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Sample records for license application design

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. License Application Design Selection Feature Report Canistered Assemblies

    International Nuclear Information System (INIS)

    Bennett, Scott M.

    1999-01-01

    The objective of the Modified Waste Emplacement Mode Design Alternative Report is to identify, describe, and evaluate waste package emplacement modes against a specified set of evaluation criteria. This evaluation of the design alternative will be used as input to the decision-making process used to identify the EDAs. The EDAs will, in turn, be evaluated against a set of evaluation criteria, and their evaluations will be used as the basis for an M and O recommendation on the LA design

  7. 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

  8. 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.)

  9. 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.

  10. 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)

  11. License Application Design Selection Feature Report: Waste Package Self Shielding Design Feature 13

    International Nuclear Information System (INIS)

    Tang, J.S.

    2000-01-01

    In the Viability Assessment (VA) reference design, handling of waste packages (WPs) in the emplacement drifts is performed remotely, and human access to the drifts is precluded when WPs are present. This report will investigate the feasibility of using a self-shielded WP design to reduce the radiation levels in the emplacement drifts to a point that, when coupled with ventilation, will create an acceptable environment for human access. This provides the benefit of allowing human entry to emplacement drifts to perform maintenance on ground support and instrumentation, and carry out performance confirmation activities. More direct human control of WP handling and emplacement operations would also be possible. However, these potential benefits must be weighed against the cost of implementation, and potential impacts on pre- and post-closure performance of the repository and WPs. The first section of this report will provide background information on previous investigations of the self-shielded WP design feature, summarize the objective and scope of this document, and provide quality assurance and software information. A shielding performance and cost study that includes several candidate shield materials will then be performed in the subsequent section to allow selection of two self-shielded WP design options for further evaluation. Finally, the remaining sections will evaluate the impacts of the two WP self-shielding options on the repository design, operations, safety, cost, and long-term performance of the WPs with respect to the VA reference design

  12. 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

  13. License application design selection feature report: Additive and fillers design feature 19

    International Nuclear Information System (INIS)

    Massari, J.R.

    1999-01-01

    The estimated additional total system life-cycle cost for each of the filler options in 1999 dollars is as follows: $923.4 million for the iron oxide option, $42.4 million to $966.4 million (depending on the extent of surface facility involvement required) for the partial iron shot fill option, $1,012 million for the complete iron shot fill option, and $134.7 million for the integral filler option (Appendix A). All of the filler options evaluated showed improvements in some aspects of pre- and post-closure waste package and repository performance. However, all of the options, except for the integral filler option, negatively impacted other areas of performance, required modification to surface facility design and operations, and invoked additional uncertainty. The iron oxide filler option will require further testing to measure thermal conductivity to ensure that peak cladding temperatures will not exceed the 350 C limit. The complete iron shot fill option may require structural improvements to the waste package design (use of partial shot fill may eliminate this concern). Both the iron shot and iron oxide options will also require further testing to confirm that the conceptual loading strategy will efficiently load a waste package in a timely manner. In addition, both shot and oxide options will require further testing to develop models for their potential to provide resistance to water flow, and, in the case of iron shot, act as an oxygen getter. Finally, uncertainty also exists as to whether the iron shot option will damage the cladding if sufficient corrosion of the shot occurs. Based on the results presented in this evaluation, the integral filler option appears to be the simplest and most cost efficient method for achieving modest improvements in pre- and post-closure performance. Since unqualified inputs were used in the development of this evaluation, they should be considered TBV (to be verified). This document will not directly support any construction

  14. 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

  15. 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.

  16. 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

  17. 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.

  18. 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...

  19. 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)

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

    International Nuclear Information System (INIS)

    1980-01-01

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

  1. 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...

  2. Personality traits of Turkish handgun license applicants.

    Science.gov (United States)

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

    2012-10-01

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

  3. 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)

  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. 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)

  6. 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)

  7. INTERNAL HAZARDS ANALYSIS FOR LICENSE APPLICATION

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-02-17

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

  8. INTERNAL HAZARDS ANALYSIS FOR LICENSE APPLICATION

    International Nuclear Information System (INIS)

    Garrett, R.J.

    2005-01-01

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

  9. 75 FR 46938 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-08-04

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

  10. 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)

  11. 75 FR 72824 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-11-26

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

  12. 75 FR 80499 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-12-22

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

  13. 78 FR 20106 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-04-03

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

  14. 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

  15. 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

  16. 77 FR 59193 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-09-26

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

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

    Science.gov (United States)

    2011-11-10

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

  18. 75 FR 20997 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-04-22

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

  19. 25 CFR 141.9 - Application for license renewal.

    Science.gov (United States)

    2010-04-01

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

  20. LTO License Application Project NPP Borssele

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  1. 77 FR 20398 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-04-04

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

  2. 76 FR 44330 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-07-25

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

  3. 77 FR 24712 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-04-25

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

  4. 78 FR 66713 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-11-06

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

  5. 76 FR 79682 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-12-22

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

  6. 75 FR 61757 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-10-06

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

  7. 76 FR 30360 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-05-25

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

  8. 77 FR 71002 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-11-28

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

  9. 78 FR 6325 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-01-30

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

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  11. 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

  12. 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.)

  13. 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.)

  14. 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

  15. 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

  16. 75 FR 48686 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-08-11

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

  17. 77 FR 18815 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-03-28

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

  18. 15 CFR 748.9 - Support documents for license applications.

    Science.gov (United States)

    2010-01-01

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

  19. 77 FR 43599 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-07-25

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

  20. 76 FR 28778 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-05-18

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

  1. 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

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

    International Nuclear Information System (INIS)

    1975-09-01

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

  3. 76 FR 47182 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-08-04

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

  4. 77 FR 72863 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-12-06

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

  5. 77 FR 12583 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-03-01

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

  6. 77 FR 64991 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-10-24

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

  7. 77 FR 26008 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-05-02

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

  8. 75 FR 67973 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-11-04

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

  9. 76 FR 78007 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-12-15

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

  10. 77 FR 70162 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-11-23

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

  11. 78 FR 38336 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-06-26

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

  12. 76 FR 23598 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-04-27

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

  13. 76 FR 56759 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-09-14

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

  14. 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

  15. License application approach for the California LLRW disposal facility

    International Nuclear Information System (INIS)

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

    1990-01-01

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

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  17. 10 CFR 781.62 - Contents of a license application.

    Science.gov (United States)

    2010-01-01

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

  18. 78 FR 17205 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-03-20

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

  19. 78 FR 75345 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-12-11

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

  20. 76 FR 22104 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-04-20

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

  1. 78 FR 50054 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-08-16

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

  2. 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...

  3. 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

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

    International Nuclear Information System (INIS)

    1976-01-01

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

  5. 78 FR 55698 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-09-11

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

  6. 77 FR 37044 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-06-20

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

  7. 78 FR 48435 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-08-08

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

  8. 76 FR 55909 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-09-09

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

  9. 78 FR 18592 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-03-27

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

  10. 76 FR 62407 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-10-07

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

  11. 78 FR 14792 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-03-07

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

  12. 77 FR 45610 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-08-01

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

  13. 10 CFR 81.40 - Contents of a license application.

    Science.gov (United States)

    2010-01-01

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

  14. 77 FR 40882 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-07-11

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

  15. 77 FR 38288 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-06-27

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

  16. 78 FR 48870 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-08-12

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

  17. 75 FR 57798 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-09-22

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

  18. 76 FR 67730 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-11-02

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

  19. 77 FR 30530 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-05-23

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

  20. 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

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

    Science.gov (United States)

    2010-10-01

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

  2. 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...

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

    International Nuclear Information System (INIS)

    Ratkai, Sandor; Katona, Tamas Janos

    2012-01-01

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

  4. 76 FR 6135 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-02-03

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

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

    International Nuclear Information System (INIS)

    1975-04-01

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

  6. 78 FR 35634 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-06-13

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

  7. 76 FR 3636 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-01-20

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

  8. 77 FR 65887 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-10-31

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

  9. 76 FR 41258 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-07-13

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

  10. 75 FR 35815 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-06-23

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

  11. 77 FR 74186 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-12-13

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

  12. 78 FR 43202 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-07-19

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

  13. 76 FR 14395 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-03-16

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

  14. 75 FR 29545 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-05-26

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

  15. 77 FR 35384 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-06-13

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

  16. 9 CFR 2.11 - Denial of initial license application.

    Science.gov (United States)

    2010-01-01

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

  17. 76 FR 7209 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-02-09

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

  18. 76 FR 38651 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-07-01

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

  19. 76 FR 33757 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-06-09

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

  20. 77 FR 13604 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-03-07

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

  1. 78 FR 60282 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-10-01

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

  2. 77 FR 39707 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-07-05

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

  3. 76 FR 16420 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-03-23

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

  4. 76 FR 65193 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-10-20

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

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

    International Nuclear Information System (INIS)

    Langenbuch, S.; Velkov, K.

    2006-01-01

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

  6. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    1993-11-01

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

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

    International Nuclear Information System (INIS)

    1976-02-01

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

  8. CATEGORIZATION OF EVENT SEQUENCES FOR LICENSE APPLICATION

    Energy Technology Data Exchange (ETDEWEB)

    G.E. Ragan; P. Mecheret; D. Dexheimer

    2005-04-14

    The purposes of this analysis are: (1) Categorize (as Category 1, Category 2, or Beyond Category 2) internal event sequences that may occur before permanent closure of the repository at Yucca Mountain. (2) Categorize external event sequences that may occur before permanent closure of the repository at Yucca Mountain. This includes examining DBGM-1 seismic classifications and upgrading to DBGM-2, if appropriate, to ensure Beyond Category 2 categorization. (3) State the design and operational requirements that are invoked to make the categorization assignments valid. (4) Indicate the amount of material put at risk by Category 1 and Category 2 event sequences. (5) Estimate frequencies of Category 1 event sequences at the maximum capacity and receipt rate of the repository. (6) Distinguish occurrences associated with normal operations from event sequences. It is beyond the scope of the analysis to propose design requirements that may be required to control radiological exposure associated with normal operations. (7) Provide a convenient compilation of the results of the analysis in tabular form. The results of this analysis are used as inputs to the consequence analyses in an iterative design process that is depicted in Figure 1. Categorization of event sequences for permanent retrieval of waste from the repository is beyond the scope of this analysis. Cleanup activities that take place after an event sequence and other responses to abnormal events are also beyond the scope of the analysis.

  9. CATEGORIZATION OF EVENT SEQUENCES FOR LICENSE APPLICATION

    International Nuclear Information System (INIS)

    G.E. Ragan; P. Mecheret; D. Dexheimer

    2005-01-01

    The purposes of this analysis are: (1) Categorize (as Category 1, Category 2, or Beyond Category 2) internal event sequences that may occur before permanent closure of the repository at Yucca Mountain. (2) Categorize external event sequences that may occur before permanent closure of the repository at Yucca Mountain. This includes examining DBGM-1 seismic classifications and upgrading to DBGM-2, if appropriate, to ensure Beyond Category 2 categorization. (3) State the design and operational requirements that are invoked to make the categorization assignments valid. (4) Indicate the amount of material put at risk by Category 1 and Category 2 event sequences. (5) Estimate frequencies of Category 1 event sequences at the maximum capacity and receipt rate of the repository. (6) Distinguish occurrences associated with normal operations from event sequences. It is beyond the scope of the analysis to propose design requirements that may be required to control radiological exposure associated with normal operations. (7) Provide a convenient compilation of the results of the analysis in tabular form. The results of this analysis are used as inputs to the consequence analyses in an iterative design process that is depicted in Figure 1. Categorization of event sequences for permanent retrieval of waste from the repository is beyond the scope of this analysis. Cleanup activities that take place after an event sequence and other responses to abnormal events are also beyond the scope of the analysis

  10. PRECLOSURE CONSEQUENCE ANALYSES FOR LICENSE APPLICATION

    Energy Technology Data Exchange (ETDEWEB)

    S. Tsai

    2005-01-12

    Radiological consequence analyses are performed for potential releases from normal operations in surface and subsurface facilities and from Category 1 and Category 2 event sequences during the preclosure period. Surface releases from normal repository operations are primarily from radionuclides released from opening a transportation cask during dry transfer operations of spent nuclear fuel (SNF) in Dry Transfer Facility 1 (DTF 1), Dry Transfer Facility 2 (DTF 2), the Canister Handling facility (CHF), or the Fuel Handling Facility (FHF). Subsurface releases from normal repository operations are from resuspension of waste package surface contamination and neutron activation of ventilated air and silica dust from host rock in the emplacement drifts. The purpose of this calculation is to demonstrate that the preclosure performance objectives, specified in 10 CFR 63.111(a) and 10 CFR 63.111(b), have been met for the proposed design and operations in the geologic repository operations area. Preclosure performance objectives are discussed in Section 6.2.3 and are summarized in Tables 1 and 2.

  11. PRECLOSURE CONSEQUENCE ANALYSES FOR LICENSE APPLICATION

    International Nuclear Information System (INIS)

    S. Tsai

    2005-01-01

    Radiological consequence analyses are performed for potential releases from normal operations in surface and subsurface facilities and from Category 1 and Category 2 event sequences during the preclosure period. Surface releases from normal repository operations are primarily from radionuclides released from opening a transportation cask during dry transfer operations of spent nuclear fuel (SNF) in Dry Transfer Facility 1 (DTF 1), Dry Transfer Facility 2 (DTF 2), the Canister Handling facility (CHF), or the Fuel Handling Facility (FHF). Subsurface releases from normal repository operations are from resuspension of waste package surface contamination and neutron activation of ventilated air and silica dust from host rock in the emplacement drifts. The purpose of this calculation is to demonstrate that the preclosure performance objectives, specified in 10 CFR 63.111(a) and 10 CFR 63.111(b), have been met for the proposed design and operations in the geologic repository operations area. Preclosure performance objectives are discussed in Section 6.2.3 and are summarized in Tables 1 and 2

  12. 21 CFR 515.20 - Approval of medicated feed mill license applications.

    Science.gov (United States)

    2010-04-01

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

  13. 21 CFR 515.21 - Refusal to approve a medicated feed mill license application.

    Science.gov (United States)

    2010-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  16. 78 FR 37324 - Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications

    Science.gov (United States)

    2013-06-20

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

  17. 47 CFR 87.47 - Application for a portable aircraft station license.

    Science.gov (United States)

    2010-10-01

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

  18. 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)

  19. 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.)

  20. 76 FR 65544 - Standard Format and Content of License Applications for Mixed Oxide Fuel Fabrication Facilities

    Science.gov (United States)

    2011-10-21

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

  1. 21 CFR 515.11 - Supplemental medicated feed mill license applications.

    Science.gov (United States)

    2010-04-01

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

  2. 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

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

    Science.gov (United States)

    2010-04-01

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

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

    Science.gov (United States)

    2013-04-12

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

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

    International Nuclear Information System (INIS)

    1977-01-01

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

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

    International Nuclear Information System (INIS)

    Boyd, Frederick C.

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    1991-08-01

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

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

    Science.gov (United States)

    2013-09-03

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

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

    Energy Technology Data Exchange (ETDEWEB)

    J. McNeish

    2002-09-13

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

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

    International Nuclear Information System (INIS)

    McNeish, J.

    2003-01-01

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

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

    Science.gov (United States)

    Tang, Hongliang; Kang, Chengxu; Tian, Youping

    2018-01-01

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

  13. 77 FR 70837 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-11-27

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

  14. 78 FR 16876 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-03-19

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

  15. 77 FR 63343 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-10-16

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

  16. 77 FR 73684 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-12-11

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

  17. 77 FR 67679 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-11-13

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

  18. 76 FR 72984 - Revised Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2011-11-28

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

  19. 76 FR 49462 - Newfound Hydroelectric Company, KTZ Hydro, LLC; Notice of Application for Transfer of License...

    Science.gov (United States)

    2011-08-10

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

  20. 76 FR 59173 - Standard Format and Content of License Applications for Conventional Uranium Mills

    Science.gov (United States)

    2011-09-23

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

  1. 75 FR 70350 - Liberty Natural Gas LLC, Liberty Liquefied Natural Gas (LNG) Deepwater Port License Application

    Science.gov (United States)

    2010-11-17

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

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

    International Nuclear Information System (INIS)

    Hedin, Allan; Andersson, Johan

    2014-01-01

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

  3. 75 FR 69080 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-11-10

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

  4. 78 FR 32650 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-05-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

    J. McNeish

    2003-12-08

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

  6. 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

  7. 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

  8. 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.

  9. 77 FR 21592 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Science.gov (United States)

    2012-04-10

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

  10. 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.

  11. 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

  12. 78 FR 69852 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-11-21

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

  13. 76 FR 72409 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-11-23

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

  14. 77 FR 3773 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-01-25

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

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

    International Nuclear Information System (INIS)

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

    1991-08-01

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

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

    International Nuclear Information System (INIS)

    1996-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

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

  18. 77 FR 74841 - Alabama Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2012-12-18

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

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

    International Nuclear Information System (INIS)

    Dandrieux, Geraldine

    2014-01-01

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

  20. 78 FR 73566 - Standard Format and Content for a License Application for an Independent Spent Fuel Storage...

    Science.gov (United States)

    2013-12-06

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

  1. 77 FR 33243 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Science.gov (United States)

    2012-06-05

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

  2. 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)

  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. 78 FR 74176 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-12-10

    ... features include the design of the lifting devices, design of the cask and fuel bridge cranes, crane... method, the fuel building bridge crane and the cask crane will be used to perform the gate lifting and... potential for a heavy load drop is extremely small. The gate lifting using the bridge crane and cask crane...

  5. 77 FR 56877 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-09-14

    ... steam bypass system to the condenser not be available. ADVs are also available to limit the releases... evaluated? Response: No. There are no changes to design, no changes to operating procedures and the revised... tube rupture (SGTR) event is one of the design basis accidents that are analyzed as part of a plant's...

  6. 78 FR 28248 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-05-14

    ... necessary to minimize bypassing of the ice condenser by the hot steam and air mixture released into the lower compartment during a Design Basis Accident (DBA). This ensures that most of the gases pass through... proposed change does not involve a change in the operational limits or the design capabilities of the...

  7. System 80+ Design and Licensing : Improving Plant Reliability

    International Nuclear Information System (INIS)

    Newman, Robert E.

    1989-01-01

    The U. S. nuclear industry is striving to improve plant reliability and availability through improved plant design, component designs and plant maintenance. In an effort to improve safety and to demonstrate that commercial nuclear power is economically competitive with other energy sources, the utilities, nuclear vendors, architect engineers and constructors, and component suppliers are all participating in an industry-wide effort to develop improved Light Water Reactor (LWR) designs that are based upon the many years of successful LWR operation. In an age when the world faces the environmental pressures of the greenhouse effect and acid rain, electricity generated from nuclear energy must play an increasing role in the energy picture of Korea, the United States and the rest of the world. This paper discusses the plant availability requirement that has been established by the industry-wide effort mentioned above. After briefly describing Combustion Engineering's program for development of the System 80 Plus standard design and the participation of the Korea Advanced Energy Research Institute (KAERI) in the program, the paper then describes the design features that are being incorporated into System 80+. The industry ALRR Program has established a very ambitious criterion of 87% for the plant availability of future nuclear units. To satisfy such a requirement, the next generation of nuclear plants will include a great many design improvements that reflect the hundreds of years of operating experience that we have accrued. C-ESA's System 80+ will include a number of design changes that improve operating margins and make the plant easier to operate and maintain. Not surprisingly, there is a great deal of overlap between improved safety and improved reliability. In the end, our design will satisfy the future needs of the utilities, the regulators, and the public. C-E is very pleased that KAERI is working with US to achieve these important goals

  8. 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.

  9. 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.)

  10. Preparing to Submit a License Application for Yucca Mountain

    International Nuclear Information System (INIS)

    W.J. Arthur; M.D. Voegele

    2005-01-01

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

  11. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

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

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

    International Nuclear Information System (INIS)

    1996-02-01

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

  14. 77 FR 12830 - Pershing County Water Conservation District; Notice of Intent To File License Application, Filing...

    Science.gov (United States)

    2012-03-02

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

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

    Directory of Open Access Journals (Sweden)

    Li Weiwei

    2016-01-01

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

  16. 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

  17. 78 FR 38078 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-06-25

    ... essentially leak tight barrier against the uncontrolled release of radioactivity to the environment for... frequency currently required by TS. Industry experience supports the conclusion that Type B and C testing...-OCS-GEH-520, ``AP1000 Plant Startup Human Factors Engineering Design Verification Plan,'' from...

  18. 78 FR 77729 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-12-24

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

  19. 77 FR 25753 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2012-05-01

    ... thermal shock are bounded by the current analyses. Systems will continue to operate within their design.... Markley. Entergy Nuclear Operations, Inc., Docket No. 50-247, Indian Point Nuclear Generating Unit 2... the SG tube below the top of the SG tubesheet from periodic inspections. In addition, this amendment...

  20. 77 FR 61433 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Science.gov (United States)

    2012-10-09

    ... attacks up to and including the design basis cyber attack threat, thereby achieving high assurance that... provide assurance that safety-related SSCs are protected from cyber attacks. Implementation of 10 CFR 73... of ``high assurance of adequate protection against cyber attacks.'' The proposed revision would not...

  1. 78 FR 19746 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-04-02

    ... cases to mail copies on electronic storage media. Participants may not submit paper copies of their... consequences of the offsite dose and control room dose projections for the currently approved design basis FHA... [American Society of Mechanical Engineers Boiler and Pressure Vessel Code], Section XI, Appendix G edition...

  2. 78 FR 49298 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Science.gov (United States)

    2013-08-13

    ... of amendment request: September 25, 2012, as supplemented by letter dated December 17, 2012. A... the refueling accident with XM fuel is not increased because the upper bail handle is designed to be... supplemented by letter dated May 16, 2013 (ADAMS Accession No. ML13141A291). Description of amendment request...

  3. 78 FR 70589 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-11-26

    ... valves to be closed and meet Inservice Testing (IST) Program leakage requirements. The additional... of 68 [deg]F or a higher temperature that is determined to represent the most reactive state... (BWR) fuel designs which may be more reactive at shutdown temperatures above 68 [deg]F. [[Page 70593...

  4. 78 FR 51219 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Science.gov (United States)

    2013-08-20

    ... the remaining relevant safety barriers for defueled plants (i.e., fuel cladding and spent fuel cooling... reduction in margin of safety because containment structure fission product barrier design margin is... previously evaluated; or (3) involve a significant reduction in a margin of safety. The basis for this...

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

    International Nuclear Information System (INIS)

    1989-07-01

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

  6. Evaluation on licensability of KNGR system design (II)

    Energy Technology Data Exchange (ETDEWEB)

    Park, G. C.; Seo, K. R. [Seoul National Univ., Seoul (Korea, Republic of); Kim, J. K. [Hanyang Univ., Seoul (Korea, Republic of)] (and others)

    2001-01-15

    The CE methodology of DBA analysis are reviewed. Though UPTF test is different from the KNGR in the geometrical configuration of the down-corner, this was used as a reference to investigate the validity of CEFLASH and COMPERC-II codes in DBA analysis of KNGR. it revealed that CEFLASH is conservative but COMPERC-II for the Refill and Reflood phase is needed for the detailed investigation on ECC bypass, Entrainment, condensation phenomena, CCFL. The direct bypass rate based on the benchmark problem was quantitatively measured. The test model was scaled by the linear scaling methodology, and the accident conditions were the reflood phase at a CB-DEGB LBLOCA. The initial total air flow rate was determined considering the volume scaling factor (1/1000) on criteria of the KNGR design value. The volume rates of ECC water injected: through the DVI nozzles were changed for several case. The direct bypass ratio was about 22 % on the condition of the KNGR scaled-down air volume flow and ECC water velocity at about 1 m/s. The fast neutron fluence at the Reactor Pressure Vessel(RPV) of KNGR designed for 60 years of lifetime was calculated by Monte Carlo simulations and Discrete Ordinates Method for reactor pressure vessel integrity assessment. KNGR core geometry was modeled on a three-dimensional. In the full-scope Monte Carlo method, the maximum fast neutron flux at inner vessel belt line was estimated as 2.738 x 10{sup 10} neutrons/cm{sup 2}{center_dot}see. In the ROCS+MCNP4B calculation, the maximum flux of 2.769 x 10{sup 10} neutrons/ cm{sup 2}{center_dot}see at the RPV was obtained by tallying neutrons crossing the inner surface of the RPV. In ROCS+TORT Calculation, the maximum flux of 3.190 x 10{sup 10} neutrons/cm{sup 2} {center_dot}see was obtained at inner RPV belt line. The lifetime of KNGR was estimated on the basis of conservative end of life fluence limit value of the ABB-CE System 80+. Approximately, 72 Effective Full Power Years (EFPYs), equivalent to 90 calendar

  7. 78 FR 13342 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-02-27

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

  8. 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

  9. 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

  10. 77 FR 73054 - Application for a License To Export Radioactive Waste

    Science.gov (United States)

    2012-12-07

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

  11. 77 FR 14445 - Application for a License To Export Steel Forging

    Science.gov (United States)

    2012-03-09

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

  12. 75 FR 15743 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2010-03-30

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

  13. 75 FR 6223 - Application For a License To Export High-Enriched Uranium

    Science.gov (United States)

    2010-02-08

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

  14. 77 FR 1956 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2012-01-12

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

  15. 75 FR 7525 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2010-02-19

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

  16. 75 FR 71102 - White Mountain Hydroelectric Corp.; Notice of Application for Amendment of License, and...

    Science.gov (United States)

    2010-11-22

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

  17. 76 FR 4417 - Liberty Natural Gas LLC, Liberty Liquefied Natural Gas (LNG) Deepwater Port License Application

    Science.gov (United States)

    2011-01-25

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

  18. 77 FR 76483 - Ocean Transportation Intermediary License Applicants The Commission gives notice that the...

    Science.gov (United States)

    2012-12-28

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

  19. Designing Adaptive Web Applications

    DEFF Research Database (Denmark)

    Dolog, Peter

    2008-01-01

    Learning system to study a discipline. In business to business interaction, different requirements and parameters of exchanged business requests might be served by different services from third parties. Such applications require certain intelligence and a slightly different approach to design. Adpative web......The unique characteristic of web applications is that they are supposed to be used by much bigger and diverse set of users and stakeholders. An example application area is e-Learning or business to business interaction. In eLearning environment, various users with different background use the e......-based applications aim to leave some of their features at the design stage in the form of variables which are dependent on several criteria. The resolution of the variables is called adaptation and can be seen from two perspectives: adaptation by humans to the changed requirements of stakeholders and dynamic system...

  20. Modular Mobile Application Design

    OpenAIRE

    Jim Hahn; Nathaniel Ryckman

    2012-01-01

    This article describes the development of the Minrva library app for Android phones. The decisions to build a native application with Java and use a modular design are discussed. The application includes five modules: catalog search, in-building navigation, a barcode scanning feature, and up to date notifications of circulating technology availability. A sixth module, Amazon recommendations, that is not included in the version of the app that was released is also discussed. The article also r...

  1. 75 FR 61474 - Juneau Hydropower, Inc.; Notice of Intent To File License Application, Filing of Pre-Application...

    Science.gov (United States)

    2010-10-05

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

  2. 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...

  3. 78 FR 28845 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-05-16

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

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

    International Nuclear Information System (INIS)

    1979-01-01

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

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

    International Nuclear Information System (INIS)

    Roberts, J.; Griffin, W.R.

    1992-01-01

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

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

    International Nuclear Information System (INIS)

    Boissier, Fabrice; Voinis, Sylvie

    2014-01-01

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

  8. 75 FR 32780 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-06-09

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

  9. 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)

  10. 76 FR 19097 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-04-06

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

  11. 77 FR 23719 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-04-20

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

  12. 75 FR 6398 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-02-09

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

  13. 75 FR 66099 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-10-27

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

  14. 75 FR 60124 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-09-29

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

  15. Modular Mobile Application Design

    Directory of Open Access Journals (Sweden)

    Jim Hahn

    2012-10-01

    Full Text Available This article describes the development of the Minrva library app for Android phones. The decisions to build a native application with Java and use a modular design are discussed. The application includes five modules: catalog search, in-building navigation, a barcode scanning feature, and up to date notifications of circulating technology availability. A sixth module, Amazon recommendations, that is not included in the version of the app that was released is also discussed. The article also reports on the findings of two rounds of usability testing and the plans for future development of the app.

  16. 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

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

    International Nuclear Information System (INIS)

    1985-01-01

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

  18. 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...

  19. 75 FR 52343 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-08-25

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

  20. 76 FR 67188 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-10-31

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

  1. 78 FR 30921 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-05-23

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

  2. 76 FR 10593 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-02-25

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

  3. 76 FR 71608 - Notice of Availability of Combined License Applications

    Science.gov (United States)

    2011-11-18

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

  4. 76 FR 77021 - Notice of Availability of Combined License Applications

    Science.gov (United States)

    2011-12-09

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

  5. 76 FR 72725 - Notice of Availability of Combined License Applications

    Science.gov (United States)

    2011-11-25

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

  6. 78 FR 10173 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-02-13

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

  7. 75 FR 28250 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-05-20

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

  8. 76 FR 12962 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-03-09

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

  9. 77 FR 32115 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-05-31

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

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

    Science.gov (United States)

    Fishel, Fred; Langeland, Ken

    2011-01-01

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

  11. 77 FR 34030 - BOST1 Hydroelectric LLC; Notice of Intent To File License Application, Filing of Pre-Application...

    Science.gov (United States)

    2012-06-08

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

  12. 77 FR 6552 - Mahoning Hydropower, LLC; Notice of Intent To File License Application, Filing of Pre-Application...

    Science.gov (United States)

    2012-02-08

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

  13. 78 FR 45578 - Application For a License to Export Radioactive Waste

    Science.gov (United States)

    2013-07-29

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

  14. 77 FR 73056 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2012-12-07

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

  15. 77 FR 73055 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2012-12-07

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

  16. 77 FR 51579 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2012-08-24

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

  17. 78 FR 33448 - Application for a License To Export High-Enriched Uranium

    Science.gov (United States)

    2013-06-04

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

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

    Science.gov (United States)

    2010-04-01

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

  19. 75 FR 467 - Notice of Opportunity for Hearing, License Application Request of Powertech (USA) Inc. Dewey...

    Science.gov (United States)

    2010-01-05

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

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

    International Nuclear Information System (INIS)

    1975-12-01

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

  1. 76 FR 63668 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Science.gov (United States)

    2011-10-13

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

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

    International Nuclear Information System (INIS)

    1976-01-01

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

  3. 76 FR 71082 - Strata Energy, Inc., Ross Uranium Recovery Project; New Source Material License Application...

    Science.gov (United States)

    2011-11-16

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

  4. 78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

    Science.gov (United States)

    2013-07-05

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

  5. 78 FR 64493 - Juneau Hydropower, Inc.; Notice of Subsequent Draft License Application (DLA) and Draft...

    Science.gov (United States)

    2013-10-29

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

  6. 76 FR 52994 - Application for a License To Export Heavy Water

    Science.gov (United States)

    2011-08-24

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

  7. 76 FR 53693 - Notice of Invitation To Participate; Coal Exploration License Application COC-74911, Colorado

    Science.gov (United States)

    2011-08-29

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

  8. Piezoresistor design and applications

    CERN Document Server

    Doll, Joseph C

    2013-01-01

    This book is a comprehensive guide to piezoresistive MEMS sensor design. Piezoresistors transduce mechanical loads into electrical signals via a resistance change, and comprise a substantial portion of the commercial MEMS sensors market. Applications of piezoresistors include strain gauges, accelerometers, pressure sensors, force sensors, chemical sensors and resonators. This book also: ·         Demonstrates how the latest piezoresistor models and optimization techniques can be integrated for high performance piezoresistor design ·         Covers in detail piezoresistor sensitivity and noise models, signal conditioning, fabrication processes, low-power design and numerical optimization techniques ·         Provides an up-to-date discussion of alternative piezoresistive materials and MEMS transduction techniques ·         Explores in detail the tradeoffs in size, performance and complexity between piezoresistive sensing and popular alternatives (capacitive, piezoelectric an...

  9. 76 FR 25690 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-05-05

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

  10. 10 CFR 40.31 - Application for specific licenses.

    Science.gov (United States)

    2010-01-01

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

  11. 76 FR 9015 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2011-02-16

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

  12. 76 FR 71034 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-11-16

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

  13. 78 FR 63475 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-10-24

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

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

    International Nuclear Information System (INIS)

    1975-01-01

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

  15. 7 CFR 46.4 - Application for license.

    Science.gov (United States)

    2010-01-01

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

  16. 75 FR 42446 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2010-07-21

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

  17. 75 FR 63476 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2010-10-15

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

  18. 78 FR 23252 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-04-18

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

  19. 77 FR 9657 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-02-17

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

  20. 78 FR 78956 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-12-27

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

  1. 78 FR 68444 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-11-14

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

  2. 77 FR 21559 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-04-10

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

  3. 78 FR 48435 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-08-08

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

  4. 78 FR 56229 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2013-09-12

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

  5. 76 FR 31962 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-06-02

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

  6. 77 FR 35079 - License Renewal Application for Seabrook Station, Unit 1 ; NextEra Energy Seabrook, LLC

    Science.gov (United States)

    2012-06-12

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

  7. 75 FR 13786 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-03-23

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

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

    Science.gov (United States)

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

    2017-06-01

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

  9. 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

  10. 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

  11. 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

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

    International Nuclear Information System (INIS)

    1989-09-01

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

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  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. Frequency Analysis of Aircraft hazards for License Application

    International Nuclear Information System (INIS)

    K. Ashley

    2006-01-01

    The preclosure safety analysis for the monitored geologic repository at Yucca Mountain must consider the hazard that aircraft may pose to surface structures. Relevant surface structures are located beneath the restricted airspace of the Nevada Test Site (NTS) on the eastern slope of Yucca Mountain, near the North Portal of the Exploratory Studies Facility Tunnel (Figure 1). The North Portal is located several miles from the Nevada Test and Training Range (NTTR), which is used extensively by the U.S. Air Force (USAF) for training and test flights (Figure 1). The NTS airspace, which is controlled by the U.S. Department of Energy (DOE) for NTS activities, is not part of the NTTR. Agreements with the DOE allow USAF aircraft specific use of the airspace above the NTS (Reference 2.1.1 [DIRS 103472], Section 3.1.1 and Appendix A, Section 2.1; and Reference 2.1.2 [DIRS 157987], Sections 1.26 through 1.29). Commercial, military, and general aviation aircraft fly within several miles to the southwest of the repository site in the Beatty Corridor, which is a broad air corridor that runs approximately parallel to U.S. Highway 95 and the Nevada-California border (Figure 2). These aircraft and other aircraft operations are identified and described in ''Identification of Aircraft Hazards'' (Reference 2.1.3, Sections 6 and 8). The purpose of this analysis is to estimate crash frequencies for aircraft hazards identified for detailed analysis in ''Identification of Aircraft Hazards'' (Reference 2.1.3, Section 8). Reference 2.1.3, Section 8, also identifies a potential hazard associated with electronic jamming, which will be addressed in this analysis. This analysis will address only the repository and not the transportation routes to the site. The analysis is intended to provide the basis for: (1) Categorizing event sequences related to aircraft hazards; (2) Identifying design or operational requirements related to aircraft hazards

  16. Frequency Analysis of Aircraft hazards for License Application

    Energy Technology Data Exchange (ETDEWEB)

    K. Ashley

    2006-10-24

    The preclosure safety analysis for the monitored geologic repository at Yucca Mountain must consider the hazard that aircraft may pose to surface structures. Relevant surface structures are located beneath the restricted airspace of the Nevada Test Site (NTS) on the eastern slope of Yucca Mountain, near the North Portal of the Exploratory Studies Facility Tunnel (Figure 1). The North Portal is located several miles from the Nevada Test and Training Range (NTTR), which is used extensively by the U.S. Air Force (USAF) for training and test flights (Figure 1). The NTS airspace, which is controlled by the U.S. Department of Energy (DOE) for NTS activities, is not part of the NTTR. Agreements with the DOE allow USAF aircraft specific use of the airspace above the NTS (Reference 2.1.1 [DIRS 103472], Section 3.1.1 and Appendix A, Section 2.1; and Reference 2.1.2 [DIRS 157987], Sections 1.26 through 1.29). Commercial, military, and general aviation aircraft fly within several miles to the southwest of the repository site in the Beatty Corridor, which is a broad air corridor that runs approximately parallel to U.S. Highway 95 and the Nevada-California border (Figure 2). These aircraft and other aircraft operations are identified and described in ''Identification of Aircraft Hazards'' (Reference 2.1.3, Sections 6 and 8). The purpose of this analysis is to estimate crash frequencies for aircraft hazards identified for detailed analysis in ''Identification of Aircraft Hazards'' (Reference 2.1.3, Section 8). Reference 2.1.3, Section 8, also identifies a potential hazard associated with electronic jamming, which will be addressed in this analysis. This analysis will address only the repository and not the transportation routes to the site. The analysis is intended to provide the basis for: (1) Categorizing event sequences related to aircraft hazards; (2) Identifying design or operational requirements related to aircraft hazards.

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

    International Nuclear Information System (INIS)

    Heinonen, Jussi

    2014-01-01

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

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

    International Nuclear Information System (INIS)

    1978-01-01

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

  19. 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

  20. 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...

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  2. 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)

  3. 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.

  4. 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

  5. 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

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

    International Nuclear Information System (INIS)

    Husain, A.

    1984-01-01

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

  7. 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...

  8. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-08-01

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

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

    International Nuclear Information System (INIS)

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

    1994-08-01

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

  11. From applicant to designated

    DEFF Research Database (Denmark)

    Hansen, Louise Ejgod

    The paper focuses on the challenges concerning strategic leadership of European Capitals of Culture (ECoC) during the transition from candidate city to designated city. The paper presents an analysis of the current situation in the city of Aarhus, Denmark that was designated in 2012 for the ECo......C-title in 2017. In the period after the designation the Foundation Aarhus 2017 was established with the appointment of the board in June 2013 and with the administrative and programme manager in place during the summer of 2013. Prior to this the development of the programme including strategic cultural policy...

  12. 77 FR 23241 - Lock+ Hydro Friends Fund XXX, LLC; Notice of Intent To File License Application, Filing of Pre...

    Science.gov (United States)

    2012-04-18

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

  13. 47 CFR 25.137 - Application requirements for earth stations operating with non-U.S. licensed space stations.

    Science.gov (United States)

    2010-10-01

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

  14. 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

  15. 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

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

    International Nuclear Information System (INIS)

    Pittiglio, C.L. Jr.

    1987-08-01

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

  17. Digital system design and application with VHDL and FPGA

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Gang; Jo, Yun Seok

    2002-09-15

    Contents of this book are digital system design modeling using VHDL like VHDL basics, writing VHDL for synthesis and VHDL environments, combinational logic design such as 4bit full adder and parallel combinational BCD multiplier sequential logic design, including Johnson counter, stop-watch, Dice game, traffic light controller, elevator controller and alarm clock, complex applications design like dynamic input/output circuit, PS/2 keyboard, LCD, VGA and UART. It also has a supplement about free license for ModelSim and Guide for 3100 X board user.

  18. Digital system design and application with VHDL and FPGA

    International Nuclear Information System (INIS)

    Lee, Gang; Jo, Yun Seok

    2002-09-01

    Contents of this book are digital system design modeling using VHDL like VHDL basics, writing VHDL for synthesis and VHDL environments, combinational logic design such as 4bit full adder and parallel combinational BCD multiplier sequential logic design, including Johnson counter, stop-watch, Dice game, traffic light controller, elevator controller and alarm clock, complex applications design like dynamic input/output circuit, PS/2 keyboard, LCD, VGA and UART. It also has a supplement about free license for ModelSim and Guide for 3100 X board user.

  19. 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.)

  20. 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

  1. Designing scientific applications on GPUs

    CERN Document Server

    Couturier, Raphael

    2013-01-01

    Many of today's complex scientific applications now require a vast amount of computational power. General purpose graphics processing units (GPGPUs) enable researchers in a variety of fields to benefit from the computational power of all the cores available inside graphics cards.Understand the Benefits of Using GPUs for Many Scientific ApplicationsDesigning Scientific Applications on GPUs shows you how to use GPUs for applications in diverse scientific fields, from physics and mathematics to computer science. The book explains the methods necessary for designing or porting your scientific appl

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

    International Nuclear Information System (INIS)

    Hill, Brittain

    2014-01-01

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

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

    International Nuclear Information System (INIS)

    Goldstein, L.; Malone, J.

    2000-01-01

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

  4. SOFTWARE FOR DESIGNING PARALLEL APPLICATIONS

    Directory of Open Access Journals (Sweden)

    M. K. Bouza

    2017-01-01

    Full Text Available The object of research is the tools to support the development of parallel programs in C/C ++. The methods and software which automates the process of designing parallel applications are proposed.

  5. 18 CFR 16.10 - Information to be provided by an applicant for new license: Filing requirements.

    Science.gov (United States)

    2010-04-01

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

  6. 75 FR 3261 - Powertech (USA) Inc.; Dewey-Burdock Project; New Source Material License Application; Notice of...

    Science.gov (United States)

    2010-01-20

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

  7. 76 FR 40905 - Turnagain Arm Tidal Electric Energy Project; Notice of Intent To File License Application, Filing...

    Science.gov (United States)

    2011-07-12

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

  8. 77 FR 58370 - Pennamaquan Tidal Power LLC; Notice of Intent To File License Application, Filing of Pre...

    Science.gov (United States)

    2012-09-20

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

  9. 76 FR 81992 - PPL Bell Bend, LLC; Combined License Application for Bell Bend Nuclear Power Plant; Exemption

    Science.gov (United States)

    2011-12-29

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

  10. 75 FR 51451 - Erie Boulevard Hydropower, L.P.; Notice of Intent To File License Application, Filing of Pre...

    Science.gov (United States)

    2010-08-20

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

  11. SMES, design and applications

    International Nuclear Information System (INIS)

    Juengst, K.P.

    1993-01-01

    Present days' electric power supply of many countries are mature densely meshed systems delivering electric energy at nearly any place, at any time, of any amount, and at a high level of quality. As there is little energy stored intrinsically in the electric system, load variations have to be followed by control of the generation system. At present e.g. fast changes are handled through a permanent reserve of 2.5 % in the power plants. This reserve must be activated within 5 s. The system, however, may have to face more difficulties in future due to trends on either side of suppliers and consumers of electric power. The power production becomes more complex, in some countries the distances between production and consumption may grow, there will be more competition among suppliers, the acceptance of new power stations and transmission lines is uncertain, industry expands at places with insufficient infrastructure, and more industrial customers need high power quality. A way out can be offered by application of SMES, e.g. a reasonable way to keep power quality is to add more storage of energy in a rapidly and easily available and effective form. The SMES system (Superconducting Magnetic Energy Storage), therefore, has found renewed interest. The special features of SMES are highly attractive such as direct storage of electric energy, high power extraction out of little stored energy, capability of frequent and even deep discharges, response to demand within milliseconds, simultaneous supply of active and reactive power, long lifetime, and no environmental problems. (orig.)

  12. 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)

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

    International Nuclear Information System (INIS)

    J.A. McClure

    2004-01-01

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

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

    Science.gov (United States)

    Minkov, V; Klammer, H; Brix, G

    2017-07-01

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

  15. A Robust Design Applicability Model

    DEFF Research Database (Denmark)

    Ebro, Martin; Lars, Krogstie; Howard, Thomas J.

    2015-01-01

    to be applicable in organisations assigning a high importance to one or more factors that are known to be impacted by RD, while also experiencing a high level of occurrence of this factor. The RDAM supplements existing maturity models and metrics to provide a comprehensive set of data to support management......This paper introduces a model for assessing the applicability of Robust Design (RD) in a project or organisation. The intention of the Robust Design Applicability Model (RDAM) is to provide support for decisions by engineering management considering the relevant level of RD activities...

  16. 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)

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

    International Nuclear Information System (INIS)

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

    1985-02-01

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

  18. Designing and Programming CICS Applications

    CERN Document Server

    Horswill, John

    2011-01-01

    CICS is an application server that delivers industrial-strength, online transaction management for critical enterprise applications. Proven in the market for over 30 years with many of the world's leading businesses, CICS enables today's customers to modernize and extend their applications to take advantage of the opportunities provided by e-business while maximizing the benefits of their existing investments. Designing and Programming CICS Applications will benefit a diverse audience. It introduces new users of IBM's mainframe (OS/390) to CICS features. It shows experienced users how t

  19. Application of discrete event simulation to MRS design

    International Nuclear Information System (INIS)

    Bali, M.; Standley, W.

    1993-01-01

    The application of discrete event simulation to the Monitored, Retrievable Storage (MRS) material handling operations supported the MRS conceptual design effort and established a set of tools for use during MRS detail design and license application. The effort to develop a design analysis tool to support the MRS project started in 1991. The MRS simulation has so far identified potential savings and suggested methods of improving operations to enhance throughput. Immediately, simulation aided the MRS conceptual design effort through the investigation of alternative cask handling operations and the sizing and sharing of expensive equipment. The simulation also helped analyze the operability of the current design of MRS under various waste acceptance scenarios. Throughout the simulation effort, the model development and experimentation resulted in early identification and resolution of several design and operational issues

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  1. The safety case in support of the license application of the surface repository of low-level waste in Dessel, Belgium

    International Nuclear Information System (INIS)

    Wacquier, William; Cool, Wim

    2014-01-01

    The modern concept of the safety case, developed by the OECD/NEA for geological repositories of high- and medium-level waste has been successfully applied by ONDRAF/ NIRAS for a surface repository for Category A waste (i.e. low-level waste) in Belgium in the current project phase 2006-2012. This resulted in the submission on 31 January 2013 by ONDRAF/NIRAS of an application for a 'construction and operation license' to the safety authorities. The benefits of using the notion of the safety case have been that: i) safety has been incorporated in an integrated manner within all assessment basis, design and safety assessment activities; ii) the process of development of the license application has gained in clarity and traceability; iii) the documentation of the license application contains multiple lines of argumentation for safety rather than argumentation based only on quantitative radiological impact calculations. To offer a comprehensive view on the safety argumentation and its development, it has been found useful to develop the argumentation not only along a safety statements structure but also along the safety report structure. (authors)

  2. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

  4. 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

  5. Automation of the DoD Export License Application Review Process

    National Research Council Canada - National Science Library

    Young, Shelton

    2002-01-01

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

  6. 78 FR 30914 - Grand River Dam Authority Notice of Application for Temporary Variance of License and Soliciting...

    Science.gov (United States)

    2013-05-23

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

  7. 77 FR 39675 - Applications for Licensing as a Non-Leveraged Rural Business Investment Company Under the Rural...

    Science.gov (United States)

    2012-07-05

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

  8. 78 FR 4467 - UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3...

    Science.gov (United States)

    2013-01-22

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

  9. 76 FR 81994 - UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit...

    Science.gov (United States)

    2011-12-29

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

  10. 76 FR 11522 - In the Matter of Progress Energy Florida, Inc. (Combined License Application, Levy County Nuclear...

    Science.gov (United States)

    2011-03-02

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

  11. 75 FR 69063 - Port Bailey Wild Enterprises, LLC; PB Energy, Inc.; Notice of Application for Transfer of License...

    Science.gov (United States)

    2010-11-10

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

  12. 78 FR 61984 - Copper Valley Electric Association, Inc.; Notice of Application To Amend License and Accepted for...

    Science.gov (United States)

    2013-10-09

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

  13. 78 FR 14528 - Mayo Hydropower, LLC, Avalon Hydropower, LLC; Notice of Application for Transfer of License, and...

    Science.gov (United States)

    2013-03-06

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

  14. 78 FR 5196 - Notice of Invitation To Participate; Exploration for Coal in Colorado License Application COC-75642

    Science.gov (United States)

    2013-01-24

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

  15. 76 FR 55701 - Notice of Invitation to Participate; Exploration for Coal in Colorado License Application COC-74895

    Science.gov (United States)

    2011-09-08

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

  16. 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)

  17. Geosynthetic applications in landfill design

    International Nuclear Information System (INIS)

    Alshunnar, I.S.; Afifi, S.S.; Tiseo, B.

    1996-01-01

    Landfills are designed to contain waste and to provide protection against discharges of leachate into the environment. Main components of a landfill include a liner system, a leachate collection system, and a cover system. Traditional designs have typically incorporated clay soils for containment and sands with embedded piping for leachate collection. As a result of recent advances in design, geosynthetic materials are now widely used for components. While these materials present cost and feasibility advantages, they also pose significant challenges in stability evaluations, handing during installation, and quality assurance. This paper presents an overview of applications of geosynthetics in design and construction, including: Advantages, disadvantages, design criteria, possible economic benefits of various systems, and related construction considerations. 2 figs., 1 tab

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

    International Nuclear Information System (INIS)

    1976-06-01

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

  19. 47 CFR 97.21 - Application for a modified or renewed license grant.

    Science.gov (United States)

    2010-10-01

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

  20. 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

  1. RFID design fundamentals and applications

    CERN Document Server

    Lozano-Nieto, Albert

    2010-01-01

    RFID is an increasingly pervasive tool that is now used in a wide range of fields. It is employed to substantiate adherence to food preservation and safety standards, combat the circulation of counterfeit pharmaceuticals, and verify authenticity and history of critical parts used in aircraft and other machinery-and these are just a few of its uses. Goes beyond deployment, focusing on exactly how RFID actually worksRFID Design Fundamentals and Applications systematically explores the fundamental principles involved in the design and characterization of RFID technologies. The RFID market is expl

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

    International Nuclear Information System (INIS)

    Schneidesch, C.R.; Zhang Jinzhao

    2004-01-01

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

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

    International Nuclear Information System (INIS)

    Tanguy, Loic

    2014-01-01

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

  4. 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...

  5. 76 FR 77565 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-12-13

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

  6. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1998-12-01

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

  8. 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

  9. 75 FR 54330 - Intent To Grant an Exclusive Field of Use License of a U.S. Government-Owned Patent Application

    Science.gov (United States)

    2010-09-07

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

  10. 75 FR 39668 - Intent To Grant a Field of Use Exclusive License of a U.S. Government-Owned Patent Application

    Science.gov (United States)

    2010-07-12

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

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

    Directory of Open Access Journals (Sweden)

    Geum-Hee Jeong

    2005-06-01

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

  12. Multiscale Model Simulations of Temperature and Relative Humidity for the License Application of the Proposed Yucca Mountain Repository

    Science.gov (United States)

    Buscheck, T.; Glascoe, L.; Sun, Y.; Gansemer, J.; Lee, K.

    2003-12-01

    ; these variables are determined every 20 m for each emplacement drift in the repository. The MSTHM accounts for 3-D drift-scale and mountain-scale heat flow and captures the influence of the key engineering-design variables and natural-system factors affecting TH conditions in the emplacement drifts and adjoining host rock. Presented is a synopsis of recent MSTHM calculations conducted to support the Total System Performance Assessment for the License Application (TSPA-LA). This work was performed under the auspices of the U.S. Department of Energy by University of California Lawrence Livermore National Laboratory under contract No. W-7405-Eng-48.

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

    International Nuclear Information System (INIS)

    Xu Guoqing

    2014-01-01

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

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

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

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

  15. 76 FR 52699 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-08-23

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

  16. 75 FR 61521 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-10-05

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

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

    International Nuclear Information System (INIS)

    1987-01-01

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

  18. 76 FR 73727 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-11-29

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

  19. 76 FR 61391 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-10-04

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

  20. 76 FR 39136 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-07-05

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

  1. 75 FR 37471 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-06-29

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

  2. 75 FR 48370 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-08-10

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

  3. 47 CFR 74.113 - Supplementary reports with application for renewal of license.

    Science.gov (United States)

    2010-10-01

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

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

    International Nuclear Information System (INIS)

    Bassin, N.

    1984-10-01

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

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

    International Nuclear Information System (INIS)

    1981-06-01

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

  6. 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

  7. 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

  8. Short Pulse Laser Applications Design

    International Nuclear Information System (INIS)

    Town, R.J.; Clark, D.S.; Kemp, A.J.; Lasinski, B.F.; Tabak, M.

    2008-01-01

    We are applying our recently developed, LDRD-funded computational simulation tool to optimize and develop applications of Fast Ignition (FI) for stockpile stewardship. This report summarizes the work performed during a one-year exploratory research LDRD to develop FI point designs for the National Ignition Facility (NIF). These results were sufficiently encouraging to propose successfully a strategic initiative LDRD to design and perform the definitive FI experiment on the NIF. Ignition experiments on the National Ignition Facility (NIF) will begin in 2010 using the central hot spot (CHS) approach, which relies on the simultaneous compression and ignition of a spherical fuel capsule. Unlike this approach, the fast ignition (FI) method separates fuel compression from the ignition phase. In the compression phase, a laser such as NIF is used to implode a shell either directly, or by x rays generated from the hohlraum wall, to form a compact dense (∼300 g/cm 3 ) fuel mass with an areal density of ∼3.0 g/cm 2 . To ignite such a fuel assembly requires depositing ∼20kJ into a ∼35 (micro)m spot delivered in a short time compared to the fuel disassembly time (∼20ps). This energy is delivered during the ignition phase by relativistic electrons generated by the interaction of an ultra-short high-intensity laser. The main advantages of FI over the CHS approach are higher gain, a lower ignition threshold, and a relaxation of the stringent symmetry requirements required by the CHS approach. There is worldwide interest in FI and its associated science. Major experimental facilities are being constructed which will enable 'proof of principle' tests of FI in integrated subignition experiments, most notably the OMEGA-EP facility at the University of Rochester's Laboratory of Laser Energetics and the FIREX facility at Osaka University in Japan. Also, scientists in the European Union have recently proposed the construction of a new FI facility, called HiPER, designed to

  9. 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

  10. 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)

  11. 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)

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

    Science.gov (United States)

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

    2016-01-01

    Experimental studies suggest a relationship between pesticide exposure and renal impairment, but epidemiological evidence is limited. We evaluated the association between exposure to 39 specific pesticides and end-stage renal disease (ESRD) incidence in the Agricultural Health Study, a prospective cohort study of licensed pesticide applicators in Iowa and North Carolina. Via linkage to the US Renal Data System, we identified 320 ESRD cases diagnosed between enrolment (1993-1997) and December 2011 among 55 580 male licensed pesticide applicators. Participants provided information on use of pesticides via self-administered questionnaires. Lifetime pesticide use was defined as the product of duration and frequency of use and then modified by an intensity factor to account for differences in pesticide application practices. Cox proportional hazards models, adjusted for age and state, were used to estimate associations between ESRD and: (1) ordinal categories of intensity-weighted lifetime use of 39 pesticides, (2) poisoning and high-level pesticide exposures and (3) pesticide exposure resulting in a medical visit or hospitalisation. Positive exposure-response trends were observed for the herbicides alachlor, atrazine, metolachlor, paraquat, and pendimethalin, and the insecticide permethrin. More than one medical visit due to pesticide use (HR=2.13; 95% CI 1.17 to 3.89) and hospitalisation due to pesticide use (HR=3.05; 95% CI 1.67 to 5.58) were significantly associated with ESRD. Our findings support an association between ESRD and chronic exposure to specific pesticides, and suggest pesticide exposures resulting in medical visits may increase the risk of ESRD. Clinicaltrials.gov NCT00352924. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

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

    Energy Technology Data Exchange (ETDEWEB)

    D. L. Fillmore

    2003-10-01

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

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

    International Nuclear Information System (INIS)

    1988-01-01

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

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

    International Nuclear Information System (INIS)

    1987-01-01

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

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

    Science.gov (United States)

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

    2007-01-01

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

  18. 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

  19. License renewal

    International Nuclear Information System (INIS)

    Newberry, S.

    1993-01-01

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

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  1. Biomedical Optical Imaging Technologies Design and Applications

    CERN Document Server

    2013-01-01

    This book provides an introduction to design of biomedical optical imaging technologies and their applications. The main topics include: fluorescence imaging, confocal imaging, micro-endoscope, polarization imaging, hyperspectral imaging, OCT imaging, multimodal imaging and spectroscopic systems. Each chapter is written by the world leaders of the respective fields, and will cover: principles and limitations of optical imaging technology, system design and practical implementation for one or two specific applications, including design guidelines, system configuration, optical design, component requirements and selection, system optimization and design examples, recent advances and applications in biomedical researches and clinical imaging. This book serves as a reference for students and researchers in optics and biomedical engineering.

  2. 34 CFR 395.17 - Suspension of designation as State licensing agency.

    Science.gov (United States)

    2010-07-01

    ... protection of Federal property on which vending machines subject to the requirements of § 395.32 are located in the State. Upon the suspension of such designation, vending machine income from vending machines... maintenance, operation and protection of the Federal property on which such vending machines are located...

  3. Application architecture for .NET designing applications and services

    CERN Document Server

    Microsoft. Redmond

    2003-01-01

    Get expert architectural and design-level guidance for building distributed solutions with the Microsoft® .NET Framework-learning how to synthesize your knowledge of application development, servers, and infrastructure and business requirements. This guide assumes you are familiar with .NET component development and the basic principles of a layered distributed application design. It examines architectural issues and solution design for a range of project stakeholders-whether you build and design applications and services, recommend appropriate technologies and products for applications and s

  4. Design research and industrial applicability

    DEFF Research Database (Denmark)

    Andreasen, Mogens Myrup

    1997-01-01

    Imprinted paper (copies of overheads in English) on the nature of design research, the transformation process for industrial utilization and the challenges of ENDREA from industry.......Imprinted paper (copies of overheads in English) on the nature of design research, the transformation process for industrial utilization and the challenges of ENDREA from industry....

  5. Safety culture for engineering companies. Licensing and design bases for Cofrentes NPP

    International Nuclear Information System (INIS)

    Nhorte Gomez, M.D.

    1994-01-01

    Safety culture must be given higher priority by all organisations. It must not be considered a separate concept, attributable to just one particular organisation, or a single responsible party. It is important to apply this criterion throughout the different phases of a nuclear power plant project (design, construction, commissioning and operation) without becoming isolated or dissociated. Nevertheless, it is absolutely essential to apply and consider it during operation, so to ensure highest possible safety standards. Consideration must also be given to the interfaces and interconnections between the different parties involved in the project (Owner of the NPP, Main Engineering Company, Main Supplier, Regulatory Body, etc) to build a SAFETY CULTURE in a collective and effective way. In applying the safety culture, an engineering company emphasises the following concepts: - Personal dedication and sense of responsibility in all those involved in any activity related to the safety of Nuclear Power Plants. - Clearly defined and readily accessible areas of responsibility and channels of communication - Strict adherence to procedures - Internal review of activities (Design review) (Author)

  6. Designing proteins for therapeutic applications.

    Science.gov (United States)

    Lazar, Greg A; Marshall, Shannon A; Plecs, Joseph J; Mayo, Stephen L; Desjarlais, John R

    2003-08-01

    Protein design is becoming an increasingly useful tool for optimizing protein drugs and creating novel biotherapeutics. Recent progress includes the engineering of monoclonal antibodies, cytokines, enzymes and viral fusion inhibitors.

  7. 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.

  8. 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)

  9. 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

  10. Designing Inclusive Systems Designing Inclusion for Real-world Applications

    CERN Document Server

    Clarkson, John; Robinson, Peter; Lazar, Jonathan; Heylighen, Ann

    2012-01-01

    The Cambridge Workshops on Universal Access and Assistive Technology (CWUAAT) are a series of workshops held at a Cambridge University College every two years. The workshop theme: “Designing inclusion for real-world applications” refers to the emerging potential and relevance of the latest generations of inclusive design thinking, tools, techniques, and data, to mainstream project applications such as healthcare and the design of working environments. Inclusive Design Research involves developing tools and guidance enabling product designers to design for the widest possible population, for a given range of capabilities. There are five main themes: •Designing for the Real-World •Measuring Demand And Capabilities •Designing Cognitive Interaction with Emerging Technologies •Design for Inclusion •Designing Inclusive Architecture In the tradition of CWUAAT, we have solicited and accepted contributions over a wide range of topics, both within individual themes and also across the workshop’s scope. ...

  11. Smart metering design and applications

    CERN Document Server

    Weranga, K S K; Chandima, D P

    2013-01-01

    Taking into account the present day trends and the requirements, this Brief focuses on smart metering of electricity for next generation energy efficiency and conservation. The contents include discussions on the smart metering concepts and existing technologies and systems as well as design and implementation of smart metering schemes together with detailed examples.

  12. 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...

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

    International Nuclear Information System (INIS)

    1994-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

  16. Heterogeneous Catalysis: Understanding for Designing, and Designing for Applications

    OpenAIRE

    Corma Canós, Avelino

    2016-01-01

    Despite the introduction of high-throughput and combinatorial methods that certainly can be useful in the process of catalysts optimization, it is recognized that the generation of fundamental knowledge at the molecular level is key for the development of new concepts and for reaching the final objective of solid catalysts by design … Corma Canós, A. (2016). Heterogeneous Catalysis: Understanding for Designing, and Designing for Applications. Angewandte Chemie International Edition. 55(21)...

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

    International Nuclear Information System (INIS)

    Olsson, Olle

    2014-01-01

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

  18. Optical design applications for enhanced illumination performance

    Science.gov (United States)

    Gilray, Carl; Lewin, Ian

    1995-08-01

    Nonimaging optical design techniques have been applied in the illumination industry for many years. Recently however, powerful software has been developed which allows accurate simulation and optimization of illumination devices. Wide experience has been obtained in using such design techniques for practical situations. These include automotive lighting where safety is of greatest importance, commercial lighting systems designed for energy efficiency, and numerous specialized applications. This presentation will discuss the performance requirements of a variety of illumination devices. It will further cover design methodology and present a variety of examples of practical applications for enhanced system performance.

  19. 78 FR 29391 - Luminant Generation Company, LLC; Combined License Application for Comanche Peak Nuclear Power...

    Science.gov (United States)

    2013-05-20

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

  20. 78 FR 36014 - Deepwater Port License Application: Liberty Natural Gas, LLC, Port Ambrose Deepwater Port

    Science.gov (United States)

    2013-06-14

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

  1. 75 FR 32450 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2010-06-08

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

  2. 75 FR 57266 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2010-09-20

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

  3. Composite materials design and applications

    CERN Document Server

    Gay, Daniel; Tsai, Stephen W

    2002-01-01

    PART ONE. PRINCIPLES OF CONSTRUCTIONCOMPOSITE MATERIALS, INTEREST AND PROPERTIESWhat is Composite Material Fibers and MatrixWhat can be Made Using Composite Materials?Typical Examples of Interest on the Use of Composite MaterialsExamples on Replacing Conventional Solutions with CompositesPrincipal Physical PropertiesFABRICATION PROCESSESMolding ProcessesOther Forming ProcessesPractical Hints in the Manufacturing ProcessesPLY PROPERTIESIsotropy and AnisotropyCharacteristics of the Reinforcement-Matrix MixtureUnidirectional PlyWoven FabricsMats and Reinforced MatricesMultidimensional FabricsMetal Matrix CompositesTestsSANDWICH STRUCTURES:What is a Sandwich Structure?Simplified FlexureA Few Special AspectsFabrication and Design ProblemsNondestructive Quality ControlCONCEPTION AND DESIGNDesign of a Composite PieceThe LaminateFailure of LaminatesSizing of LaminatesJOINING AND ASSEMBLYRiveting and BoltingBondingInsertsCOMPOSITE MATERIALS AND AEROSPACE CONSTRUCTIONAircraftHelicoptersPropeller Blades for AirplanesTur...

  4. 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

  5. A conceptual toolbox for designing CSCW applications

    DEFF Research Database (Denmark)

    Bødker, Susanne; Christiansen, Ellen

    1995-01-01

    This paper presents a conceptual toolbox, developed to support the design of CSCW applications in a large Esprit project, EuroCODE. Here, several groups of designers work to investigate computer support for cooperative work in large use organizations, at the same time as they work to develop...... an open development platform for CSCW applications. The conceptual toolbox has been developed to support communication in and among these design groups, between designers and users and in future use of the open development platform. Rejecting the idea that one may design from a framework describing CSCW......, the toolbox aims to support design by doing and help bridging between work with users, technical design, and insights gained from theoretical and empirical CSCW research....

  6. Emerging memory technologies design, architecture, and applications

    CERN Document Server

    2014-01-01

    This book explores the design implications of emerging, non-volatile memory (NVM) technologies on future computer memory hierarchy architecture designs. Since NVM technologies combine the speed of SRAM, the density of DRAM, and the non-volatility of Flash memory, they are very attractive as the basis for future universal memories. This book provides a holistic perspective on the topic, covering modeling, design, architecture and applications. The practical information included in this book will enable designers to exploit emerging memory technologies to improve significantly the performance/power/reliability of future, mainstream integrated circuits. • Provides a comprehensive reference on designing modern circuits with emerging, non-volatile memory technologies, such as MRAM and PCRAM; • Explores new design opportunities offered by emerging memory technologies, from a holistic perspective; • Describes topics in technology, modeling, architecture and applications; • Enables circuit designers to ex...

  7. 76 FR 5614 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-02-01

    ... against cyber attacks up to and including the design basis threat. Part one of the proposed change is... of adequate protection against cyber attacks, up to and including the design basis threat. The... you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS...

  8. Proposed format and content of license applications for deep geologic terminal repositories for radioactive material

    International Nuclear Information System (INIS)

    1978-01-01

    Chapters are devoted to the following: introduction and general description; summary safety analysis; site characteristics; principal design criteria; repository design; operations systems; management of onsite generated waste; radiation protection; accident safety analysis; conduct of operations; operating controls and limits; and quality assurance

  9. 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

  10. 76 FR 67723 - CRD Hydroelectric, LLC; Notice of Application To Amend License and Accepted for Filing...

    Science.gov (United States)

    2011-11-02

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

  11. Design and Analysis of Web Application Frameworks

    DEFF Research Database (Denmark)

    Schwarz, Mathias Romme

    -state manipulation vulnerabilities. The hypothesis of this dissertation is that we can design frameworks and static analyses that aid the programmer to avoid such errors. First, we present the JWIG web application framework for writing secure and maintainable web applications. We discuss how this framework solves...... some of the common errors through an API that is designed to be safe by default. Second, we present a novel technique for checking HTML validity for output that is generated by web applications. Through string analysis, we approximate the output of web applications as context-free grammars. We model......Numerous web application frameworks have been developed in recent years. These frameworks enable programmers to reuse common components and to avoid typical pitfalls in web application development. Although such frameworks help the programmer to avoid many common errors, we nd...

  12. Designing Interactive Applications to Support Novel Activities

    Directory of Open Access Journals (Sweden)

    Hyowon Lee

    2013-01-01

    Full Text Available R&D in media-related technologies including multimedia, information retrieval, computer vision, and the semantic web is experimenting on a variety of computational tools that, if sufficiently matured, could support many novel activities that are not practiced today. Interactive technology demonstration systems produced typically at the end of their projects show great potential for taking advantage of technological possibilities. These demo systems or “demonstrators” are, even if crude or farfetched, a significant manifestation of the technologists’ visions in transforming emerging technologies into novel usage scenarios and applications. In this paper, we reflect on design processes and crucial design decisions made while designing some successful, web-based interactive demonstrators developed by the authors. We identify methodological issues in applying today’s requirement-driven usability engineering method to designing this type of novel applications and solicit a clearer distinction between designing mainstream applications and designing novel applications. More solution-oriented approaches leveraging design thinking are required, and more pragmatic evaluation criteria is needed that assess the role of the system in exploiting the technological possibilities to provoke further brainstorming and discussion. Such an approach will support a more efficient channelling of the technology-to-application transformation which are becoming increasingly crucial in today’s context of rich technological possibilities.

  13. 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

  14. 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.)

  15. Computer Applications in the Design Process.

    Science.gov (United States)

    Winchip, Susan

    Computer Assisted Design (CAD) and Computer Assisted Manufacturing (CAM) are emerging technologies now being used in home economics and interior design applications. A microcomputer in a computer network system is capable of executing computer graphic functions such as three-dimensional modeling, as well as utilizing office automation packages to…

  16. Design of hardware accelerators for demanding applications.

    NARCIS (Netherlands)

    Jozwiak, L.; Jan, Y.

    2010-01-01

    This paper focuses on mastering the architecture development of hardware accelerators. It presents the results of our analysis of the main issues that have to be addressed when designing accelerators for modern demanding applications, when using as an example the accelerator design for LDPC decoding

  17. 76 FR 4381 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-01-25

    ... proposed herein will have no impact upon the Reactor Building or AVS [Annulus Ventilation System] relative....6.10 and TS 3.6.16 maintain the required design margins of the Reactor Building and AVS for all...

  18. 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

  19. RF microwave circuit design for wireless applications

    CERN Document Server

    Rohde, Ulrich L

    2012-01-01

    Provides researchers and engineers with a complete set of modeling, design, and implementation tools for tackling the newest IC technologies Revised and completely updated, RF/Microwave Circuit Design for Wireless Applications, Second Edition is a unique, state-of-the-art guide to wireless integrated circuit design that provides researchers and engineers with a complete set of modeling, design, and implementation tools for tackling even the newest IC technologies. It emphasizes practical design solutions for high-performance devices and circuitry, incorporating ample exa

  20. 75 FR 3217 - J&T Hydro Company; H. Dean Brooks and W. Bruce Cox; Notice of Application for Transfer of License...

    Science.gov (United States)

    2010-01-20

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

  1. 75 FR 15419 - Notice of Intent To Grant Exclusive License of U.S. Patent Application No. 12/432,842 Filed April...

    Science.gov (United States)

    2010-03-29

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

  2. Active and passive beam application design guide for global application

    CERN Document Server

    Rimmer, Julian

    2015-01-01

    The Active and Passive Beam Application Design Guide is the result of collaboration by worldwide experts to give system designers a current, authoritative guide on successfully applying active and passive beam technology. Active and Passive Beam Application Design Guide provide energy-efficient methods of cooling, heating, and ventilating indoor areas, especially spaces that require individual zone control and where internal moisture loads are moderate. The systems are simple to operate, with low maintenance requirements. This book is an essential resource for consulting engineers, architects, owners, and contractors who are involved in the design, operation, and installation of these systems. Building on REHVA’s Chilled Beam Application Guidebook, this new guide provides up-to-date tools and advice for designing, commissioning, and operating chilled-beam systems to achieve a determined indoor climate, and includes examples of active and passive beam calculations and selections. Dual units (SI and I-P) are...

  3. 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)

  4. 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)

  5. CCD research. [design, fabrication, and applications

    Science.gov (United States)

    Gassaway, J. D.

    1976-01-01

    The fundamental problems encountered in designing, fabricating, and applying CCD's are reviewed. Investigations are described and results and conclusions are given for the following: (1) the development of design analyses employing computer aided techniques and their application to the design of a grapped structure; (2) the role of CCD's in applications to electronic functions, in particular, signal processing; (3) extending the CCD to silicon films on sapphire (SOS); and (4) all aluminum transfer structure with low noise input-output circuits. Related work on CCD imaging devices is summarized.

  6. 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)

  7. 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)

  8. 77 FR 9998 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2012-02-21

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

  9. 77 FR 10491 - Progress Energy Carolinas, Inc.; Notice of Application for Amendment of License and Soliciting...

    Science.gov (United States)

    2012-02-22

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

  10. 77 FR 28372 - South Carolina Public Service Authority; Notice of Application for Amendment of License and...

    Science.gov (United States)

    2012-05-14

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

  11. 77 FR 38618 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2012-06-28

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

  12. 76 FR 51016 - Idaho Power Company; Notice of Application for Amendment of License and Soliciting Comments...

    Science.gov (United States)

    2011-08-17

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

  13. 78 FR 51753 - AUC, LLC Reno Creek, In Situ Project, New Source Material License Application

    Science.gov (United States)

    2013-08-21

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

  14. 76 FR 3927 - Ameren Missouri; Combined License Application for Callaway Plant Unit 2; Exemption

    Science.gov (United States)

    2011-01-21

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

  15. 77 FR 76539 - Ameren Missouri; Combined License Application For Callaway Plant, Unit 2; Exemption

    Science.gov (United States)

    2012-12-28

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

  16. 77 FR 63301 - Juneau Hydropower, Inc.; Notice of Draft License Application and Preliminary Draft Environmental...

    Science.gov (United States)

    2012-10-16

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

  17. 76 FR 18801 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2011-04-05

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

  18. 77 FR 13369 - Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2012-03-06

    ... months'' in TS 5.5.2, ``Systems Integrity Monitoring Program,'' and TS 5.5.7, ``Ventilation Filter... from Design Basis Accident (DBA) analyses. They are prescribed by American Society of Mechanical... protective actions are initiated are not altered by the proposed changes. Sufficient equipment remains...

  19. 77 FR 50092 - Duke Energy Carolinas, LLC; Notice of Application for Amendment of License and Soliciting...

    Science.gov (United States)

    2012-08-20

    .... e. Name of Project: Catawba-Wateree Hydroelectric Project. f. Location: Lake Norman in Iredell..., Duke Energy Carolinas, LLC authorized modifications to the marina, which now consists of two multi-slip... layout is mostly similar to the originally-approved design except that the docks have shifted location...

  20. 75 FR 458 - Notice; Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2010-01-05

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

  1. Nuclear Fuel Recovery and Recycling Center. License application, PSAR, volume 1

    International Nuclear Information System (INIS)

    1976-01-01

    A summary of the location and major design features of the proposed Nuclear Fuel Recovery and Recycling Center is presented. The safety aspects of the proposed facilities and operations are summarized, taking into account possible normal and abnormal operating and environmental conditions. A chapter on site characteristics is included

  2. 75 FR 68831 - Notice; Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2010-11-09

    ..., evaluate, and mitigate cyber attacks up to and including the design basis cyber attack threat, thereby... protected from cyber attacks. The addition of the Cyber Security Plan to the Physical Security Plan will not... assurance that safety-related SSCs are protected from cyber attacks. Implementation of 10 CFR 73.54 and the...

  3. 75 FR 70032 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Science.gov (United States)

    2010-11-16

    ..., evaluate, and mitigate cyber attacks up to and including the design basis cyber attack threat, thereby... protected from cyber attacks. The implementation and incorporation of the Cyber Security Plan into the FOL...-related SSCs are protected from cyber attacks. Implementation of 10 CFR 73.54 and inclusion of the Cyber...

  4. 76 FR 20377 - Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant...

    Science.gov (United States)

    2011-04-12

    ... cyber attacks up to and including the design basis cyber attack threat, thereby achieving high assurance... attacks. The Cyber Security Plan will not alter previously evaluated Final Safety Analysis Report (FSAR... from cyber attacks. Implementation of 10 CFR 73.54 and the inclusion of a plan in the FOL do not result...

  5. 75 FR 51490 - Notice; Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2010-08-20

    ... 73.54 are to be implemented to identify, evaluate, and mitigate cyber attacks up to and including the design basis cyber attack threat, thereby achieving high assurance that CGS's digital computer and communications systems and networks are protected from cyber attacks. The CGS Cyber Security Plan will not alter...

  6. 76 FR 62862 - Notice; Applications and Amendments to Facility Operating Licenses Involving Proposed No...

    Science.gov (United States)

    2011-10-11

    ... proposed reload design or safety analysis limits for each cycle reload core. The associated margin of... limits are unaffected, and cycle specific analyses will show that the analysis limits are met, the change... and resolve requests for access to SUNSI, and motions for protective orders, in a timely fashion in...

  7. Nuclear Fuel Recovery and Recycling Center. License application, PSAR, volume 3

    International Nuclear Information System (INIS)

    1976-01-01

    Volume 3 comprises Chapter 5 which provides descriptive information on Nuclear Fuel Recovery and Recycling Center buildings and other facilities, including their locations. The design features discussed include those used to withstand environmental and accidental forces and to insure radiological protection

  8. 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.

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

    International Nuclear Information System (INIS)

    1975-01-01

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

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

    International Nuclear Information System (INIS)

    1975-01-01

    An application to construct and operate Black Fox Station, Units 1 and 2, is presented. The two BWR type reactors will have a rated core thermal power of 3579 MW(t) and a net electrical power of approximately 1150 MW(e). The facility will be located in Inola Township, 23 miles east of Tulsa on the east side of the Verdigris River in Rogers County, Oklahoma

  11. Edwin I. Hatch Nuclear Plant, Unit 2. License application, general information

    International Nuclear Information System (INIS)

    1975-01-01

    An application for a direct cycle BWR is presented. The reactor will be located about 11 miles north of Baxley, Ga., near the south bank of the Ultamaha River in Appling County close to Hatch-1 Reactor. The core thermal power level will be 2537 MW(t) and the electrical power level will be 795 MW(e). Mechanical cooling towers will be utilized

  12. Licensing in BE system code calculations. Applications and uncertainty evaluation by CIAU method

    International Nuclear Information System (INIS)

    Petruzzi, Alessandro; D'Auria, Francesco

    2007-01-01

    The evaluation of uncertainty constitutes the necessary supplement of Best Estimate (BE) calculations performed to understand accident scenarios in water cooled nuclear reactors. The needs come from the imperfection of computational tools on the one side and from the interest in using such tool to get more precise evaluation of safety margins. In the present paper the approaches to uncertainty are outlined and the CIAU (Code with capability of Internal Assessment of Uncertainty) method proposed by the University of Pisa is described including ideas at the basis and results from applications. Two approaches are distinguished that are characterized as 'propagation of code input uncertainty' and 'propagation of code output errors'. For both methods, the thermal-hydraulic code is at the centre of the process of uncertainty evaluation: in the former case the code itself is adopted to compute the error bands and to propagate the input errors, in the latter case the errors in code application to relevant measurements are used to derive the error bands. The CIAU method exploits the idea of the 'status approach' for identifying the thermal-hydraulic conditions of an accident in any Nuclear Power Plant (NPP). Errors in predicting such status are derived from the comparison between predicted and measured quantities and, in the stage of the application of the method, are used to compute the uncertainty. (author)

  13. Application and design of solar photovoltaic system

    International Nuclear Information System (INIS)

    Li Tianze; Lu Hengwei; Jiang Chuan; Hou Luan; Zhang Xia

    2011-01-01

    Solar modules, power electronic equipments which include the charge-discharge controller, the inverter, the test instrumentation and the computer monitoring, and the storage battery or the other energy storage and auxiliary generating plant make up of the photovoltaic system which is shown in the thesis. PV system design should follow to meet the load supply requirements, make system low cost, seriously consider the design of software and hardware, and make general software design prior to hardware design in the paper. To take the design of PV system for an example, the paper gives the analysis of the design of system software and system hardware, economic benefit, and basic ideas and steps of the installation and the connection of the system. It elaborates on the information acquisition, the software and hardware design of the system, the evaluation and optimization of the system. Finally, it shows the analysis and prospect of the application of photovoltaic technology in outer space, solar lamps, freeways and communications.

  14. 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

  15. Guide to request license for teletherapy practice

    International Nuclear Information System (INIS)

    2000-01-01

    In this work the steps to request license for teletherapy practice are described , among these steps they it continued it plows to request the qualified personnel's yams, the operation authorization, application purpose, license type

  16. List of Nuclear Materials Licensing Actions Received

    Data.gov (United States)

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

  17. Implantable biomedical microsystems design principles and applications

    CERN Document Server

    Bhunia, Swarup; Sawan, Mohamad

    2015-01-01

    Research and innovation in areas such as circuits, microsystems, packaging, biocompatibility, miniaturization, power supplies, remote control, reliability, and lifespan are leading to a rapid increase in the range of devices and corresponding applications in the field of wearable and implantable biomedical microsystems, which are used for monitoring, diagnosing, and controlling the health conditions of the human body. This book provides comprehensive coverage of the fundamental design principles and validation for implantable microsystems, as well as several major application areas. Each co

  18. DESIGN QUALITY IN MECHANICAL ENGINEERING APPLICATION

    Directory of Open Access Journals (Sweden)

    Ayşegül Akdogan Eker

    2010-09-01

    Full Text Available There is a close relationship between material chose and quality in mechanical engineering application like there is in all the other engineering applications. If this relation is balanced then engineering success increases. Material chose comes to fore in the design process most of the time. The two most important responsibilities of the design engineer in here is to chose suitable material and to know the production processes about design. The chose of material of a design that will fulfill the needs all through its life has great importance. It is needed to limit the material applicants by choosing the most suitable ones among variable material. Choosing materials that were examined before and whose behavior is well known provides the designer to feel confident. However since using highly successful materials would increase the competitive power of the designs; designers should follow the developments in materials and know the features of new materials. The description of these features can be interpreted within quality. Quality from the point of engineer is the total fulfillment of expectations.Engineer today are faced with very important problems such as fast technological innovations, a dynamic socio-economical environment, global rivalry. One of the life buoys they stick while trying to solve these problems is total method of quality control. Total Quality model which can provide higher competitive power compared to classical management model brings success only when applied with its whole components. "Approach toward prevention" and "measurement and statistics" have an important place among these elements. The first step of the approach toward prevention composes of design quality and Quality Function Deployment (QFD, or in other words The House of Quality method that will provide this. In this paper; considering the quality function deployment, how the chose of material are done in mechanical engineering applications will be explained.

  19. Thermoelectric nanomaterials materials design and applications

    CERN Document Server

    Koumoto, Kunihito

    2014-01-01

    Presently, there is an intense race throughout the world to develop good enough thermoelectric materials which can be used in wide scale applications. This book focuses comprehensively on very recent up-to-date breakthroughs in thermoelectrics utilizing nanomaterials and methods based in nanoscience. Importantly, it provides the readers with methodology and concepts utilizing atomic scale and nanoscale materials design (such as superlattice structuring, atomic network structuring and properties control, electron correlation design, low dimensionality, nanostructuring, etc.). Furthermore, also

  20. 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)

  1. Safety requirements applicable to the SMART design

    International Nuclear Information System (INIS)

    Seul, Kwang Won; Kim, Wee Kyong; Kim, Hho Jung

    1999-01-01

    The 330 MW thermal power of integral reactor, named SMART (System integrated Modular Advanced ReacTor), is under development at KAERI for seawater desalination application and electricity generation. The final product of nuclear desalination plant (NDP) is electricity and fresh water. Thus, in addition to the protection of the public around the plant facility from the possible release of radioactive materials, the fresh water should be prevented from radioactivity contamination. In this study, to ensure the safety of SMART reactor in the early stage of design development, the safety requirements applicable to the SMART design were investigated, based on the current regulatory requirements for the existing NPPs and the advanced light water reactor (LWR) designs. The interface requirements related to the desalination facility were also investigated, based on the recent IAEA research activities pertaining to the NDP. As a result, it was found that the current regulatory requirements and guidance for the existing NPPs and advanced LWR designs are applicable to the SMART design and its safety evaluation. However, the safety requirements related to the SMART-specific design and the desalination plant are needed to develop in the future to assure the safety of the SMART reactor

  2. 75 FR 4571 - Government-Owned Inventions; Availability for Licensing

    Science.gov (United States)

    2010-01-28

    .... Applications: Therapies for tumors associated with NF1 (including brain and peripheral nervous system tumors...-US-01). Licensing Status: Available for licensing. Licensing Contact: Patrick P. McCue, Ph.D.; 301...

  3. Functionalized conjugated polyelectrolytes design and biomedical applications

    CERN Document Server

    Wang, Shu

    2014-01-01

    Functionalized Conjugated Polyelectrolytes presents a comprehensive review of these polyelectrolytes and their biomedical applications. Basic aspects like molecular design and optoelectronic properties are covered in the first chapter. Emphasis is placed on the various applications including sensing (chemical and biological), disease diagnosis, cell imaging, drug/gene delivery and disease treatment. This book explores a multi-disciplinary topic of interest to researchers working in the fields of chemistry, materials, biology and medicine. It also offers an integrated perspective on both basic research and application issues. Functionalized conjugated polyelectrolyte materials, which have already drawn considerable interest, will become a major new direction for biomedicine development.

  4. 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)

  5. Clinch River Breeder Reactor Plant. License application, statement of general information

    International Nuclear Information System (INIS)

    1975-01-01

    Application is made for a reactor facility consisting of a liquid metal cooled reactor and steam generator system, a steam turbine driven electric generating system, electrical switchyard, and related auxiliaries and supporting structures. The primary system is located in an inert atmosphere in shielded vaults within a containment structure. Sodium coolant is used to remove heat from the core and radial blanket. Heat from the primary sodium is transferred in heat exchangers to non radioactive sodium which is used to convert feed-water into steam which is superheated to drive a tandem-compound generator. A single shaft multi-stage turbine generator produces 380 MW(e) with steam conditions of 1450 psig at 900 0 F. Fuel is sintered ceramic pellets of mixed uranium-plutonium oxides encapsulated in stainless steel. There are 198 fuel assemblies with each assembly consisting of 217 fuel rods placed in a hexagonal channel. Plutonium enrichment ranges from 1817 to 32.0 percent by weight. Axial blanket sections contain depleted UO 2 with 99.8 percent 238 U and 0.2 percent 235 U by weight. The proposed location of the plant is within the corporate limits of the city of Oak Ridge in Roane County, Tennessee. (U.S.)

  6. Clinical application analysis of andrographolide total ester sulfonate injection, a traditional Chinese medicine licensed in China.

    Science.gov (United States)

    Zhao, Ying; Huang, Pu; Chen, Zhe; Zheng, Si-Wei; Yu, Jin-Yang; Shi, Chen

    2017-04-01

    Andrographolide total ester sulfonate (ATES) injection is one of the products of traditional Chinese medicine (TCM) currently used against viral infection in China. ATES injection was approved for manufacturing and marketing in January 2002. It is indicated for acute respiratory infections, tonsillitis, chronic obstructive pulmonary disease, influenza, foot and mouth disease, bronchiolitis, herpangina, mumps, infectious mononucleosis and psychosis. However, its usage also carries risk. We investigated the use of ATES at the Wuhan Union Hospital from January 2014 to December 2014 and evaluated its real-world clinical application using the hospital centralized monitoring method. A total of 848 cases were enrolled in this study. In these cases, it was mainly used for postoperative anti-inflammation and treating upper respiratory infection, pneumonia and bronchitis. Among them, 39.86% were contraindicated. Irregular medication of adults and children accounted for 1.91% and 23.38%, respectively. Improper choice of solvent accounted for 3.18%. The choice of intravenous drip versus aerosol inhalation was reasonable. A case of adverse events (AEs) was observed in the monitoring period, and the incidence of adverse drug reaction (ADR) of ATES injection was 0.12%. ATES injection in our hospital is relatively safe with a low incidence of adverse reactions. The study assesses the clinical usage and adverse reactions of ATES injection, and provides suggestions for rational use in clinical practice.

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. Licensing safety critical software

    International Nuclear Information System (INIS)

    Archinoff, G.H.; Brown, R.A.

    1990-01-01

    Licensing difficulties with the shutdown system software at the Darlington Nuclear Generating Station contributed to delays in starting up the station. Even though the station has now been given approval by the Atomic Energy Control Board (AECB) to operate, the software issue has not disappeared - Ontario Hydro has been instructed by the AECB to redesign the software. This article attempts to explain why software based shutdown systems were chosen for Darlington, why there was so much difficulty licensing them, and what the implications are for other safety related software based applications

  17. On the design of application protocols

    NARCIS (Netherlands)

    van Sinderen, Marten J.

    1995-01-01

    In the last decades, much effort has been spent on the design and provision of sophisticated communication infrastructures. The development of end-user oriented distributed system applications, leaning on top of these communication infrastructures, so far has attracted little attention. This is

  18. 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)

  19. 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

  20. 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