WorldWideScience

Sample records for specification design licensing

  1. 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

  2. 31 CFR 596.309 - Specific license.

    Science.gov (United States)

    2010-07-01

    ... FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM LIST GOVERNMENTS SANCTIONS REGULATIONS General Definitions § 596.309 Specific license. The term specific license means any license or...

  3. Specificity in the licensing process of reduced enrichment in the Bulgarian research reactor

    International Nuclear Information System (INIS)

    Vitkova, Marietta; Gorinov, Ivan

    2005-01-01

    The presented paper considers some specific questions of the licensing process regarding the reconstruction of the Bulgarian IRT-2000 research reactor, which includes conversion to the low enriched fuel. This specificity has risen as a result of two facts. The design of the reactor reconstruction was made on the basis of the existing fresh 36% highly enriched fuel. But after finishing of the design process, this fresh highly enriched fuel was shipped back to Russia in the framework of the RERTR program. These facts have involved some changes in both - in the licensing and the design processes. Re-analysis of the neutronic and thermal-hydraulic calculations is required to be made on the base of the technical specifications of the new LEU fuel. To facilitate the licensing process the NRA has adopted regulatory acceptance criteria for approval of the reactor core design with LEU fuel. (author)

  4. Establishment of the international collaboration and licensing preparation planning for the specific design of a prototype SFR

    International Nuclear Information System (INIS)

    Kim, Y. G.; Joo, H. K.; Cho, C. H.; Yoo, J. W.; Lee, D. U.; Ahn, K. S.; Hwang, Y. S.

    2013-05-01

    The conceptual design of prototype of Gen IV SFR (PGSFR) will be early determined through the review of the international experts. After this, the technology demonstration plan and validation of fuel design will be determined in more detail. The project will be accomplished efficiently by introducing the proven technology already validated from the international collaboration. The conceptual design and its requirements of PGSFR will be reviewed by ANL, who has a lot of design experiences in the metal fueled SFR development. The collaboration with ANL has been done through Work For Others (WFO) contract, and the MOU was signed between SFRA and Terra Power(USA), and SFRA and IGCAR. The licensing issues raised during PFBR and FBTR licensing in India will be discussed and reflected into the PGSFR design by inviting the high level expert from India, for example Dr. Chetal in IGCAR. The specific design, technology validation plan and fuel development plan will be established in more detail through the annual International Technical Review Meeting (ITRM) and experimental facilities available from the international institute and companies, which will be the basis for shortening the project period and to reduce the development cost

  5. Site Specific Vendor's License

    Data.gov (United States)

    Montgomery County of Maryland — This dataset contains information of a site-specific vendor's license which is required if an individual sells or offers to sell goods or services from a stationary...

  6. 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...

  7. 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

  8. 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)

  9. 31 CFR 595.312 - Specific license.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Specific license. 595.312 Section 595.312 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) OFFICE OF FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM SANCTIONS REGULATIONS General Definitions...

  10. 10 CFR 34.61 - Records of the specific license for industrial radiography.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Records of the specific license for industrial radiography. 34.61 Section 34.61 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND... Records of the specific license for industrial radiography. Each licensee shall maintain a copy of its...

  11. DESIGN AND LICENSING TRENDS OF THE GENERAL EDUCATIONAL PROGRAMS IN LATVIA

    OpenAIRE

    Mihailovs, Ivans Jānis; Krūmiņa, Aira Aija

    2016-01-01

    The general education program designing and licensing trends in Latvia in the period from 2010 to 2014 are analyzed in the article. Based on the general education program licensing data, it found that there isn’t a trend to license author’s program in primary education, while the secondary level of education author's programs are designed and licensed more often. The fact that primary education is more licensed programs in mathematics, science and technology, but in general secondary educatio...

  12. 31 CFR 594.307 - Licenses; general and specific.

    Science.gov (United States)

    2010-07-01

    ...) OFFICE OF FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY GLOBAL TERRORISM SANCTIONS REGULATIONS General Definitions § 594.307 Licenses; general and specific. (a) Except as otherwise specified, the term...

  13. 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

  14. 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)

  15. New nuclear plant design and licensing process

    International Nuclear Information System (INIS)

    Luangdilok, W.

    1996-01-01

    This paper describes latest developments in the nuclear power reactor technology with emphasis on three areas: (1) the US technology of advanced passive light water reactors (AP600 and S BWR), (2) regulatory processes that certify their safety, and (3) current engineering concerns. The goal is to provide and insight of how the government's regulatory agency guarantees public safety by looking into how new passive safety features were designed and tested by vendors and how they were re-evaluated and retested by the US NRC. The paper then discusses the US 1989 nuclear licensing reform (10 CFR Part 52) whose objectives are to promote the standardization of nuclear power plants and provide for the early and definitive resolution of site and design issues before plants are built. The new licensing process avoids the unpredictability nd escalated construction cost under the old licensing process. Finally, the paper summarizes engineering concerns found in current light water reactors that may not go away in the new design. The concerns are related the material and water chemistry technology in dealing with corrosion problems in water-cooled nuclear reactor systems (PWRs and BWRs). These engineering concerns include core shroud cracking (BWRs), jet pump hold-down beam cracking (BWRs), steam generator tube stress corrosion cracking (PWR)

  16. 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

  17. Data bank usage in reload design and licensing

    International Nuclear Information System (INIS)

    Goudey, J.L.; Hansen, E.C.; Scigliano, S.M.; Williams, R.D.

    1986-01-01

    In 1977 the Nuclear Energy Business Operations of General Electric Company (GE) began a major project to automate sequential execution of the data transfer between the various computer programs used in performing calculations to support design, release, licensing, and core management of fuel used in boiling water reactors (BWRs). A centralized and controlled data bank was designed and implemented to complement the data management system and to achieve the following objectives: (1) enhance the quality and reliability of engineering data used for design and licensing of BWR fuel; (2) provide for traceability and long-term retrievability of engineering data as required by 10CFR50, Appendix B; (3) standardize the location and minimize the redundancy of engineering data; and (4) make engineering data readily available to all individuals and computer programs with a need for it. The structure of this data bank, which has become known as the BWR Engineering Data Bank or BWR/EDB, was purposefully left flexible and expandable with the ability to accommodate numerical, logical, and textual data. The BWR/EDB has been used by GE during fuel release, fuel and core design, reload licensing, and core management activities for 30 to 40 commercial power reactors over the past several years

  18. 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.

  19. 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

  20. 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

  1. 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...

  2. 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.)

  3. 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)

  4. Licensing management system prototype system design

    International Nuclear Information System (INIS)

    Immerman, W.H.; Arcuni, A.A.; Elliott, J.M.; Chapman, L.D.

    1983-11-01

    This report is a design document for a prototype implementation of a licensing management system (LMS) as defined in SAND83-7080. It describes the concept of operations for full implementation of an LMS in accordance with the previously defined functional requirements. It defines a subset of a full LMS suitable for meeting prototype implementation goals, and proposes a system design for this subset. The report describes overall system design considerations consistent with, but more explicit than the general characteristics required by the LMS functional definition. A high level design is presented for just those functions selected for prototype implementation. The report also provides a data element dictionary describing the structured logical data elements required to implement the selected functions

  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. 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)

  7. ACR: Licensing and design readiness

    International Nuclear Information System (INIS)

    Alizadeh, A.

    2009-01-01

    Full text The Canadian nuclear technology has a long history dating back to the 1940s. In this regard, Canada is in a unique situation, shared only by a very few countries, where original nuclear power technology has been invented and further developed. Canadian Nuclear Safety Commission (CNSC), then called AECB, was established in 1946. CNSC focuses on nuclear security, nuclear safety, establishing health and safety regulations, and has also played an instrumental role in the formation of the IAEA. CNSC has provided assistance to the establishment of regulatory authorities in AECL's client countries such as Korea, Argentina, China and Romania. AECL has developed the Gen III+ ACR 1000 as evolutionary advancement of the current CANDU 6 reactor. ACR-1000 has evolved from AECL's in depth experience with CANDU systems, components, and materials, as well as the feedback received from owners and operators of CANDU plants. The ACR-1000 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. ACR-1000 has completed its Basic Engineering, has advanced in the licensing process in Canada, and is ready for deployment in Canadian and world markets. EC6 is an evolution of CANDU 6 and is a Gen III natural uranium fuelled reactor. Its medium size and potential for fuel localization and advanced fuel cycles is an optimal strategic solution in many markets.AECL's reactor products are shown to be compliant with a variety of licensing and regulatory requirements. These include the new CNSC DRD-337, IAEA NS-R1, and EUR. This allows the countries interested in CANDU reactor products to be confident of its licensing in their own regulatory regimes.

  8. TVA experience in BWR reload design and licensing

    International Nuclear Information System (INIS)

    Robertson, J.D.

    1986-01-01

    TVA has developed and implemented the capability to perform BWR reload core design and licensing analyses. The advantages accruing from this capability include the tangible cost-savings from performing reload analyses in-house. Also, ''intangible'' benefits such as increased operating flexibility and the ability to accommodate multivendor fuel designs have been demonstrated. The major disadvantage with performing in-house analyses is the cost associated with development and maintenance of the analytical methods and staff expertise

  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. 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

  11. 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

  12. 10 CFR 40.34 - Special requirements for issuance of specific licenses.

    Science.gov (United States)

    2010-01-01

    ... license to manufacture industrial products and devices containing depleted uranium, or to initially....32; (2) The applicant submits sufficient information relating to the design, manufacture, prototype... industrial product or device to provide reasonable assurance that possession, use, or transfer of the...

  13. Impact of ITER liquid metal design options on safety level and licensing - Sweden

    International Nuclear Information System (INIS)

    Harfors, C.; Devell, L.; Johansson, Kjell; Lundell, B.; Rolandsson, S.

    1993-01-01

    The safety level and licensability of five design options for ITER coolant, breeding material and structural material are assessed, with emphasis on some specified accident scenarios. The safety level is assessed in terms of barrier requirements and the feasibility to construct and qualify such a barrier. The licensability in Sweden of each design option is assessed based on the indicated safety level and on a judgement of the technical feasibility to construct and qualify the ITER tokamak itself, based on the selected design option. 20 refs

  14. Aseismic Design Licensings and guidelines for nuclear power plant in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Yoshizawa, Kazumi [Agency of Natural Resources and Energy, Tokyo (Japan)

    1997-03-01

    This paper describes Aseismic Design Licensing for Japanese Nuclear Power Plants which includes system, procedures and brief contents concerned application, permit and inspection, and the `Examination Guide for Aseismic Design of the Nuclear Power Reactor Facilities` which focused principals of seismic design loads, load combinations, and allowable limits. (J.P.N.)

  15. Aseismic Design Licensings and guidelines for nuclear power plant in Japan

    International Nuclear Information System (INIS)

    Yoshizawa, Kazumi

    1997-01-01

    This paper describes Aseismic Design Licensing for Japanese Nuclear Power Plants which includes system, procedures and brief contents concerned application, permit and inspection, and the 'Examination Guide for Aseismic Design of the Nuclear Power Reactor Facilities' which focused principals of seismic design loads, load combinations, and allowable limits. (J.P.N.)

  16. CANFLEX-NU fuel licensing status and issues in Korea

    International Nuclear Information System (INIS)

    Geun-Sun Auh; Jun-Sang Park; Sweng-Woong Woo; Yong-Ho Ryu

    1999-01-01

    The CANFLEX-NU Fuel Design Report (FDR) for Wolsung 1,2,3,4 was submitted for licensing review in July 1996. The FDR contains sections of fuel rod design, fuel bundle design, nuclear design and thermal-hydraulic design. Each section describes the design bases, design methodology and design evaluation results showing that the design bases are met. The CANFLEX-NU fuel design is not finalized yet in Korean licensing point of view. For example, among others, new Xc-BL correlation is needed to be developed, fuel rod gap reduction effect is to be considered in the Critical Heat Flux, more information for power ramp defect of fuel rod especially in the end-cap weld region is needed in the fuel rod design, and enough data are not available in irradiated conditions in the fuel rod and bundle designs. The specific detailed technical licensing issues and their backgrounds are explained for the CANFLEX-NU FDR in Korea. The Korean nuclear regulation environment is changing due to the Korean government policy of overall regulation reduction. The contents and timetables of Korean nuclear regulation changes are also explained for new fuel licensing. (author)

  17. 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

  18. New Reactor Siting, Licensing and Construction Experience. Proceedings of the 2. CNRA International Workshop on 'New Reactor Siting, Licensing and Construction Experience'

    International Nuclear Information System (INIS)

    2013-01-01

    This report documents the proceedings from the 2. Workshop on New Reactor Siting, Licensing and Construction Experience. A total of 45 specialists from 16 countries and international organisations attended. The meeting was sponsored by the OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities and hosted by the US Nuclear Regulatory Commission (U.S.NRC). The objectives of the workshop were to provide a forum to exchange information on lessons learned from siting, licensing and constructing new nuclear power plants around the world. Key focus areas included siting practices and regulatory positions that have been enhanced as a result of the Fukushima accident; lessons learned from licensing and design review approaches and challenges, construction experience and recommendations for regulatory oversight; and regulatory cooperation on generic and design specific issues through the MDEP specific working groups. The workshop was structured in 4 technical sessions, each followed by ample time for panel discussions. The first technical session was devoted to regulatory cooperation on generic and design specific issues, MDEP working groups (EPR, AP1000), vendor inspection co-operation, digital I and C, and codes and standards. The second technical session was intended to discuss and share regulatory positions on siting practices and enhancements as a result of lessons learned from Fukushima accident. The third technical session addressed the construction experience and regulatory oversight of new reactor construction activities. And the fourth technical session included presentations on the lessons learned from regulatory licensing reviews of new reactor designs

  19. Development of quantitative goals for inherent safety feature design and licensing

    International Nuclear Information System (INIS)

    Kastenberg, W.E.; Apostolakis, G.; Dhir, V.K.; Okrent, D.

    1987-01-01

    There is now considerable interest in the development of advanced fast reactors whose major focus is inherent safety. The achievement of inherent safety can be viewed from several aspects. In the Integral Fast Reactor Concept the approach is to utilize the intrinsic characteristics of pool-type liquid metal fast breeder reactors (LMFBRs) and the properties of metal fuels to integrate a high degree of inherent safety into the design. The PRISM and SAFR concepts focus on other inherent safety features. The reactors discussed above represent a radical departure from existing LWR designs as well as previous LMFBR designs (e.g., CRBRP) which are based, for the most part, on the General Design Criteria found in 10CFR50 Appendix. In view of these parallel developments (advanced reactors exploiting inherent safety and the use of quantitative goals to augment licensing), there appears to be a need to perform research on the development of methods for designing, assessing, and licensing inherent safety features in advanced reactors. The objectives of such research are outlined

  20. Design, implementation and licensing of improvement measures

    International Nuclear Information System (INIS)

    Rousset, P.

    2000-01-01

    Modifications are designed to contribute to improve the level of safety, and the level of performance of the plants. The successful implementation of a modification depends on the quality of the design and particularly the good fitting of the modification in the existing design, on the perfect consistency of the licensing approach and on the good management of the project constraints and interfaces. Over the last ten years, FRAMATOME has accumulated a large and varied experience in these activities, as shown in the few examples briefly described in the presentation. Within the Mochovce completion project, FRAMATOME has been in charge of the basic design or implementation of about twenty safety measures. This involved establishing efficient partnerships with design organizations and suppliers in the Slovak Republic, Czech Republic, and Russia. A similar approach is used in the frame of the Kozloduy 5-6 modernization program, where the basic engineering contract is conducted since 1998 and the main contract under discussion. From the very beginning of the TACIS program FRAMATOME has been involved in projects dealing with the design of reactor safety systems. For example, an extensive work aiming at developing a methodology for accident analysis in VVER reactor was initiated in 1993, in collaboration with Siemens, Kurchatov Institute and OKB Gidropress. This methodology was recently used successfully in a new project with the objective to evaluate the possible modification of reactor protection signals of some Russian reactors. Within the PHARE program, a complete analysis of the primary to secondary leakage risk was conducted for Paks nuclear power plant. This involved the writing and validation of the relevant emergency procedure, specification of the leak detection system, study of an improved design of the collector cover, and recommendation of some systems modifications. A last example is the study of the modifications of main steam lines performed in the frame

  1. Electronic licensing filing system development and implementation experience

    International Nuclear Information System (INIS)

    Walderhaug, J.

    1993-01-01

    The Electronic Licensing Filing System (ELFS) is a microcomputer-based integrated document search and retrieval system for the Nuclear Regulatory Affairs Division of Southern California Edison (SCE). ELFS allows the user access to the current licensing basis of a subject by providing an easily searchable electronic information data base consisting of regulatory correspondence, design-bases documentation, licensing documents [updated final safety and analysis report (UFSAR) and technical specifications], and regulatory guidance or directives [10CFR, generic letters, bulletins, notices, circulars, regulatory guides, policy statements, and selected US Nuclear Regulatory Commission (NRC) regulations]. It is used in the preparation of correspondence and submittals to the NRC, 50.59 safety evaluations, design-bases reconstitution, and commitment tracking and management

  2. 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)

  3. 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)

  4. 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)

  5. 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.

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

    International Nuclear Information System (INIS)

    Popp, D.M.

    2000-01-01

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

  7. Cooperation in reactor design evaluation and licensing

    International Nuclear Information System (INIS)

    Kaufer, B.; Wasylyk, A.

    2014-01-01

    In January 2007 the World Nuclear Association (WNA) established the Cooperation in Reactor Design Evaluation and Licensing (CORDEL) Working Group with the aim of stimulating a dialogue between the nuclear industry (including reactor vendors, operators and utilities) and nuclear regulators (national and international organisations) on the benefits and means of achieving a worldwide convergence of reactor safety standards for reactor designs. From the time of its inception to the present, CORDEL has evolved from a group of experts discussing how to achieve international standardisation in nuclear safety design to an established and recognised working group dedicated to analysing and forging common understandings in key areas as input to major decisions on nuclear energy policy. This paper will review the general directions and activities CORDEL plans to undertake during the next five-year period, including its general strategy, activities, priorities and interactions with its customers in order to meet its objectives. (author)

  8. Cooperation in reactor design evaluation and licensing

    Energy Technology Data Exchange (ETDEWEB)

    Kaufer, B.; Wasylyk, A. [World Nuclear Association, London (United Kingdom)

    2014-07-01

    In January 2007 the World Nuclear Association (WNA) established the Cooperation in Reactor Design Evaluation and Licensing (CORDEL) Working Group with the aim of stimulating a dialogue between the nuclear industry (including reactor vendors, operators and utilities) and nuclear regulators (national and international organisations) on the benefits and means of achieving a worldwide convergence of reactor safety standards for reactor designs. From the time of its inception to the present, CORDEL has evolved from a group of experts discussing how to achieve international standardisation in nuclear safety design to an established and recognised working group dedicated to analysing and forging common understandings in key areas as input to major decisions on nuclear energy policy. This paper will review the general directions and activities CORDEL plans to undertake during the next five-year period, including its general strategy, activities, priorities and interactions with its customers in order to meet its objectives. (author)

  9. 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

  10. Licensing aspects in the verification of the SNR 300 design concept against hypothetical accidents

    International Nuclear Information System (INIS)

    Kugler, E.; Wiesner, S.

    1976-01-01

    The German prototype of a fast breeder reactor, the SNR 300, is being built near Kalkar on the Lower Rhine. It is a loop-type fast sodium-cooled reactor, designed and constructed by Interatom, Bensberg. Experiences gained from the first phase of construction are described. The report is restricted to the aspects of the SNR 300 design against a core disruptive accident (CDA) and its consequences and to the difficulties having arisen in the verification of the design concept so far. Some examples of the detailed design are described and discussed from the licensing authority's point of view showing that the difficulties have been typical for a prototype reactor subjected to a regular licensing procedure

  11. Establishment of regulatory framework for the development reactor licensing

    International Nuclear Information System (INIS)

    Jo, Jong C.; Yune, Young G.; Kim, Woong S.; Ahn, Sang K.; Kim, In G.; Kim, Hho J.

    2003-01-01

    With a trend that various types of advanced reactor designs are currently under development worldwide, the Korea Atomic Energy Research Institute has been developing an advanced reactor called ' System-integrated Modular Advanced Reactor (SMART)', which is a small sized integral type pressurized water reactor with a rated thermal power of 330 MW. To demonstrate the safety and the performance of the SMART reactor design, the SMART Research and Development Center has embarked to build a scaled-down pilot plant of SMART, called 'SMART-P' with a rated thermal power of 65 MW. In preparation for the forthcoming applications for both construction permit and operating license of SMART-P in the near future, the Korea Institute of Nuclear Safety is developing a new regulatory framework for licensing review of such a development reactor, which covers establishment of licensing process, identification and resolution of technical and safety issues, development of regulatory evaluation or verification-purpose computer codes and analytical methods, and establishment of design-specific, general design and operating criteria, regulations, and associated regulatory guides. This paper presents the current activities for establishing a regulatory framework for the licensing of a research and development reactor. Discussions are made on the SMART-P development program, the current Korean regulatory framework for reactor licensing, the SMART-P licensing-related issues, and the approach and strategy for developing an effective regulatory framework for the SMART-P licensing

  12. 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.

  13. 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

  14. The impact of safety standards updating for design purposes in nuclear power plants licensing

    International Nuclear Information System (INIS)

    Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

    2009-01-01

    The Brazilian experience of nuclear power plants licensing was consolidated by the use of the Brazilian, American, German and IAEA standards. Independently of the set of norms, standards or guides to be used, this set should be in consonance with the state-of-art or the current state of knowledge in science and technology. In the general design criteria of US NRC or German BMI, or in the Brazilian norms (CNEN) or even, in the IAEA standards, this aspect is always emphasized. On the other hand, the international operational experience of nuclear reactors (for example, TMI accident) also contributes to the updating of norms and standards. The use of new technologies (for example, digital technology) impels the norms and standards to adopt new design criteria related to the new technological context. Moreover, we must add the particular vision that each country can have concerning to specific topics in nuclear safety. This work discusses how the norms, standards and guides used in the nuclear licensing are being reviewed to cope with the requirement of the state-of-art. In order to accomplish this aim we took some general design criteria to exemplify how they are fulfilled, mainly those related directly with the protection of the defense-in-depth barriers: primary coolant system, containment vessel and containment systems, including external events and severe accidents. In complement to the deterministic analysis, it is also discussed the design criteria related to the human factors engineering and probabilistic safety analysis, including severe accidents aspects. (author)

  15. Specification of requirements to get a license for an Independent Spent Fuel Dry Storage Installation (ISFSI) at the site of the NPP-LV

    International Nuclear Information System (INIS)

    Serrano R, M. L.

    2015-09-01

    This article describes some of the work done in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) to define specifically the requirements that the Federal Electricity Commission (CFE) shall meet to submit for consideration of CNSNS an operation request of an Independent Spent Fuel Dry Storage Installation (ISFSI). The project of a facility of this type arose from the need to provide storage capacity for spent nuclear fuel in the nuclear power plant of Laguna Verde (NPP-LV) and to continue the operation at the same facility in a safe manner. The licensing of these facilities in the United States of America has two modes: specific license or general license. The characteristics of these licenses are described in this article. However, in Mexico the existing national legislation is not designed for such license types, in fact there is a lack of standards or regulations in this regard. The regulatory law of Article 27 of the Constitution in the nuclear matter, only generally establishes that this type of facility requires an authorization from the Ministry of Energy. For this reason and because there is not a national legislation, was necessary to use the legislation that provides the Nuclear Regulatory Commission of USA, the US NRC. However, it cannot be applied as is established, so was necessary that the CNSNS analyze one by one the requirements of both types of license and determine what would be required to NPP-LV to submit its operating license of ISFSI. The American regulatory applicable to an ISFSI, the 10-Cfr-72 of the US NRC, establishes the requirements for both types of licenses. Chapter 10-Cfr was analyzed in all its clauses and coupled to the laws, regulations and standards as well as to the requirements established by CNSNS, all associated with a store spent fuel on site; the respective certification of containers for spent fuel dry storage was not included in this article, even though the CNSNS also performed that activity under the

  16. Characterization of design ground motion for the central and eastern United States: licensing implications

    International Nuclear Information System (INIS)

    Litehiser, J.; Carrato, P.

    2005-01-01

    For the first time in decades several US utilities are exploring the possibility of building new Nuclear Power Plant (NPP) generating capacity in the Central and Eastern United States (CEUS). Among the many topics that must be considered to license a nuclear plant (NPP) is appropriate design to mitigate the potential effects of vibratory ground motion from earthquakes. Agreement on seismic design ground motion was not always easy during licensing of the last generation of NPPs. Therefore, over the last few decades both industry and the United States Nuclear Regulatory Commission (USNRC) have worked to find ground motion criteria that recognize and overcome earlier licensing difficulties. Such criteria should be stable and easily implemented. Important and complementary programs under the direction of the Lawrence Livermore National Laboratory (LLNL) and the Electric Power Research Institute (EPRI) were part of this effort, and these studies resulted in probabilistic seismic hazard assessments (PSHAs) for a number of CEUS NPP sites. These results and the concepts underlying them are now incorporated into both USNRC regulation and regulatory guidance. Nevertheless, as the utilities and the NRC begin a renewed licensing dialog, issues of regulatory interpretation of earthquake ground motion design criteria have emerged. These issues are as fundamental as the shape and amplitude of ground motion design response spectra and as significant as the impact of these spectra on structural design. Successful and timely resolution of these issues will significantly impact the future of nuclear power in the US. The purpose of this paper is to briefly describe some of these issues and the approaches that have been proposed for their resolution. (authors)

  17. 10 CFR 60.43 - License specification.

    Science.gov (United States)

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES Licenses...) Restrictions as to the physical and chemical form and radioisotopic content of radioactive waste. (2) Restrictions as to size, shape, and materials and methods of construction of radioactive waste packaging. (3...

  18. Integrating Cloud-Computing-Specific Model into Aircraft Design

    Science.gov (United States)

    Zhimin, Tian; Qi, Lin; Guangwen, Yang

    Cloud Computing is becoming increasingly relevant, as it will enable companies involved in spreading this technology to open the door to Web 3.0. In the paper, the new categories of services introduced will slowly replace many types of computational resources currently used. In this perspective, grid computing, the basic element for the large scale supply of cloud services, will play a fundamental role in defining how those services will be provided. The paper tries to integrate cloud computing specific model into aircraft design. This work has acquired good results in sharing licenses of large scale and expensive software, such as CFD (Computational Fluid Dynamics), UG, CATIA, and so on.

  19. 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

  20. RECOGNITION DESIGN OF LICENSE PLATE AND CAR TYPE USING TESSERACT OCR AND EmguCV

    Directory of Open Access Journals (Sweden)

    Antonius Herusutopo

    2012-10-01

    Full Text Available The goal of the research is to design and implement software that can recognize license plates and car types from images. The method used for the research is soft computing using library of EmguCV. There are four phases in creating the software, i.e., input image process, pre-processing, training processing and recognition. Firstly, user enters the car image. Then, the program reads and does pre-processing the image from bitmap form into vector. The next process is training process, which is learning phase in order the system to be able recognize an object (in this case license plate and car type, and in the end is the recognition process itself. The result is data about the car types and the license plates that have been entered. Using simulation, this software successfully recognized license plate by 80.223% accurate and car type 75% accurate.Keywords: Image; Pre-Processing; License plate and Car Type Recognition, Training

  1. 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

  2. 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

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

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  4. Establishing a safety and licensing basis for generation IV advanced reactors. License by test

    International Nuclear Information System (INIS)

    Kadak, Andrew C.

    2001-01-01

    The license by test approach to licensing is a novel method of licensing reactors. It provides an opportunity to deal with innovative non-water reactors in a direct way on a time scale that could permit early certification based on tests of a demonstration reactor. The uncertainties in the design and significant contributors to risk would be identified in the PRA during the design. Deterministic analysis computer codes could be tested on a real reactor. Scaling effects and associated uncertainties would be minimized. License by test is an approach that has sufficient merit to be developed and tested

  5. Environmental qualification design for NPP refurbishment to comply with revised licensing requirements

    International Nuclear Information System (INIS)

    MacBeth, M. J.; Hemmings, R. L.

    2002-01-01

    Recent Canadian Nuclear Regulatory decisions have imposed Environmental Qualification (EQ) requirements for twenty-four Reactor Building (RB) airlocks at the four-unit Pickering Nuclear Generating Station-B (PNGS-B) facility. This paper describes the EQ modification design work completed by CANATOM-NPM for the problematic aspects for such projects. The airlocks allow RB access while providing a containment boundary and are designed to prevent a potential breach of containment for all analysed station conditions. Each PNGS-B unit has three large equipment airlocks and three smaller personnel airlocks. The airlocks must function under postulated worst-case design basis accident(DBA) conditions for assigned mission durations. The design must ensure that accident conditions cannot spuriously initiate an un-requested door opening. CANATOM-NPM reviewed site data to specify the necessary EQ modifications required to satisfy licensing requirements while providing a correct and complete as-found record of the existing airlock installation. The design team assessed the installed airlocks configuration against environmental qualification requirements to finalize the list of necessary modifications. A comprehensive, cross-discipline review of proposed design changes was completed to identify any further changes required to satisfy the final EQ licensing goal. The design team also conducted a design review of the EQ modification installation strategy to integrate the design deliverables with the installation team requirements while attempting to minimize necessary outage time for EQ modification installations. This project was completed on schedule and within the cost limitations required by the client with comprehensive, high quality final design packages. Overall improvements were realized for OPG system drawings and the electronic documentation of design data. The EQ modifications designed by CANATOM-NPM will ensure the continued operation of the PNGS-B NPP past December 31

  6. 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)

  7. 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

  8. EC6 design features and pre-project licensing review

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  9. 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

  10. Issues related to the licensing of final disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    Medici, M.A.; Alvarez, D.E.; Lee Gonzales, H.; Piumetti, E.H.; Palacios, E.

    2010-01-01

    The licensing process of a final disposal facility for radioactive waste involves the design, construction, pre-operation, operation, closure and post closure stages. While design and pre-operational stages are, to a reasonable extent, similar to other kind of nuclear or radioactive facilities, construction, operation, closure and post-closure of a radioactive waste disposal facility have unique meanings. As consequence of that, the licensing process should incorporate these particularities. Considering the long timeframes involved at each stage of a waste disposal facility, it is convenient that the development of the project being implemented in and step by step process, be flexible enough as to adapt to new requirements that would arise as a consequence of technology improvements or due to variations in the socio-economical and political conditions. In Argentina, the regulatory Standard AR 0.1.1 establishes the general guideline for the 'Licensing of Class I facilities (relevant facilities)'. Nevertheless, for radioactive waste final disposal facilities a new specific guidance should be developed in addition to the Basic Standard mentioned. This paper describes the particularities of final disposal facilities indicating that a specific licensing system for this type of facilities should be foreseen. (authors) [es

  11. Nuclear fuel licensing requirements: present status and future trends

    International Nuclear Information System (INIS)

    Gantchev, T.; Vitkova, M.; Gorinov, I.; Datcheva, D.; Rashkova, N.

    2001-01-01

    The nuclear fuel licensing process must be directed to establishing of criteria for licensing (fuel safety criteria) and relationship between safety limits, technical specifications and operational conditions. This paper discusses the fuel safety criteria as used by NRC and Russian vendor. A survey on the available fuel behavior, modeling and related computer codes is given with respect to help the licensing process including new safety features of general changes in fuel design and operational conditions. Several types of computer codes that are used in safety analysis are sensitive to fuel-related parameters. The need for further code development and verification has been stated on many occasions: new design elements, such as different cladding materials, higher burnup, different fuel microstructure and use of MOX fuel can affect the performance of these codes. Regulatory inspection practices during operation and refueling in different countries are also shown. Future trends are discussed in particular with regard to the coming high burnup and to new core management schemes

  12. FOSS License Selection and Code Management

    OpenAIRE

    Vescuso, Peter

    2011-01-01

    With nearly 2,000 free and open source software (FLOSS) licenses, software license proliferation¿ can be a major headache for software development organizations trying to speed development through software component reuse, as well as companies redistributing software packages as components of their products. Scope is one problem: from the Free Beer license to the GPL family of licenses to platform-specific licenses such as Apache and Eclipse, the number and variety of licenses make it difficu...

  13. The SLOWPOKE licensing model

    Energy Technology Data Exchange (ETDEWEB)

    Snell, V. G.; Takats, F.; Szivos, K.

    1989-08-15

    The SLOWPOKE Energy System (SES-10) is a 10 MW heating reactor that has been developed in Canada. It will be capable of running without a licensed operator in continuous attendance, and will be sited in urban areas. It has forgiving safety characteristics, including transient time-scales of the order of hours. A process called `up-front` licensing has been evolved in Canada to identify, and resolve, regulatory concerns early in the process. Because of the potential market in Hungary for nuclear district heating, a licensing plan has been developed that incorporates Canadian licensing experience, identifies specific Hungarian requirements, and reduces the risk of licensing delays by seeking agreement of all parties at an early stage in the program.

  14. 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)

  15. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1981-08-01

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors

  16. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-04-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis

  17. NRC's license renewal regulations

    International Nuclear Information System (INIS)

    Akstulewicz, Francis

    1991-01-01

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

  18. 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)

  19. 7 CFR 6.28 - Transfer of license.

    Science.gov (United States)

    2010-01-01

    ... Licensing Authority will transfer to such other person the historical, nonhistorical or designated license... escrow with the sole condition for return of escrow being that the Licensing Authority determines that... to whom the historical licenses were issued during the quota year in which the sale or conveyance...

  20. Benchmark for license plate character segmentation

    Science.gov (United States)

    Gonçalves, Gabriel Resende; da Silva, Sirlene Pio Gomes; Menotti, David; Shwartz, William Robson

    2016-09-01

    Automatic license plate recognition (ALPR) has been the focus of many researches in the past years. In general, ALPR is divided into the following problems: detection of on-track vehicles, license plate detection, segmentation of license plate characters, and optical character recognition (OCR). Even though commercial solutions are available for controlled acquisition conditions, e.g., the entrance of a parking lot, ALPR is still an open problem when dealing with data acquired from uncontrolled environments, such as roads and highways when relying only on imaging sensors. Due to the multiple orientations and scales of the license plates captured by the camera, a very challenging task of the ALPR is the license plate character segmentation (LPCS) step, because its effectiveness is required to be (near) optimal to achieve a high recognition rate by the OCR. To tackle the LPCS problem, this work proposes a benchmark composed of a dataset designed to focus specifically on the character segmentation step of the ALPR within an evaluation protocol. Furthermore, we propose the Jaccard-centroid coefficient, an evaluation measure more suitable than the Jaccard coefficient regarding the location of the bounding box within the ground-truth annotation. The dataset is composed of 2000 Brazilian license plates consisting of 14000 alphanumeric symbols and their corresponding bounding box annotations. We also present a straightforward approach to perform LPCS efficiently. Finally, we provide an experimental evaluation for the dataset based on five LPCS approaches and demonstrate the importance of character segmentation for achieving an accurate OCR.

  1. NUHOMS modular spent-fuel storage system: Design, licensing and construction

    International Nuclear Information System (INIS)

    McLean, J.C.

    1990-08-01

    Carolina Power ampersand Light Company, the US Department of Energy, and the Electric Power Research Institute are participating in a cooperative program to demonstrate the NUHOMS (NUTECH Horizontal Modular Storage) System for storing spent nuclear fuel. This storage concept/design was developed by NUTECH Engineers, which is also participating in the project. The project involves the design, construction, and testing of three reinforced concrete storage modules and three stainless steel canisters at the H. B. Robinson Steam Electric Plant. Testing will focus on (1) the system's operating and fuel handling features, and (2) verification of the design basis of the thermal and shielding performance of the storage modules. As part of the project, NRC approval of the NUTECH Topical Report on NUHOMS has been obtained as well as issuance of a 10CFR Part 72 Materials License for the H. B. Robinson site. 6 refs., 13 figs., 22 tabs

  2. 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

  3. 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.)

  4. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-07-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  5. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-05-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  6. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1983-01-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  7. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1983-03-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  8. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-11-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  9. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-10-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  10. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-08-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  11. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-09-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  12. Radioprotection guidelines to the elaboration of a specific standard for the licensing of radioactive facilities on the practice of oil and gas well logging

    International Nuclear Information System (INIS)

    Gomes, Rogerio dos Santos; Gomes, Joana D'Arc Ramos Lopes; Costa, Mara Lucia de Lara; Miranda, Marcia Valeria F.E. Sa

    2011-01-01

    The regulatory process in oil and gas well logging has shown the need for specific standard for the issuance of a license authorizing the use of sealed sources in well logging activities, in order to guarantee the quality of many factors from the point of view of radiation protection. Currently, have been used only generic radiation protection standards, but are not comprehensive or technically suitable for a well logging licensing purpose. The lack of a specific standard for licensing in radioactive well logging operations in Brazil, weakens the nuclear regulatory body in your aim of regulate and licensing the activity. This work establish, as main objective, a guideline for the future Brazilian radioprotection code in well logging operations, presenting relevant aspects not covered by generic radiation protection standards. (author)

  13. Radioprotection guidelines to the elaboration of a specific standard for the licensing of radioactive facilities on the practice of oil and gas well logging

    International Nuclear Information System (INIS)

    Gomes, Rogerio dos Santos; Gomes, Joana D'Arc Ramos Lopes; Costa, Mara Lucia de Lara; Miranda, Marcia Valeria F.E. Sa

    2011-01-01

    The regulatory process in oil and gas well logging has shown the need for specific standard for the issuance of a license authorizing the use of sealed sources in well logging activities, in order to guarantee the quality of many factors from the point of view of radiation protection. Currently, have been used only generic radiation protection standards, but are not comprehensive or technically suitable for a well logging licensing purpose. The lack of a specific standard for licensing in radioactive well logging operations in Brazil, weakens the nuclear regulatory body in your aim of regulate and licensing the activity. This work establish, as main objective, a guideline for the future Brazilian radioprotection code in well logging operations, presenting relevant aspects not covered by genetic radiation protection standards. (author)

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. Exporting the Canadian licensing program

    International Nuclear Information System (INIS)

    Whelan, D.J.

    1981-06-01

    This paper deals with the problems of an overseas regulatory agency in licensing a Canadian-supplied nuclear plant which is referenced to a plant in Canada. Firstly, the general problems associated with the use of a reference plant are discussed. This is followed by a discussion of specific problems which arise from the licensing practices in Canada. The paper concludes with recommendations to simplify the task of demonstrating the licensability of an overseas CANDU plant

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

    International Nuclear Information System (INIS)

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

    1998-07-01

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

  1. Guideline for the licensing of various designs of ionisation smoke alarms

    International Nuclear Information System (INIS)

    1978-01-01

    The purpose of the guideline is to set up criteria for the construction licensing of ionisation smoke alarms and to determine their use. This guarantees that only those ISA are licensed which correspond to the level of science and technology and that the ISA to be licensed fulfills the demands of radiation protection. The recommendations of OECD/NEA are also born in mind. (orig./HP) [de

  2. Teacher License Reciprocity. 50-State Review

    Science.gov (United States)

    Aragon, Stephanie

    2017-01-01

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

  3. Looking at the licensability of System 80+ in the UK

    International Nuclear Information System (INIS)

    Molnar, C.M.

    1993-01-01

    There are today no internationally-sanctioned nuclear power plant design or licensing guidelines, or acceptance criteria, available for a standard plant design that would have multi-national regulatory acceptability. On the contrary, a diversity of national regulations govern the design and licensing of nuclear power stations around the world. When licensing a nuclear facility in this environment, it is important for all parties (utility, designer and regulator) to recognise consciously that there are numerous solutions available to satisfy varying safety requirements. There is no one right-way - there are only trade-offs justified on safety, performance benefit and cost, which, taken together, fashion designs that conform to national licensing requirements. (Author)

  4. Licensing decisions and safety research related to LMFBR accidents

    International Nuclear Information System (INIS)

    Denise, R.P.; Speis, T.P.; Kelber, C.N.; Curtis, R.T.

    1977-01-01

    The licensing approach which ensures adequate protection of the public health and safety against serious accidents is described. This paper describes the role of core melt and core disruptive accidents in the design, safety research, and licensing processes, using the Clinch River Breeder Reactor (CRBR) as a focal point. Major design attention is placed on the prevention of these accidents so that the probability of core melt accidents is reduced to a sufficiently low level that they are not treated as design basis accidents. Additional requirements are placed upon the design to further reduce residual risk. This licensing process is supported by a confirmatory research program designed to provide an independent basis for licensing judgements. It has as a goal the resolution of generic safety issues prior to the establishment of a commercial LMFBR industry. The program includes accident analysis, experiments in materials interactions, aerosol transport and system integrity and planning for new safety test facilities. The problems are approached in a multi-disciplinary functional manner that identifies key safety issues and centralizes efforts to resolve them. The near term objectives of the program support the licensing of the Clinch River Breeder Reactor (CRBR) and the proposed Prototype Large Breeder Reactor (PLBR). The long term objectives of the program support the licensing of commercial LMFBRs during the late 1980's and beyond. This safety research is designed to provide an independent basis for the licensing judgements which must be made by the Nuclear Regulatory Commission

  5. Design reviews from a regulatory perspective

    International Nuclear Information System (INIS)

    Foster, B.D.

    1991-01-01

    This paper presents views on the role of the licensing engineer in the design process with specific emphasis on design reviews and the automated information management tools that support design reviews. The licensing engineer is seen as an important member of a design review team. The initial focus of the licensing engineer during design reviews is shown to be on ensuring that applicable regulatory requirements are addressed by the design. The utility of an automated tool, such as a commitments management system, to support regulatory requirements identification is discussed. The next responsibility of the licensing engineer is seen as verifying that regulatory requirements are transformed into measurable performance requirements. Performance requirements are shown to provide the basis for developing detailed design review criteria. Licensing engineer input during design reviews is discussed. This input is shown to be especially critical in cases where review findings may impact application of regulatory requirements. The use of automated tools in supporting design reviews is discussed. An information structure is proposed to support design reviews in a regulated environment. This information structure is shown to be useful to activities beyond design reviews. Incorporation of the proposed information structure into the Licensing Support System is proposed

  6. An overview of the licensing approach of the South African nuclear regulatory authority

    International Nuclear Information System (INIS)

    Clapisson, G.A.; Hill, T.F.; Henderson, N.R.; Keenan, N.H.; Metcalf, P.E.; Mysenkov, A.

    1997-01-01

    This paper describes the approach adopted by the South African Nuclear Regulatory Authority, the Council for Nuclear Safety (CNS) in licensing nuclear installations in South Africa. An introduction to the current South African legislation and the CNS philosophy pertaining to the licensing of nuclear installations is discussed. A typical process for granting a nuclear licence is then presented. The risk assessment process, which is used to verify compliance with the fundamental safety standards and to establish licensing requirements for a specific nuclear installation, is discussed. Based on the outcome of this assessment process, conditions of licence are set down. The generic content of a nuclear licence and mechanisms to ensure ongoing compliance with the risk criteria are presented. The regulatory process discussed in this paper, based on such a fundamental approach, may be adapted to any type of nuclear installation taking into account plant specific designs and characteristics. (author)

  7. Regulatory analysis for final rule on nuclear power plant license renewal

    International Nuclear Information System (INIS)

    1991-12-01

    This regulatory analysis provides the supporting information for the final rule (10 CFR Part 54) that defines the Nuclear Regulatory Commission's requirements for renewing the operating licenses of commercial nuclear power plants. A set of four specific alternatives for the safety review of license renewal applications is defined and evaluated. These are: Alternative A-current licensing basis; Alternative B-extension of Alternative A to require assessment and managing of aging; Alternative C -- extension of Alternative B to require assessment of design differences against selected new-plant standards using probabilistic risk assessment; and Alternative D -- extension of Alternative B to require compliance with all new-plant standards. A quantitative comparison of the four alternatives in terms of impact-to-value ratio is presented, and Alternative B is the most cost-beneficial safety review alternative

  8. Licensing Support System: Preliminary data scope analysis

    International Nuclear Information System (INIS)

    1989-01-01

    The purpose of this analysis is to determine the content and scope of the Licensing Support System (LSS) data base. Both user needs and currently available data bases that, at least in part, address those needs have been analyzed. This analysis, together with the Preliminary Needs Analysis (DOE, 1988d) is a first effort under the LSS Design and Implementation Contract toward developing a sound requirements foundation for subsequent design work. These reports are preliminary. Further refinements must be made before requirements can be specified in sufficient detail to provide a basis for suitably specific system specifications. This document provides a baseline for what is known at this time. Additional analyses, currently being conducted, will provide more precise information on the content and scope of the LSS data base. 23 refs., 4 figs., 8 tabs

  9. 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

  10. Managing Licensing in a Market for Technology

    DEFF Research Database (Denmark)

    Arora, Ashish; Fosfuri, Andrea; Rønde, Thomas

    2013-01-01

    , we find that interdependency across business units may result in more, not less, decentralization. Furthermore, even though centralization results in less information, centralized licensing deals are larger. Our model conforms to the existing evidence that reports heterogeneity across firms in both......Technology licensing is an important means for companies to extract more value from their intellectual assets. We build a model that helps understand how licensing activity should be organized within large corporations. More specifically, we compare decentralization—where the business unit using...... the technology makes licensing decisions—to centralized licensing. The business unit has superior information about licensing opportunities but may not have the appropriate incentives because its rewards depend on product market performance. If licensing is decentralized, the business unit forgoes valuable...

  11. 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

  12. HTR-PM Safety requirement and Licensing experience

    International Nuclear Information System (INIS)

    Li Fu; Zhang Zuoyi; Dong Yujie; Wu Zongxin; Sun Yuliang

    2014-01-01

    HTR-PM is a 200MWe modular pebble bed high temperature reactor demonstration plant which is being built in Shidao Bay, Weihai, Shandong, China. The main design parameters of HTR-PM were fixed in 2006, the basic design was completed in 2008. The review of Preliminary Safety Analysis Report (PSAR) of HTR-PM was started in April 2008, completed in September 2009. In general, HTR- PM design complies with the current safety requirement for nuclear power plant in China, no special standards are developed for modular HTR. Anyway, Chinese Nuclear Safety Authority, together with the designers, developed some dedicated design criteria for key systems and components and published the guideline for the review of safety analysis report of HTR-PM, based on the experiences from licensing of HTR-10 and new development of nuclear safety. The probabilistic safety goal for HTR-PM was also defined by the safety authority. The review of HTR-PM PSAR lasted for one and a half years, with 3 dialogues meetings and 8 topics meetings, with more than 2000 worksheets and answer sheets. The heavily discussed topics during the PSAR review process included: the requirement for the sub-atmospheric ventilation system, the utilization of PSA in design process, the scope of beyond design basis accidents, the requirement for the qualification of TRISO coating particle fuel, and etc. Because of the characteristics of first of a kind for the demonstration plant, the safety authority emphasized the requirement for the experiment and validation, the PSAR was licensed with certain licensing conditions. The whole licensing process was under control, and was re-evaluated again after Fukushima accident to be shown that the design of HTR-PM complies with current safety requirement. This is a good example for how to license a new reactor. (author)

  13. Design/licensing of on-site package for core component

    International Nuclear Information System (INIS)

    Ogasawara, K.; Chohzuka, T.; Shimura, T.; Kikuchi, T.; Fujiwara, R.; Karigome, S.; Takani, M.

    1993-01-01

    For storage of used core components which are produced from reactors, Tohoku EPCO decided to construct a site bunker at Onagawa site. It was also decided to develop and fabricate one packaging to transport core components from the reactor buildings to the site bunker. The packaging will be used within the power station; therefore, it shall comply with 'The Law for the Business of Electric Power' and relevant Notification. The main requirements of the packaging are as follows: 1) The number of contents, such as channel boxes and control rods, shall be as large as possible. 2) The weight and the outer dimensions of the packaging shall be within the limitation of the reactor building and the site bunker. 3) Materials shall be selected from those which have been already applied for existing packagings and utilized without any problems. 4) It shall be considered during design of trunnions that handling equipment, such as lifting beam, can be used for not only this packaging but also for existing spent fuel packagings. The design of the packaging is completed and has been licensed. The packaging is scheduled to be utilized from November, 1993. (J.P.N.)

  14. 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

  15. Fuel licensing process for an industrial use. ATF licensing process for an industrial use - Utility's perspective

    International Nuclear Information System (INIS)

    Waeckel, Nicolas

    2013-01-01

    To develop and license a breakthrough nuclear fuel technology for commercial use is becoming challenging. All the former safety analysis design limits (SAFDLs) defined in the 1970's for the standard UO 2 -Zr fuels, might no longer be applicable. Identification of the appropriate safety analysis design limits For each type of innovative fuel, the developers will have to identify and investigate all the possible failure/ruins scenarios (not only those related to severe accidents but also those related to normal operation). In order to save time and to focus on the best options, those failure scenarios (which could be 'killers' for the ATF concept) have to be determined early enough in the development process. Based on the above failure scenarios, the developers will have to propose the licensing limits (and the experimental protocol to determine and to justify them). As mentioned earlier, the licensing limits should not be defined against the accidental conditions only. For the operators, the (good) in-reactor fuel behaviour is crucial. As an example, in the case of the new fuel concepts coming with an outer coating, it is important to include the analysis of the consequences of the loss of this protective outer layer in the licensing process due to a manufacturing defect or an inevitable in-reactor fretting wear. Obviously, the new/specific SAFDLs will have to be endorsed by the regulators (which could be a long process by itself). Identification of a commercial reactor to irradiate the first ATF A commercial NPP is not a material test reactor (MTR); irradiating lead test fuel rods (LTFRs) or lead test assemblies (LTAs) implies strict requirements regarding the manufacturing processes [which should not include chemicals (additives or solvents) potentially incompatible with the nuclear technical specifications], the compatibility with the hosting fuel core (in terms of geometry, enrichment, thermal hydraulic performances, etc.) and the robustness and

  16. License - Gclust Server | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us Gclust Server License License to Use This Database Last updated : 2009/09/14 You may use this database...scribed below. The Standard License specifies the license terms regarding the use of this database and the r...equirements you must follow in using this database. The Additional License specif...icense. Standard License The Standard License for this database is the license specified in the Creative Com...mons Attribution-Share Alike 2.1 Japan . If you use data from this database, plea

  17. 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

  18. 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

  19. 10 CFR Appendix B to Part 52 - Design Certification Rule for the System 80+ Design

    Science.gov (United States)

    2010-01-01

    ... environmental issues concerning severe accident mitigation design alternatives associated with the information...-specific DCD. b. A proposed departure from Tier 2, other than one affecting resolution of a severe accident... severe accident design feature identified in the plant-specific DCD, requires a license amendment if: (1...

  20. Utilization of NPP Krsko plant specific simulator

    International Nuclear Information System (INIS)

    Fifnja, I.; Pribozic, F.; Krajnc, J.

    2002-01-01

    NPP Krsko started with licensed operator training using its own plant-specific full scope simulator in April 2000. Today, two years after simulator was completed, the benefits of simulator use are visible in various fields. The simulator was effectively used to conduct licensed operator continuing training and practical examinations. Two-year continuous training program was designed to help maintain and improve operator performance. The simulator was also used to provide just-in-time training prior to plant evolutions. Together with licensed operators the non-licensed operators are also included into simulator training to provide affective team training opportunity and to foster good communication and increase scenario realism. Now, the first group of initial licensed operator training using plant-specific simulator is also almost completed. It is the first time that NPP Krsko training department conducted complete initial training and this will represent the great experience for future training. Besides training, the simulator was also utilized for procedure development and validation, operating standards development, testing of plant modifications and other activities, like emergency preparedness procedures validation and training exercises.(author)

  1. 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.

  2. Clustering Vehicle Temporal and Spatial Travel Behavior Using License Plate Recognition Data

    OpenAIRE

    Huiyu Chen; Chao Yang; Xiangdong Xu

    2017-01-01

    Understanding travel patterns of vehicle can support the planning and design of better services. In addition, vehicle clustering can improve management efficiency through more targeted access to groups of interest and facilitate planning by more specific survey design. This paper clustered 854,712 vehicles in a week using K-means clustering algorithm based on license plate recognition (LPR) data obtained in Shenzhen, China. Firstly, several travel characteristics related to temporal and spati...

  3. The changing shape of U.S. licensing philosophy

    International Nuclear Information System (INIS)

    Remick, F.J.

    1992-01-01

    The shape of U.S. nuclear licensing and regulatory philosophy and process has already changed. The new process requires NRC review and approval of the vendor designs before a prospective utility license applicant purchases the design and begins construction. The new philosophy has resulted from the lessons learned from extensive operating experience accumulated in the United States. New criteria established for judging reactor designs include the capability of future designs to be more tolerant of accidents beyond the traditional design basis events. Qualitative and quantitative goals have been chosen as a guide for allocating resources for regulation of the currently operating plants. The changing shape of nuclear licensing and regulatory philosophy is also a result of economic circumstances in the United States. All will have a better opportunity to take part in the process which is most likely to encourage further development of safe nuclear energy in the United States. (author)

  4. Quality assurance for nuclear power plants licensing aspect

    International Nuclear Information System (INIS)

    Borovoy, W.F.G.

    1976-02-01

    For the nuclear industry, specific criteria must be implemented to provide sufficient assurance that nuclear plants will be constructed and operated to conform with design, regulatory and code requirements. In Israel the inspections or audits are performed by the IAEC Licensing Division. Local position on ANSI QA standards as well as the eighteen criteria are shown. Lists of American standards are presented. The responsibility for quality assurance is not shared, but reinforced by each responsible unit in the supply chain. (B.G.)

  5. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FACILITIES Pt. 50, App.N Appendix N to Part 50—Standardization of Nuclear Power Plant Designs: Permits To...

  6. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FOR NUCLEAR POWER PLANTS Pt. 52, App. N Appendix N to Part 52—Standardization of Nuclear Power Plant...

  7. Department of Energy licensing strategy

    International Nuclear Information System (INIS)

    Frei, M.W.

    1984-01-01

    The Department of Energy (DOE) is authorized by the Nuclear Waste Policy Act of 1982 (Act) to site, design, construct, and operate mined geologic repositories for high-level radioactive wastes and is required to obtain licenses from the Nuclear Regulatory Commission (NRC) to achieve that mandate. To this end the DOE has developed a licensing approach which defines program strategies and which will facilitate and ease the licensing process. This paper will discuss the regulatory framework within which the repository program is conducted, the DOE licensing strategy, and the interactions between DOE and NRC in implementing the strategy. A licensing strategy is made necessary by the unique technical nature of the repository. Such a facility has never before been licensed; furthermore, the duration of isolation of waste demanded by the proposed EPA standard will require a degree of reliance on probabilistic performance assessment as proof of compliance that is a first of a kind for any industry. The licensing strategy is also made necessary by the complex interrelationships among the many involved governmental agencies and even within DOE itself, and because these relationships will change with time. Program activities which recognize these relationships are essential for implementing the Act. The guiding principle in this strategy is an overriding commitment to safeguarding public health and safety and to protecting the environment

  8. Development of Advanced Non-LOCA Analysis Methodology for Licensing

    International Nuclear Information System (INIS)

    Jang, Chansu; Um, Kilsup; Choi, Jaedon

    2008-01-01

    KNF is developing a new design methodology on the Non-LOCA analysis for the licensing purpose. The code chosen is the best-estimate transient analysis code RETRAN and the OPR1000 is aimed as a target plant. For this purpose, KNF prepared a simple nodal scheme appropriate to the licensing analyses and developed the designer-friendly analysis tool ASSIST (Automatic Steady-State Initialization and Safety analysis Tool). To check the validity of the newly developed methodology, the single CEA withdrawal and the locked rotor accidents are analyzed by using a new methodology and are compared with current design results. Comparison results show a good agreement and it is concluded that the new design methodology can be applied to the licensing calculations for OPR1000 Non-LOCA

  9. The licensing processes influence on nuclear market

    International Nuclear Information System (INIS)

    Locatelli, Giorgio; Mancini, Mauro; Sainati, Tristano; Sallinen, Liisa

    2011-01-01

    The paper deals with the licensing nuclear power plants; it focuses primarily on the licensing process implications into the international nuclear market. Nowadays there are twenty-six countries that are planning to build new nuclear facilities, and thirty-seven where nuclear reactors are proposed; on the other hand, there are mainly ten international reactor vendors. At international level, there are few vendors that have sufficient resources, capabilities and experience to carry out the design and delivering of a nuclear power plant in the international market; On the other hand, the licensing processes are strictly dependent on national law frameworks, and on the nuclear policies. The paper proposes a comparison of six licensing processes (the ones established in Finland, France, Italy, South Korea, USA and UK), and analyzes its main features and implications; the IAEA licensing process is taken as reference point. The objective of the paper is to propose a systemic approach for considering the licensing procedures. The framework proposed enables facilitating the licensing management and inferring the main features of licensing contexts. The paper concludes with a forecast of the nuclear licensing context, especially with respect to the fourth generation of nuclear reactors. (author)

  10. License - Open TG-GATEs | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us Open TG-GATEs License License to Use This Database Last updated : 2012/05/24 You may use this database...scribed below. The Standard License specifies the license terms regarding the use of this database and the r...equirements you must follow in using this database. The Additional License specif...icense. Standard License The Standard License for this database is the license specified in the Creative Com...mons Attribution-Share Alike 2.1 Japan . If you use data from this database, plea

  11. Licensing of nuclear reactor operators

    International Nuclear Information System (INIS)

    1979-09-01

    Recommendations are presented for the licensing of nuclear reactor operators in units licensed according to the legislation in effect. They apply to all physical persons designated by the Operating Organization of the nuclear reactor or reactors to execute any of the following functional activities: a) to manipulate the controls of a definite reactor b) to direct the authorized activities of the reactor operators licesed according to the present recommendations. (F.E.) [pt

  12. 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

  13. Driver licensing and reasons for delaying licensure among young adults ages 18-20, United States, 2012

    OpenAIRE

    Tefft, Brian C; Williams, Allan F; Grabowski, Jurek G

    2014-01-01

    Background Motor vehicle crashes are the leading cause of death for teens and young adults in the United States. Graduated driver licensing (GDL) systems were designed to protect young novice drivers by limiting their exposure to specific risks while they gain experience driving. In the United States, most states? GDL systems only apply to new drivers younger than 18. Some experts suggest that GDL might encourage young people to wait until age 18 to obtain a license, to avoid GDL requirements...

  14. Operating reactors licensing actions summary. Volume 5, No. 2

    International Nuclear Information System (INIS)

    1985-04-01

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management. This summary report is published primarily for internal NRC use in managing the Operating Reactors Licensing Actions Program

  15. 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)

  16. Collegiate Licensing in Canada and the Statutory Advantage.

    Science.gov (United States)

    Burshtein, Sheldon

    1985-01-01

    Discusses a specific provision in a Canadian statute enabling universities and other educational institutions to obtain protection and financial gain in a collegiate licensing program, an advantage not held in other countries or by other trademark licensers in Canada. (MSE)

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

    International Nuclear Information System (INIS)

    Houghton, W.J.

    1980-06-01

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

  18. Comparison of licensing activities for operating plants designed by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Thoma, J.O.

    1985-01-01

    This report provides a comparison of a number of licensing activities for the operating Babcock and Wilcox (B and W) plants with emphasis on Rancho Seco. The factors selected were a comparison of staff resources expended in FY84, active licensing action reviews, implementation of NUREG-0737 modifications, exemptions to regulations, SALP reports, enforcement actions, and Licensee Event Reports (LERs). The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1)

  19. Specifications in early conceptual design work

    DEFF Research Database (Denmark)

    Hansen, Claus Thorp; Andreasen, Mogens Myrup

    2007-01-01

    In early conceptual design the design team is working in an uncertain situation, where the understanding of a need is limited and not much is known about the solution space. In this situation the design team has to both analyse need and explore solution space. Thus, the team has to formulate design...... specifications, which express attractive product goals, and has to synthesise the product idea. The authors of this paper see a challenge to enhance and improve our understanding of the nature of design specifications as a means to support the synthesis of a product idea. In this empirical study we analyse...... the structure and content of design specifications during early ideation activities, where initial design specifications are formulated and a product idea is synthesised. We have analysed specification documents of 19 teams of novice designers. Our analysis indicates that a productive product design...

  20. Operating reactors licensing actions summary. Vol.4, No. 4

    International Nuclear Information System (INIS)

    1984-06-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors

  1. Operating reactors licensing actions summary. Volume 5, No. 7

    International Nuclear Information System (INIS)

    1985-09-01

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  2. Operating reactors licensing actions summary. Vol. 3, No. 3

    International Nuclear Information System (INIS)

    1983-04-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regularory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program

  3. Hydropower : A Regulatory Guide to Permitting and Licensing in Idaho, Montana, Oregon, and Washington.

    Energy Technology Data Exchange (ETDEWEB)

    McCoy, Gilbert A.

    1992-12-01

    The design, construction and operation of a hydropower project can result in many potential impacts. These potential impacts are of concern to a host of federal, state, and local authorities. Early consultation with land and water management, fish and wildlife resource protection, and health and human safety-oriented agencies should occur to determine specific concerns and study requirements for each proposed project. This Guide to Permitting and Licensing outlines the characteristic features of attractive hydropower sites; summarizes an array of developmental constraints; illustrates potential environmental impacts and concerns; and summarizes all federal, state, and local permitting and licensing requirements.

  4. Hydropower: A Regulatory Guide to Permitting and Licensing in Idaho, Montana, Oregon, and Washington.

    Energy Technology Data Exchange (ETDEWEB)

    McCoy, Gilbert A.

    1992-12-01

    The design, construction and operation of a hydropower project can result in many potential impacts. These potential impacts are of concern to a host of federal, state, and local authorities. Early consultation with land and water management, fish and wildlife resource protection, and health and human safety-oriented agencies should occur to determine specific concerns and study requirements for each proposed project. This Guide to Permitting and Licensing outlines the characteristic features of attractive hydropower sites; summarizes an array of developmental constraints; illustrates potential environmental impacts and concerns; and summarizes all federal, state, and local permitting and licensing requirements.

  5. Control room habitability survey of licensed commercial nuclear power generating stations

    International Nuclear Information System (INIS)

    Driscoll, J.W.

    1988-10-01

    This document presents the results of a survey of control room habitability systems at twelve commercial nuclear generating stations. The survey, conducted by Argonne National Laboratory (ANL), is part of an NRC program initiated in response to concerns and recommendations of the Advisory Committee on Reactor Safeguards (ACRS). The major conclusion of the report is that the numerous types of potentially significant discrepancies found among the surveyed plants may be indicative of similar discrepancies throughout the industry. The report provides plant-specific and generalized findings regarding safety functions with respect to the consistency of the design, construction, operation and testing of control room habitability systems and corresponding Technical Specifications compared with descriptions provided in the license basis documentation including assumptions in the operator toxic gas concentration and radiation dose calculations. Calculations of operator toxic gas concentrations and radiation doses were provided in the license basis documentation and were not performed by the ANL survey team. Recommendation for improvements are provided in the report

  6. The road to MYRRHA. The pre-licensing phase and FEED

    International Nuclear Information System (INIS)

    2014-01-01

    The article discusses the study phase of the future research reactor MYRRHA. This study phase covers three major areas: Research and Development, licensing and engineering. In 2013, substantial progress was made in the licensing and engineering processes: licensing is currently in the pre-licensing phase, while, for engineering, the Front-end Engineering and Design (FEED) contract was signed for the construction of the non-nuclear parts of MYRRHA. The article highlights work associated with the the pre-licensing phase and the FEED.

  7. Survey of extreme load design regulatory agency licensing requirements for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Stevenson, J D

    1976-04-01

    Since 1965, when extreme load requirements began to be considered explicitly in nuclear power plant design, there has been a gradual divergence in requirements imposed by national regulatory agencies. However, nuclear plant safety is an international problem because of the potential international effects of any postulated plant failure. For this reason this paper has been prepared in an attempt to highlight the differences in national criteria currently used in the extreme load design of nuclear plant facilities. No attempt has been made to evaluate the relative merit of the criteria established by the various national regulatory agencies. This paper presents the results of a recent survey made of national atomic energy regulatory agencies and major nuclear steam supply design agencies, which requested a summary of current licensing criteria associated with earthquake, extreme wind (tornado), flood, airplane crash and accident (pipe break) loads applicable within the various national jurisdictions. Also presented are a number of comparisons which are meant to illustrate the differences in national regulatory criteria.

  8. Survey of extreme load design regulatory agency licensing requirements for nuclear power plants

    International Nuclear Information System (INIS)

    Stevenson, J.D.

    1976-01-01

    Since 1965, when extreme load requirements began to be considered explicitly in nuclear power plant design, there has been a gradual divergence in requirements imposed by national regulatory agencies. However, nuclear plant safety is an international problem because of the potential international effects of any postulated plant failure. For this reason this paper has been prepared in an attempt to highlight the differences in national criteria currently used in the extreme load design of nuclear plant facilities. No attempt has been made to evaluate the relative merit of the criteria established by the various national regulatory agencies. This paper presents the results of a recent survey made of national atomic energy regulatory agencies and major nuclear steam supply design agencies, which requested a summary of current licensing criteria associated with earthquake, extreme wind (tornado), flood, airplane crash and accident (pipe break) loads applicable within the various national jurisdictions. Also presented are a number of comparisons which are meant to illustrate the differences in national regulatory criteria. (Auth.)

  9. 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)

  10. 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)

  11. Licensed bases management for advanced nuclear plants

    International Nuclear Information System (INIS)

    O'Connell, J.; Rumble, E.; Rodwell, E.

    2001-01-01

    Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

  12. Licensed bases management for advanced nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    O' Connell, J [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E; Rodwell, E [EPRI, Palo Alto, CA (United States)

    2001-07-01

    Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

  13. Operating reactors licensing actions summary. Vol. 3, No. 6

    International Nuclear Information System (INIS)

    1983-07-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  14. Operating reactors licensing actions summary. Volume 5, No. 6

    International Nuclear Information System (INIS)

    1985-08-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management. This summary report is published for internal NRC use in managing the Operating Reactors Licensing Actions Program. Its content will change based on NRC management informational requirements

  15. RM - ODP to express nuclear licensing

    International Nuclear Information System (INIS)

    Barbosa, E.A.; Martucci, M. Jr.

    2002-01-01

    The scope of CNEN (Comissao Nacional de Energia Nuclear) is established by standards and procedures, which allow one context where several activities for nuclear licensing are realized by persons, machines and other entities of real world and by software systems. The CNEN objectives for licensing nuclear installations can be specified and they define how the systems are consisted, its nature, and which important elements were considered relevant for its constitution. The behavior, where the software will be operated, was likely defined in this paper through all aspects of its business process, which means from its licensing context. The concepts and definition showed here defined one specifics business domain, through ODP context. The functionalities of nuclear licensing process, the relationship scope and the rules of interaction that contributed for to specify the nuclear licensing process were defined, too. Therefore, the definition of the domain follows the orientation of architecture concepts and allows to implement the reflection model, where, with the auxiliary from IDEF0 (Integration Definition for Function Modeling) diagrams, the interactions between extern domains were mapped

  16. The Design and Development of Driving Game as an Evaluation Instrument for Driving License Test

    OpenAIRE

    Abdul Hadi Abdul Razak; Mohd Hairy Manap

    2013-01-01

    The focus of this paper is to highlight the design and development of an educational game prototype as an evaluation instrument for the Malaysia driving license static test. This educational game brings gaming technology into the conventional objective static test to make it more effective, real and interesting. From the feeling of realistic, the future driver can learn something, memorized and use it in the real life. The current online objective static test only make th...

  17. 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

  18. 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

  19. Design and quality assurance of control and instrumentation systems, licensing practice in Austria

    International Nuclear Information System (INIS)

    Fasko, Peter.

    1978-01-01

    The practicised way how licensing of control and instrumentation systems is performed in Austria, is related. As there is no national regulations in Austria for licensing nuclear power plants, it tries to adopt international regulations for its own purpose. (author)

  20. Licensing reform in the USA

    International Nuclear Information System (INIS)

    1991-01-01

    The licensing process for nuclear power plants in the USA is currently in two distinct stages: the issuance of a construction permit followed later by the issuance of an operation license. The ''two-step'' process has come under heavy criticism from the U.S. nuclear industry on the grounds that it causes uncertainty and delays and therefore inhibits new commitments to nuclear power plants. In 1989 the NRC published new regulations for the licensing of nuclear power plants which provide for the issuance of early site permits, safety certifications of standard designs, and combined construction permits and operating licences. The new rule was challenged by intervenors representing antinuclear groups who filed a legal challenge seeking to have the rule set aside on the grounds that it violates the Atomic Energy Act which they allege makes two-step licensing mandatory. In November 1990 the US Court of Appeals upheld the NRC's authority to issue combined licenses. An appeal for a rehearing has been filed. The paper analyses the events and the possible consequences of an adverse court decision. It reviews the options open to the NRC and industry if the court decision is upheld. The possibility of congressional action to amend the Atomic Energy Act is discussed. (author)

  1. Operating reactors licensing actions summary. Volume 5, Number 1

    International Nuclear Information System (INIS)

    1985-03-01

    This document is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program

  2. Licensed bases management for advanced nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    O' Connell, J. [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E.; Rodwell, E. [EPRI, Palo Alto, CA (United States)

    2001-07-01

    Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

  3. Structural Design Challenges in Design Certification Applications for New Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Miranda, M.; Braverman, J.; Wei, X.; Hofmayer, C.; Xu, J.

    2011-07-17

    The licensing framework established by the U.S. Nuclear Regulatory Commission under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” provides requirements for standard design certifications (DCs) and combined license (COL) applications. The intent of this process is the early reso- lution of safety issues at the DC application stage. Subsequent COL applications may incorporate a DC by reference. Thus, the COL review will not reconsider safety issues resolved during the DC process. However, a COL application that incorporates a DC by reference must demonstrate that relevant site-specific de- sign parameters are confined within the bounds postulated by the DC, and any departures from the DC need to be justified. This paper provides an overview of structural design chal- lenges encountered in recent DC applications under the 10 CFR Part 52 process, in which the authors have participated as part of the safety review effort.

  4. 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

  5. The case against a smoker's license.

    Directory of Open Access Journals (Sweden)

    Jeff Collin

    Full Text Available Tobacco continues to kill millions of people around the world each year and its use is increasing in some countries, which makes the need for new, creative, and radical efforts to achieve the tobacco control endgame vitally important. One such effort is discussed in this PLOS Medicine Debate, where Simon Chapman presents his proposal for a "smoker's license" and Jeff Collin argues against. Chapman sets out a case for introducing a smart card license for smokers designed to limit access to tobacco products and encourage cessation. Key elements of the smoker's license include smokers setting daily limits, financial incentives for permanent license surrender, and a test of health risk knowledge for commencing smokers. Collin argues against the proposal, saying that it would shift focus away from the real vector of the epidemic--the tobacco industry--and that by focusing on individuals it would censure victims, increase stigmatization of smokers, and marginalize the poor.

  6. The case for a smoker's license.

    Directory of Open Access Journals (Sweden)

    Simon Chapman

    Full Text Available BACKGROUND TO THE DEBATE: Tobacco continues to kill millions of people around the world each year and its use is increasing in some countries, which makes the need for new, creative, and radical efforts to achieve the tobacco control endgame vitally important. One such effort is discussed in this PLOS Medicine Debate, where Simon Chapman presents his proposal for a "smoker's license" and Jeff Collin argues against. Chapman sets out a case for introducing a smart card license for smokers designed to limit access to tobacco products and encourage cessation. Key elements of the smoker's license include smokers setting daily limits, financial incentives for permanent license surrender, and a test of health risk knowledge for commencing smokers. Collin argues against the proposal, saying that it would shift focus away from the real vector of the epidemic--the tobacco industry--and that by focusing on individuals it would censure victims, increase stigmatization of smokers, and marginalize the poor.

  7. The case for a smoker's license.

    Science.gov (United States)

    Chapman, Simon

    2012-01-01

    Tobacco continues to kill millions of people around the world each year and its use is increasing in some countries, which makes the need for new, creative, and radical efforts to achieve the tobacco control endgame vitally important. One such effort is discussed in this PLOS Medicine Debate, where Simon Chapman presents his proposal for a "smoker's license" and Jeff Collin argues against. Chapman sets out a case for introducing a smart card license for smokers designed to limit access to tobacco products and encourage cessation. Key elements of the smoker's license include smokers setting daily limits, financial incentives for permanent license surrender, and a test of health risk knowledge for commencing smokers. Collin argues against the proposal, saying that it would shift focus away from the real vector of the epidemic--the tobacco industry--and that by focusing on individuals it would censure victims, increase stigmatization of smokers, and marginalize the poor.

  8. The case against a smoker's license.

    Science.gov (United States)

    Collin, Jeff

    2012-01-01

    Tobacco continues to kill millions of people around the world each year and its use is increasing in some countries, which makes the need for new, creative, and radical efforts to achieve the tobacco control endgame vitally important. One such effort is discussed in this PLOS Medicine Debate, where Simon Chapman presents his proposal for a "smoker's license" and Jeff Collin argues against. Chapman sets out a case for introducing a smart card license for smokers designed to limit access to tobacco products and encourage cessation. Key elements of the smoker's license include smokers setting daily limits, financial incentives for permanent license surrender, and a test of health risk knowledge for commencing smokers. Collin argues against the proposal, saying that it would shift focus away from the real vector of the epidemic--the tobacco industry--and that by focusing on individuals it would censure victims, increase stigmatization of smokers, and marginalize the poor.

  9. Forum on specification and Design Languages

    CERN Document Server

    Maehne, Torsten

    2015-01-01

    This book brings together a selection of the best papers from the sixteenth edition of the Forum on specification and Design Languages Conference (FDL), which was held in September 2013 in Paris, France. FDL is a well-established international forum devoted to dissemination of research results, practical experiences and new ideas in the application of specification, design and verification languages to the design, modeling and verification of integrated circuits, complex hardware/software embedded systems, and mixed-technology systems. • Covers applications of formal methods for specification, verification and debug; • Includes embedded analog and mixed-signal system design; • Enables model-driven engineering for embedded systems design and development.

  10. 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

  11. Licensing activities for advanced reactors in NNC

    International Nuclear Information System (INIS)

    Chevalier, A.B.H.; Mustoe, J.; Walters, J.; Ingham, E.L.

    2001-01-01

    NNC has been involved in safety and licensing activities for advanced reactors for many years. Most recently NNC has been involved with national regulators or their representatives for the HTR (High Temperature Reactor) reactor and the possible siting of ITER (International Thermonuclear Experimental Reactor) within Europe. Commonalties between the two activities can be seen, even though one is a fission process and the other based on a completely new technology. Both have the potential to generate power at a very low overall exposure to the public and station staff, but both also need to demonstrate to the regulator the safety of a design which differs from the standard LWR practice. In both concepts passive design features provide a major part of the safety argument, but the detailed assessment and justification of these features in licensing terms still needs to be made. A number of critical safety issues can be identified, which generally apply to any advanced system. These are: Safety categorization, codes and standards; confinement or containment; ALARA; safety code modelling and data; Occupational Exposure; occupational exposures; decommissioning and waste; no evacuation, or no emergency plans. The UK is notable for a flexible licensing regime, which allows a safety case to be built up from first principles, where this is applicable. In addition, experience of licensing gas cooled, water cooled and liquid metal plant, as well as extensive experience outside the UK provides NNC with a unique insight into the different licensing methodologies which can be applied in the licensing process. This paper discusses some possible approaches which could be applied in order to satisfy regulatory demands when addressing the critical issues listed above. (author)

  12. 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.)

  13. ABWR certification work brings US licensing stability nearer

    International Nuclear Information System (INIS)

    Wilkins, D.R.; Quirk, J.F.

    1991-01-01

    The Advanced Boiling Water Reactor (ABWR) is now approaching Final Design Approval by the US Nuclear Regulatory Commission (NRC) and will then proceed on to the certification phase of the NRC's new standard plant licensing process. Successful completion of this will usher in a new era of standardization and reactor licensing stability in the US. (author)

  14. Design Specifications for Adaptive Real-Time Systems

    Science.gov (United States)

    1991-12-01

    TICfl \\ E CT E Design Specifications for JAN’\\ 1992 Adaptive Real - Time Systems fl Randall W. Lichota U, Alice H. Muntz - December 1991 \\ \\\\/ 0 / r...268-2056 Technical Report CMU/SEI-91-TR-20 ESD-91-TR-20 December 1991 Design Specifications for Adaptive Real - Time Systems Randall W. Lichota Hughes...Design Specifications for Adaptive Real - Time Systems Abstract: The design specification method described in this report treats a software

  15. The USNCR license renewal process

    International Nuclear Information System (INIS)

    Kuo, Pao-Tsin

    2002-01-01

    The US Congress promulgated a law in 1954, entitled 'Atomic Energy Act'. This Act states that operating licenses for commercial nuclear power plants are limited to a fixed term of 40 years, but they may be renewed for a period not to exceed 20 years. The terms were established mainly for economic considerations, not based on technical limitations. The U.S. Nuclear Regulatory Commission (USNRC) published the license renewal rule, Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54), in December, 1991. The rule has since been amended in May, 1995. The underlying principle of the rule is that the regulatory process is adequate for ensuring safety of operating plants. The regulatory process includes NRC's issuance of Orders, Bulletins, Generic Letters, and Information Notices, as well as a number of special inspections in addition to the continuous oversight and routine inspection activities performed by on-site inspectors. Because of this comprehensive regulatory process, compilation of the current license basis or re-verification of the current licensing basis is not considered necessary for a license renewal review. The USNRC also determined on the basis of the findings of its research programs that active structures and components are well maintained by the existing programs. Therefore, the focus of the license renewal review is on passive, long-lived structures and components and on time-limited ageing analyses. The time-limited ageing analyses are for those structures and components which were originally designed to a 40 year service life

  16. 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...

  17. Towards a theory of product design specifications

    DEFF Research Database (Denmark)

    Hansen, Claus Thorp; Andreasen, Mogens Myrup

    2004-01-01

    , which express the customers¿ need and perception of value. In this paper we will scrutinize this assumption. We outline the roles and tasks of the product design specification in order to identify the requirements on a theory of product design specifications and we identify existing theory elements....... In the design methodology literature we find guidelines and methods to compile a product design specification. The contributions are based on the common underlying assumption that it is meaningful and the only feasible approach to interpret the result of a need analysis into a set of technical specifications...... to build such a theory of product design specifications upon....

  18. Engaging design materials, formats and Framings in specific, situated co-designing

    DEFF Research Database (Denmark)

    Agger Eriksen, Mette

    Engaging co-designers in specific situations of co- designing often also means engaging tangible working materials. However, it can be challenging, so rather than seeing it as applying design methods, the paper propose applying what I call a micro-material perspective. The practical concept captu......-design situations" clustered in three quite well- known types of co-design situations framed for; Exploring Current Use(r) Practices, Mapping Networks and Co-Designing (Possible) Futures.......Engaging co-designers in specific situations of co- designing often also means engaging tangible working materials. However, it can be challenging, so rather than seeing it as applying design methods, the paper propose applying what I call a micro-material perspective. The practical concept...... captures both paying attention to the physical design materials, the formats of their exploration and the framings of focus when understanding and planning such specific co-design situations. To exemplify applying the perspective, the paper describes and discusses six specific examples of "co...

  19. 76 FR 79203 - Prospective Grant of Exclusive License: Avian Influenza Vaccines for Domesticated Poultry/Wild...

    Science.gov (United States)

    2011-12-21

    ... Exclusive License: Avian Influenza Vaccines for Domesticated Poultry/Wild Birds To Be Provided to the... serotypes H5N1, H1N1, H3N2, and H3N8 for poultry, swine and equine. Particularly one vaccine, a trivalent... influenza vaccines are specifically designed for poultry, swine and equine recipients, with the following...

  20. 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

  1. Nuclear power plant licensing in Canada

    International Nuclear Information System (INIS)

    Tong, J.S.C.; Waddington, J.G.

    1997-01-01

    The Canadian nuclear power plant licensing practice which has evolved over three decades provides a regulatory framework that promotes safe design and operation of CANDU power plants. From the very outset, it recognizes the need for simple and reliable safety systems which are separate from the systems that are normally used to produce electricity. Further, it requires the reliability of safety systems be demonstrated by routine tests during plant operation. Over the three decades, the analysis requirements to demonstrate the performance and reliability of plant systems that have a role in the detection and mitigating of accidents have also evolved. Today's requirements are defined in consultative documents C-6 and C-98. One recurring theme throughout the evolution of the licensing practice is the maxim of prescribing only basic safety requirements and rules so that designers and operators have the freedom to devise the best possible design features and operating practices

  2. Future of Nuclear Power: NRC emergency preparedness licensing activities agenda

    International Nuclear Information System (INIS)

    Essig, T.H.

    1995-01-01

    This talk summary addresses the issue of how future policies of the NRC will affect nuclear power in areas such as construction, emergency preparedness, and licensing. Specific topics covered include the following: Emergent EP licensing issues for operating nuclear Power Plants; 10CFR Part 52 and the process for licensing of Advanced Light Water Reactors (ALWRs); and potential revisions to emergency preparedness programs for future nuclear power plants

  3. Interim licensing criteria for physical protection of certain storage of spent fuel

    International Nuclear Information System (INIS)

    Dwyer, P.A.

    1994-11-01

    This document presents interim criteria to be used in the physical protection licensing of certain spent fuel storage installations. Installations that will be reviewed under this criteria are those that store power reactor spent fuel at decommissioned power reactor sites; independent spent fuel storage installations located outside of the owner controlled area of operating nuclear power reactors; monitored retrievable storage installations owned by the Department of Energy, designed and constructed specifically for the storage, of spent fuel; the proposed geologic repository operations area; or permanently shutdown power reactors still holding a Part 50 license. This criteria applies to both dry cask and pool storage. However, the criteria in this document does not apply to the storage of spent fuel within the owner-controlled area of operating nuclear power reactors

  4. 10 CFR 32.61 - Ice detection devices containing strontium-90; requirements for license to manufacture or...

    Science.gov (United States)

    2010-01-01

    ...; requirements for license to manufacture or initially transfer. 32.61 Section 32.61 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS CONTAINING BYPRODUCT MATERIAL... manufacture or initially transfer. An application for a specific license to manufacture or initially transfer...

  5. How Much are Flexibility and Uncertainty Worth in Patent Licensing?

    DEFF Research Database (Denmark)

    Leone, Maria Isabella; Oriani, Raffaele; Reichstein, Toke

    2015-01-01

    As patent licensing has become the prime driver of technology trade, understanding the rationales behind a properly-defined payment structure of the agreements is essential. Specifically, among the other remuneration components, upfront fees are critical in license negotiations since they imply a...

  6. 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

  7. 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

  8. Operating reactors licensing actions summary. Volume 5, No. 9

    International Nuclear Information System (INIS)

    1985-11-01

    This document is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  9. Operating reactors licensing actions summary. Volume 5, No. 8

    International Nuclear Information System (INIS)

    1985-10-01

    This summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  10. Operating reactors licensing actions summary. Volume 4, No. 9

    International Nuclear Information System (INIS)

    1984-11-01

    This document is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the division of licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  11. Operating reactors licensing actions summary. Vol. 4, No. 2

    International Nuclear Information System (INIS)

    1984-04-01

    This summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management

  12. Judicial problems in connection with preliminary decision and construction design approval in nuclear licensing procedures

    International Nuclear Information System (INIS)

    Schmieder, K.

    1977-01-01

    Standardization in nuclear engineering makes two demands on a legal instrument which is to make this standardization possible and which is to promote standardization in the nuclear licensing practice: On the basis of just one licence for a constructional part or a component, its applicability in any number of subsequent facility licensing procedures has to be warranted, and by virtue of its binding effect, standardization has to create a sufficiently big confidence protection with manufacturers, constructioneers and operators to offer sufficiently effective incentives for standardization. The nuclear preliminary decision pursuant to section 7 a of the Atomic Energy Act in the form of the component preliminary decision appears to be unsuitable as a legal instrument for standardization, as the preliminary decision refers exclusively to the construction of a concrete facility. For standardization in reactor engineering, the construction design approval appears to be basically the proper legal instrument on account of its legal structure as well as its economic effect. Its binding effect encouters a limitation with regard to third parties in so far that this limitation could question again the binding effect in a subsequent site-dependent nuclear licence procedure. The legal structure of the extent of the binding effect, which is decisive for the suitability of the construction design approval, lies with the legislator. The following questions have to be regulated: Ought the applicant to have a legal claim on the granting of a construction design approval, or ought it to be at the discretion of the authorities, and secondly, the extent of the binding effect in terms of time on the basis of the fixation of a time limit, or on the basis of the possibility of subsequent conditions to be imposed, or the revocation. (orig./HP) [de

  13. Presentation of reports for licensing of industrial irradiators

    International Nuclear Information System (INIS)

    2000-04-01

    This Regulation refers to the requirements of the Regulation CNEN-NE.6.02. 'Licensing of Radioactive Facilities', expressed in the section 6 related to the information for Previous Approval, in the subsection 7.2 related to the information for the Construction Licensing and in the subsection 9.2, related to the information for the Authorization for operation, for the specific case of industrial irradiators

  14. Support to design and construction of the PBMR plant

    International Nuclear Information System (INIS)

    Cazorla, F.; Moron, P.; Gonzalez, J. I.

    2010-01-01

    Developing the new reactor design to a licensable state for constructing a pilot plant is a tough task require specific resources, concerning knowledge and previous experience, which trespassing the pure scientific or technologic knowledge linked to the reactor conceptual design. Taking into consideration the experience derived from the collaboration between the South African company PBMR (PTY) Ltd.; the Pebble Bed Modular Reactor Designer, and Tecnatom SA, the article presents some of the aspects in which the companies or organization in charge of the design can demand external support to license and construct the pilot plants with guaranteed success. (Author)

  15. 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

  16. 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

  17. Licensing of the TRIGA Mark III reactor at the Mexican Nuclear Centre

    International Nuclear Information System (INIS)

    Ramirez, R.M.; Arrendondo, R.R.

    1990-01-01

    The TRIGA Mark III reactor at the Mexican Nuclear Centre went critical in 1968 and remained so until 1979 when the National Commission for Nuclear Safety and Safeguards (CNSNS), the Mexican regulatory authority, was set up. The reactor was therefore operating without a formal operating license, and the CNSNS accordingly requested the ININ to license the reactor under the existing conditions and to ensure that any modification of the original design complied with Standards ANSI/ANS-15 and with the code of practice set out in IAEA Safety Series No. 35. The most relevant points in granting the operating licence were: (a) the preparation of the Safety Report; (b) the formulation and application of the Quality Assurance Programme; (c) the reconditioning of the following reactor systems: the cooling systems; the ventilation and exhaust system; the monitoring system and control panel; (d) the training of the reactor operating staff at junior and senior levels; and (e) the formulation of procedures and instructions. Once the provisional operating license was obtained for the reactor it was considered necessary to modify the reactor core, which has been composed of 20% enriched standards fuel, to a mixed core based on a mixture of standard fuel and FLIP-type fuel with 70% 235 U enrichment. The CNSNS therefore requested that the mixed core be licensed and a technical report was accordingly annexed to the Safety Report, its contents including the following subjects: (a) neutron analysis of the proposed configuration; (b) reactor shutdown margins; (c) accident analysis; and (d) technical specifications. The licensing process was completed this year and we are now hoping to obtain the final operating license

  18. Licensing of advanced reactors: Status report and perspective

    International Nuclear Information System (INIS)

    King, T.

    1988-01-01

    In July, 1986, the U.S. Nuclear Regulatory Commission issued a Policy State on the Regulation of Advanced Nuclear Power Plants. As part of this policy, advanced reactor designers were encouraged to interact with NRC [Nuclear Regulatory Commission] early in the design process to obtain feedback regarding licensing requirements for advanced reactors. Accordingly, the staff has been interacting with the Department of Energy (DOE) and its contractors on the review of three advanced reactor conceptual designs: one modular high temperature gas-cooled reactor (MHTGR) and two liquid metal reactors (LMRs). This paper provides a status of the NRC review effort, describes the key policy and technical issues resulting from our review and provides the current status and approach to the development of licensing guidance on each

  19. Challenges in licensing a sodium-cooled advanced recycling reactor

    International Nuclear Information System (INIS)

    Levin, Alan E.

    2008-01-01

    As part of the Global Nuclear Energy Partnership (GNEP), the U.S. Department of Energy (DOE) has focused on the use of sodium-cooled fast reactors (SFRs) for the destruction of minor actinides derived from used reactor fuel. This approach engenders an array of challenges with respect to the licensing of the reactor: the U.S. Nuclear Regulatory Commission (NRC) has never completed the review of an application for an operating license for a sodium-cooled reactor. Moreover, the current U.S. regulatory structure has been developed to deal almost exclusively with light-water reactor (LWR) designs. Consequently, the NRC must either (1) develop a new regulatory process for SFRs, or (2) reinterpret the existing regulations to apply them, as appropriate, to SFR designs. During the 1980s and 1990s, the NRC conducted preliminary safety assessments of the Sodium Advanced Fast Reactor (SAFR) and the Power Reactor Innovative Small Module (PRISM) designs, and in that context, began to consider how to apply LWR-based regulations to SFR designs. This paper builds on that work to consider the challenges, from the reactor designer's point of view, associated with licensing an SFR today, considering (1) the evolution of SFR designs, (2) the particular requirements of reactor designs to meet GNEP objectives, and (3) the evolution of NRC regulations since the conclusion of the SAFR and PRISM reviews. (author)

  20. 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

  1. Standardized Technical Specifications for Westinghouse PWRs

    International Nuclear Information System (INIS)

    1978-01-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on Westinghouse plants currently being reviewed for an Operating License. Accordingly, the document contains specifications applicable to plants (1) with either 3 or 4 loops and (2) with and without loop stop valves. In addition, four separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric, Ice Condenser, Sub-Atmospheric, and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. The format of the STS addresses the categories required by 10 CFR 50 and consists of six sections covering the areas of: Definitions, Safety Limits and Limiting Safety System Settings, Limiting Conditions for Operation, Surveillance Requirements, Design Features, and Administrative Controls

  2. 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

  3. Will nuclear power plant standardization reduce the licensing impact on construction

    International Nuclear Information System (INIS)

    Allen, J.M.; Bingham, W.G.; Keith, D.G.

    1976-01-01

    The NRC and the nuclear industry have been pursuing standardization quite vigorously in an effort to reduce the cost and schedule for the design and construction of nuclear power plants. The NRC is currently reviewing standard plant applications submitted under each of four standardization options. In addition, the NRC has published Standard Review Plans and Standard Technical Specifications. Although problems exist in the implementation of standardization and in areas unaffected by standardization, each of these standardization methods has the potential to reduce the licensing impact on construction

  4. 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

  5. Engineered waste-package-system design specification

    International Nuclear Information System (INIS)

    1983-05-01

    This report documents the waste package performance requirements and geologic and waste form data bases used in developing the conceptual designs for waste packages for salt, tuff, and basalt geologies. The data base reflects the latest geotechnical information on the geologic media of interest. The parameters or characteristics specified primarily cover spent fuel, defense high-level waste, and commercial high-level waste forms. The specification documents the direction taken during the conceptual design activity. A separate design specification will be developed prior to the start of the preliminary design activity

  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. 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

  8. 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...

  9. 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

  10. Food Design Thinking: A Branch of Design Thinking Specific to Food Design

    Science.gov (United States)

    Zampollo, Francesca; Peacock, Matthew

    2016-01-01

    Is there a need for a set of methods within Design Thinking tailored specifically for the Food Design process? Is there a need for a branch of Design Thinking dedicated to Food Design alone? Chefs are not generally trained in Design or Design Thinking, and we are only just beginning to understand how they ideate and what recourses are available to…

  11. The licensing process of the design modifications of Cernavoda 2 NPP resulting from the operating experience of CANDU plants

    International Nuclear Information System (INIS)

    Goicea, L.

    2005-01-01

    The CANDU 6 plant now under construction in Cernavoda include over two hundred significant improvements made in order to comply with current codes and standards and licensing requirements relative to the operating CANDU 6 in Romania. These evolutionary improvements are incorporated in CANDU 6 design taking advance of CANDU operating experience, of the designer company research and development and technical advances worldwide in order to further enhance safety, reliability and economics. This paper gives a general idea of the evaluation of the modifications of the Cernavoda 2 nuclear power plant against the design of Cernavoda 1 and states the safety principles and requirements which are the basis for this evaluation. (author)

  12. 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.

  13. 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)

  14. 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...

  15. The problem of licensing and safety of nuclear power plants

    International Nuclear Information System (INIS)

    Silva, R.A. da.

    1987-01-01

    The historical evolution of licensing process of nuclear power plants is presented. The designs carried out by FURNAS for constructing Angra-1 reactor and its contribution to the Brazilian CNEN in de licensing process, are evaluated. The aims of FURNAS Research Programs are determined and the safety goals are established. (M.C.K.) [pt

  16. A licensing discussion: SMRs in Canada

    International Nuclear Information System (INIS)

    De Vos, M.

    2013-01-01

    The CNSC (Canadian AECB) is ready to regulate Small Modular Reactors (SMR) facilities in Canada. The CNSC is well situated to engage with proponents of SMR reactors in design reviews or licensing discussions. A risk-informed (graded) approach is possible in many instances for reactors but it is not a relaxation of requirements. The vendor design review process helps reduce regulatory risks by encouraging early engagement.

  17. Task-Specific Training and Job Design

    OpenAIRE

    Felipe Balmaceda

    2006-01-01

    This paper provides a simple theoretical framework based on a new type of human capital introduced by Gibbons and Waldman (2004), called task-specific training, to understand job design. Mainly, in the presence of task-specific training, promotions might result ex-post in the underutilization of human capital and thus firms at the time of designing jobs should attempt to diversify this risk.

  18. 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

  19. Resolution of thermal-hydraulic safety and licensing issues for the system 80+trademark design

    International Nuclear Information System (INIS)

    Carpentino, S.E.; Ritterbusch, S.E.; Schneider, R.E.

    1995-01-01

    The System 80+ trademark Standard Design is an evolutionary Advanced Light Water Reactor (ALWR) with a generating capacity of 3931 MWt (1350 MWe). The Final Design Approval (FDA) for this design was issued by the Nuclear Regulatory Commission (NRC) in July 1994. The design certification by the NRC is anticipated by the end of 1995 or early 1996. NRC review of the System 80+ design has involved several new safety issues never before addressed in a regulatory atmosphere. In addition, conformance with the Electric Power Research Institute (EPRI) ALWR Utility Requirements Document (URD) required that the System 80+ plant address nuclear industry concerns with regard to design, construction, operation and maintenance of nuclear power plants. A large number of these issues/concerns deals with previously unresolved generic thermal-hydraulic safety issues and severe accident prevention and mitigation. This paper discusses the thermal-hydraulic analyses and evaluations performed for the System 80+ design to resolve safety and licensing issues relevant to both the Nuclear Stream Supply System (NSSS) and containment designs. For the NSSS design, the Safety Depressurization System mitigation capability and resolution of the boron dilution concern are described. Examples of containment design issues dealing with containment shell strength, robustness of the reactor cavity walls and hydrogen mixing under severe accident conditions are also provided. Finally, the overall approach used in the application of NRC's new (NUREG-1465) radiological source term for System 80+ evaluation is described. The robustness of the System 80+ containment design to withstand severe accident consequences was demonstrated through detailed thermal-hydraulic analyses and evaluations. This advanced design to shown to meet NRC severe accident policy goals and ALWR URD requirements without any special design features and unnecessary costs

  20. Westinghouse AP1000 licensing maturity

    International Nuclear Information System (INIS)

    Schulz, T.; Vijuk, R.P.

    2005-01-01

    The Westinghouse AP1000 Program is aimed at making available a nuclear power plant that is economical in the U.S deregulated electrical power industry in the near-term. The AP1000 is two-loop 1000 MWe pressurizer water reactor (PWR). It is an up rated version of the AP600. The AP1000 uses passive safety systems to provide significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. The AP1000 uses proven technology, which builds on over 35 years of operating PWR experience. The AP1000 received Final Design Approval by the United States Nuclear Regulatory Commission (U.S. NRC) in September 2004. The AP1000 meets the US utility requirements. The AP1000 and its sister plant the AP600 have gone through a very through and complete licensing review. This paper describes the U.S. NRC review efforts of both the AP600 and the AP1000. The detail of the review and the independent calculations, evaluations and testing is discussed. The AP600 licensing documentation was submitted in 1992. The U.S. NRC granted Final Design Approval in 1999. During the intervening 7 years, the U.S. NRC asked thousands of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. For the AP1000 Westinghouse first engaged the U.S. NRC in pre-certification discussions to define the extent of the review required, since the design is so similar to the AP600. The AP1000 licensing documentation was submitted in March 2002. The U.S. NRC granted Final Design Approval in September 2004. During the intervening 2 1/2 years, the U.S. NRC asked hundreds of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. The implications of this review and approval on AP1000 applications in

  1. 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.

  2. Role of cognitive models of operators in the design, operation and licensing of nuclear power plants

    International Nuclear Information System (INIS)

    Rasmussen, J.

    1982-01-01

    Cognitive models of the behavior of nuclear power plant operators - that is, models developed in terms of human properties rather than external task characteristics - are assuming increasingly important roles in plant design, operation and licensing. This is partly due to an increased concern for human decision making during unfamiliar plant conditions, and partly due to problems that arise when modern information technology is used to support operators in complex situations. Some of the problems identified during work on interface design and risk analysis are described. First, the question of categories of models is raised. Next, the use of cognitive models for system design is discussed. The use of the available cognitive models for more effective operator training is also advocated. The need for using cognitive models in risk analysis is also emphasized. Finally, the sources of human performance data, that is, event reports, incident analysis, experiments, and training simulators are mentioned, and the need for a consistent framework for data analysis based on cognitive models is discussed

  3. Foundation for the adequacy of the licensing bases

    International Nuclear Information System (INIS)

    1991-12-01

    The objective of this report is to describe the regulatory processes that assures that any plant-specific licensing bases will provide reasonable assurance that the operation of nuclear power plants will not be inimical to the public health and safety to the end of the renewal period. It is on the adequacy of this process that the Commission has determined that a formal renewal licensing review against the full range of current safety requirements would not add significantly to safety and is not needed to assure that continued operation throughout the renewal term is not inimical to the public health and safety or common defense and security. This document illustrates in general terms how the regulatory process has evolved in major safety issue areas. It also provides examples illustrating why it is unnecessary to re-review an operating plant's basis, except for age-related degradation unique to license renewal, at the time of license renewal. The report is a supplement to the Statement of Considerations for the Nuclear Regulatory Commission's rule (10 CFR Part 54) that established the criteria and standards governing nuclear power plant license renewal

  4. Medical licensing board characteristics and physician discipline: an empirical analysis.

    Science.gov (United States)

    Law, Marc T; Hansen, Zeynep K

    2010-02-01

    This article investigates the relationship between the characteristics of medical licensing boards and the frequency with which boards discipline physicians. Specifically, we take advantage of variation in the structure of medical licensing boards between 1993 and 2003 to determine the effect of organizational and budgetary independence, public oversight, and resource constraints on rates of physician discipline. We find that larger licensing boards, boards with more staff, and boards that are organizationally independent from state government discipline doctors more frequently. Public oversight and political control over board budgets do not appear to influence the extent to which medical licensing boards discipline doctors. These findings are broadly consistent with theories of regulatory behavior that emphasize the importance of bureaucratic autonomy for effective regulatory enforcement.

  5. 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.

  6. Individual Licensing Models and Consumer Protection

    NARCIS (Netherlands)

    Guibault, L.; Liu, K.-C.; Hilty, R.M.

    2017-01-01

    Copyright law is not primarily directed at consumers. Their interests are therefore only marginally accounted for, as the copyright rules exempt specific uses of works from the right holder’s control. This chapter examines the impact of digital technology on the position of consumers of licensed

  7. Libraries and licensing

    Directory of Open Access Journals (Sweden)

    Maja Žumer

    2001-01-01

    Full Text Available In the mid 90s, the abundance of various electronic publications exposed libraries to the problems of licensing electronic content. Various licensing principles have been prepared recently to help libraries in the process; it can be said that in general, the knowledge of licensing issues has improved in libraries of all types. Libraries form consortia in order to gain stronger negotiating positions and obtain better conditions.In the article, new licensing principles are presented in more detail, as well as some domestic and foreign experiences with consortia forming.

  8. 10 CFR 50.55 - Conditions of construction permits, early site permits, combined licenses, and manufacturing...

    Science.gov (United States)

    2010-01-01

    ... construction or manufacture, or any defect found in the final design of a facility as approved and released for..., combined licenses, and manufacturing licenses. 50.55 Section 50.55 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance, Limitations, and Conditions of...

  9. ORNL's NRC-sponsored HTGR safety and licensing analysis activities for Fort St. Vrain and advanced reactors

    International Nuclear Information System (INIS)

    Ball, S.J.; Cleveland, J.C.; Harrington, R.M.

    1985-01-01

    The ORNL safety analysis program for the HTGR was established in 1974 to provide technical assistance to the USNRC on licensing questions for both Fort St. Vrain and advanced plant concepts. The emphasis has been on development of major component and system dynamic simulation codes, and use of these codes to analyze specific licensing-related scenarios. The program has also emphasized code verification, using Fort St. Vrain data where applicable, and comparing results with industry-generated codes. By the use of model and parameter adjustment routines, safety-significant uncertainties have been identified. A major part of the analysis work has been done for the Fort St. Vrain HTGR, and has included analyses of FSAR accident scenario re-evaluations, the core block oscillation problem, core support thermal stress questions, technical specification upgrade review, and TMI action plan applicability studies. The large, 2240-MW(t) cogeneration lead plant design was analyzed in a multi-laboratory cooperative effort to estimate fission product source terms from postulated severe accidents

  10. Transporting existing VSC-24 canisters using a risk-based licensing approach

    Energy Technology Data Exchange (ETDEWEB)

    Srinivasan, R.; Sisley, S.E.; Hopf, J.E. [BNFL Fuel Solutions, Campbell, CA (United States)

    2004-07-01

    The eventual disposition of the spent fuel assemblies loaded in canisters and casks currently designed and licensed only for on-site storage is an industry-wide issue. The canister-specific BUC evaluation approach developed by BFS can be used to license many of these storage canisters and casks for transportation. This will allow these storage canisters and casks to be transported intact to a long-term storage facility or repository, thereby minimizing fuel handling operations, impact on plant operations, and occupational exposure, as well as total infrastructure costs. Application of the proposed canister-specific BUC analysis approach to a preliminary evaluation of the 58 loaded MSBs demonstrates the benefits of this approach. The results of this preliminary evaluation show that a more rigorous analysis based on the known characteristics of the loaded spent fuel, rather than the design-basis fuel parameters, produces significantly lower maximum keff values and can be used to qualify many of the existing loaded storage canisters for transportation. Transportation certification for storage canisters having more reactive spent fuel payloads may require reliance on BUC approaches that are more aggressive than current NRC guidelines allow. Credit may be required for fission- product isotopes that do not have sufficient chemical assay data for benchmarking. In addition, reduced criticality safety margins may be required. For these more-aggressive BUC approaches, a risk assessment should be provided to support the NRC-approval basis. The risk assessment should evaluate the possibility and consequences of an accidental criticality event based upon inaccuracies in the characterization of the spent-fuel payloads.

  11. Transporting existing VSC-24 canisters using a risk-based licensing approach

    International Nuclear Information System (INIS)

    Srinivasan, R.; Sisley, S.E.; Hopf, J.E.

    2004-01-01

    The eventual disposition of the spent fuel assemblies loaded in canisters and casks currently designed and licensed only for on-site storage is an industry-wide issue. The canister-specific BUC evaluation approach developed by BFS can be used to license many of these storage canisters and casks for transportation. This will allow these storage canisters and casks to be transported intact to a long-term storage facility or repository, thereby minimizing fuel handling operations, impact on plant operations, and occupational exposure, as well as total infrastructure costs. Application of the proposed canister-specific BUC analysis approach to a preliminary evaluation of the 58 loaded MSBs demonstrates the benefits of this approach. The results of this preliminary evaluation show that a more rigorous analysis based on the known characteristics of the loaded spent fuel, rather than the design-basis fuel parameters, produces significantly lower maximum keff values and can be used to qualify many of the existing loaded storage canisters for transportation. Transportation certification for storage canisters having more reactive spent fuel payloads may require reliance on BUC approaches that are more aggressive than current NRC guidelines allow. Credit may be required for fission- product isotopes that do not have sufficient chemical assay data for benchmarking. In addition, reduced criticality safety margins may be required. For these more-aggressive BUC approaches, a risk assessment should be provided to support the NRC-approval basis. The risk assessment should evaluate the possibility and consequences of an accidental criticality event based upon inaccuracies in the characterization of the spent-fuel payloads

  12. Improvement suggestions on license extension management for civil nuclear safety equipment activities

    International Nuclear Information System (INIS)

    Sun Xingjian; Liu Hongji; Han Guoli; Jia Fengcai

    2013-01-01

    Based on the concepts of Clear Requirements, Comprehensive Review, Objective Assessment, Dynamic Management, this paper gives improvement suggestions on license extension management for civil nuclear safety equipment design, manufacture, installation and non-destructive examination activities, which include establishing a relatively unified license extension review standard, combining multi-views and close linking license review and supervision, full utilizing the daily supervision and inspection results, as well as further improving motivation and elimination mechanism. (authors)

  13. 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

  14. 10 CFR 32.26 - Gas and aerosol detectors containing byproduct material: Requirements for license to manufacture...

    Science.gov (United States)

    2010-01-01

    ...: Requirements for license to manufacture, process, produce, or initially transfer. 32.26 Section 32.26 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN ITEMS... byproduct material: Requirements for license to manufacture, process, produce, or initially transfer. An...

  15. Licensing of the proposed PBMR-SA

    International Nuclear Information System (INIS)

    Clapisson, G.A.; Henderson, N.R.; Hill, T.F.; Keenan, N.H.; Metcalf, P.E.; Mysenkov, A.

    1997-01-01

    This paper describes the preliminary criteria, which are intended to be used by the South African regulatory authority (CNS), for licensing of the ESKOM proposed - South African high temperature gas-cooled Pebble Bed Modular Reactor (PBMR-SA). The CNS intends to apply the existing CNS licensing approach together with some international design criteria used for advanced reactors as well as international experience gained from the safety evaluation of the MHTGR, THTR, etc. A major requirement to this type of reactor is that it should comply with the current CNS risk criteria and provide, as a minimum, the same degree of protection to the operator, public and environment that is required for the current generation of nuclear reactors. (author)

  16. Licensing and accident reviews for an HNEC

    International Nuclear Information System (INIS)

    Clark, R.G.

    1978-09-01

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

  17. 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

  18. Licensing of MAPLE reactors in Canada

    International Nuclear Information System (INIS)

    Lee, A.G.; Labrie, J.P.; Langman, V.J.

    1999-01-01

    Full text: The Operating Licence for a MAPLE reactor (i.e., a 10 MW(th), pool-type reactor), has been approved by the Atomic Energy Control Board (AECB) on August 16th, 1999. This Operating Licence has been obtained within three years of the initiation of the MDS Nordion Medical Isotopes Reactor (MMIR) project, which entails the design, construction and commissioning of two 10 MW MAPLE reactors at AECL's Chalk River Laboratories. The scope and nature of the information required by the AECB, the licensing process and highlights of the events which led to successfully obtaining the Operating Licence for the MAPLE reactor are discussed. These discussions address all phases of the licensing process (i.e., the environmental assessment in support of siting, the Preliminary Safety Analysis Report, PSAR, in support of design, procurement and construction, the Final Safety Analysis Report, FSAR, in support of commissioning and operations, and the development of suitable quality assurance subprograms for each phase). An overview of some of the unique technical aspects associated with the MAPLE reactors, and how they have been addressed during the licensing process are also provided (e.g., applying CSA N285.0, General Requirements for Pressure-Retaining Systems and Components in CANDU Nuclear Power Plants, to a small, low pressure, low temperature research reactor, confirmation of the performance of the driver fuel via laboratory and/or in-reactor testing, validation of the computer codes used to perform the safety analyses, critical parameter uncertainty assessment, full scale hydraulic testing of the performance of the design, fuel handling, human factors validation, operator training and certification). (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. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

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

  1. Standard technical specifications for combustion engineering pressurized water reactors

    International Nuclear Information System (INIS)

    1979-08-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on Combustion Engineering plants currently being reviewed for an Operating License. Two separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. This revision of STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

  2. Meta-analysis of graduated driver licensing laws: effectiveness of specific program components : traffic tech.

    Science.gov (United States)

    2015-11-01

    Graduated driver licensing (GDL) programs in the United States do not represent a single homogeneous intervention; rather, they contain different combinations and variations of program components. Programs vary by the duration of each stage of the GD...

  3. Nuclear reactor operator licensing

    International Nuclear Information System (INIS)

    Bursey, R.J.

    1978-01-01

    The Atomic Energy Act of 1954, which was amended in 1974 by the Energy Reorganization Act, established the requirement that individuals who had the responsibility of operating the reactors in nuclear power plants must be licensed. Section 107 of the act states ''the Commission shall (1) prescribe uniform conditions for licensing individuals; (2) determine the qualifications of such individuals; and (3) issue licenses to such individuals in such form as the Commission may prescribe.'' The article discusses the types of licenses, the selection and training of individuals, and the administration of the Nuclear Regulatory Commission licensing examinations

  4. 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

  5. Licensing in an international triopoly

    Science.gov (United States)

    Ferreira, Fernanda A.; Ferreira, Flávio

    2011-12-01

    We study the effects of entry of two foreign firms on domestic welfare in the presence of licensing, when the incumbent is technologically superior to the entrants. We consider two different situations: (i) the cost-reducing innovation is licensed to both entrants; (ii) the cost-reducing innovation is licensed to just one of the entrants. We analyse three kind of license: (lump-sum) fixed-fee; (per-unit) royalty; and two-part tariff, that is a combination of a fixed-fee and a royalty. We prove that a two part tariff is never an optimal licensing scheme for the incumbent. Moreover, (i) when the technology is licensed to the two entrants, the optimal contract consists of a licensing with only output royalty; and (ii) when the technology is licensed to just one of the entrants, the optimal contract consists of a licensing with only a fixed-fee.

  6. 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...

  7. Why operators fail licensing examinations

    International Nuclear Information System (INIS)

    Roth, D.R.; Zerbo, J.N.

    1975-01-01

    A survey was conducted among nuclear utility operators who have taken NRC licensing examinations to determine which factors they considered important in their success or failure. The operators also compared the actual NRC examination with their expectations prior to taking the examination. The results of the survey supplement NRC statistics with regard to failure rates. Over 350 operators and 20 utilities participated in the survey and a good cross section of the nuclear community is represented. Reactor theory and emergency procedures are important areas in which operators found NRC emphasis to be different than expected. Observation Training and Design Lecture Series are two training segments which appear to require improvement. Recommendations are made for the use of data collected through this survey and for continuation of the effort to give operators a mechanism of supplying feedback to the training and licensing process

  8. The comparison of license management procedure for nuclear power plant in China and United States

    International Nuclear Information System (INIS)

    Yu Zusheng

    2006-01-01

    'Tow steps' license management procedure for nuclear power plant has been performed bas- ted on the requirement of 10CFR Part50-DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES in United States since last century fifties. In order to ulterior reduce the risk of investment and technical for new construction nuclear power plants, new regulations 'One step' license management procedure-10CFR Part52-EARLY SITE PERMITS; STANDARD DESIGN CERTIFICATIONS; AND COMBINED LICENSES FOR NUCLEAR POWER PLANTS issued in 1989. The new regulations has been adopted by new design of nuclear power plant, for example AP1000. ‘The similar tow steps’ license management procedure for nuclear power plant has been performed basted on the requirement of HAFO01/01 Rules for the Implementation of Regulations on the Safety Regulation for Civilian Nuclear Installations of the People's Re- public of China Part One: Application and Issuance of Safety License for Nuclear Power Plant (December 1993) in China since last century nineties. This article introduces and compares the requirements and characteristics of above license management procedure for nuclear power plant in China and United States. (author)

  9. Resolution of thermal-hydraulic safety and licensing issues for the system 80+{sup {trademark}} design

    Energy Technology Data Exchange (ETDEWEB)

    Carpentino, S.E.; Ritterbusch, S.E.; Schneider, R.E. [ABB-Combustion Engineering, Windsor, CT (United States)] [and others

    1995-09-01

    The System 80+{sup {trademark}} Standard Design is an evolutionary Advanced Light Water Reactor (ALWR) with a generating capacity of 3931 MWt (1350 MWe). The Final Design Approval (FDA) for this design was issued by the Nuclear Regulatory Commission (NRC) in July 1994. The design certification by the NRC is anticipated by the end of 1995 or early 1996. NRC review of the System 80+ design has involved several new safety issues never before addressed in a regulatory atmosphere. In addition, conformance with the Electric Power Research Institute (EPRI) ALWR Utility Requirements Document (URD) required that the System 80+ plant address nuclear industry concerns with regard to design, construction, operation and maintenance of nuclear power plants. A large number of these issues/concerns deals with previously unresolved generic thermal-hydraulic safety issues and severe accident prevention and mitigation. This paper discusses the thermal-hydraulic analyses and evaluations performed for the System 80+ design to resolve safety and licensing issues relevant to both the Nuclear Stream Supply System (NSSS) and containment designs. For the NSSS design, the Safety Depressurization System mitigation capability and resolution of the boron dilution concern are described. Examples of containment design issues dealing with containment shell strength, robustness of the reactor cavity walls and hydrogen mixing under severe accident conditions are also provided. Finally, the overall approach used in the application of NRC`s new (NUREG-1465) radiological source term for System 80+ evaluation is described. The robustness of the System 80+ containment design to withstand severe accident consequences was demonstrated through detailed thermal-hydraulic analyses and evaluations. This advanced design to shown to meet NRC severe accident policy goals and ALWR URD requirements without any special design features and unnecessary costs.

  10. 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)

  11. 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)

  12. ISO 14000 and the nuclear licensing

    International Nuclear Information System (INIS)

    Martins, Nadia Soido Falcao

    1999-01-01

    As concern grows for maintaining and improving the quality of the environment and protecting human health, all the world is turning its attention to the potential environmental in pact of their industrial activities. One of the most important contribution in that way is the International Standard ISO 14000 series. In the utilization of nuclear energy, right from the inception, the safety of personnel, environment and the population has been the basic consideration. Over the years well established licenses criteria have been proposed to limit and control the environmental impact of the plant operation and emergencies situation. In this paper are discussed some specific requirements for implementation of the environmental management system specified by ISO 14000 compared to the environmental requirements for nuclear licensing. (author)

  13. Driving Performance among Bioptic Telescope Users with Low Vision Two Years after Obtaining Their Driver's License: A Quasi-Experimental Study

    Science.gov (United States)

    Vincent, Claude; Lachance, Jean-Paul; Deaudelin, Isabelle

    2012-01-01

    This study sought to compare road safety of new drivers with low vision who have followed a specific pilot bioptic training program with other groups of drivers all matched for age and driving experience. A quasi-experimental design was used two years after drivers obtained their license. Drivers were classified in the experimental group (n = 10,…

  14. 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)

  15. Licensed Healthcare Facilities

    Data.gov (United States)

    California Natural Resource Agency — The Licensed Healthcare Facilities point layer represents the locations of all healthcare facilities licensed by the State of California, Department of Health...

  16. IRIS Licensing Status

    International Nuclear Information System (INIS)

    Kling, Charles L.; Carelli, Mario D.

    2006-01-01

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

  17. Safety philosophy and licensing practice in different member states of IAEA: Germany, F.R

    International Nuclear Information System (INIS)

    Lahner, K.

    1981-01-01

    The safety philosophy, as the basis of the design of a NPP, will be shown under the aspects of general design rules, requirements by law, reactor safety commission and nuclear or conventional technical standards. Then a discussion of the licensing practise in the Federal Republic of Germany and in the USA will follow for the different stages of conceptual design, construction and operation with special consideration of the example of the NPP Muelheim-Kaerlich. The interrelation between designer and licensing authority, reactor safety commission and technical consultants will be taken into account. (orig./RW)

  18. 2015 Business Licenses

    Data.gov (United States)

    City of Jackson, Mississippi — This data displays all business license information for the year of 2015. This information details license classifications and status. This information will updated...

  19. Teenagers' licensing decisions and their views of licensing policies: a national survey.

    Science.gov (United States)

    Williams, Allan F

    2011-08-01

    One objective was to determine teenage licensing rates on a national basis, interest in early licensure, and reasons for delay. A second objective was to learn teenagers' opinions about licensing policies, important in states considering ways to upgrade their current licensing systems. One thousand three hundred eighty-three 15- to 18-year-olds completed an online survey in November 2010. They were drawn from a nationally representative panel of US households recruited using probability-based sampling. The panel included cell phone-only households, and Internet access was provided to those without it. Weighting procedures were applied so that the study population represented the national US population of 15- to 18-year-olds. Most teens said that they were interested in getting a license as soon as legally possible, but many had not started the process. At 16, teens were about equally divided among those who had not started, those in the learner stage, and those with a restricted or full license. At 18, 62 percent had full licenses; 22 percent had not started. For those old enough to start, lack of a car, costs, parent availability, ability to get around without a car, and being busy with other activities were leading reasons for delay. The majority of teens were not in favor of higher licensing ages. Forty-six percent thought the minimum learner age should be 16; 30 percent thought the full license age should be 18 or older. The majority approved of night (78%) and passenger (57%) restrictions, and 85 and 93 percent endorsed cell phone and texting bans, respectively. When these policies were packaged together in a single law that included an age 16 start, night, passenger, cell phone and texting bans, and a full license at age 18, 74 percent of teens were in favor. Teenagers are not as supportive of strong licensing policies as parents of teens, but there is evidence that they will support comprehensive policies likely to lead to further reductions in teen crash

  20. Specification of requirements to get a license for an Independent Spent Fuel Dry Storage Installation (ISFSI) at the site of the NPP-LV; Especificacion de los requerimientos para tramitar una licencia de una instalacion independiente de almacenamiento temporal en seco de combustible gastado (ISFSI) en el sitio de la CNLV

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2015-09-15

    This article describes some of the work done in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) to define specifically the requirements that the Federal Electricity Commission (CFE) shall meet to submit for consideration of CNSNS an operation request of an Independent Spent Fuel Dry Storage Installation (ISFSI). The project of a facility of this type arose from the need to provide storage capacity for spent nuclear fuel in the nuclear power plant of Laguna Verde (NPP-LV) and to continue the operation at the same facility in a safe manner. The licensing of these facilities in the United States of America has two modes: specific license or general license. The characteristics of these licenses are described in this article. However, in Mexico the existing national legislation is not designed for such license types, in fact there is a lack of standards or regulations in this regard. The regulatory law of Article 27 of the Constitution in the nuclear matter, only generally establishes that this type of facility requires an authorization from the Ministry of Energy. For this reason and because there is not a national legislation, was necessary to use the legislation that provides the Nuclear Regulatory Commission of USA, the US NRC. However, it cannot be applied as is established, so was necessary that the CNSNS analyze one by one the requirements of both types of license and determine what would be required to NPP-LV to submit its operating license of ISFSI. The American regulatory applicable to an ISFSI, the 10-Cfr-72 of the US NRC, establishes the requirements for both types of licenses. Chapter 10-Cfr was analyzed in all its clauses and coupled to the laws, regulations and standards as well as to the requirements established by CNSNS, all associated with a store spent fuel on site; the respective certification of containers for spent fuel dry storage was not included in this article, even though the CNSNS also performed that activity under the

  1. Site-specific design optimization of wind turbines

    DEFF Research Database (Denmark)

    Fuglsang, P.; Bak, C.; Schepers, J.G.

    2002-01-01

    This article reports results from a European project, where site characteristics were incorporated into the design process of wind turbines, to enable site-specific design. Two wind turbines of different concept were investigated at six different sites comprising normal flat terrain, offshore...... and complex terrain wind farms. Design tools based on numerical optimization and aeroelastic calculations were combined with a cost model to allow optimization for minimum cost of energy. Different scenarios were optimized ranging from modifications of selected individual components to the complete design...... of a new wind turbine. Both annual energy yield and design-determining loads depended on site characteristics, and this represented a potential for site-specific design. The maximum variation in annual energy yield was 37% and the maximum variation in blade root fatigue loads was 62%. Optimized site...

  2. Standard technical specifications for Babcock and Wilcox pressurized water reactors

    International Nuclear Information System (INIS)

    1978-06-01

    The Standard Technical Specification (STS) has been structured for the broadest possible use on B and W NSSS plants currently being reviewed for an Operating License. Two separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric, and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. The format of the STS addresses the categories required by 10 CFR 50 and consists of six sections covering the areas of: Definitions, Safety Limits and Limiting Safety System Settings, Limiting Conditions for Operation, Surveillance Requirements, Design Features, and Administrative Controls

  3. Radiopharmaceutical licensing

    International Nuclear Information System (INIS)

    Mather, S.J.

    1992-01-01

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

  4. Licensing system for primary category radioactive installations

    International Nuclear Information System (INIS)

    Ramirez Riquelme, Angelica Beatriz

    1997-01-01

    The development of a licensing system for primary category radioactive installations is described, which aims to satisfy the needs of the Chilean Nuclear Energy Commission's Department of Nuclear and Radiological Safety, particularly the sections for Licensing Outside Radioactive Installations and Safety Control. This system involves the identification, control and inspection of the installations, their personnel and connected activities, for the purpose of protecting the population's health and the environment. Following the basic cycle methodology, a systems analysis and engineering stage was prepared, establishing the functions of the system's elements and defining the requirements, based on interviews with the users. This stage was followed by the design stage, focusing on the data structure, the software architecture and the procedural detail. The codification stage followed, which translated the design into legible machine-readable format. In the testing stage, the entries that were defined were proven to produce the expected data. Finally and operational and maintenance stage was developed, when the system was installed and put to use. All the above generated a useful system for the Licensing section of the Department of Nuclear and Radiological Safety, since it provides faster and easier access to information. A project is described that introduces new development tools in the Computer department following standards established by the C.CH.E.N. (author)

  5. State Licenses & Permits

    Data.gov (United States)

    Small Business Administration — Starting a business? Confused about whether you need a business license or permit? Virtually every business needs some form of license or permit to operate legally....

  6. 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

  7. Creative Commons licenses and the non-commercial condition: Implications for the re-use of biodiversity information.

    Science.gov (United States)

    Hagedorn, Gregor; Mietchen, Daniel; Morris, Robert A; Agosti, Donat; Penev, Lyubomir; Berendsohn, Walter G; Hobern, Donald

    2011-01-01

    The Creative Commons (CC) licenses are a suite of copyright-based licenses defining terms for the distribution and re-use of creative works. CC provides licenses for different use cases and includes open content licenses such as the Attribution license (CC BY, used by many Open Access scientific publishers) and the Attribution Share Alike license (CC BY-SA, used by Wikipedia, for example). However, the license suite also contains non-free and non-open licenses like those containing a "non-commercial" (NC) condition. Although many people identify "non-commercial" with "non-profit", detailed analysis reveals that significant differences exist and that the license may impose some unexpected re-use limitations on works thus licensed. After providing background information on the concepts of Creative Commons licenses in general, this contribution focuses on the NC condition, its advantages, disadvantages and appropriate scope. Specifically, it contributes material towards a risk analysis for potential re-users of NC-licensed works.

  8. License to build

    International Nuclear Information System (INIS)

    Huntelaar, Mark; Vos, Renate de; Roobol, Lars

    2007-01-01

    Full text: A new license under the nuclear power act is applied for at the Dutch Government for the building of a High Active Repackaging Unit (HAVA-VU in Dutch) at NRG in Petten, The Netherlands. This new building is necessary to comply with our nuclear license to dispose of high active nuclear waste at Petten to the intermediate storage facility (COVRA). In the first part of this paper attention is given to the formal procedure followed by the Government, what type of documents are to be submitted, what time frames are followed, how citizen participation is organized, and as final result a new license. In the second part more detailed information is given about the present license renewal needed for the High Active Repackaging Unit

  9. 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

  10. Demarcation of the licensing and supervisory procedures for nuclear engineering installations

    International Nuclear Information System (INIS)

    Schattke, H.

    1986-01-01

    The remarks can be summed up under 12 points: 1) The protective purpose outlined in Paragraph 1 No. 2 of the Atomic Energy Law is the top priority for both licensing and regulatory authorities. 2) Both authorities must aim at the best possible prevention of hazards and precautions against risks. 3) The licensing procedures cover applications for licenses, the regulatory procedures check and supervise actual activities. 4) The licensing procedures take precedence in chronology and in substance over the regulatory procedure. 5) The licensing procedure is a preliminary check on the intention to carry out nuclear activities before the event; whereas the regulatory procedure controls the licensee after the event to ensure that the latter's activities really do conform to the framework laid down in the license. 6) The licensing procedure must be verified by state supervision with regard to its prognostic activity. 7) The examination criteria are largely identical for both the authorites. 8) The examination tools for the licensing and regulatory authorities also coincide to a large extent. Legal differences in the possible means of enforcement have no effect in practice. 9) Decisions made by either authority can be either in the licensee's favour or to its disadvantage. Nevertheless, the contents of decisions differ widely between the two authorities. 10) The regulatory authorities execute and prepare the decisions of the licensing authorites. 11) Licensing decisions can be designated static/prognostic, whereas regulatory measures accompany the actual performance of the plant and the operating personnel in a dynamic/controlling manner. 12) Regulatory instructions are usually of a temporary nature, whereas licensing actions are permanent as a rule. (orig.) [de

  11. Evaluation of Terminated Nuclear Material Licenses

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  12. Progresses and challenges in supporting activities toward a license to operate European TBM systems in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Poitevin, Y., E-mail: yves.poitevin@f4e.europa.eu [Fusion for Energy, Barcelona (Spain); Ricapito, I.; Zmitko, M. [Fusion for Energy, Barcelona (Spain); Tavassoli, F. [CEA, DEN, F-91191 Gif-sur-Yvette (France); Thomas, N. [ATMOSTAT, F-94815 Villejuif (France); De Dinechin, G. [CEA, DEN, F-91191 Gif-sur-Yvette (France); Bucci, Ph. [CEA DRT, 38000 Grenoble (France); Rey, J. [Karlsruhe Institute of Technology, Postfach 3640, Karlsruhe (Germany); Ibarra, A. [CIEMAT, Madrid (Spain); Panayotov, D. [Fusion for Energy, Barcelona (Spain); Giancarli, L. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance (France); Calderoni, P.; Galabert, J.; Vallory, J. [Fusion for Energy, Barcelona (Spain); Aiello, A. [C.R. ENEA Brasimone, I-40032 Camugnano (Italy)

    2014-10-15

    Highlights: • First EUROFER steel design limits have been introduced in RCC-MRx. • Preliminary fabrication/welding procedure specifications for the European TBM box are under standardization. • Post irradiation examination (PIE) of beryllium pebbles irradiated at 17% of DEMO fluence target has been achieved. • Dynamic modeling of the TBM Systems with EcosimPro{sup ®} has been developed. - Abstract: Licensing a pressurized nuclear equipment like the European Test Blanket Modules (TBM) Systems and, on the longer term, breeder blankets of a fusion demonstration reactor (DEMO), will require presenting to the Regulator and the Agreed Notified Body, along with design and safety analyses, supporting data like consolidated materials data and design limits, qualified fabrication procedures specifications and validated modeling tools that go often over today's state-of-the-art of nuclear industry. TBM systems feature indeed a newly developed structural material and advanced fabrication processes that were not referenced in any nuclear construction codes before, new type of functional materials, complex structures geometry and many interconnected sub-systems exchanging tritium by permeation or fluid mass transfer. For many years now, Europe has structured its development activities on TBM Systems toward the preparation of licensing. First tangible results are now arising: the EUROFER structural material has been introduced in the RCC-MRx nuclear code, supported by a database of several thousands of test records; TBM box fabrication procedure specifications are under standardization by industry in view of their qualification; a modeling tool for accurate simulation of tritium transport in TBM systems has been developed in view of refining conservative inventory data published in preliminary safety reports and optimizing waste management. Remaining challenges are identified and discussed.

  13. 15 CFR 750.7 - Issuance of licenses.

    Science.gov (United States)

    2010-01-01

    ... of transportation cost, drayage, port charges, warehousing, currency fluctuations, etc.; (iv... each CCL commodity entry will list a specific “Unit” for those commodities controlled by that entry... commonly used in trade may also be shown on the license. Though this unit may be shown on the approved...

  14. 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

  15. Safety aspects of nuclear plant licensing in Canada

    International Nuclear Information System (INIS)

    Jennekens, J.H.F.

    1975-01-01

    The legislative authority is laid down in the Atomic Energy Control Act, 1946, declaring atomic energy a matter of national interest and establishing the Atomic Energy Control Board (AECB) as the competent body for regulating all aspects of atomic energy. The Act also vests a Minister designated by the Government with research and exploitation functions; thus, by Ministerial order, Atomic Energy of Canada Limited was established in 1952 as a State-owned company. The Nuclear Liability Act, 1970, channels all liability for nuclear damage to the operator of a nuclear installation and requires him to obtain insurance in the amount of $75 million, part of which may be re-insured by the Government. The licensing requirements comprise the issuance of a site approval, a construction licence and an operating licence. The AECB is assisted in its licensing functions by its Nuclear Plant Licensing Directorate and by the Reactor Safety Advisory Committee co-operating with each other in making extensive safety assessments of a licence application. A site evaluation report, a preliminary safety report and a final safety report are required in relation to the siting, construction and operation of a nuclear power plant. The Canadian reactor safety philosophy is based on the concept of defence in depth, implemented through a multi-step approach, which includes avoidance of malfunctions, provision of special safety systems, periodic inspection and testing, and avoidance of human errors. Specific criteria and principles have evolved in applying this basic safety philosophy and radiation protection standards are derived from international recommendations. Stringent control is exercised over the management of radioactive waste and management facilities must meet the engineering and procedural requirements of AECB before they can be placed in operation. (author)

  16. Contestable Licensing

    OpenAIRE

    Zvika Neeman; Gerhard O. Orosel

    2000-01-01

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

  17. Effects of Californian PRC 25500 on nuclear power plant licensing

    International Nuclear Information System (INIS)

    Hahn, F.J.

    1976-01-01

    The California Public Resources Code 25500 established the Energy Resources Conservation and Development Commission on January 7, 1976. This Act mandated that the Commission process applications for new power plants within very specific timeframes. The paper presents the intent and timing of the two-phase licensing procedure and illustrates the effect of this procedure on power plants already into the NRC licensing process and on power plants which are in the beginning of the site selection process

  18. License or entry decision for innovator in international duopoly with convex cost functions

    OpenAIRE

    Hattori, Masahiko; Tanaka, Yasuhito

    2017-01-01

    We consider a choice of options for a foreign innovating firm to license its new cost-reducing technology to a domestic incumbent firm or to enter the domestic market with or without license under convex cost functions. With convex cost functions the domestic market and the foreign market are not separated, and the results depend on the relative size of those markets. In a specific case with linear demand and quadratic cost, entry without license strategy is never the optimal strategy for the...

  19. Changing mobility patterns and road mortality among pre-license teens in a late licensing country: an epidemiological study.

    Science.gov (United States)

    Twisk, Divera; Bos, Niels; Shope, Jean T; Kok, Gerjo

    2013-04-11

    Whereas the safety of teens in early licensing countries has been extensively studied, little is known about the safety of pre-license teens in late licensing countries, where these teens also may be at risk. This risk exists because of the combination of a) increasing use of travel modes with a high injury risk, such as bicycles and mopeds, b) inexperience, and c) teens' developmental stage, known to be associated with risk taking and novelty seeking, especially among males. To explore the magnitude and nature of pre-license road risk, this study analysed epidemiological data from the Netherlands, and hypothesized that in this late licensing country, 'independent travel' and the use of riskier modes of transport increase among pre-license teens 10 to 17 years of age, resulting in higher fatality rates, with 'experience' and 'gender' as risk modifying factors. National travel and fatality data of pre-license adolescents in the Netherlands were analysed by traffic role (cyclist, pedestrian, car passenger and moped rider), and compared to a younger age group (0-9 years) and an older age group (18+ years). The study of travel data showed that teens migrate from being car occupants to being users of riskier modes of transport, specifically bicycles and mopeds. This migration resulted in a strong rise in road fatalities, illustrating the importance of mobility patterns for understanding changes in road fatalities in this age group. The data further suggested a protective role of early cycle experience for young adolescent cyclists, particularly for young males. But further study into the underlying mechanism is needed to confirm this relationship. Moped risk was extremely high, especially among young males, and even higher than that of young male car drivers. The study confirmed the importance of changes in mobility patterns for understanding the rising road mortality when youngsters enter into their teens. The focus on fatalities has led to an underestimation of the

  20. 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

  1. Decay heat removal plan of the SNR-300: a licensed concept

    International Nuclear Information System (INIS)

    Morgenstern, F.H.; Gyr, W.; Stoetzel, H.; Vossebrecker, H.

    1976-01-01

    The report describes how the decay heat removal plan of the SNR-300 has been established in 3 essential licensing steps, thus giving a very significant example for the slow but steady progress in the overall licensing process of the plant. (1) Introduction of an ECCS in addition to the 3 main heat transfer chains as a back-up for rather unlikely and undefined occurrences, 1970; (2) Experimental and computational demonstration of a reliable functioning of the in-vessel natural convection of the fluid flow, 1974; and (3) Proof of fulfilling the general safety and specific reliability criteria for the overall decay heat removal plan; i.e., the 3 main heat transfer chains with specific installations on the steam/water system side and the ECCS, 1976. Some special problem areas, for instance the cavity concept provided for the pipe fracture accident, have still to be licensed, but they do not contribute considerably to the overall risk

  2. 31 CFR 596.306 - License.

    Science.gov (United States)

    2010-07-01

    ... ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM LIST GOVERNMENTS SANCTIONS REGULATIONS General Definitions § 596.306 License. Except as otherwise specified, the term license means any license or...

  3. Understanding Licensing Behavior

    DEFF Research Database (Denmark)

    Cabaleiro, Goretti; Moreira, Solon; Reichstein, Toke

    The potential for rent dissipation has been argued to be the main cause of firms? licensing out behavior being stifled.However, this aspect has been scarcely studied empirically. We draw on rent dissipation arguments, and hypothesize that firms suffering from the not-invented-here (NIH) syndrome......, firms in competitive product markets, and firms that have incurred substantial sunk cost are associated with lower rates of technology out-licensing. We also posit that sunk costs negatively moderate the relationship between competition in the licensor?s product market, and licensing rate. We test our...

  4. Standard technical specifications for General Electric boiling water reactors

    International Nuclear Information System (INIS)

    1979-08-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on General Electric plants currently being reviewed for an Operating License. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. This revision of the GE-STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

  5. Procedural violation in the licensing procedure and possible legal consequences; Verfahrensmaengel im Konzessionierungsverfahren und etwaige Rechtsfolgen

    Energy Technology Data Exchange (ETDEWEB)

    Meyer-Hetling, Astrid; Probst, Matthias Ernst; Wolkenhauer, Soeren [Kanzlei Becker Buettner Held (BBH), Berlin (Germany)

    2012-07-15

    With respect to paragraph 46 sect. 2 to 4 EnWG (Energy Economy Law) communities are required to provide a publication procedure and competition procedure ('licensing procedure') for the new assignment of easement agreements for the establishment of local power supply systems and natural gas supply systems. The specific design of the selection process legally is regulated only rudimentary. Nevertheless old concessionaires increasingly deny the statutory grid transfer to the new concessionaires relying on supposed errors in the selection process. The unclear legal situation and the inconsistent, sometimes unreasonably strict jurisdiction and jurisprudence of antitrust as well as regulatory authorities resulted to a considerable legal certainty in communities and grid operators. Unless the legislature establishes the necessary legal clarity, the competent courts and authorities are invoked to act moderately in the examination of licensing procedures.

  6. Design of multi-specificity in protein interfaces.

    Directory of Open Access Journals (Sweden)

    Elisabeth L Humphris

    2007-08-01

    Full Text Available Interactions in protein networks may place constraints on protein interface sequences to maintain correct and avoid unwanted interactions. Here we describe a "multi-constraint" protein design protocol to predict sequences optimized for multiple criteria, such as maintaining sets of interactions, and apply it to characterize the mechanism and extent to which 20 multi-specific proteins are constrained by binding to multiple partners. We find that multi-specific binding is accommodated by at least two distinct patterns. In the simplest case, all partners share key interactions, and sequences optimized for binding to either single or multiple partners recover only a subset of native amino acid residues as optimal. More interestingly, for signaling interfaces functioning as network "hubs," we identify a different, "multi-faceted" mode, where each binding partner prefers its own subset of wild-type residues within the promiscuous binding site. Here, integration of preferences across all partners results in sequences much more "native-like" than seen in optimization for any single binding partner alone, suggesting these interfaces are substantially optimized for multi-specificity. The two strategies make distinct predictions for interface evolution and design. Shared interfaces may be better small molecule targets, whereas multi-faceted interactions may be more "designable" for altered specificity patterns. The computational methodology presented here is generalizable for examining how naturally occurring protein sequences have been selected to satisfy a variety of positive and negative constraints, as well as for rationally designing proteins to have desired patterns of altered specificity.

  7. Nuclear power stations licensing

    International Nuclear Information System (INIS)

    Solito, J.

    1978-04-01

    The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n 0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed [pt

  8. 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

  9. Safety philosophy and licensing practice in different member states of IAEA: Spain

    International Nuclear Information System (INIS)

    Alonso, A.

    1981-01-01

    With the aim of presenting the licensing experience in Spain, the countries with nuclear activities are divided into three main groups: exporters, qualified importers and importers, being Spain in the second group. The licensing problems, and therefore the licensing experience, are different in the different groups of countries. Moreover, the experience in Spain is enriched by the following facts: an early start, a substantial program and a diversity of types, pressurized and boiling water reactors, and suppliers, American and German plants. Reference is made to the basic legal documents governing licensing in Spain, together with the difficulties in adopting and applying detailed regulations. Within this framework, the licensing experience in Spain is described with reference to the reference plant concept, later enlarged to include the reference-site reference plant concept, ending in the most practical approach of the reference problem concept. Finally specific licensing problems are introduced with reference to the Spanish operating nuclear power plants, the ones under commissioning and in an advanced state of construction and the ones just staring construction. (orig./RW)

  10. Technical specifications (Docket No. 50-400): Appendix ''A'' to License No. NPF-63

    International Nuclear Information System (INIS)

    1987-01-01

    This report presents specifications concerning the Shearon Harris Nuclear Power Plant in the areas of: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  11. ITER Safety and Licensing

    International Nuclear Information System (INIS)

    Girard, J-.P; Taylor, N.; Garin, P.; Uzan-Elbez, J.; GULDEN, W.; Rodriguez-Rodrigo, L.

    2006-01-01

    The site for the construction of ITER has been chosen in June 2005. The facility will be implemented in Europe, south of France close to Marseille. The generic safety scheme is now under revision to adapt the design to the host country regulation. Even though ITER will be an international organization, it will have to comply with the French requirements in the fields of public and occupational health and safety, nuclear safety, radiation protection, licensing, nuclear substances and environmental protection. The organization of the central team together with its partners organized in domestic agencies for the in-kind procurement of components is a key issue for the success of the experimentation. ITER is the first facility that will achieve sustained nuclear fusion. It is both important for the experimental one-of-a-kind device, ITER itself, and for the future of fusion power plants to well understand the key safety issues of this potential new source of energy production. The main safety concern is confinement of the tritium, activated dust in the vacuum vessel and activated corrosion products in the coolant of the plasma-facing components. This is achieved in the design through multiple confinement barriers to implement the defence in depth approach. It will be demonstrated in documents submitted to the French regulator that these barriers maintain their function in all postulated incident and accident conditions. The licensing process started by examination of the safety options. This step has been performed by Europe during the candidature phase in 2002. In parallel to the final design, and taking into account the local regulations, the Preliminary Safety Report (RPrS) will be drafted with support of the European partner and others in the framework of ITER Task Agreements. Together with the license application, the RPrS will be forwarded to the regulatory bodies, which will launch public hearings and a safety review. Both processes must succeed in order to

  12. Standard technical specifications for Babcock and Wilcox pressurized water reactors

    International Nuclear Information System (INIS)

    Virgilio, M.

    1979-07-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on B and W NSSS plants currently being reviewed for an Operating License. Two separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. This revision of STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

  13. Forum on Specifications and Design Languages 2012

    CERN Document Server

    2014-01-01

    This book brings together a selection of the best papers from the fifteenth edition of the Forum on specification and Design Languages Conference (FDL), which was held in September 2012 at Vienna University of Technology, Vienna, Austria.  FDL is a well-established international forum devoted to dissemination of research results, practical experiences and new ideas in the application of specification, design and verification languages to the design, modeling and verification of integrated circuits, complex hardware/software embedded systems, and mixed-technology systems.  ·         Covers Assertion Based Design, Verification & Debug; ·         Includes language-based modeling and design techniques for embedded systems; ·         Covers design, modeling and verification of mixed physical domain and mixed signal systems that include significant analog parts in electrical and non-electrical domains; ·         Includes formal and semi-formal system level design methods fo...

  14. Licensing new nuclear energy plants in the 90s

    International Nuclear Information System (INIS)

    Miller, J.H. III; Bishop, R.W.

    1992-01-01

    This paper reports that the framework for nuclear regulation in the United States was established by Congress in the Atomic Energy Act of 1954 (AEA). Under the AEA, the nuclear power program in the United States was launched with a technology just being developed and a nuclear power industry in its infancy. The regulations fashioned by the Atomic Energy Commission under the AEA took into account the evolving state of the technology and the emerging industry in those formative years. The process required a utility desiring to build and operate a nuclear power plant to obtain two separate licenses: one authorizing construction and one authorizing operation. At the construction permit stage, generally only preliminary design information was available and a construction permit could be issued with as little as ten to fifteen percent of the facility design completed. Thereafter, design completion, along with research and development required to address open technical issues, progressed in tandem with construction in what is fairly characterized as a design-as-you-go process. Only as plant construction approached completion was the adequacy of the final design evaluated in connection with the operating license review process

  15. Computational network design from functional specifications

    KAUST Repository

    Peng, Chi Han

    2016-07-11

    Connectivity and layout of underlying networks largely determine agent behavior and usage in many environments. For example, transportation networks determine the flow of traffic in a neighborhood, whereas building floorplans determine the flow of people in a workspace. Designing such networks from scratch is challenging as even local network changes can have large global effects. We investigate how to computationally create networks starting from only high-level functional specifications. Such specifications can be in the form of network density, travel time versus network length, traffic type, destination location, etc. We propose an integer programming-based approach that guarantees that the resultant networks are valid by fulfilling all the specified hard constraints and that they score favorably in terms of the objective function. We evaluate our algorithm in two different design settings, street layout and floorplans to demonstrate that diverse networks can emerge purely from high-level functional specifications.

  16. Learning-by-Licensing: How Chinese Firms Benefit From Licensing-In Technologies

    DEFF Research Database (Denmark)

    Wang, Yuandi; Roijakkers, N.; Vanhaverbeke, W.

    2012-01-01

    This paper explores how interfirm variations in their in-licensed technology portfolios influence subsequent innovation performance. Existing studies mainly assume licensed technologies are homogeneously accessible to firms, and a prevailing explanation as to why firms vary in their innovation pe...

  17. 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

  18. Standard technical specifications for Westinghouse pressurized water reactors

    International Nuclear Information System (INIS)

    Wagner, P.C.

    1979-07-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on Westinghouse plants currently being reviewed for an Operating License. Accordingly, the document contains specifications applicable to plants with (1) either 3 or 4 loops and (2) with and without loop stop valves. In addition, four separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric, Ice Condenser, Sub-Atmospheric, and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. This revision of the STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

  19. Lessons learned from the licensing process for the Clinch River Breeder Reactor Plant

    International Nuclear Information System (INIS)

    Dickson, P.W.; Clare, G.H.

    1991-01-01

    This paper presents the experience of licensing a specific liquid-metal fast breeder reactor (LMFBR), the Clinch River Breader Reactor Plant (CRBRP). It was a success story in that the licensing process was accomplished in a very short time span. The actions of the applicant and the actions of the US Nuclear Regulatory Commission (NRC) in response are presented and discussed to provide guidance to future efforts to license unconventional reactors. The history is told from the perspective of the authors. As such, some of the reasons given for success or lack of success are subjective interpretations. Nevertheless, the authors' positions provided them an excellent viewpoint to make these judgements. During the second phase of the licensing process, they were the CRBRP Technical Director and the Licensing Manager, respectively, for the Westinghouse Electric Corporation, the prime contractor for the reactor plant

  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. Flexible licensing

    Directory of Open Access Journals (Sweden)

    Martyn Jansen

    2012-07-01

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

  2. Engineering and licensing progress of the HTR-Module

    Energy Technology Data Exchange (ETDEWEB)

    Weisbrodt, I A

    1988-07-01

    This report deals not only with the latest status of Siemens/Interatom's HTR-Module but also reflects the latest engineering and licensing progress of the HTR-Module against the background of the specified design requirements and of the discussions on passively safe reactors. Therefore, I intend to report also about two examples of the accident analysis - one design basis accident, i.e. the leak-before-break of the reactor pressure vessel and one beyond design accident, i. e. massive water ingress.

  3. Engineering and licensing progress of the HTR-Module

    International Nuclear Information System (INIS)

    Weisbrodt, I.A.

    1988-01-01

    This report deals not only with the latest status of Siemens/Interatom's HTR-Module but also reflects the latest engineering and licensing progress of the HTR-Module against the background of the specified design requirements and of the discussions on passively safe reactors. Therefore, I intend to report also about two examples of the accident analysis - one design basis accident, i.e. the leak-before-break of the reactor pressure vessel and one beyond design accident, i. e. massive water ingress

  4. Trends in nuclear licensing

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-06-01

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

  5. Trends in nuclear licensing

    International Nuclear Information System (INIS)

    Dalton, N.W.

    1990-01-01

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

  6. Summary of NRR future licensing activities

    International Nuclear Information System (INIS)

    2001-01-01

    In response to a renewed interest in building nuclear power plants, the NRC has created organizations within its major program offices to prepare the NRC staff for new applications (early site permits [ESPs], design certifications, and combined licenses) and to manage special task groups and pro-application reviews of new reactor designs. Activities planned in FY2001 and FY2002 include: (1) evaluating the ability of the NRC staff to support future application reviews under 10 CFR Parts 50 and 52; (2) performing pre-application reviews of the API 000 (a light-water reactor design with passive safety systems), Pebble Bed Modular Reactor (PBMR - a high-temperature gas-cooled reactor design), ESPs, IRIS (an advanced light-water reactor design), and GT-MHR (a high-temperature gas-cooled reactor design); (3) initiating and/or performing related rulemakings that will update 10 CPR Part 52 to reflect lessons learned from certifying three nuclear plant designs, update Tables S-3 and S-4 of 10 CFR Part 51 to address higher burnup fuel considerations and non-LWR advanced designs, and address alternative siting considerations; (4) reactivating the construction inspection program; and, (5) interacting with stakeholders to ensure there is a clear understanding of upcoming activities related to future applications and to solicit stakeholder input. In FY2002 and FY200S, activities are expected to include: (1) managing the reviews of fine new applications resulting from the pre-application reviews (including one design certification, one combined license, and three ESP reviews); (2) managing two pre-application reviews (IRIS and QT-MHR); (3) updating regulatory and review guidance for new applications, i.e., Standard Review Plans (SRPs), Regulatory Guides, and referenced codes and standards, and identifying where enhancements are needed; (4) developing independent codes to analyze the safety of non-LWR designs, with supporting validation testing; and, (5) addressing regulatory

  7. Predictors of actual turnover in a national sample of newly licensed registered nurses employed in hospitals.

    Science.gov (United States)

    Brewer, Carol S; Kovner, Christine T; Greene, William; Tukov-Shuser, Magdalene; Djukic, Maja

    2012-03-01

    This paper is a report of a study of factors that affect turnover of newly licensed registered nurses in United States hospitals. There is a large body of research related to nursing retention; however, there is little information specific to newly licensed registered nurse turnover. Incidence rates of turnover among new nurses are unknown because most turnover data are not from nationally representative samples of nurses. This study used a longitudinal panel design to obtain data from 1653 registered nurses who were recently licensed by examination for the first time. We mailed surveys to a nationally representative sample of hospital registered nurses 1 year apart. The analytic sample consisted of 1653 nurses who responded to both survey mailings in January of 2006 and 2007. Full-time employment and more sprains and strains (including back injuries) result in more turnover. Higher intent to stay and hours of voluntary overtime and more than one job for pay reduces turnover. When we omitted intent to stay from the probit model, less job satisfaction and organizational commitment led to more turnover, confirming their importance to turnover. Magnet Recognition Award(®) hospitals and several other work attributes had no effect on turnover.   Turnover problems are complex, which means that there is no one solution to decreasing turnover. Multiple points of intervention exist. One specific approach that may improve turnover rates is hospital policies that reduce strains and sprains. © 2011 The Authors. Journal of Advanced Nursing © 2011 Blackwell Publishing Ltd.

  8. Driver licensing and reasons for delaying licensure among young adults ages 18-20, United States, 2012.

    Science.gov (United States)

    Tefft, Brian C; Williams, Allan F; Grabowski, Jurek G

    2014-12-01

    Motor vehicle crashes are the leading cause of death for teens and young adults in the United States. Graduated driver licensing (GDL) systems were designed to protect young novice drivers by limiting their exposure to specific risks while they gain experience driving. In the United States, most states' GDL systems only apply to new drivers younger than 18. Some experts suggest that GDL might encourage young people to wait until age 18 to obtain a license, to avoid GDL requirements, resulting in older teenagers having less driving experience and higher crash risk than they might have had without GDL. This study examined the prevalence and timing of licensure among young adults, and explored factors associated with delaying licensure among those not licensed before age 18. An online questionnaire was completed by 1,039 persons aged 18-20 years, recruited from a representative panel of United States households. Main outcome measures were acquisition of driver's license (a) within 12 months of the state minimum age for licensure, (b) before age 18. Associations of timing of licensure with demographic characteristics were assessed using multivariable logistic regression. Respondents not licensed before age 18 were asked to rate the importance of various possible reasons for delaying licensure. 54% of respondents were licensed before age 18. Blacks (37%; adjusted Prevalence Ratio 0.67, 95% Confidence Interval 0.48-0.93) and Hispanics (29%; adjusted Prevalence Ratio 0.60, 95% Confidence Interval 0.45-0.81) were less likely than non-Hispanic whites (67%) to be licensed before age 18. Lower household income was independently associated with delayed licensure (P self-reported reasons for not becoming licensed sooner were not having a car, being able to get around without driving, and costs associated with driving. There was little evidence that GDL is a major contributor to delayed licensure; however, a substantial minority of young people do not obtain a driver

  9. 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.

  10. 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

  11. An examination of the perceived teaching competencies of novice alternatively licensed and traditionally licensed high school science teachers

    Science.gov (United States)

    Shea, Kathleen A.

    In most states, there are two routes to teacher licensure; traditional and alternative. The alternative route provides an accelerated entry into the classroom, often without the individual engaging in education coursework or a practicum. No matter the route, teaching skills continue to be learned by novice teachers while in the classroom with the guidance of a school-based mentor. In this study, the perceptions of mentor teachers of traditionally and alternatively licensed high school science teachers were compared with respect to mentees' science teaching competency. Further, the study explored the novice teachers' self-perception of their teaching competency. A survey, consisting of 56 Likert-type questions, was completed by mentors (N = 79) and novice high school science teachers (N = 83) in six northeastern states. The results revealed a statistically significant difference in the perceptions of the mentors of traditionally and alternatively licensed novice high school science teachers in the areas of general pedagogical knowledge, pedagogical content knowledge and professional growth, with more favorable perceptions recorded by mentors of traditionally licensed science teachers. There were no differences in the perceptions of the mentors with respect to novice high school teachers' content knowledge. There was no statistical difference in the self-perceptions of competency of the novice teachers. While alternative routes to licensure in science may be a necessity, the results of this study indicate that the lack of professional preparation may need to be addressed at the school level through the agency of the mentor. This study indicates that mentors must be prepared to provide alternatively licensed novice teachers with different assistance to that given to traditionally licensed novice teachers. School districts are urged to develop mentoring programs designed to develop the teaching competency of all novice teachers regardless of the route that led them

  12. Material specification for ductile cast iron in the United States

    International Nuclear Information System (INIS)

    Sorenson, K.B.

    1987-01-01

    The United States currently does not have formal design criteria for qualifying ductile cast iron (DCI) transportation casks. There is also no dedicated material standard for DCI for this particular application. A draft ASTM material specification has been written and is currently in the ASTM approval process. This paper reviews the brief history of the development of the specification, the technical basis for the material properties, the ASTM approval process and the current status of the draft specification. The expected implications of having an adopted ASTM specification on the licensing process are also discussed. (orig./DG)

  13. Clustering Vehicle Temporal and Spatial Travel Behavior Using License Plate Recognition Data

    Directory of Open Access Journals (Sweden)

    Huiyu Chen

    2017-01-01

    Full Text Available Understanding travel patterns of vehicle can support the planning and design of better services. In addition, vehicle clustering can improve management efficiency through more targeted access to groups of interest and facilitate planning by more specific survey design. This paper clustered 854,712 vehicles in a week using K-means clustering algorithm based on license plate recognition (LPR data obtained in Shenzhen, China. Firstly, several travel characteristics related to temporal and spatial variability and activity patterns are used to identify homogeneous clusters. Then, Davies-Bouldin index (DBI and Silhouette Coefficient (SC are applied to capture the optimal number of groups and, consequently, six groups are classified in weekdays and three groups are sorted in weekends, including commuting vehicles and some other occasional leisure travel vehicles. Moreover, a detailed analysis of the characteristics of each group in terms of spatial travel patterns and temporal changes are presented. This study highlights the possibility of applying LPR data for discovering the underlying factor in vehicle travel patterns and examining the characteristic of some groups specifically.

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

    International Nuclear Information System (INIS)

    Asselstine, J.K.

    1986-01-01

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

  15. Interior Design's Role in Educational Specifications.

    Science.gov (United States)

    Keller, Mary Ann

    1986-01-01

    An experienced interior designer, equipped with a well-written educational specification, will specify the best materials and coordinate colors, materials, and furnishings in line with the district's budget. (MLF)

  16. 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

  17. Licensing of nuclear facilities according to the Bulgarian Act on the Safe Use of Nuclear Energy

    International Nuclear Information System (INIS)

    Stoyanova-Todorova, P.

    2004-01-01

    The new Bulgarian Act on the Safe Use of Nuclear Energy /Nuclear Act/ has replaced the former Act on the Use of Nuclear Energy for Peaceful Purposes. The new Nuclear Act covers the activities involving nuclear energy and sources of ionising radiation mainly by establishing a consistent licensing regime. About 13 regulations specifying the provisions of the Nuclear Act have been recently adopted by the Council of Ministers, the most important one being the Regulation on the Procedure for Issue of Licenses and Permits for the Safe Use of Nuclear Energy. The Chairman of the Nuclear Regulatory Agency (NRA) is authorised by the law to consider any application for issue of a license or a permit under the Bulgarian Nuclear Act. The procedure starts with an application, filed with the NRA, and continues about nine months. The final decision could be for issuing of the license or permit or a refusal for issuing the claimed document. The denial must be grounded and is subject to appeal. The Nuclear Act prescribes the conditions for issuing of two types of licensing documents (authorisations): licenses and permits. From a legal point of view the two types of licensing documents have one and the same nature - they are individual administrative acts according to the Bulgarian law. That is why there is no difference between them in terms of the issuing procedure. The difference between licenses and permits could be explained as follows: while a license is issued for reiterated activities, a permit is issued for non-reoccurring activities, this division being a specific feature of the Bulgarian Nuclear Act. In the field of nuclear facilities usage only one type of license is provided for by the Nuclear Act - a license for operation of a nuclear facility unit. For the rest of the activities issuing of permits is envisaged, those permits being in compliance with the main stages of the authorisation process formulated by the IAEA, following the step-by-step approach - siting, design

  18. 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

  19. Patient-specific hip prostheses designed by surgeons

    Directory of Open Access Journals (Sweden)

    Coigny Florian

    2016-09-01

    Full Text Available Patient-specific bone and joint replacement implants lead to better functional and aesthetic results than conventional methods [1], [2], [3]. But extracting 3D shape information from CT Data and designing individual implants is demanding and requires multiple surgeon-to-engineer interactions. For manufacturing purposes, Additive Manufacturing offers various advantages, especially for low volume manufacturing parts, such as patient specific implants. To ease these new approaches and to avoid surgeon-to-engineer interactions a new design software approach is needed which offers highly automated and user friendly planning steps.

  20. CEQ regulations called peril to nuclear licensing process

    International Nuclear Information System (INIS)

    O'Neill, J.V.

    1979-01-01

    Court challenges are expected over regulations of the Council on Environmental Quality (CEQ) that were designed to improve nuclear-licensing decisions, but that have actually changed the meanings of National Environmental Policy Act (NEPA) regulations. The legal implications of these changes could, unless resolved, make the licensing process for nuclear facilities even more uncertain. Agency comments are thought to be critical, although the CEQ has declined to release them, and some question the Council's legality. The Nuclear Regulatory Commission faults the CEQ regulations for revising existing law, being inconsistent with the responsibilities of an independent regulatory body, and extending the CEQ's authority beyond the role assigned by NEPA and the President's Executive Order

  1. Graduated driver licensing and differential deterrence: The effect of license type on intentions to violate road rules.

    Science.gov (United States)

    Poirier, Brigitte; Blais, Etienne; Faubert, Camille

    2018-01-01

    In keeping with the differential deterrence theory, this article assesses the moderating effect of license type on the relationship between social control and intention to violate road rules. More precisely, the article has two objectives: (1) to assess the effect of license type on intentions to infringe road rules; and (2) to pinpoint mechanisms of social control affecting intentions to violate road rules based on one's type of driver license (a restricted license or a full license). This effect is examined among a sample of 392 young drivers in the province of Quebec, Canada. Drivers taking part in the Graduated Driver Licensing (GDL) program have limited demerit points and there is zero tolerance for drinking-and-driving. Propensity score matching techniques were used to assess the effect of the license type on intentions to violate road rules and on various mechanisms of social control. Regression analyses were then conducted to estimate the moderating effect of license type. Average treatment effects from propensity score matching analyses indicate that respondents with a restricted license have lower levels of intention to infringe road rules. While moral commitment and, to a lesser extent, the perceived risk of arrest are both negatively associated with intentions to violate road rules, the license type moderates the relationship between delinquent peers and intentions to violate road rules. The effect of delinquent peers is reduced among respondents with a restricted driver license. Finally, a diminished capability to resist peer pressure could explain the increased crash risk in months following full licensing. Copyright © 2017 Elsevier Ltd. All rights reserved.

  2. 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.)

  3. 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)

  4. Licensing issues associated with the use of computers in the nuclear industry

    International Nuclear Information System (INIS)

    Ehrenberger, W.D.; Bloomfield, R.E.

    1987-01-01

    Computers are increasingly important to ensuring the safety of nuclear power stations. They have been proposed or introduced into operator information systems, operational control systems, as well as into systems for core protection and plant protection. Although the developments in the individual countries are not at the same pace, they do tend to render similar results. Particular licensing problems arise because of the increasing complexity of computer systems and the software involved. In the past licensing has been closely connected with the mental understanding of the systems to be licensed. This understanding is endangered with greater complexity of the systems. Although several ''manual'' methods of licensing exist, the problem of cost effective licensing is still more or less unsolved. For the future it is expected that tools will reduce the licensing efforts leaving the licenser and assessor free to concentrate on the most important issues. Such tools will probably make use of artificial intelligence techniques. They will enable the inclusion of more complex functions into safety systems and thereby increase the number of safety criteria and the number of echelons od defense. Another important use of artificial intelligence techniques will be the area of operator information systems and maintenance, including computer hardware maintenance. They will provide early detection of problems in the plant and thereby largely enhance plant availability and safety. Further studies are being proposed in the fields of software licensing tools, artificial intelligence, fail-safe and fault-tolerant software architectures, test procedures and system specification

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  7. 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...

  8. Summary report on safety and licensing strategy support for the ABR prototype

    International Nuclear Information System (INIS)

    Cahalan, J. E.; Nuclear Engineering Division

    2007-01-01

    Argonne National Laboratory is providing support to the US Department of Energy in the Global Nuclear Energy Partnership (GNEP) in certification of an advanced, sodium-cooled fast reactor. The reactor is to be constructed as a prototype for future commercial power reactors that will produce electricity while consuming actinides recovered from light water reactor spent fuel. This prototype reactor has been called the Advanced Burner Reactor, or ABR, and is now often referred to as the advanced recycle reactor. As part of its activities, Argonne is providing technical services to assist definition of a safety and licensing strategy for the ABR prototype, and to further implementation of the strategy. In FY06, an organizational meeting was held for DOE and its laboratory contractors to discuss licensing alternatives and review previous licensing experience for the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor Plant (CRBRP). Near the end of FY06, a report summarizing the discussions and conclusions was written. One of the top-level conclusions recorded in the report was a recommendation to follow a licensing strategy that included the US Nuclear Regulatory Commission (NRC) as the regulatory review and licensing authority. In FY07, activities ar Argonne to support safety and licensing progress have continued. These activities have focused on further evaluation of licensing alternatives; assessment of design, analysis, and documentation implications of licensing paths; and initial technical interactions with the Nuclear Regulatory Commission. This report summarizes FY07 activities

  9. Licensing and Other Controls of the Drinking Driver.

    Science.gov (United States)

    Waller, Patricia F.

    Driver licensing, the only state program with the opportunity for routine personal contact with every driver, has unmatched potential for both general and specific countermeasures to the problem of drunk driving. General countermeasures apply to large groups of drivers prior to the occurrence of any infraction. They may be considered basically…

  10. 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)

  11. 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

  12. Internet MEMS design tools based on component technology

    Science.gov (United States)

    Brueck, Rainer; Schumer, Christian

    1999-03-01

    The micro electromechanical systems (MEMS) industry in Europe is characterized by small and medium sized enterprises specialized on products to solve problems in specific domains like medicine, automotive sensor technology, etc. In this field of business the technology driven design approach known from micro electronics is not appropriate. Instead each design problem aims at its own, specific technology to be used for the solution. The variety of technologies at hand, like Si-surface, Si-bulk, LIGA, laser, precision engineering requires a huge set of different design tools to be available. No single SME can afford to hold licenses for all these tools. This calls for a new and flexible way of designing, implementing and distributing design software. The Internet provides a flexible manner of offering software access along with methodologies of flexible licensing e.g. on a pay-per-use basis. New communication technologies like ADSL, TV cable of satellites as carriers promise to offer a bandwidth sufficient even for interactive tools with graphical interfaces in the near future. INTERLIDO is an experimental tool suite for process specification and layout verification for lithography based MEMS technologies to be accessed via the Internet. The first version provides a Java implementation even including a graphical editor for process specification. Currently, a new version is brought into operation that is based on JavaBeans component technology. JavaBeans offers the possibility to realize independent interactive design assistants, like a design rule checking assistants, a process consistency checking assistants, a technology definition assistants, a graphical editor assistants, etc. that may reside distributed over the Internet, communicating via Internet protocols. Each potential user thus is able to configure his own dedicated version of a design tool set dedicated to the requirements of the current problem to be solved.

  13. Licensing in an International Market

    Science.gov (United States)

    Ferreira, Fernanda A.

    2008-09-01

    We study the effects of entry of a foreign firm on domestic welfare in the presence of licensing, when the entrant is technologically superior to the incumbent. We show that foreign entry increases domestic welfare for sufficiently large technological differences between the firms under both fixed-fee licensing and royalty licensing.

  14. 22 CFR 120.20 - License.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false License. 120.20 Section 120.20 Foreign Relations DEPARTMENT OF STATE INTERNATIONAL TRAFFIC IN ARMS REGULATIONS PURPOSE AND DEFINITIONS § 120.20 License. License means a document bearing the word “license” issued by the Directorate of Defense Trade...

  15. Surgeon Design Interface for Patient-Specific Concentric Tube Robots.

    Science.gov (United States)

    Morimoto, Tania K; Greer, Joseph D; Hsieh, Michael H; Okamura, Allison M

    2016-06-01

    Concentric tube robots have potential for use in a wide variety of surgical procedures due to their small size, dexterity, and ability to move in highly curved paths. Unlike most existing clinical robots, the design of these robots can be developed and manufactured on a patient- and procedure-specific basis. The design of concentric tube robots typically requires significant computation and optimization, and it remains unclear how the surgeon should be involved. We propose to use a virtual reality-based design environment for surgeons to easily and intuitively visualize and design a set of concentric tube robots for a specific patient and procedure. In this paper, we describe a novel patient-specific design process in the context of the virtual reality interface. We also show a resulting concentric tube robot design, created by a pediatric urologist to access a kidney stone in a pediatric patient.

  16. Radioisotope thermoelectric generator licensed hardware package and certification tests

    International Nuclear Information System (INIS)

    Goldmann, L.H.; Averette, H.S.

    1994-01-01

    This paper presents the Licensed Hardware package and the Certification Test portions of the Radioisotope Thermoelectric Generator Transportation System. This package has been designed to meet those portions of the Code of Federal Regulations (10 CFR 71) relating to ''Type B'' shipments of radioactive materials. The detailed information for the anticipated license is presented in the safety analysis report for packaging, which is now in process and undergoing necessary reviews. As part of the licensing process, a full-size Certification Test Article unit, which has modifications slightly different than the Licensed Hardware or production shipping units, is used for testing. Dimensional checks of the Certification Test Article were made at the manufacturing facility. Leak testing and drop testing were done at the 300 Area of the US Department of Energy's Hanford Site near Richland, Washington. The hardware includes independent double containments to prevent the environmental spread of 238 Pu, impact limiting devices to protect portions of the package from impacts, and thermal insulation to protect the seal areas from excess heat during accident conditions. The package also features electronic feed-throughs to monitor the Radioisotope Thermoelectric Generator's temperature inside the containment during the shipment cycle. This package is designed to safely dissipate the typical 4500 thermal watts produced in the largest Radioisotope Thermoelectric Generators. The package also contains provisions to ensure leak tightness when radioactive materials, such as a Radioisotope Thermoelectric Generator for the Cassini Mission, planned for 1997 by the National Aeronautics and Space Administration, are being prepared for shipment. These provisions include test ports used in conjunction with helium mass spectrometers to determine seal leakage rates of each containment during the assembly process

  17. 48 CFR 227.7203-4 - License rights.

    Science.gov (United States)

    2010-10-01

    ... Software and Computer Software Documentation 227.7203-4 License rights. (a) Grant of license. The... license, under an irrevocable license granted or obtained by the contractor which developed the software... granted to the Government. The scope of a computer software license is generally determined by the source...

  18. ITER, On the way to call for the license

    International Nuclear Information System (INIS)

    Alejaidre, C.; Girard, J.P.

    2007-01-01

    Full text of publication follows: All the seven ITER Parties have now ratified the lTER Agreement, which was signed in Paris in November last year. On October 24, 2007 the ITER Agreement enters officially into force. The licensing procedure to start construction shall be launched within the coming months in order to start construction at the beginning of 2009. The Host Party, Europe and the Host State, France have already participated together with the ITER Organization (IO) to a public debate to present the project to the neighboring populations (January to May 2006) and other administrative procedures to prepare the site and the roads for heavy loads. According to host state law on licensing of nuclear facilities, IO will send a set of administrative documents including a safety assessment (called Preliminary Safety Report) and public hearing files including impact studies and risk analysis. The review and public hearing are expected mid-08 to be consistent with the start of nuclear building construction on site. The latest update of the design took into account of inputs from: -An internal design review managed through eight specialist groups including safety and licensing, - Host State regulations (technical and QA), which should be fulfilled as quoted in the ITER agreement, - Site adaptation including land configuration, environmental conditions and external hazards. The ITER designers, in close contact with the Participant Teams, are proceeding with the adaptation of the generic design to comply with these new inputs. The codes and standards for all equipment are also under revision in order to fit with the expected requirements, taking into account the procurement sharing agreement and the French regulations. In the earlier stage of ITER design fusion took benefit from fission knowledge, in the present stage fusion is taking the lead as can be demonstrated by the update of the European mechanical code RCC-MR, now ready and updated to the vacuum vessel design

  19. 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

  20. 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.

  1. Technology Licensing and Firm Innovation

    DEFF Research Database (Denmark)

    Moreira, Solon

    acquisition. The findings indicate that technology licensing is positively related to the number of inventions produced by the licensee in the years subsequent to the licensing deal. Subsequently, I investigate the moderating effect that organizational slack and myopia have on this main relationship....... The findings also suggest that high levels of Organizational Slack (available financial resources) strengthen the positive effect of licensing on innovation. However, higher levels of Organizational Myopia (the extent to which a firm draws on its own knowledge) can decrease the main effect of licensing....

  2. Ebooks Licensing and Canadian Copyright Legislation: A Few Considerations

    Directory of Open Access Journals (Sweden)

    Tony G Horava

    2009-06-01

    Full Text Available Ebooks have become increasingly common in collection development strategies. The availability and delivery of monographs in digital formats has gained significantly in popularity in many libraries, particularly in the academic sector. Licensing is the common method of acquiring ebooks, whether as a subscription or a purchase. Libraries have had to transform selection and workflow processes in order to acquire ebooks in an efficient manner. Little attention, however, has been paid to the interplay between licensing as a contractual arrangement and the statutory rights available under Canadian copyright law. Fair dealing is a concept of critical importance in Canadian copyright, as it provides the foundation for user rights in support of culture, learning, and innovation. There are other provisions of specific value for libraries, such as interlibrary loans and access by persons with perceptual disabilities. This article will examine these issues and proposes a few strategies that libraries can adopt to ensure that statutory rights are not eroded in licensing agreements

  3. Pharmaceutical new product development: the increasing role of in-licensing.

    Science.gov (United States)

    Edwards, Nancy V

    2008-12-01

    Many pharmaceutical companies are facing a pipeline gap because of the increasing economic burden and uncertainty associated with internal research and development programs designed to develop new pharmaceutical products. To fill this pipeline gap, pharmaceutical companies are increasingly relying on in-licensing opportunities. New business development identifies new pharmaceuticals that satisfy unmet needs and are a good strategic fit for the company, completes valuation models and forecasts, evaluates the ability of the company to develop and launch products, and pursues in-licensing agreements for pharmaceuticals that cannot be developed internally on a timely basis. These agreements involve the transfer of access rights for patents, trademarks, or similar intellectual property from an outside company in exchange for payments. Despite the risks, in-licensing is increasingly becoming the preferred method for pharmaceutical companies with pipeline gaps to bring new pharmaceuticals to the clinician.

  4. 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 ...

  5. THTR steam generator licensing experience as seen by the manufacturer

    International Nuclear Information System (INIS)

    Fricker, H.W.

    1981-01-01

    This paper describes the licensing procedures of the manufacture of the 300 MWe THTR steam generator. The following problems are discussed: operating data, design, materials used, manufacture and installation of the generator, and also quality control

  6. Computational network design from functional specifications

    KAUST Repository

    Peng, Chi Han; Yang, Yong Liang; Bao, Fan; Fink, Daniel; Yan, Dongming; Wonka, Peter; Mitra, Niloy J.

    2016-01-01

    of people in a workspace. Designing such networks from scratch is challenging as even local network changes can have large global effects. We investigate how to computationally create networks starting from only high-level functional specifications

  7. The need for legislative framework (licensing)

    International Nuclear Information System (INIS)

    Krech, H.

    1977-01-01

    For reasons of public acceptance the basis of a licensing system should be laid down in a law, details can be fixed in regulations below the law-level. The competence for licensing nuclear installations should be attributed to one body, which is not a the same time charged with the promotion of nuclear energy. The licensing authority has to be provided with sufficient technical advice, given by experts organized in advisory bodies. Normally a licensing procedure is split into several steps (site approval, construction permit, operation licence), each step can be subdivided. Some general aspects of licensing conditions (personal, technical and financial) as well as of the licensing procedure are outlined. The participation of the public is of particular importance but also involves most intricate problems. The paper concludes with some critical remarks on the role of administrative courts with respect to the licensing of nuclear power plants. (orig.) [de

  8. 31 CFR 596.305 - General license.

    Science.gov (United States)

    2010-07-01

    ... FOREIGN ASSETS CONTROL, DEPARTMENT OF THE TREASURY TERRORISM LIST GOVERNMENTS SANCTIONS REGULATIONS General Definitions § 596.305 General license. The term general license means any license or authorization...

  9. 76 FR 10378 - Government-Owned Inventions; Availability for Licensing

    Science.gov (United States)

    2011-02-24

    ... the indicated licensing contact at the Office of Technology Transfer, National Institutes of Health... Residues From Recombinant Proteins Description of Technology: Affinity tags are commonly used to facilitate... inventors have now cloned, expressed and purified bovine carboxypeptidase B (BoCPB), which is specific for...

  10. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    International Nuclear Information System (INIS)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C.

    2004-01-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  11. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

    2004-07-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  12. 7 CFR 1753.7 - Plans and specifications (P&S).

    Science.gov (United States)

    2010-01-01

    ... specifications prepared by the borrower's engineer. The specifications prepared by the borrower's engineer and... its contractor complies with the insurance and bond requirements. (4) Telecommunications software license provision. If the borrower is required to enter into a software license agreement in order to use...

  13. Tast Force report on bonding and perpetual care of nuclear licensed activities

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    Potential issues which should be considered prior to the adoption and implementation of a bonding or perpetual care program are examined. The following topics are discussed: problem definition; major processors; factors in setting the amount of a bond; waste handling licensees; ore refineries and mills; former AEC licensed facilities; other specific licenses; authority; states where it is deemed that amendment of existing statutes is necessary to authorize imposition of a bonding requirement for licenses; administration; and recommendations. The following appendices are included: summary of cost estimate to decontaminate the American Nuclear Company; report on 1974 national conference on radiation control workshop no. 3; suggested changes to state regulations; and suggested legislation for licensee bonding and perpetual care trust funds

  14. EMPIRICAL STUDY OF CAR LICENSE PLATES RECOGNITION

    Directory of Open Access Journals (Sweden)

    Nasa Zata Dina

    2015-01-01

    Full Text Available The number of vehicles on the road has increased drastically in recent years. The license plate is an identity card for a vehicle. It can map to the owner and further information about vehicle. License plate information is useful to help traffic management systems. For example, traffic management systems can check for vehicles moving at speeds not permitted by law and can also be installed in parking areas to se-cure the entrance or exit way for vehicles. License plate recognition algorithms have been proposed by many researchers. License plate recognition requires license plate detection, segmentation, and charac-ters recognition. The algorithm detects the position of a license plate and extracts the characters. Various license plate recognition algorithms have been implemented, and each algorithm has its strengths and weaknesses. In this research, I implement three algorithms for detecting license plates, three algorithms for segmenting license plates, and two algorithms for recognizing license plate characters. I evaluate each of these algorithms on the same two datasets, one from Greece and one from Thailand. For detecting li-cense plates, the best result is obtained by a Haar cascade algorithm. After the best result of license plate detection is obtained, for the segmentation part a Laplacian based method has the highest accuracy. Last, the license plate recognition experiment shows that a neural network has better accuracy than other algo-rithm. I summarize and analyze the overall performance of each method for comparison.

  15. The Hierarchical Specification and Mechanical Verification of the SIFT Design

    Science.gov (United States)

    1983-01-01

    The formal specification and proof methodology employed to demonstrate that the SIFT computer system meets its requirements are described. The hierarchy of design specifications is shown, from very abstract descriptions of system function down to the implementation. The most abstract design specifications are simple and easy to understand, almost all details of the realization were abstracted out, and are used to ensure that the system functions reliably and as intended. A succession of lower level specifications refines these specifications into more detailed, and more complex, views of the system design, culminating in the Pascal implementation. The section describes the rigorous mechanical proof that the abstract specifications are satisfied by the actual implementation.

  16. A systematic design method for robust synthetic biology to satisfy design specifications.

    Science.gov (United States)

    Chen, Bor-Sen; Wu, Chih-Hung

    2009-06-30

    Synthetic biology is foreseen to have important applications in biotechnology and medicine, and is expected to contribute significantly to a better understanding of the functioning of complex biological systems. However, the development of synthetic gene networks is still difficult and most newly created gene networks are non-functioning due to intrinsic parameter uncertainties, external disturbances and functional variations of intra- and extra-cellular environments. The design method for a robust synthetic gene network that works properly in a host cell under these intrinsic parameter uncertainties and external disturbances is the most important topic in synthetic biology. In this study, we propose a stochastic model that includes parameter fluctuations and external disturbances to mimic the dynamic behaviors of a synthetic gene network in the host cell. Then, based on this stochastic model, four design specifications are introduced to guarantee that a synthetic gene network can achieve its desired steady state behavior in spite of parameter fluctuations, external disturbances and functional variations in the host cell. We propose a systematic method to select a set of appropriate design parameters for a synthetic gene network that will satisfy these design specifications so that the intrinsic parameter fluctuations can be tolerated, the external disturbances can be efficiently filtered, and most importantly, the desired steady states can be achieved. Thus the synthetic gene network can work properly in a host cell under intrinsic parameter uncertainties, external disturbances and functional variations. Finally, a design procedure for the robust synthetic gene network is developed and a design example is given in silico to confirm the performance of the proposed method. Based on four design specifications, a systematic design procedure is developed for designers to engineer a robust synthetic biology network that can achieve its desired steady state behavior

  17. 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)

  18. Technical issues and approach to license dry storage of LWR fuel in the United States

    International Nuclear Information System (INIS)

    Johnson, A.B.; Beeman, G.H.; Creer, J.M.; Gilbert, E.R.

    1984-01-01

    Dry storage is emerging as an important alternative to wet storage for US utilities, even though wet storage will remain the principal storage method, at least until the federal government begins to accept fuel in 1998. Dry storage has been licensed in several countries. In the USA, dry storage issues are related to storage system performance and behavior of spent fuel during storage. There is a coordinated US effort among electric utilities, the Electric Power Research Institute (EPRI), the Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC) to license two dry storage concepts: metal casks, and horizontal storage modules. The following activities are underway to resolve the licensing issues associated with dry storage and to establish the licensing basis: a) summarize and assimilate domestic and foreigh dry storage experience; b) conduct tests which resolve specific licensing issues; c) conduct cooperative demonstrations of the leading dry storage concepts; d) establish criteria and justifications for generic licensing. The paper summarizes the licensing issues and the approach to their resolution

  19. Managing Licensing in a Market for Technology

    DEFF Research Database (Denmark)

    Arora, Ashish; Rønde, Thomas; Fosfuri, Andrea

    the technology makes licensing decisions—to centralized licensing. The business unit has superior information about licensing opportunities but may not have the appropriate incentives because its rewards depend upon product market performance. If licensing is decentralized, the business unit forgoes valuable...... licensing opportunities since the rewards for licensing are (optimally) weaker than those for product market profits. This distortion is stronger when production-based incentives are more powerful, making centralization more attractive. Growth of technology markets favors centralization and drives higher...

  20. Alpena Community College Commercial Driver's License Program. Evaluation Summary.

    Science.gov (United States)

    Alpena Community Coll., MI.

    The Alpena Community College (ACC) Drivers Education Program was developed to deliver a basic skills program providing specific job-related basic skills instruction to approximately 300 workers throughout Michigan who desired to pass the Commercial Drivers License (CDL) examination. Other program goals were to establish greater partnerships…

  1. Cask development, testing, and licensing

    International Nuclear Information System (INIS)

    Quinn, G.J.; Haelsig, R.T.; Warrant, M.M.

    1986-01-01

    The NuPac 125-B Rail Cask was developed to provide a safe means of transporting the damaged core of Three Mile Island Unit 2 from the TMI site at Middletown, PA, to the Idaho National Engineering laboratory (INEL) at Idaho Falls, ID. The development of the NuPac 125-B Rail Cask posed two engineering and technical management challenges; Licensing Strategy - The NuPac 125-B Rail Cask represented the first irradiated fuel rail cask developed within the United States in the past decade, a decade characterized by changing nuclear regulations, and Accelerated Schedule - The TMI-2 defueling schedule demanded a cask development schedule one-third as long as normally required. These challenges governed the overall development and licensing process for the cask. First, a high degree of conservation was incorporated into the design to allow quick, simplified demonstrations of adequacy to regulatory staff. Second, redundant design techniques were employed in all areas of uncertainty. The testing program eliminated performance uncertainties and validated predictions and predictive models. Drop tests of a quarter-scale model of the cask were conducted, and results were correlated with analytic predictions to verify structural and mechanical performance of the cask. Full-scale tests of the canisters were conducted to verify structural behavior of canister internals which provide criticality control. This paper describes the testing program for the NuPac 125-B Rail Cask, presents results therefrom, and correlates findings with Regulation 10 CFR 71 of the U.S. Nuclear Regulatory Commission

  2. Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations

    International Nuclear Information System (INIS)

    2007-01-01

    The major result of the work is the identification of consensus and common technical positions on a set of important licensing issues raised by the design and operation of computer-based systems used in Nuclear Power Plants for safety functions. The purpose is to introduce greater consistency and more mutual acceptance into current practices. To achieve these common positions, detailed consideration was paid to the licensing approaches followed in the different countries represented by the experts of the task force. The report is intended to be useful: - to coordinate regulators' and safety experts' technical viewpoints in the design of regulators' national policies and in revisions of guidelines; - as a reference in safety cases and demonstrations of safety of software based systems; - as guidance for system design specifications by manufacturers and major I and C suppliers on the international market. The task force decided at an early stage to focus attention on computer based systems used in Nuclear Power Plants for the implementation of safety functions; namely, those systems classified by the IAEA as 'Safety Systems'. Therefore, recommendations of this report - except those of chapter 1.11 - primarily address 'safety systems' and not 'safety related systems'. It was felt that the most difficult aspects of the licensing of digital programmable systems are rooted in the specific properties of the technology. The objective was therefore to delineate practical and technical licensing guidance, rather than discussing or proposing basic principles or requirements. The design requirements and the basic principles of nuclear safety in force in each member state are assumed to remain applicable. This report represents the consensus view achieved by the experts who contributed to the task force. It is the result of what was at the time of its initiation a first attempt at the international level to achieve consensus among nuclear regulators on practical methods for

  3. Post-hoc simulation study to adopt a computerized adaptive testing (CAT) for a Korean Medical License Examination.

    Science.gov (United States)

    Seo, Dong Gi; Choi, Jeongwook

    2018-05-17

    Computerized adaptive testing (CAT) has been adopted in license examinations due to a test efficiency and accuracy. Many research about CAT have been published to prove the efficiency and accuracy of measurement. This simulation study investigated scoring method and item selection methods to implement CAT in Korean medical license examination (KMLE). This study used post-hoc (real data) simulation design. The item bank used in this study was designed with all items in a 2017 KMLE. All CAT algorithms for this study were implemented by a 'catR' package in R program. In terms of accuracy, Rasch and 2parametric logistic (PL) model performed better than 3PL model. Modal a Posteriori (MAP) or Expected a Posterior (EAP) provided more accurate estimates than MLE and WLE. Furthermore Maximum posterior weighted information (MPWI) or Minimum expected posterior variance (MEPV) performed better than other item selection methods. In terms of efficiency, Rasch model was recommended to reduce test length. Simulation study should be performed under varied test conditions before adopting a live CAT. Based on a simulation study, specific scoring and item selection methods should be predetermined before implementing a live CAT.

  4. 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

  5. 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

  6. 75 FR 76757 - Licensing Support System Advisory Review Panel

    Science.gov (United States)

    2010-12-09

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

  7. Two Approaches to Reactor Decommissioning: 10 CFR Part 50 License Termination and License Amendment, Lessons Learned from the Regulatory Perspective

    International Nuclear Information System (INIS)

    Watson, B.A.; Buckley, J.T.; Craig, C.M.

    2006-01-01

    Trojan Nuclear Plant (Trojan) and Maine Yankee Nuclear Plant (Maine Yankee) were the first two power reactors to complete decommissioning under the U. S. Nuclear Regulatory Commission's (NRC's) License Termination Rule (LTR), 10 CFR Part 20, Subpart E. The respective owners' decisions to decommission the sites resulted in different approaches to both the physical aspects of the decommissioning, and the approach for obtaining approval for completing the decommissioning in accordance with regulations. Being in different States, the two single-unit pressurized water reactor sites had different State requirements and levels of public interest that impacted the decommissioning approaches. This resulted in significant differences in decommissioning planning, conduct of decommissioning operations, volumes of low- level radioactive waste disposed, and the final status survey (FSS) program. While both licensees have Independent Spent Fuel Storage Installations (ISFSIs), Trojan obtained a separate license for the ISFSI in accordance with the requirements of 10 CFR Part 72 and terminated their 10 CFR Part 50 license. Maine Yankee elected to obtain a general license under 10 CFR Part 50 for the ISFSI and reduce the physical site footprint to the ISFSI through a series of license amendments. While the NRC regulations are flexible and allow different approaches to ISFSI licensing there are separate licensing requirements that must be addressed. In 10 CFR 50.82, the NRC mandates public participation in the decommissioning process. For Maine Yankee, public input resulted in the licensee entering into an agreement with a concerned citizen group and resulted in State legislation that significantly lowered the dose limit below the NRC radiological criteria of 25 mrem (0.25 mSv) per year (yr) in 10 CFR 20.1402 for unrestricted use. The lowering of the radiological criteria resulted in a significant dose modeling effort using site-specific Derived Concentrations Guideline Levels (DCGLs

  8. SPEAR-FCODE-GAMMA functional specifications. Final report

    International Nuclear Information System (INIS)

    Fiero, I.B.

    1983-03-01

    SPEAR FCODE GAMMA (SFG), a conceptual fuel-performance code for use in licensing analyses, has been defined and characterized as a set of functional specifications. The potential licensing-related applications of SFG are established and discussed. General code specifications including regulatory, interface, hardware application, code model and software, and operational specifications are discussed. The code input and output information including data requirements as well as formatting aspects are detailed. Finally, the SFG code-accuracy guidelines are established and the validation process is described

  9. 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)

  10. 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)

  11. Overview of NORM and activities by a NORM licensed permanent decontamination and waste processing facility

    Energy Technology Data Exchange (ETDEWEB)

    Mirro, G.A. [Growth Resources, Inc., Lafayette, LA (United States)

    1997-02-01

    This paper presents an overview of issues related to handling NORM materials, and provides a description of a facility designed for the processing of NORM contaminated equipment. With regard to handling NORM materials the author discusses sources of NORM, problems, regulations and disposal options, potential hazards, safety equipment, and issues related to personnel protection. For the facility, the author discusses: description of the permanent facility; the operations of the facility; the license it has for handling specific radioactive material; operating and safety procedures; decontamination facilities on site; NORM waste processing capabilities; and offsite NORM services which are available.

  12. 31 CFR 560.501 - Effect of license or authorization.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Effect of license or authorization. 560.501 Section 560.501 Money and Finance: Treasury Regulations Relating to Money and Finance... respect to, any property which would not otherwise exist under ordinary principles of law. (d) Specific...

  13. Designing Epigenome Editors: Considerations of Biochemical and Locus Specificities.

    Science.gov (United States)

    Sen, Dilara; Keung, Albert J

    2018-01-01

    The advent of locus-specific protein recruitment technologies has enabled a new class of studies in chromatin biology. Epigenome editors enable biochemical modifications of chromatin at almost any specific endogenous locus. Their locus specificity unlocks unique information including the functional roles of distinct modifications at specific genomic loci. Given the growing interest in using these tools for biological and translational studies, there are many specific design considerations depending on the scientific question or clinical need. Here we present and discuss important design considerations and challenges regarding the biochemical and locus specificities of epigenome editors. These include how to account for the complex biochemical diversity of chromatin; control for potential interdependency of epigenome editors and their resultant modifications; avoid sequestration effects; quantify the locus specificity of epigenome editors; and improve locus specificity by considering concentration, affinity, avidity, and sequestration effects.

  14. FHR Generic Design Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Flanagan, George F [ORNL; Holcomb, David Eugene [ORNL; Cetiner, Sacit M [ORNL

    2012-06-01

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC) - based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  15. Standard Specification for Nuclear Facility Transient Worker Records

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1995-01-01

    1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. 1.2 This specification applies to records to be used for in-processing only. 1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications). 1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD...

  16. Free Software Licenses and Other Free Licenses: Genetic Code of Digital Common Goods

    OpenAIRE

    Marco Ciurcina

    2017-01-01

    This article explores the history and describes the main features of free software licenses and other free licenses in an attempt to shed light on the reasons for their success in promoting individual behaviors converging towards the collective construction of digital commons.

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

    International Nuclear Information System (INIS)

    Asselstine, J.K.

    1986-01-01

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

  18. Main aspects in licensing of a type B(U) package design for the transport of 12.95 PBq of cobalt 60

    International Nuclear Information System (INIS)

    Lopez Vietri, J.R.; Novo, R.G.; Bianchi, A.J.

    1995-01-01

    This paper points out the relevant technical issues related to the licensing process, of a type B(U) package design, with cylindrical form and 9.3 ton mass, approved by the Argentine Competent Authority for the transport of 12.95 PBq of cobalt 60 as special form radioactive material. It is briefly described the heat transfer analysis, the structural performance under impulsive loads and the shielding calculation under both normal and accidental conditions of transport, as well as the comparative analysis of the results obtained from design, pre-operational tests and independent evaluation performed by the Argentine Competent Authority to verify the compliance with the Regulations for the Safe Transport of Radioactive Material of the International Atomic Energy Agency. (author). 14 refs., 1 fig., tabs

  19. The probabilistic approach and the deterministic licensing procedure

    International Nuclear Information System (INIS)

    Fabian, H.; Feigel, A.; Gremm, O.

    1984-01-01

    If safety goals are given, the creativity of the engineers is necessary to transform the goals into actual safety measures. That is, safety goals are not sufficient for the derivation of a safety concept; the licensing process asks ''What does a safe plant look like.'' The answer connot be given by a probabilistic procedure, but need definite deterministic statements; the conclusion is, that the licensing process needs a deterministic approach. The probabilistic approach should be used in a complementary role in cases where deterministic criteria are not complete, not detailed enough or not consistent and additional arguments for decision making in connection with the adequacy of a specific measure are necessary. But also in these cases the probabilistic answer has to be transformed into a clear deterministic statement. (orig.)

  20. Free Software Licenses and Other Free Licenses: Genetic Code of Digital Common Goods

    Directory of Open Access Journals (Sweden)

    Marco Ciurcina

    2017-06-01

    Full Text Available This article explores the history and describes the main features of free software licenses and other free licenses in an attempt to shed light on the reasons for their success in promoting individual behaviors converging towards the collective construction of digital commons.

  1. 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)

  2. Decay power evaluation for licensing analysis

    International Nuclear Information System (INIS)

    Tran, H.; Schrock, V.E.

    1987-01-01

    The ANSI/ANS 5.1-1979 Standard on Decay Power in shutdown reactors has been available as the basis for accident analysis for the past 7 yr. The US Nuclear Regulatory Commission has made a commitment to use this standard in new licensing approaches and has approved a licensing model for boiling water. More sweeping changes in the licensing rules are currently under review that will involve the use of best-estimate models and a statistical evaluation of the uncertainty (95% confidence level) in the key results. The structure of the decay power standard is well suited for such applications because it provides a statistically meaningful uncertainty in the decay power from fission products. The normalized decay power is a function specific to each point in the reactor volume due to the fact that the fuel composition develops a spatial dependence as burnup proceeds and decay power depends on the mix of fissioning nuclides. For reactor safety calculations it is desirable to employ a single temporal decay power function for the whole core inasmuch as many variations of accident parameters are required. This is the usual approach in large system thermal-hydraulics codes. Such a single representative or generic curve for a specified total operating power history can be acceptable but at the expense of some increase in the uncertainty. In this paper, the author present a method of evaluating the additional uncertainty in the decay power associated with use of a generic curve

  3. Compulsory licensing in Canada and Thailand: comparing regimes to ensure legitimate use of the WTO rules.

    Science.gov (United States)

    Lybecker, Kristina M; Fowler, Elisabeth

    2009-01-01

    This paper examines two recent examples of compulsory licensing legislation: one globally embraced regime and one internationally controversial regime operating under the same WTO rules. In particular, we consider Canadian legislation and the use of compulsory licensing for HIV/AIDS drugs destined for a developing country. This is then contrasted with the conditions under which Thai authorities are pursuing compulsory licenses, the outcomes of their compulsory licenses, as well as the likely impact of the Thai policy. Finally, we construct a rubric to evaluate characteristics of a successful regime. This is used to analyze the Canadian and Thai regimes and frame the expected implications of each national policy. It is hoped that the assessment will guide changes to compulsory licensing design to ensure that legitimate regimes are embraced while illegitimate ones are disallowed.

  4. Licensing Teachers: Lessons from Other Professions.

    Science.gov (United States)

    Haberman, Martin

    1986-01-01

    The licensing of teachers should be modeled against professions similar to teaching rather than professions like medicine and architecture that are vastly different. Applying similar licensing practices can raise the status of teaching. Ignoring these licensing practices will prevent teachers from functioning as professionals. (MD)

  5. Safety and licensing issues for Indian PHWRs

    International Nuclear Information System (INIS)

    Srinivasan, G.R.; Das, M.

    1997-01-01

    India has achieved competency in design, construction, commissioning and operation of Pressurized Heavy Water Reactor based Nuclear Power Plants and has completed more than 120 reactor operating years with an extremely satisfactory safety record. In this paper, the safety management in NPCIL and operational safety aspects are discussed, licensing and regulatory approach is described and some of the main safety issues for Indian PHWRs are brought out. (author)

  6. Automated Design of Application-Specific Smart Camera Architectures

    NARCIS (Netherlands)

    Caarls, W.

    2008-01-01

    Parallel heterogeneous multiprocessor systems are often shunned in embedded system design, not only because of their design complexity but because of the programming burden. Programs for such systems are architecture-dependent: the application developer needs architecture-specific knowledge to

  7. Licensing of nuclear and radioactive installations in Peru

    International Nuclear Information System (INIS)

    Medina Gironzini, E.

    1987-01-01

    In Peru, the Regulation for Ionizing Radiation Sources is applied, which establishes the norms and procedures to follow in the nuclear and radioactive installations of the country in order to assure their correct operation as concerns to the nuclear safety and radiological protection, allowing the emission of the respective licenses. As for the nuclear facilities, this authorization includes the Previous License, the Construction License and the Operation License (provisional and definitive) and for radioactive facilities and equipment generating ionizing radiations: the Construction License and the Operation License. The personnel also require a license that can be an operator license (as for nuclear reactors) or a supervisor license (for nuclear and radioactive facilities). In spite of the above mentioned regulation and its long enforcement period, less than 10% of radioactive facilities in this country are licensed, due to different problems which will be solved in the medium term. (Author)

  8. Whom to Choose as License Partner?

    DEFF Research Database (Denmark)

    Laursen, Keld; Reichstein, Toke; Trombini, Giulia

    2013-01-01

    between technology and market forces: if partners are market distant, the likelihood of technology license contractual partnership decreases with partners’ technological distance. Using data on the formation of license partnerships in the global biopharmaceutical industry over the period 1994......This paper investigates the matching of firms on the market for technology. The paper forwards two dimensions along which license formation occurs: technology and product-market. Both sides of the market search for a partner representing potential for high technology synergies to maximize licensing...

  9. 7 CFR 6.32 - Globalization of licenses.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 1 2010-01-01 2010-01-01 false Globalization of licenses. 6.32 Section 6.32 Agriculture Office of the Secretary of Agriculture IMPORT QUOTAS AND FEES Dairy Tariff-Rate Import Quota Licensing § 6.32 Globalization of licenses. If the Licensing Authority determines that entries of an article...

  10. 42 CFR 431.710 - Provisional licenses.

    Science.gov (United States)

    2010-10-01

    ... Licensing Nursing Home Administrators § 431.710 Provisional licenses. To fill a position of nursing home... 42 Public Health 4 2010-10-01 2010-10-01 false Provisional licenses. 431.710 Section 431.710 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES...

  11. 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.

  12. 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

  13. Safety features and licensing of CNNC-ACP100

    Energy Technology Data Exchange (ETDEWEB)

    Zhong, F., E-mail: Zhongfj2000@163.com [Nuclear Power Inst. of China, National Key Lab. of Science and Technology on Reactor System Design Technology (China)

    2014-07-01

    ACP100 is an innovatory modular pressurized water reactor, the engineering safety systems fully adopt passive safety design technology. Its inherent safety and passive features/systems are verified via testing facilities and are highlighted at certain levels of defence in depth. The licensing of ACP 100 is within current LWR framework and meets up-to-date codes and requirements in nuclear safety. (author)

  14. Nuclear facilities licensing

    International Nuclear Information System (INIS)

    Carvalho, A.J.M. de.

    1978-01-01

    The need for the adoption of a legal and normative system, defining objectives, pescriptions and the process of nuclear licensing and building of nuclear power plants in Brazil is enphasized. General rules for the development of this system are presented. The Brazilian rules on the matter are discussed. A general view of the German legal system for nuclear power plant licensing and the IAEA recommendations on the subject are finally presented. (A.L.S.L.) [pt

  15. 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.)

  16. To License or Not to License: An Examination of State Statutes Regarding Private Investigators and Digital Examiners

    Directory of Open Access Journals (Sweden)

    Thomas Lonardo

    2008-09-01

    Full Text Available In this paper the authors examine statutes that regulate, license, and enforce investigative functions in each US state. After identification and review of Private Investigator licensing requirements, the authors find that very few state statutes explicitly differentiate between Private Investigators and Digital Examiners. After contacting all state agencies the authors present a distinct grouping organizing state approaches to professional Digital Examiner licensing. The authors conclude that states must differentiate between Private Investigator and Digital Examiner licensing requirements and oversight.

  17. International standardization of nuclear reactor designs - the way forward

    International Nuclear Information System (INIS)

    Raetzke, Christian

    2010-01-01

    The concept of 'International Standardization of Nuclear Reactor Designs' means that vendors could build their designs in every country without having to adapt it specifically to national safety requirements. Such standardization would have two main effects. It would greatly facilitate nuclear new build worldwide by giving greater efficiency and certainty to the national licensing procedures; by taking into account the fact that vendors, and nowadays also utilities, are active across borders; by helping developing countries to establish their nuclear new build programmes; and by reducing the strain on human resources on both the regulators' and the industry's side. The second valuable effect of standardization would be to further enhance safety by improving the exchange of construction and operating experience among a number of reactors belonging to fleets of the same design. The World Nuclear Association's CORDEL (Cooperation in Reactor Design Evaluation and Licensing) Group has developed a concept for implementation of international standardization of reactor designs. It has defined a number of steps to be taken by industry. At the same time, possibilities offered by national and international regulatory mechanisms would have to be fully made use of, and some changes in regulatory frameworks might be necessary. Some steps especially towards greater cooperation of regulators have already been taken; however, much still remains to be done. The concept of deploying standardized reactor designs across a number of countries supposes an alignment and, if possible, harmonization of national safety standards; a streamlining of national licensing procedures, making them more efficient and predictable; and the willingness of national regulators to take into account licensing done in other countries. In the end, this should lead to a mutual acceptance of design approvals or, in a more distant future, even to a multinational design approval process. All in all, the concept

  18. Specification styles in distributed systems design and verification

    NARCIS (Netherlands)

    Vissers, C.A.; Scollo, Giuseppe; van Sinderen, Marten J.; Brinksma, Hendrik

    1991-01-01

    Substantial experience with the use of formal specification languages in the design of distributed systems has shown that finding appropriate structures for formal specifications presents a serious, and often underestimated problem. Its solutions are of great importance for ensuring the quality of

  19. 77 FR 71404 - Notice of Intent to License Government-Owned Inventions; Intent to License on a Partially...

    Science.gov (United States)

    2012-11-30

    ... DEPARTMENT OF DEFENSE Department of the Army Notice of Intent to License Government-Owned Inventions; Intent to License on a Partially-Exclusive Basis AGENCY: Department of the Army, DoD. ACTION... by the Secretary of the Army. The US Army Edgewood Chemical Biological Center intends to license...

  20. 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

  1. Licensing of ''grandfather's'' facilities: Ukrainian experience

    International Nuclear Information System (INIS)

    Mikolaitchouk, H.; Bogdan, L.; Steinberg, N.

    1995-01-01

    In the former USSR, unlike most countries, radioactive waste management activities including waste disposal needed no license. But after the USSR breakdown the Ukrainian Parliament -- Verkhovna Rada -- invoked the revised Law on Business activities. According to Article 4 of the Law, in order to treat or to dispose radioactive waste every enterprise has to get a special permission or license. In compliance with the Law, the Cabinet of Ministers by its Ordinance of January 13, 1993, authorized the Ukrainian State Committee for Nuclear and Radiation Safety (UkrSCNRS) to issue special permissions or licenses for waste treatment and disposal. And that requirement was valid not only for future activities but also for existing facilities in operation. Taking into account the undergoing legislative process, SCNRS began to develop its licensing process without waiting for the special nuclear laws to be passed. On the basis of the legislation already in effect, first of all the Law on Enterprises (full responsibility of enterprises for their activities) and Law on Business activities (requirement to have a license for special types of activities), the newly formed national regulatory body had to identify all the enterprises that needed to be licensed, to establish relevant procedures, to develop related regulatory documents, to implement these procedures and documents at operating enterprises, and for each case to make a decision concerning feasibility of issuing a license, period of validity and license conditions

  2. 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)

  3. 10 CFR 781.51 - Nonexclusive licenses.

    Science.gov (United States)

    2010-01-01

    ... corporate structure of which licensee is a part, if any. However, the license shall not be assignable or... license upon the policies of the United States Government; (3) The effect of the license upon domestic and... extent of U.S. Government contribution to the development of the invention; (iv) The degree of...

  4. 7 CFR 6.33 - License fee.

    Science.gov (United States)

    2010-01-01

    ... certified mail, return receipt requested, advising the licensee that if payment is not mailed in accordance.... Where the license at issue is a historical license, this will result, pursuant to § 6.23(b), in the person's loss of historical eligibility for such license. (d) Licensees may elect not to accept certain...

  5. Chinese License Plates Recognition Method Based on A Robust and Efficient Feature Extraction and BPNN Algorithm

    Science.gov (United States)

    Zhang, Ming; Xie, Fei; Zhao, Jing; Sun, Rui; Zhang, Lei; Zhang, Yue

    2018-04-01

    The prosperity of license plate recognition technology has made great contribution to the development of Intelligent Transport System (ITS). In this paper, a robust and efficient license plate recognition method is proposed which is based on a combined feature extraction model and BPNN (Back Propagation Neural Network) algorithm. Firstly, the candidate region of the license plate detection and segmentation method is developed. Secondly, a new feature extraction model is designed considering three sets of features combination. Thirdly, the license plates classification and recognition method using the combined feature model and BPNN algorithm is presented. Finally, the experimental results indicate that the license plate segmentation and recognition both can be achieved effectively by the proposed algorithm. Compared with three traditional methods, the recognition accuracy of the proposed method has increased to 95.7% and the consuming time has decreased to 51.4ms.

  6. 25 CFR 11.601 - Marriage licenses.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Marriage licenses. 11.601 Section 11.601 Indians BUREAU... ORDER CODE Domestic Relations § 11.601 Marriage licenses. A marriage license shall be issued by the clerk of the court in the absence of any showing that the proposed marriage would be invalid under any...

  7. Specification, Design, and Analysis of Advanced HUMS Architectures

    Science.gov (United States)

    Mukkamala, Ravi

    2004-01-01

    During the two-year project period, we have worked on several aspects of domain-specific architectures for HUMS. In particular, we looked at using scenario-based approach for the design and designed a language for describing such architectures. The language is now being used in all aspects of our HUMS design. In particular, we have made contributions in the following areas. 1) We have employed scenarios in the development of HUMS in three main areas. They are: (a) To improve reusability by using scenarios as a library indexing tool and as a domain analysis tool; (b) To improve maintainability by recording design rationales from two perspectives - problem domain and solution domain; (c) To evaluate the software architecture. 2) We have defined a new architectural language called HADL or HUMS Architectural Definition Language. It is a customized version of xArch/xADL. It is based on XML and, hence, is easily portable from domain to domain, application to application, and machine to machine. Specifications written in HADL can be easily read and parsed using the currently available XML parsers. Thus, there is no need to develop a plethora of software to support HADL. 3) We have developed an automated design process that involves two main techniques: (a) Selection of solutions from a large space of designs; (b) Synthesis of designs. However, the automation process is not an absolute Artificial Intelligence (AI) approach though it uses a knowledge-based system that epitomizes a specific HUMS domain. The process uses a database of solutions as an aid to solve the problems rather than creating a new design in the literal sense. Since searching is adopted as the main technique, the challenges involved are: (a) To minimize the effort in searching the database where a very large number of possibilities exist; (b) To develop representations that could conveniently allow us to depict design knowledge evolved over many years; (c) To capture the required information that aid the

  8. Generic environmental impact statement for license renewal of nuclear plants. Final report

    International Nuclear Information System (INIS)

    1996-05-01

    This GEIS examines the possible environmental impacts that could occur as a result of renewing the licenses of individual nuclear power plants under 10 CFR 54. To the extent possible, it establishes the bounds and significance of these potential impacts. The analysis encompasses all operating light-water reactors. For each type of environmental impact, the GEIS attempts to establish generic findings covering as many plants as possible. While plant and site-specific information is used in developing the generic findings, the NRC does not intend for the GEIS to be a compilation of individual plant environmental impacts statements. This document has three principal objectives: (1) to provide an understanding of the types and severity of environmental impacts that may occur as a result of license renewal, (2) to identify and assess those impacts that are expected to be generic to license renewal, and (3) to support rulemaking (10 CFR 51) to define the number and scope of issues that need to be addressed by the applicants in plant-by-plant license renewal proceedings

  9. The optimal licensing contract in a differentiated Stackelberg model.

    Science.gov (United States)

    Hong, Xianpei; Yang, Lijun; Zhang, Huaige; Zhao, Dan

    2014-01-01

    This paper extends the work of Wang (2002) by considering a differentiated Stackelberg model, when the leader firm is an inside innovator and licenses its new technology by three options, that is, fixed-fee licensing, royalty licensing, and two-part tariff licensing. The main contributions and conclusions of this paper are threefold. First of all, this paper derives a very different result from Wang (2002). We show that, with a nondrastic innovation, royalty licensing is always better than fixed-fee licensing for the innovator; with a drastic innovation, royalty licensing is superior to fixed-fee licensing for small values of substitution coefficient d; however when d becomes closer to 1, neither fee nor royalty licensing will occur. Secondly, this paper shows that the innovator is always better off in case of two-part tariff licensing than fixed-fee licensing no matter what the innovation size is. Thirdly, the innovator always prefers to license its nondrastic innovation by means of a two-part tariff instead of licensing by means of a royalty; however, with a drastic innovation, the optimal licensing strategy can be either a two-part tariff or a royalty, depending upon the differentiation of the goods.

  10. AVC/H.264 patent portfolio license

    Science.gov (United States)

    Skandalis, Dean A.

    2006-08-01

    MPEG LA, LLC offers a joint patent license for the AVC (a/k/a H.264) Standard (ISO/IEC IS 14496-10:2004). Like MPEG LA's other licenses, the AVC Patent Portfolio License is offered for the convenience of the marketplace as an alternative enabling users to access essential intellectual property owned by many patent holders under a single license rather than negotiating licenses with each of them individually. The AVC Patent Portfolio License includes essential patents owned by DAEWOO Electronics Corporation; Electronics and Telecommunications Research Institute (ETRI); France Telecom, societe anonyme; Fujitsu Limited; Hitachi, Ltd.; Koninklijke Philips Electronics N.V.; LG Electronics Inc.; Matsushita Electric Industrial Co., Ltd.; Microsoft Corporation; Mitsubishi Electric Corporation; Robert Bosch GmbH; Samsung Electronics Co., Ltd.; Sedna Patent Services, LLC; Sharp Kabushiki Kaisha; Siemens AG; Sony Corporation; The Trustees of Columbia University in the City of New York; Toshiba Corporation; UB Video Inc.; and Victor Company of Japan, Limited. Another is expected also to join as of August 1, 2006. MPEG LA's objective is to provide worldwide access to as much AVC essential intellectual property as possible for the benefit of AVC users. Therefore, any party that believes it has essential patents is welcome to submit them for evaluation of their essentiality and inclusion in the License if found essential.

  11. The Optimal Licensing Contract in a Differentiated Stackelberg Model

    Directory of Open Access Journals (Sweden)

    Xianpei Hong

    2014-01-01

    Full Text Available This paper extends the work of Wang (2002 by considering a differentiated Stackelberg model, when the leader firm is an inside innovator and licenses its new technology by three options, that is, fixed-fee licensing, royalty licensing, and two-part tariff licensing. The main contributions and conclusions of this paper are threefold. First of all, this paper derives a very different result from Wang (2002. We show that, with a nondrastic innovation, royalty licensing is always better than fixed-fee licensing for the innovator; with a drastic innovation, royalty licensing is superior to fixed-fee licensing for small values of substitution coefficient d; however when d becomes closer to 1, neither fee nor royalty licensing will occur. Secondly, this paper shows that the innovator is always better off in case of two-part tariff licensing than fixed-fee licensing no matter what the innovation size is. Thirdly, the innovator always prefers to license its nondrastic innovation by means of a two-part tariff instead of licensing by means of a royalty; however, with a drastic innovation, the optimal licensing strategy can be either a two-part tariff or a royalty, depending upon the differentiation of the goods.

  12. Nuclear licensing in Slovenia

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  13. Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

    International Nuclear Information System (INIS)

    Seidensticker, R.W.

    1987-01-01

    The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as hospitals, emergency facilities, buildings with very high-cost equipment (e.g., computers) and as a strategy to reduce loss of life and expensive equipment in earthquakes. Such a design approach is in complete contrast to the conventional seismic design strategy in which the structure and components are provided with sufficient strength and ductility to resist the earthquake forces and to prevent structural collapses or failure. The use of seismic isolation for nuclear plants can, therefore, be expected to be a significant licensing issue. For isolation, the licensing process must shift away in large measure from the superstructure and concentrate on the behavior of the seismic isolation system. This paper is not intended to promote the advantages of seismic isolation system, but to explore in some detail those technical issues which must be satisfactorily addressed to achieve full licensability of the use of seismic isolation as a viable, attractive and economical alternative to current traditional design approaches. Special problems and topics associated with testing and codes and standards development are addressed. A positive program for approach or strategy to secure licensing is presented

  14. Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

    Energy Technology Data Exchange (ETDEWEB)

    Seidensticker, R.W.

    1987-01-01

    The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as hospitals, emergency facilities, buildings with very high-cost equipment (e.g., computers) and as a strategy to reduce loss of life and expensive equipment in earthquakes. Such a design approach is in complete contrast to the conventional seismic design strategy in which the structure and components are provided with sufficient strength and ductility to resist the earthquake forces and to prevent structural collapses or failure. The use of seismic isolation for nuclear plants can, therefore, be expected to be a significant licensing issue. For isolation, the licensing process must shift away in large measure from the superstructure and concentrate on the behavior of the seismic isolation system. This paper is not intended to promote the advantages of seismic isolation system, but to explore in some detail those technical issues which must be satisfactorily addressed to achieve full licensability of the use of seismic isolation as a viable, attractive and economical alternative to current traditional design approaches. Special problems and topics associated with testing and codes and standards development are addressed. A positive program for approach or strategy to secure licensing is presented.

  15. IRS/TUEV activities during the licensing procedure. Safety assessment and preexamination

    International Nuclear Information System (INIS)

    Fendler, H.

    1976-01-01

    Short summary about the IRS/TUEV activities in the licensing procedure for a nuclear power plant: work for assessments, for pre-examination and approval specifications and drawings and for the quality control, time and the manpower necessary for this work. (orig./HP) [de

  16. 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)

  17. The licensing of nuclear plants as an example of conflicts of authority in parallel licensing procedures

    International Nuclear Information System (INIS)

    Henseler, P.

    1982-01-01

    Although the results obtained cannot be translated into installation licences related to the clean air act or to building codes without reservations, they can be generalized as follows: If several authorities have to assess one and the same project in independent procedures, they do not only have to use the metric used for subject-specific licensing prerequisites, but also the one used for the common weal. Then the spheres of responsibility require division. Oriented towards the purpose of the relevant laws, it has to be settled first for the sake of which public interest the authorities involved substantiate of a licensing reservation at all. All the decisions which fall within the sphere of responsibility of a certain authority are reserved and may not be prejudged by other authorities involved by issuing acts of regulation with externally binding effects. Insofar as similar or related public interests are to be considered in several licencing procedures (to be conducted) and insofar as there is no possibility of assigning the safeguarding of these interests to a special field of activity of one of the authorities involved, diverging results have to be accepted. (orig./HP) [de

  18. 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

  19. 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

  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. Research and development associated with licensing of MHTGR [Modular High Temperature Gas-Cooled Reactor

    International Nuclear Information System (INIS)

    Jones, H.

    1990-01-01

    The Modular High Temperature Gas-Cooled Reactor (MHTGR) currently under development by the US Department of Energy (US-DOE) for commercial applications has top-level goals of producing safe, economical power for the US utility industry. The utility industry has been represented in formulating design and licensing requirements through both a ''Utility User Requirements Document'' and by participating in the DOE system engineering process known as the ''Integrated Approach.'' The result of this collaboration has been to set stringent goals for both the safety and operational reliability of the MHTGR. To achieve these goals, the designer must have access to a more comprehensive data base of properties in several fields of technology than is currently available. A technology development program has been planned to provide this data to the designer in time to support both his design activities and the submittal of formal licensing application documents. The US-DOE has chosen the Oak Ridge National Laboratory (ORNL) to take the lead in planning and executing these technology programs. When completed these will augment the designer's current data base and provide the necessary depth to meet the stringent goals which have been set for the MHTGR. It is worth noting that the goals of safety and operational reliability are complementary, and the data required from the technology development program will be similar. Therefore, the program to support the licensing of the MHTGR is not separate from that required for design, but is a subset of that which meets all the requirements that result from implementing the US-DOE's integrated approach. 38 figs

  2. M5TM alloy high burnup behavior and worldwide licensing

    International Nuclear Information System (INIS)

    Mardon, J.P.; Hoffmann, P.B.; Garner, G.L.

    2005-01-01

    The in-reactor behavior of advanced PWR Zirconium alloys at burnups equal to or below licensing limits has been widely reported. Specifically, the advanced alloy M5 has demonstrated impressive improvements over Zircaloy-4 for fuel rod cladding and fuel assembly structural components. To demonstrate superiority of the alloy at burnups beyond current licensing limits, M5 has been operated in PWR at burnups exceeding 71 GWd/tU in the United States and 78 GWd/tU in Europe. Two extensive irradiation programs have been performed in the United States to demonstrate alloy M5 performance beyond current licensing limits. Four M5 TM fuel rods were exposed to four 24-month cycles in a 15x15 reactor beginning in 1995. Additionally, one 17x17 lead assembly containing M5 fuel rods and guide tubes was operated for four 18-month cycles beginning from 1997. Post-irradiation examinations (PIE) performed after all four cycles in the 15x15 demonstration program revealed excellent performance in the licensed burnup and in the high burnup stages of the experience. Examination of the 4th cycle 17x17 assembly will be accomplished in two stages the first of which is scheduled for June 2005. Moreover, several irradiation campaigns have been performed in Europe in order to confirm the excellent M5 in-pile behavior in demanding PWRs irradiation conditions with regard to void fraction, heat flux, lithium content and temperature. Results from the high burnup fuel examinations verify that the excellent performance achieved up to 62 GWd/tU was continued into higher burnup. The results of high burnup PIE campaigns for European and American PWR's are presented in this paper. Measured performance indicators include fuel assembly dimensional stability parameters (assembly length, fuel rod length, assembly bow, fuel rod bow, fuel rod radial creep and spacer grid width), oxidation measurements (fuel rod and guide tube) and hydrogen pick-up data (fuel rod). In the framework of PCI studies, power ramp

  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. Implementation procedures for design certification

    International Nuclear Information System (INIS)

    Ritterbusch, S. E.; Brinkman, C. B.; Crump, M. W.

    1995-01-01

    The desire for safer plants arose primarily as the result of the Three Mile Island accident and the realization that plant safety could be impacted by complex plant systems interactions that are not easily identified through the traditional 'system-by-system' design process. Hence, it became apparent that the ALWR designs would have to be addressed through plant-wide Probabilistic Safety Assessments (PSAs) that addressed both accident-prevention and accident-mitigation design features. Prior to Design Certification the 'two-step' licensing process in the United States was not efficient. Utilities had to commit large amounts of capital to plant construction without confidence that an operating license would be issued when construction permit was issued often required design changes that resulted in significant construction delays. The 55 utilities operating nuclear plants in the U. S. each had their own design and operating preferences, resulting in many customized plants with a minimum of economic benefit from standardization. This was addressed by the U. S. Nuclear Regulatory Commission (NRC) in a new regulation (Title 10 of the Code of Federal Regulations, Part 52 or '10 CFR 52') which provides certification of a design that can later be referenced by an applicant for a Combined Operating License (COL). Identifying an ALWR solution for previously unanalyzed severe accident scenarios appeared difficult, at best, since severe accident research had to be performed and since there was no regulatory precedent. This meant that complex technical issues and licensing review policies had to be developed without the benefit of licensing standards or experience. As a result, a system of iterative interactions between the regulator and the industry was established, wherein a design or safety requirement would be proposed, then discussed along with development of the corresponding design feature, and finally revised and documented via NRC 'guidance'

  5. Current status of LTO licensing programme for Bohunice nuclear power plant

    International Nuclear Information System (INIS)

    Borak, J.; Kupca, L.

    2012-01-01

    The objective of long term operation (LTO) licensing programme for Bohunice nuclear power plant is to demonstrate that the relevant structures and components shall perform their functions throughout the entire LTO period during which they shall meet all the relevant safety requirements. All the activities-which should result in utility's request to obtain the licence for LTO-must be performed in line with the relevant legal basis. As of May 2012, the anticipated duration of currently running programme is thirteen months. All relevant documentation, required by the established legal basis, shall be submitted to the licensing authority one year before the Unit 3 design life expiry. (author)

  6. Transit safety retrofit package development : architecture and design specifications.

    Science.gov (United States)

    2014-05-01

    The Architecture and Design Specifications capture the TRP system architecture and design that fulfills the technical : objectives stated in the TRP requirements document. : The document begins with an architectural overview that identifies and descr...

  7. Changing mobility patterns and road mortality among pre-license teens in a late licensing country : an epidemiological study.

    NARCIS (Netherlands)

    Twisk, D.A.M. Bos, N.M. Shope, J.T. & Kok, G.

    2013-01-01

    Whereas the safety of teens in early licensing countries has been extensively studied, little is known about the safety of pre-license teens in late licensing countries, where these teens also may be at risk. This risk exists because of the combination of a) increasing use of travel modes with a

  8. 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...

  9. 78 FR 5840 - Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115

    Science.gov (United States)

    2013-01-28

    ... University of Illinois Advanced TRIGA Reactor, License No. R-115 The U.S. Nuclear Regulatory Commission (NRC) is noticing the termination of Facility Operating License No. R-115, for the University of Illinois... Operating License No. R-115 is terminated. The above referenced documents may be examined, and/or copied for...

  10. Research overview : design specifications for hybrid vehicles

    NARCIS (Netherlands)

    Hofman, T.; Druten, van R.M.

    2004-01-01

    In this paper a method is proposed for determination of the design specifications regarding the energy exchange systems for different chargesustaining hybrid vehicles of different vehicle classes. Hybrid drivetrains for vehicles combine multiple power sources in order to increase the driving

  11. Lessons Learned from Design and Construction of New US Nuclear Facility

    International Nuclear Information System (INIS)

    Seamans, S. E.; Horvath, D. A.

    2012-01-01

    For reasons related to licensing uncertainty, economic slowdown, and questionable financial backing, no new nuclear facility projects have been undertaken in the United States since the Three Mile Island Incident in 1979; however, a need for such facilities (both nuclear power plants and nuclear fuel facilities) continues and various incentives leading to the start of a nuclear renaissance have occurred. One incentive is a complete overhaul by the US Nuclear Regulatory Commission of the earlier two step licensing process under 10 CFR 50. The earlier approach required first a construction permit and then an operating license, whereas the new approach allows a more streamlined (one step) combined license (COL) approach utilizing Standard Design Certifications via the regulatory framework created by 10 CFR 52. Other incentives include US Government backed loan guarantees as well as private company contributions. One aspect to the new process has been consideration and implementation of many new topic-specific regulations and industry standards which have continued to evolve during the past 30 years in spite of the lack of new plant design and construction activity. Therefore, an Owner attempting a new nuclear facility project under 10 CFR 52 needs to address a myriad of new requirements previously unconsidered. Several new projects including both power plants and fuel facilities have begun the new licensing process with its many new requirements to consider, but a uranium enrichment facility has run the gamut first. This paper will summarize many of the lessons learned from designing, constructing and testing this first new nuclear facility to be built in the US in over 30 years.(author).

  12. A meta-analytic review of moral licensing.

    Science.gov (United States)

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

    2015-04-01

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

  13. Licensing assessment of the CANDU pressurized heavy water reactor. Volume I. Preliminary safety information document

    International Nuclear Information System (INIS)

    1977-06-01

    The PHWR design contains certain features that will require significant modifications to comply with USNRC siting and safety requirements. The most significant of these features are the reactor vessel; control systems; quality assurance program requirements; seismic design of structures, systems and components; and providing an inservice inspection program capability. None of these areas appear insolvable with current state-of-the-art engineering or with upgrading of the quality assurance program for components constructed outside of the USA. In order to be licensed in the U. S., the entire reactor assembly would have to be redesigned to comply with ASME Boiler and Pressure Vessel Code, Section III, Division 1 and Division 2. A summary matrix at the end of this volume identifies compliance of the systems and structures of the PHWR plant with the USNRC General Design Criteria. The matrix further identifies the estimated incremental cost to a 600 MWe PHWR that would be required to license the plant in the U. S. Further, the matrix identifies whether or not the incremental licensing cost is size dependent and the relative percentage of the base direct cost of a Canadian sited plant

  14. Nuclear safety requirements for operation licensing of Egyptian research reactors

    International Nuclear Information System (INIS)

    Ahmed, E.E.M.; Rahman, F.A.

    2000-01-01

    From the view of responsibility for health and nuclear safety, this work creates a framework for the application of nuclear regulatory rules to ensure safe operation for the sake of obtaining or maintaining operation licensing for nuclear research reactors. It has been performed according to the recommendations of the IAEA for research reactor safety regulations which clearly states that the scope of the application should include all research reactors being designed, constructed, commissioned, operated, modified or decommissioned. From that concept, the present work establishes a model structure and a computer logic program for a regulatory licensing system (RLS code). It applies both the regulatory inspection and enforcement regulatory rules on the different licensing process stages. The present established RLS code is then applied to the Egyptian Research Reactors, namely; the first ET-RR-1, which was constructed and still operating since 1961, and the second MPR research reactor (ET-RR-2) which is now in the preliminary operation stage. The results showed that for the ET-RR-1 reactor, all operational activities, including maintenance, in-service inspection, renewal, modification and experiments should meet the appropriate regulatory compliance action program. Also, the results showed that for the new MPR research reactor (ET-RR-2), all commissioning and operational stages should also meet the regulatory inspection and enforcement action program of the operational licensing safety requirements. (author)

  15. Algeria schedules onshore licensing round

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This paper reports that Algeria's Sonatrach will conduct its first international onshore exploration licensing round in a move designed to triple drilling activity in the country. A second round will follow next April. Sonatrach plans to drill 200 wells during 1991-95, which will require the current level of 37/year to be almost trebled toward the end of the period. To this end foreign operators are being courted in an open exploration bidding round. Deadline for bid submittal in Nov. 30. Companies may enter singly or in groups to form partnerships with Sonatrach. Foreign licensees will be able to take a maximum 49% of production under Algerian law

  16. Specification and Design of Electrical Flight System Architectures with SysML

    Science.gov (United States)

    McKelvin, Mark L., Jr.; Jimenez, Alejandro

    2012-01-01

    Modern space flight systems are required to perform more complex functions than previous generations to support space missions. This demand is driving the trend to deploy more electronics to realize system functionality. The traditional approach for the specification, design, and deployment of electrical system architectures in space flight systems includes the use of informal definitions and descriptions that are often embedded within loosely coupled but highly interdependent design documents. Traditional methods become inefficient to cope with increasing system complexity, evolving requirements, and the ability to meet project budget and time constraints. Thus, there is a need for more rigorous methods to capture the relevant information about the electrical system architecture as the design evolves. In this work, we propose a model-centric approach to support the specification and design of electrical flight system architectures using the System Modeling Language (SysML). In our approach, we develop a domain specific language for specifying electrical system architectures, and we propose a design flow for the specification and design of electrical interfaces. Our approach is applied to a practical flight system.

  17. An introduction to intellectual property licensing for technology companies

    Science.gov (United States)

    Meier, Lawrence H.

    2001-05-01

    Intellectual property licensing is an important issue facing all technology companies. Before entering into license agreements a number of issues need to be addressed, including invention ownership, obtaining and identifying licensable subject matter, and developing a licensing strategy. There are a number of important provisions that are included in most intellectual property license agreements. These provisions include definitions, the license grant, consideration, audit rights confidentiality, warranties, indemnification, and limitation of liability. Special licensing considerations exist relative to each type of intellectual property, and when the other party is a foreign company or a university.

  18. 75 FR 55799 - Government-Owned Inventions; Availability for Licensing

    Science.gov (United States)

    2010-09-14

    ... licensing. Licensing Contact: Patrick P. McCue, PhD, (301) 435-5560; [email protected] . Collaborative... Reference No. E-051-2010/0-US-01). Licensing Status: Available for licensing. Licensing Contact: Patrick P... for the brain tumors or brain cancers indentified as gliomas, glioblastomas, or astrocytomas. This...

  19. 77 FR 47393 - Ocean Transportation Intermediary License Revocations

    Science.gov (United States)

    2012-08-08

    ...: Voluntary surrender of license. License No.: 12454N. Name: Federation Exports-Imports Inc. Address: 747...: Natco International Transports USA, L.L.C. Address: 12415 SW 136th Avenue, Bay 4, Miami, FL 33186 Date...: Voluntary surrender of license. License No.: 022773F. Name: WLI (USA) Inc. Address: 175-01 Rockaway Blvd...

  20. More than a House of Cards: Developing a Firm Foundation for Streaming Media and Consumer-Licensed Content in the Library

    Directory of Open Access Journals (Sweden)

    William Cross

    2016-09-01

    Full Text Available This article will introduce traditional library practice for licensing multimedia content and discuss the way that consumer-licensing and streaming services disrupt that practice. Sections II and III describe the statutory copyright regime designed by Congress to facilitate the socially-valuable work done by libraries and the impact of the move from ownership to licensed content. Collecting multimedia materials has always presented special legal challenges for libraries, particularly as licensed content has replaced the traditional practice of purchasing and circulation based on the first sale doctrine. These issues have grown even more complex as streaming services like Netflix and Amazon and video game downloads through services like Steam have come to dominate the landscape. Section IV will describe the way that consumer-licensed materials, which not only remove the ownership that undergirds library practice, but also the ability to negotiate for library use, imperil the congressionally-designed balance. Section V will present a path forward for libraries to develop robust, cutting-edge collections that reflect a sophisticated understanding of the contractual and copyright issues at play.

  1. Multiframe Superresolution of Vehicle License Plates Based on Distribution Estimation Approach

    Directory of Open Access Journals (Sweden)

    Renchao Jin

    2016-01-01

    Full Text Available Low-resolution (LR license plate images or videos are often captured in the practical applications. In this paper, a distribution estimation based superresolution (SR algorithm is proposed to reconstruct the license plate image. Different from the previous work, here, the high-resolution (HR image is estimated via the obtained posterior probability distribution by using the variational Bayesian framework. To regularize the estimated HR image, a feature-specific prior model is proposed by considering the most significant characteristic of license plate images; that is, the target has high contrast with the background. In order to assure the success of the SR reconstruction, the models representing smoothness constraints on images are also used to regularize the estimated HR image with the proposed feature-specific prior model. We show by way of experiments, under challenging blur with size 7 × 7 and zero-mean Gaussian white noise with variances 0.2 and 0.5, respectively, that the proposed method could achieve the peak signal-to-noise ratio (PSNR of 22.69 dB and the structural similarity (SSIM of 0.9022 under the noise with variance 0.2 and the PSNR of 19.89 dB and the SSIM of 0.8582 even under the noise with variance 0.5, which are 1.84 dB and 0.04 improvements in comparison with other methods.

  2. 14 CFR 1245.108 - License to contractor.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false License to contractor. 1245.108 Section... INTELLECTUAL PROPERTY RIGHTS Patent Waiver Regulations § 1245.108 License to contractor. (a) Each contractor.... The license extends to the contractor's domestic subsidiaries and affiliates, if any, within the...

  3. License protection with a tamper-resistant token

    NARCIS (Netherlands)

    Chong, C.N.; Ren, Bin; Doumen, J.M.; Etalle, Sandro; Hartel, Pieter H.; Corin, R.J.; Lim, Chae Hoon; Yung, Moti

    Content protection mechanisms are intended to enforce the usage rights on the content. These usage rights are carried by a license. Sometimes, a license even carries the key that is used to unlock the protected content. Unfortunately, license protection is difficult, yet it is important for digital

  4. Optimization strategies for cask design and container loading in long term spent fuel storage

    International Nuclear Information System (INIS)

    2006-12-01

    As delays are incurred in implementing reprocessing and in planning for geologic repositories, storage of increasing quantities of spent fuel for extended durations is becoming a growing reality. Accordingly, effective management of spent fuel continues to be a priority topic. In response, the IAEA has organized a series of meetings to identify cask loading optimisation issues in preparation for a technical publication on Optimization Strategies for Cask/Container Loading in Long Term Spent Fuel Storage. This publication outlines the optimisation process for cask design, licensing and utilization, describing three principal groups of optimization activities in terms of relevant technical considerations such as criticality, shielding, structural design, operations, maintenance and retrievability. The optimization process for cask design, licensing, and utilization is outlined. The general objectives for the design of storage casks, including storage casks that are intended to be transportable, are summarized. The nature of optimization within the design process is described. The typical regulatory and licensing process is outlined, focusing on the roles of safety regulations, the regulator, and the designer/applicant in the optimization process. Based on the foregoing, a description of the three principal groups of optimization activities is provided. The subsequent chapters of this document then describe the specific optimization activities within these three activity groups, in each of the several design disciplines

  5. A materials engineering view of license renewal at the US Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Banic, M.

    1999-01-01

    This paper discusses the treatment of license renewal at the US Nuclear Regulatory Commission (NRC) with emphasis on the review process by the staff of the Materials and Chemical Engineering Branch (EMCB). The paper covers the rules governing license renewal, the applications received, the schedule, the approach, and the technical issues. The NRC has a tight schedule of 30-36 months to renew a license. To date, Baltimore Gas and Electric (BG and E) and Duke Power have applied for license renewal. Expecting more applicants, the staff has taken steps to address the public's concern that the effects of aging will be adequately managed and the industry's concern that the reviews will be timely, efficient, and uniform. These steps include identifying aging effects and making the results available in a report and computerized database, approving topical reports and aging management programs for generic use, and reviewing aging management programs according to specific criteria. Materials Engineering staff have a major role because many of the aging issues are materials related. (author)

  6. Personality Factors and Nuclear Power Plant Operators: Initial License Success

    Science.gov (United States)

    DeVita-Cochrane, Cynthia

    Commercial nuclear power utilities are under pressure to effectively recruit and retain licensed reactor operators in light of poor candidate training completion rates and recent candidate failures on the Nuclear Regulatory Commission (NRC) license exam. One candidate failure can cost a utility over $400,000, making the successful licensing of new operators a critical path to operational excellence. This study was designed to discover if the NEO-PI-3, a 5-factor measure of personality, could improve selection in nuclear utilities by identifying personality factors that predict license candidate success. Two large U.S. commercial nuclear power corporations provided potential participant contact information and candidate results on the 2014 NRC exam from their nuclear power units nation-wide. License candidates who participated (n = 75) completed the NEO-PI-3 personality test and results were compared to 3 outcomes on the NRC exam: written exam, simulated operating exam, and overall exam result. Significant correlations were found between several personality factors and both written and operating exam outcomes on the NRC exam. Further, a regression analysis indicated that personality factors, particularly Conscientiousness, predicted simulated operating exam scores. The results of this study may be used to support the use of the NEO-PI-3 to improve operator selection as an addition to the current selection protocol. Positive social change implications from this study include support for the use of a personality measure by utilities to improve their return-on-investment in candidates and by individual candidates to avoid career failures. The results of this study may also positively impact the public by supporting the safe and reliable operation of commercial nuclear power utilities in the United States.

  7. Report of the Task Force on bonding and perpetual care of nuclear licensed activities

    International Nuclear Information System (INIS)

    Snellings, D.D. Jr.

    1975-01-01

    The primary concern was to consider the bonding and perpetual care requirements of state-licensed shallow land burial sites used for the disposal of radioactive wastes. The specific charge of the task force was to examine in detail the requirements for establishing bonding and perpetual care programs for all types of licensed nuclear activities and to report the findings of the task force as guidance to assist states in program development. Goals and recommendations of the task force are discussed

  8. A Strategy for Material-specific e-Textile Interaction Design

    DEFF Research Database (Denmark)

    Gowrishankar, Ramyah; Bredies, Katharina; Ylirisku, Salu

    2017-01-01

    The interaction design of e-Textile products are often characterized by conventions adopted from electronic devices rather than developing interactions that can be specific to e-Textiles. We argue that textile materials feature a vast potential for the design of novel digital interactions....... Especially the shape-reformation capabilities of textiles may inform the design of expressive and aesthetically rewarding applications. In this chapter, we propose ways in which the textileness of e-Textiles can be better harnessed. We outline an e-Textile Interaction Design strategy that is based...... on defining the material-specificity of e-Textiles as its ability to deform in ways that match the expectations we have of textile materials. It embraces an open-ended exploration of textile-related interactions (for e.g. stretching, folding, turning-inside-out etc.) and their potential for electronic...

  9. 47 CFR 97.5 - Station license required.

    Science.gov (United States)

    2010-10-01

    .... (3) A military recreation station license grant. A military recreation station license grant may be... States military recreational premises where the station is situated. The person must not be a... the balance of the license term and the suspension is still in effect, suspended for the balance of...

  10. 24 CFR 3286.203 - Installation license required.

    Science.gov (United States)

    2010-04-01

    ... performance of the installation work in compliance with the requirements of this part. (3) A license is not required for individuals working as direct employees of a licensed installer or for the company that... and competent performance of all employees working under the licensed installer's supervision and for...

  11. 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

  12. A comparative analysis of the domestic and foreign licensing processes for power and non-power reactors

    International Nuclear Information System (INIS)

    Joe, J. C.; Youn, Y. K.; Kim, W. S.; Kim, H. J.

    2003-01-01

    The System-integrated Modular Advanced Reactor (SMART), a small to medium sized integral type Pressurized Water Reactor (PWR) has been developed in Korea. Now, SMART-P, a 1/5 scaled-down of the SMART, is being developed for the purpose of demonstrating the safety and performance of SMART design. The SMART-P is a first-of-a-kind reactor which is utilized for the research and development of a power reactor. Since the licensing process of such a reactor is not clearly specified in the current Atomic Energy Act, a comparative survey and analysis of domestic and foreign licensing processes for power and non-power reactors has been carried out to develop the rationale and technical basis for establishing the licensing process of such a reactor. The domestic and foreign licensing processes of power and non-power reactors have been surveyed and compared, including those of the U.S.A., Japan, France, U.K., Canada, and IAEA. The general trends in nuclear reactor classification, licensing procedures, regulatory technical requirements, and other licensing requirements and regulations have been investigated. The results of this study will be used as the rationale and technical basis for establishing the licensing process of reactors at development stage such as SMART-P

  13. 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

  14. NPP License Renewal and Aging Management: Revised Guidance

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  15. 76 FR 31307 - Notice of Intent To License Government-Owned Inventions; Intent To License Exclusively

    Science.gov (United States)

    2011-05-31

    ... DEPARTMENT OF DEFENSE Department of the Army Notice of Intent To License Government-Owned Inventions; Intent To License Exclusively AGENCY: Department of the Army, DoD. ACTION: Notice. SUMMARY: The... Army. The US Army Edgewood Chemical Biological Center and the US Army Research Laboratory intend to...

  16. 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

  17. 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.

  18. 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...

  19. 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

  20. Conceptual Design on the System Architecture of Intellectual Export Control System(IXCS)

    International Nuclear Information System (INIS)

    Jeong, Seung Ho; Yang, Seung Hyo; Tae, Jae Woong; Shin, Dong Hoon

    2013-01-01

    The commodity classification is for identifying strategic commodity, and the export license is for verifying that exports have met the requirement by the national legislation following international obligations (i. e. NSG guidelines) Since 2008, the 'Nuclear Export Promotion Service (NEPS)' System has been used as a total IT system providing various functions for exporters and reviewers. However, reviewers who make the decisions for commodity classification and export license, may have difficulties caused by ambiguity of criteria. For example, it is not sure whether a CVCS (Chemical Volume Control System) of a certain nuclear reactor plant belongs to strategic commodity or not. The NEPS is a useful system helping users save their time, but it cannot provide solutions reducing ambiguity of each classification or license case. To solve these problems and provide more efficient ways to their decisions, various intelligent IT solutions are searched and studied. A functional architecture of IXCS is defined and designed conceptually. This conceptual design will be utilized to make database specification and to find the optimized artificial algorithm for review processes

  1. 13th Forum for Specification and Design Languages (FDL) conference

    CERN Document Server

    Morawiec, Adam; System Specification and Design Languages : Selected Contributions from FDL 2010

    2012-01-01

    This book brings together a selection of the best papers from the thirteenth edition of the Forum on specification and Design Languages Conference (FDL), which was held in Southampton, UK in September 2010.  FDL is a well established international forum devoted to dissemination of research results, practical experiences and new ideas in the application of specification, design and verification languages to the design, modelling and verification of integrated circuits, complex hardware/software embedded systems, and mixed-technology systems. Covers design verification, automatic synthesis and mechanized debug aids; Includes language-based modeling and design techniques for embedded systems; Covers design, modeling and verification of mixed physical domain and mixed signal systems that include significant analog parts in electrical and non-electrical domains; Includes formal and semi-formal system level design methods for complex embedded systems based on the Unified Modelling Language (UML) and Model Driven E...

  2. License Auctions with Royalty Contracts for (Winners and) Losers

    OpenAIRE

    Wolfstetter, Elmar; Giebe, Thomas

    2007-01-01

    This paper revisits the licensing of a non–drastic process innovation by an outside innovator to a Cournot oligopoly. We propose a new mechanism that combines a restrictive license auction with royalty licensing. This mechanism is more profitable than standard license auctions, auctioning royalty contracts, fixed–fee licensing, pure royalty licensing, and two-part tariffs. The key features are that royalty contracts are auctioned and that losers of the auction are granted the option to si...

  3. 76 FR 17840 - Notice of Intent To License Government-Owned Inventions; Intent To License Exclusively

    Science.gov (United States)

    2011-03-31

    ... DEPARTMENT OF DEFENSE Department of the Army Notice of Intent To License Government-Owned Inventions; Intent To License Exclusively AGENCY: Department of the Army, DoD. ACTION: Notice. SUMMARY: The... McGill telephone: 410-436-8467, [email protected]us.army.mil , U.S. Army Edgewood Chemical Biological Center...

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

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains parts 2-7 and appendix 15A for section 15 (Accident Analysis) of the ADM Design and Analysis. Topics covered in these parts are: decrease in heat removal; decrease in RCS flow rate; power distribution anomalies; increase in RCS inventory; decrease in RCS inventory; release of radioactive materials. The appendix covers radiological release models. Also contained here are five technical specifications for section 16 (Technical Specifications) of the ADM Design and Analysis. They are: TS 1.0 Use and Applications; TS 2.0 Safety Limits; TS 3.0 LCO Availability; TS 3.1 Reactivity Control; and TS 3.2 Power Distribution

  5. The System 80+ Standard Plant design control document. Volume 18

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains the following technical specifications of section 16 (Technical Specifications) of the ADM Design and Analysis: TS 3.3 Instrumentation; TS 3.4 Reactor Coolant System; TS 3.5 Emergency Core Cooling System; TS 3.6 Containment Systems; TS 3.7 Plant Systems; TS 3.8 Electrical Power Systems; TS 3.9 Refueling Operations; TS 4.0 Design Features; TS 5.0 Administrative Controls. Appendix 16 A Tech Spec Bases is also included. It contains the following: TS B2.0 Safety Limits Bases; TS B3.0 LCO Applicability Bases; TS B3.1 Reactivity Control Bases; TS B3.2 Power Distribution Bases

  6. IRIS. Progress in licensing and toward deployment

    International Nuclear Information System (INIS)

    Petrovic, B.; Carelli, M.D.; Kling, C.L.; Cavlina, N.; Grgic, D.

    2006-01-01

    The International Reactor Innovative and Secure (IRIS) is an advanced, integral, light water cooled, pressurized reactor of smaller generating capacity (1000 MWt, or 335 MWe). It is being developed through a strong international partnership by a team lead by Westinghouse and including organizations from 10 countries. The main objective of the project is to offer a simple nuclear power plant with outstanding safety, attractive economics and enhanced proliferation resistance characteristics ready for deployment within the next decade. IRIS embodies the requirements set forth by the recently announced US DOE Global Nuclear Energy Partnership (GNEP) program for worldwide deployment of a smaller-scale reactors and provides a viable bridge to Generation IV reactors. IRIS is designed to address the needs of both developed and emerging markets. Its smaller power level provides deployment flexibility in larger developed markets, and makes it in particular well suited for markets with limited grids or where the annual energy demand growth is moderate. Due to its short construction time and the staggered build option, IRIS significantly reduces the required financing, improves cash flow, and provides a viable solution for economies with limited resources. While based on proven and worldwide accepted LWR technology, IRIS introduces a number of innovative solutions to simplify its design and improve safety and operational characteristics, including the integral primary system and its components, as well as the safety-by-design approach. These features will be tested and demonstrated in a testing program that has been initiated. As its centerpiece, the program will include the integral test facility. Results of this program will support licensing with the US NRC. A multinational licensing is considered to facilitate worldwide deployment. (author)

  7. 75 FR 23808 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-05-04

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

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

    International Nuclear Information System (INIS)

    Hannon, J.N.

    1984-07-01

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

  9. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    International Nuclear Information System (INIS)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

  10. 75 FR 52039 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-08-24

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

  11. Standardization of the licensing process in the United States

    International Nuclear Information System (INIS)

    Villa, R.

    1986-01-01

    The paper discusses a major problem with the design review process for light water reactors. Major confusion exists over the design-basis requirements for a future nuclear power plant in the US. It is not at all clear how the conclusions of a severe accident review are to be integrated into the design approval process. The separation between a design-basis review and a severe accident review makes absolutely no sense if the severe accident review is to have an influence on the design. If an acceptable design is defined during the deterministic review, it is destructive to allow new design-basis requirements to appear during the probabilistic review. Clearly, the review process has too many undefined steps. It is believed that once all of the requirements are defined for a future design, and once the licensing process is exactly defined, the industry can begin a productive and successful standardization program

  12. The licensing of shipping containers for radioactive materials

    International Nuclear Information System (INIS)

    Schulz-Forberg, B.

    1987-01-01

    In the Federal Republic of Germany the competent Federal Minister regulated the licensing procedure in a guideline while assigning the PTB the function of competent authority, and stipulating that BAM is to execute design inspection for approval. On completion of design inspection, BAM summarizes the results in a certificate which also states the measures required to be taken in quality monitoring in the manufacturing and maintenance of packagings. A sheet specifies the implemental provisions covering quality-assurance measures in planning, manufacturing, commissioning and operation of shipping items of types B(U) and B(M), and of nuclear safety classes I, II, and III. (orig./DG) [de

  13. 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

  14. Technical evaluation report of the Fort St. Vrain final draft upgraded technical specifications

    International Nuclear Information System (INIS)

    Kimura, C.Y.

    1989-01-01

    This report is a technical evaluation of the final draft of the Fort St. Vrain (FSV) Upgraded Technical Specifications (UT/S) as issued by Public Service of Colorado (PSC) on May 27, 1988 with subsequent supplemental updates issued on June 15, 1988 and August 5, 1988. It has been compared for consistency, and safety conservatism with the Fort St. Vrain (FSV) Updated Final Safety Analysis Report (FSAR), the FSV Safety Evaluation Report (SER), the Facility Operating License, DPR-34, and all amendments to the Facility Operating License issued as of June 1, 1988, and Appendix A to the Operating License DPR-34, Technical Specifications. Because of the age of the plant, no supplements to the Fort St. Vrain SER have been issued since the original SER was not issued as a WASH or a NUREG report. This made it necessary to review all amendments to the Facility Operating License since they would contain the safety evaluations done to support changes to the Facility Operating License. The upgraded Fort St. Vrain Technical Specifications were also broadly compared with the latest Westinghouse Standard Technical Specifications (WSTS) to assure that what was proposed for Fort St. Vrain was consistent with the latest NRC staff practices for standard technical specifications

  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. Fire safety regulations and licensing

    International Nuclear Information System (INIS)

    Berg, H.P.

    1998-01-01

    Experience of the past tow decades of nuclear power plant operation and results obtained from modern analytical techniques confirm that fires may be a real threat to nuclear safety and should receive adequate attention from the design phase throughout the life of the plant. Fire events, in particular influence significantly plant safety due to the fact that fires have the potential to simultaneously damage components of redundant safety-related equipment. Hence, the importance of fire protection for the overall safety of a nuclear power plant has to be reflected by the fire safety regulations and to be checked during the licensing process of a plant as well as during the continuous supervision of the operating plant

  17. Preliminary evaluation of licensing issues associated with U.S.-sited CANDU-PHW nuclear power plants

    International Nuclear Information System (INIS)

    van Erp, J.B.

    1977-12-01

    The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S

  18. Preliminary evaluation of licensing issues associated with U. S. -sited CANDU-PHW nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    van Erp, J B

    1977-12-01

    The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S.

  19. 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)

  20. Four Essays on Technology Licensing and Firm Innovation

    DEFF Research Database (Denmark)

    Moreira, Solon

    &D strategies. On the supply side, the existing literature has been focused on understanding how technology licensing can be used by firms as a mechanism to recover investments in innovative activities and to foster learning opportunities. On the demand side, it has been shown that licensing is an important...... source that firms can tap into to feed their internal needs for innovative knowledge. While several studies have examined technology licensing through the lens of the licensor, research on how firms rely on licensing contracts to acquire knowledge and improve their innovation performance still leaves......Licensing contracts represent one of the most widely used mechanisms to exchange technologies and transfer know-how between firms. Due to the opportunities that licensing creates for firms operating on both sides of the markets for technology, it has increasingly become an integral part of firms’ R...

  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. Effectiveness of Oregon's teen licensing program : final report.

    Science.gov (United States)

    2008-06-01

    Significant changes in Oregons teen licensing laws went into effect on March 1, 2000. The new laws expanded the provisional driving license program which had been in effect since October 1989 and established a graduated driver licensing (GDL) prog...

  3. Procedural Aspects of Compulsory Licensing Under TRIPS

    DEFF Research Database (Denmark)

    Wested, Jakob; Minssen, Timo

    2017-01-01

    and discussion addressed the framework and context for CL provided by the TRIPS convention. Both the specific requirements enshrined in TRIPS art 31 and the broader objectives and principles enshrined in TRIPS, e.g. transfer and dissemination of technology (art 7), protection of public health (art 8......In 2013, Indian authorities granted a compulsory license to NATCO Pharmaceuticals for a patented pharmaceutical product sold by Bayer. This decision raised several complex issues regarding the grant a CL and their consistency with the principles and objectives of TRIPS. Furthermore, in January 2017...

  4. Assessment of the licensing aspects of HTGR in Yugoslavia

    International Nuclear Information System (INIS)

    Varazdinec, Z.

    1990-01-01

    This paper deals not only with the licensing procedure in Yugoslavia, but also reflects the Utility/Owner approach to the assessment of the licensability of the HTGR during the site selection process and especially during bid evaluation process. Besides the description of the existing procedure which was implemented on licensing of LWR program, the assessment of some licensing aspects of HTGR has been presented to describe possible implementation on licensing procedure. (author)

  5. Assessment of the licensing aspects of HTGR in Yugoslavia

    Energy Technology Data Exchange (ETDEWEB)

    Varazdinec, Z [Institut za Elektroprivredu-Zagreb, Zagreb (Yugoslavia)

    1990-07-01

    This paper deals not only with the licensing procedure in Yugoslavia, but also reflects the Utility/Owner approach to the assessment of the licensability of the HTGR during the site selection process and especially during bid evaluation process. Besides the description of the existing procedure which was implemented on licensing of LWR program, the assessment of some licensing aspects of HTGR has been presented to describe possible implementation on licensing procedure. (author)

  6. Special feature of the facilities for final disposal of radioactive waste and its potential impact on the licensing process

    International Nuclear Information System (INIS)

    Lee Gonzales, Horacio M.; Medici, Marcela A.; Alvarez, Daniela E.; Biaggio, Alfredo L.

    2009-01-01

    During the lifetime of a radioactive waste disposal facility it is possible to identify five stages: design, construction, operation, closure and post-closure. While the design, and pre-operation stages are, to some extent, similar to other kind of nuclear or radioactive facilities; construction, operation, closure and post-closure have quite special meanings in the case of radioactive waste disposal systems. For instance, the 'closure' stage of a final disposal facility seems to be equivalent to the commissioning stage of a conventional nuclear or radioactive facility. This paper describes the unique characteristics of these stages of final disposal systems, that lead to concluded that their licensing procedure can not be assimilated to the standard licensing procedures in use for other nuclear or radioactive facilities, making it necessary to develop a tailored license system. (author)

  7. An ontology based trust verification of software license agreement

    Science.gov (United States)

    Lu, Wenhuan; Li, Xiaoqing; Gan, Zengqin; Wei, Jianguo

    2017-08-01

    When we install software or download software, there will show up so big mass document to state the rights and obligations, for which lots of person are not patient to read it or understand it. That would may make users feel distrust for the software. In this paper, we propose an ontology based verification for Software License Agreement. First of all, this work proposed an ontology model for domain of Software License Agreement. The domain ontology is constructed by proposed methodology according to copyright laws and 30 software license agreements. The License Ontology can act as a part of generalized copyright law knowledge model, and also can work as visualization of software licenses. Based on this proposed ontology, a software license oriented text summarization approach is proposed which performances showing that it can improve the accuracy of software licenses summarizing. Based on the summarization, the underline purpose of the software license can be explicitly explored for trust verification.

  8. 48 CFR 252.227-7007 - License term-running royalty.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false License term-running... of Provisions And Clauses 252.227-7007 License term—running royalty. As prescribed at 227.7009-4(b), insert the following clause in patent releases, license agreements, and assignments: License Term—Running...

  9. 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...

  10. License - AcEST | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available List Contact us AcEST License to Use This Database Last updated : 2010/02/15 You may use this database in co...he Standard License specifies the license terms regarding the use of this database and the requirements you ...must follow in using this database. The Additional License specifies those items ... 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, please be sure attribute this database

  11. Crossing boundaries: a comprehensive survey of medical licensing laws and guidelines regulating the interstate practice of pathology.

    Science.gov (United States)

    Hiemenz, Matthew C; Leung, Stanley T; Park, Jason Y

    2014-03-01

    In the United States, recent judicial interpretation of interstate licensure laws has found pathologists guilty of malpractice and, more importantly, the criminal practice of medicine without a license. These judgments against pathologists highlight the need for a timely and comprehensive survey of licensure requirements and laws regulating the interstate practice of pathology. For all 50 states, each state medical practice act and state medical board website was reviewed. In addition, each medical board was directly contacted by electronic mail, telephone, or US registered mail for information regarding specific legislation or guidelines related to the interstate practice of pathology. On the basis of this information, states were grouped according to similarities in legislation and medical board regulations. This comprehensive survey has determined that states define the practice of pathology on the basis of the geographic location of the patient at the time of surgery or phlebotomy. The majority of states (n=32) and the District of Columbia allow for a physician with an out-of-state license to perform limited consultation to a physician with the specific state license. Several states (n=5) prohibit physicians from consultation without a license for the specific state. Overall, these results reveal the heterogeneity of licensure requirements between states. Pathologists who either practice in multiple states, send cases to out-of-state consultants, or serve as consultants themselves should familiarize themselves with the medical licensure laws of the states from which they receive or send cases.

  12. Safety of Nuclear Power Plants: Design. Specific Safety Requirements

    International Nuclear Information System (INIS)

    2012-01-01

    On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

  13. Occupational radiation dose assessment for a non site specific spent fuel storage facility

    International Nuclear Information System (INIS)

    Hadley, J.; Eble, R.G. Jr.

    1997-01-01

    To expedite the licensing process of the non site specific Centralized Interim Storage Facility (CISF) the Department of Energy has completed a phase I CISF Topical Safety Analysis Report (TSAR). The TSAR will be used in licensing the phase I CISF if a site is designated. An occupational radiation does assessment of the facility operations is performed as part of the phase I CISF design. The first phase of the CISF has the capability to receive, transfer, and store SNF in dual-purpose cask/canister systems (DPC's). Currently there are five vendor technologies under consideration. The preliminary dose assessment is based on estimated occupational exposures using traditional power plant ISFSI and transport cask handling processes. The second step in the process is to recommend ALARA techniques to reduce potential exposures. A final dose assessment is completed implementing the ALARA techniques and a review is performed to ensure that the design is in compliance with regulatory criteria. The dose assessment and ALARA evaluation are determined using the following input information: Dose estimates from vendor SAR's; ISFSI experience with similar systems; Traditional methods of operations; Expected CISF cask receipt rates; and feasible ALARA techniques. 5 refs., 1 tab

  14. Development and Field Test of Competency Based Instructional Material for a Career Mobility Program for Licensed Practical Nurses. Final Report.

    Science.gov (United States)

    Bergen Community Coll., Paramus, NJ.

    The Associate Degree Nursing Program at Bergen Community College developed and field tested competency-based instructional modules in a program designed to allow licensed practical nurses to qualify to take the certification examination for registered nurses after a year of study. Thirteen licensed practical nurses were enrolled in the first class…

  15. 10 CFR 71.5 - Transportation of licensed material.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Transportation of licensed material. 71.5 Section 71.5 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL General Provisions § 71.5 Transportation of licensed material. (a) Each licensee who transports licensed...

  16. Mixed-Methods Design in Biology Education Research: Approach and Uses.

    Science.gov (United States)

    Warfa, Abdi-Rizak M

    Educational research often requires mixing different research methodologies to strengthen findings, better contextualize or explain results, or minimize the weaknesses of a single method. This article provides practical guidelines on how to conduct such research in biology education, with a focus on mixed-methods research (MMR) that uses both quantitative and qualitative inquiries. Specifically, the paper provides an overview of mixed-methods design typologies most relevant in biology education research. It also discusses common methodological issues that may arise in mixed-methods studies and ways to address them. The paper concludes with recommendations on how to report and write about MMR. © 2016 L. A.-R. M. Warfa. CBE—Life Sciences Education © 2016 The American Society for Cell Biology. This article is distributed by The American Society for Cell Biology under license from the author(s). It is available to the public under an Attribution–Noncommercial–Share Alike 3.0 Unported Creative Commons License (http://creativecommons.org/licenses/by-nc-sa/3.0).

  17. Improved best estimate plus uncertainty methodology, including advanced validation concepts, to license evolving nuclear reactors

    International Nuclear Information System (INIS)

    Unal, C.; Williams, B.; Hemez, F.; Atamturktur, S.H.; McClure, P.

    2011-01-01

    Research highlights: → The best estimate plus uncertainty methodology (BEPU) is one option in the licensing of nuclear reactors. → The challenges for extending the BEPU method for fuel qualification for an advanced reactor fuel are primarily driven by schedule, the need for data, and the sufficiency of the data. → In this paper we develop an extended BEPU methodology that can potentially be used to address these new challenges in the design and licensing of advanced nuclear reactors. → The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. → The methodology includes a formalism to quantify an adequate level of validation (predictive maturity) with respect to existing data, so that required new testing can be minimized, saving cost by demonstrating that further testing will not enhance the quality of the predictive tools. - Abstract: Many evolving nuclear energy technologies use advanced predictive multiscale, multiphysics modeling and simulation (M and S) capabilities to reduce the cost and schedule of design and licensing. Historically, the role of experiments has been as a primary tool for the design and understanding of nuclear system behavior, while M and S played the subordinate role of supporting experiments. In the new era of multiscale, multiphysics computational-based technology development, this role has been reversed. The experiments will still be needed, but they will be performed at different scales to calibrate and validate the models leading to predictive simulations for design and licensing. Minimizing the required number of validation experiments produces cost and time savings. The use of multiscale, multiphysics models introduces challenges in validating these predictive tools - traditional methodologies will have to be modified to address these challenges. This paper gives the basic aspects of a methodology that can potentially be used to address these new challenges in

  18. Incorporation of severe accidents in the licensing of nuclear power plants

    International Nuclear Information System (INIS)

    Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

    2011-01-01

    Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

  19. Incorporation of severe accidents in the licensing of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz, E-mail: bayout@cnen.gov.b, E-mail: sidney@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN) Rio de Janeiro, RJ (Brazil)

    2011-07-01

    Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

  20. 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.