System (INIS)

    Ball, S.J.; Conklin, J.C.; Harrington, R.M.; Cleveland, J.C.; Clapp, N.E. Jr.

    1982-01-01

    The Oak Ridge National Laboratory (ORNL) safety analysis program for the HTGR includes development and verification of system response simulation codes, and applications of these codes to specific Fort St. Vrain reactor licensing problems. Licensing studies addressed the oscillation problems and the concerns about large thermal stresses in the core support blocks during a postulated accident

  17. The role the safety analysis report and other documents in the licensing procedure in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Albrecht, E.; Ballhaus, S.

    1975-01-01

    Legal requirements for the licensing procedure, requirements for and preparation of licensing documents, authorities and experts participating in the licensing procedure, course of the atomic licensing procedure e.g. application for construction and operation, public hearing, site and concept license, partial licenses. (HP) [de

  18. Irreducible projective representations and their physical applications

    Science.gov (United States)

    Yang, Jian; Liu, Zheng-Xin

    2018-01-01

    An eigenfunction method is applied to reduce the regular projective representations (Reps) of finite groups to obtain their irreducible projective Reps. Anti-unitary groups are treated specially, where the decoupled factor systems and modified Schur’s lemma are introduced. We discuss the applications of irreducible Reps in many-body physics. It is shown that in symmetry protected topological phases, geometric defects or symmetry defects may carry projective Rep of the symmetry group; while in symmetry enriched topological phases, intrinsic excitations (such as spinons or visons) may carry projective Rep of the symmetry group. We also discuss the applications of projective Reps in problems related to spectrum degeneracy, such as in search of models without sign problem in quantum Monte Carlo simulations.

  19. Licensing authority's control of radiation sources and nuclear materials in Brazil

    International Nuclear Information System (INIS)

    Binns, D.A.C.

    2002-01-01

    Full text: The Brazilian Nuclear Energy Commission is the national licensing authority and among its responsibilities is the control of nuclear materials and radiation sources. This control is carried out in three different ways: 1) Control of the import and export of nuclear materials and radiation sources. To be able to import or export any nuclear material or radiation source, the user has to have an explicit permission of the licensing authority. This is controlled by electronic means in which the user has to fill a special form found on the licensing authority's home page, where he has to fill in his name, license number, license number of his radiation protection officer and data of the material to be imported or exported. These data are checked with a data base that contains all the information of the licensed users and qualified personnel before authorization is emitted. The airport authorities have already installed x-ray machines to check all baggages entering or leaving the country. 2) Transport and transfer permit for radiation sources. In order to transport and/or transfer radiations sources and nuclear materials within the country, the user(s) have to submit an application to the licensing authority. The user(s) fill out an application form where he fills in his company's name, licensing I.D., radiation protection officer's name and I.D and identification of the sources involved. These information are checked with the licensing operations data before the operations is permitted. 3) Inspections and radiation monitoring systems. Routine and regulatory inspections are continuously carried out where the user's radiation sources and nuclear materials inventory are checked. Also the physical security and protection of these materials are verified. The installation of monitoring systems is an item that is being discussed with the airport authorities so as to increase the possibilities of detecting any illegal transport of these materials. (author)

  20. 47 CFR 25.148 - Licensing provisions for the Direct Broadcast Satellite Service.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Licensing provisions for the Direct Broadcast Satellite Service. 25.148 Section 25.148 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Applications and Licenses Space Stations § 25.148...

  1. Application of Project Portfolio Management

    Science.gov (United States)

    Pankowska, Malgorzata

    The main goal of the chapter is the presentation of the application project portfolio management approach to support development of e-Municipality and public administration information systems. The models of how people publish and utilize information on the web have been transformed continually. Instead of simply viewing on static web pages, users publish their own content through blogs and photo- and video-sharing slides. Analysed in this chapter, ICT (Information Communication Technology) projects for municipalities cover the mixture of the static web pages, e-Government information systems, and Wikis. So, for the management of the ICT projects' mixtures the portfolio project management approach is proposed.

  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. 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...

  4. 47 CFR 13.17 - Replacement license.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false Replacement license. 13.17 Section 13.17 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL COMMERCIAL RADIO OPERATORS General § 13.17 Replacement... request a replacement. The application must be accompanied by the required fee and submitted to the...

  5. Licensing topical report: interpretation of general design criteria for high-temperature gas-cooled reactors

    International Nuclear Information System (INIS)

    Orvis, D.D.; Raabe, P.H.

    1980-01-01

    This Licensing Topical Report presents a set of General Design Criteria (GDC) which is proposed for applicability to licensing of graphite-moderated, high-temperature gas-cooled reactors (HTGRs). Modifications as necessary to reflect HTGR characteristics and design practices have been made to the GDC derived for applicability to light-water-cooled reactors and presented in Appendix A of Part 50, Title 10, Code of Federal Regulations, including the Introduction, Definitions, and Criteria. It is concluded that the proposed set of GDC affords a better basis for design and licensing of HTGRs

  6. Steam generator replacement project in 2000

    International Nuclear Information System (INIS)

    Cerjak, J.; Holz, R.; Haus, J.; Gloaguen, C.

    1999-01-01

    NE Krsko has awarded the contract for the Steam Generator Replacement Project, which is one of the modernization projects in Krsko, to the Consortium of Siemens / Framatome in February 1998. This paper deals with the various aspects of the project: scope planning, engineering, preparation of modification packages for licensing, management, major techniques used, etc., showing also the status of the activities for the project which are scheduled to be performed in April through June 2000. The project is being performed on a turnkey basis, that means the Consortium is performing all engineering, preparation of the modification packages and site activities; NE Krsko is dealing with the licensing of the project.(author)

  7. To License or Not to License Remanufacturing Business?

    Directory of Open Access Journals (Sweden)

    Zu-Jun Ma

    2018-01-01

    Full Text Available Many original equipment manufacturers (OEMs face the choice of whether to license an independent remanufacturer (IR to remanufacture their used products. In this paper, we develop closed-loop supply chain models with licensed and unlicensed remanufacturing operations to analyze the competition and cooperation between an OEM and an IR. The OEM sells new products and collects used products through trade-ins, while the IR intercepts the OEM’s cores to produce remanufactured products and sell them in the same market. We derive optimal decisions for each of the two types of firms in licensed and unlicensed remanufacturing scenarios and identify conditions under which the OEM and the IR would be most likely to cooperate with each other in implementing remanufacturing. The results show although it is beneficial for an OEM to license an IR to remanufacture its cores, it is not always necessary for an IR to accept OEM’s authorization. Moreover, we contrast the result for licensed remanufacturing scenario in the decentralized system with that in the centrally coordinated system to quantify potential inefficiency resulting from decentralization of decision making.

  8. Technology licensing in China

    DEFF Research Database (Denmark)

    Wang, Yuandi; Li-Ying, Jason; Chen, Jin

    2015-01-01

    We explore the landscape of technology licensing among Chinese entities in the period 2000–12, using a unique database on technological licensing from the State Intellectual Property Office of China. We find that: first, among Chinese licensee organizations, firms have dominated in terms...... of the number of licensed technologies; second, the geographical distribution of licensed technologies among the provinces has gradually reached a new quantitative balance; third, utility models are the most popular technologies to be licensed and the majority of technology licensing in China has been between...... Chinese entities, and most transactions have been local within provinces; and finally, Chinese firms have gradually in-licensed newer and newer technologies, but the technologies in-licensed from foreign sources are by no means state-of-the-art. We make several suggestions for innovation policy...

  9. The DIALOGUE project. Report from the Actors group

    International Nuclear Information System (INIS)

    1993-11-01

    The DIALOGUE project has been conducted by the Swedish Nuclear Power Inspectorate (SKI) since 1990. The aim of the project was to stimulate a dialogue between different interest groups within Sweden. The purpose of this dialogue was to establish a licensing process, prior to a future licensing of a repository for spent nuclear waste, in which several of the parties involved are reasonably confident. The DIALOGUE project was carried out with the participation of other government agencies, municipalities and environmental groups and was headed by the former chairman of the National Licensing Board for Environmental Protection

  10. PWR reactor pressure vessel internals license renewal industry report; revision 1. Final report

    International Nuclear Information System (INIS)

    Schwirian, R.; Robison, G.

    1994-07-01

    The U.S. nuclear power industry, through coordination by the Nuclear Management and Resources Council (NUMARC), and sponsorship by the U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), has evaluated age-related degradation effects for a number of major plant systems, structures and components, in the license renewal technical Industry Reports (IRs). License renewal applicants may choose to reference these IRs in support of their plant-specific license renewal applications, as an equivalent to the integrated plant assessment provisions of the license renewal rule (10 CFR Part 54). Pressurized water reactor (PWR) reactor pressure vessel (RPV) internals designed by all three U.S. PWR nuclear steam supply system vendors have been evaluated relative to the effects of age-related degradation mechanisms; the capability of current design limits; inservice examination, testing, repair, refurbishment, and other programs to manage these effects; and the assurance that these internals can continue to perform their intended safety functions in the license renewal term. This industry report (IR), one of a series of ten, provides a generic technical basis for evaluation of PWR reactor pressure vessel internals for license renewal

  11. 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...

  12. 75 FR 35019 - Hampshire Paper Company; Notice Rejecting Application, Waiving Regulations, and Soliciting...

    Science.gov (United States)

    2010-06-21

    ... Paper Company; Notice Rejecting Application, Waiving Regulations, and Soliciting Applications June 15, 2010. On June 2, 2010, Hampshire Paper Company (Hampshire Paper), licensee for the Emeryville....\\1\\ \\1\\ Hampshire Paper was issued a major license for the project on June 17, 1982, for a term of 30...

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

    International Nuclear Information System (INIS)

    1987-04-01

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

  14. Licensing process characteristics of Small Modular Reactors and spent nuclear fuel repository

    Energy Technology Data Exchange (ETDEWEB)

    Söderholm, Kristiina, E-mail: kristiina.soderholm@fortum.com [Fortum Power (Finland); Tuunanen, Jari, E-mail: jari.tuunanen@fortum.com [Fortum Power (Finland); Amaba, Ben, E-mail: baamaba@us.ibm.com [IBM Complex Systems (United States); Bergqvist, Sofia, E-mail: sofia.bergqvist@se.ibm.com [IBM Rational Software (Sweden); Lusardi, Paul, E-mail: plusardi@nuscalepower.com [NuScale Power (United States)

    2014-09-15

    Highlights: • We examine the licensing process challenges of modular nuclear facilities. • We compare the features of Small Modular Reactors and spent nuclear fuel repository. • We present the need of nuclear licensing simplification. • Part of the licensing is proposed to be internationally applicable. • Systems engineering and requirements engineering benefits are presented. - Abstract: This paper aims to increase the understanding of the licensing processes characteristics of Small Modular Reactors (SMR) compared with licensing of spent nuclear fuel repository. The basis of the SMR licensing process development lies in licensing processes used in Finland, France, the UK, Canada and the USA. These countries have been selected for this study because of their various licensing processes and recent actions in the new NPP construction. Certain aspects of the aviation industry licensing process have also been studied and selected practices have been investigated as possibly suitable for use in nuclear licensing. Suitable features for SMR licensing are emphasized and suggested. The licensing features of the spent nuclear fuel deep repository along with similar features of SMR licensing are discussed. Since there are similar types of challenges of lengthy licensing time frames, as well as modular features to be taken into account in licensing, these two different nuclear industry fields can be compared. The main SMR features to take into account in licensing are: • Standardization of the design. • Modularity. • Mass production. • Serial construction. Modularity can be divided into two different categories: the first category is simply a single power plant unit constructed of independently engineered modules (e.g. construction process for Westinghouse AP-1000 NPP) and the second one a power plant composed of many reactor modules, which are manufactured in factories and installed as needed (e.g. NuScale Power SMR design). The deep underground repository

  15. The nuclear licensing and supervisory procedures for nuclear facilities in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1982-02-01

    A combined system has been developed in the Federal Republic of Germany: the States execute the Atomic Energy Act on behalf of the Federal Government. Despite these differences, the safety requirements and the safety standard achieved vary only insignificantly, as a result of a world-wide communication and of international cooperation. The legal prerequesites for the German nuclear licensing procedures have been established about 20 years ago, and, by a number of amendments have been adapted to new perceptions and developments. Several supplementary ordinances, due to further developments in nuclear technology, are being prepared. The work on associated technical provision, which had been neglected for a long time, has in recent years been tackled systematically and should, before long, lead to a comprehensive programme of safety standards, which simplifies and expedites the nuclear licensing procedures. Essential features of the licensing procedure are the phased structure and the division into intermediate steps which render it possible to adapt the safety requirements to the advancing state of science and technology. The responsible authorities call in experts for the safety verification of the application documents. It is the task of these experts to make assessments and to conduct quality examinations in the manufacturing plants and at the site, and to carry out recurrent tests. The public is involved by the announcement of the projects, the display of the documents and by the opportunity to raise objections during the licensing procedure. Licenses granted can be contested before the administrative courts. This procedure paves the way for the achievement of a satisfactory balance between private and public interests. (orig./HP)

  16. Licensing Support Network: An Electronic Discovery System

    International Nuclear Information System (INIS)

    Gil, A. V.; Jensen, D.; McKinnon, B.

    2002-01-01

    The necessary authorization for the U. S. Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) to submit a License Application (LA) is contingent upon the policy process defined in the Nuclear Waste Policy Act, as amended (NWPA), with some steps yet to occur. In spite of this uncertainty, the DOE must take prudent and appropriate action now, and over the next several years, to prepare for submittal of an application and to facilitate the U. S. Nuclear Regulatory Commission (NRC) review of this application, if the Yucca Mountain site is recommended and approved for repository development. One of these steps the DOE has taken involves working with the NRC's Advisory Review Panel to develop Licensing Support Network (LSN) requirements and guidelines. The NRC has made a prototype of the LSN web page available at www.LSNNET.gov. The OCRWM part of the LSN currently has an indefinite life cycle and may need to remain in existence until the repository is closed, which could be as long as 325 years

  17. 37 CFR 5.25 - Petition for retroactive license.

    Science.gov (United States)

    2010-07-01

    ... invention of a pending application and no petition under § 1.181 has been filed, a final rejection of the..., DEPARTMENT OF COMMERCE GENERAL SECRECY OF CERTAIN INVENTIONS AND LICENSES TO EXPORT AND FILE APPLICATIONS IN... be renewed. Failure to renew the petition within the set time period will result in a final denial of...

  18. Project development and commercialisation of on-line analysis systems

    International Nuclear Information System (INIS)

    Watt, J.S.

    2000-01-01

    A project team first in the Australian Atomic Energy Commission (AAEC) and since 1982 in CSIRO has developed many on-line analysis systems for the mineral and energy industries. The development of these projects, usually lasting 7-10 years, has followed a common pattern of laboratory R and D, field trials, commercialisation and technology transfer. This successful pattern is illustrated using examples of the development of systems for the on-line analysis of mineral slurries, for determination of the ash content of coal on conveyors, and for determination of the flow rates of oil, water and gas in pipelines. The first two systems, licensed to Australian companies, are used world-wide. They are now the market leaders for radioisotope gauges in their application field. The third, the multiphase flow meter, was licensed in 1997 to an international company. This meter has even greater potential than the other two systems for economic benefit from its use and for numbers of installations. (author)

  19. Image simulation for automatic license plate recognition

    Science.gov (United States)

    Bala, Raja; Zhao, Yonghui; Burry, Aaron; Kozitsky, Vladimir; Fillion, Claude; Saunders, Craig; Rodríguez-Serrano, José

    2012-01-01

    Automatic license plate recognition (ALPR) is an important capability for traffic surveillance applications, including toll monitoring and detection of different types of traffic violations. ALPR is a multi-stage process comprising plate localization, character segmentation, optical character recognition (OCR), and identification of originating jurisdiction (i.e. state or province). Training of an ALPR system for a new jurisdiction typically involves gathering vast amounts of license plate images and associated ground truth data, followed by iterative tuning and optimization of the ALPR algorithms. The substantial time and effort required to train and optimize the ALPR system can result in excessive operational cost and overhead. In this paper we propose a framework to create an artificial set of license plate images for accelerated training and optimization of ALPR algorithms. The framework comprises two steps: the synthesis of license plate images according to the design and layout for a jurisdiction of interest; and the modeling of imaging transformations and distortions typically encountered in the image capture process. Distortion parameters are estimated by measurements of real plate images. The simulation methodology is successfully demonstrated for training of OCR.

  20. The PRINCE Project and its Applications- VERSION2

    OpenAIRE

    Bescos, Sylvie; Bisière, Christophe; Gailly, Pierre-Joseph; Krautter, Wolfgang

    1992-01-01

    The Esprit project Prince aims at development of an industrial Constraint Logic Programing environment based on the Prolog III language. In parallel, the current technology is being validated within the project on representative real-world examples. This paper describes the current status of the three application domains which were Selected to demonstrate the applicability and usefulness of CLP. These applications deal with industrial systems engineering, medium term banking planning and jobs...

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