WorldWideScience

Sample records for siting licensing development

  1. Site Specific Vendor's License

    Data.gov (United States)

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

  2. Post-TMI developments in U.S. nuclear power siting and licensing policies

    International Nuclear Information System (INIS)

    Rowden, M.A.

    1981-10-01

    The regulatory consequences of the Three Mile Island accident continue to exert a dominating influence on the American nuclear power programme, in particular on siting and licensing policies. The major regulatory and legislative measures are discussed and also listed in chronological order and summarized in the Appendices to the paper. These summaries illustrate the shift in focus of the regulatory measures from an initial emphasis on licensing constraints to a change so as to expedite the licensing procedure. (NEA) [fr

  3. Licensing plan for UMTRA project disposal sites

    International Nuclear Information System (INIS)

    1993-09-01

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

  4. Mock Site Licensing Demonstration Project. Final report

    International Nuclear Information System (INIS)

    Roop, R.D.

    1986-06-01

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

  5. Sellafield - a nuclear licensed site

    International Nuclear Information System (INIS)

    Bloom, Phillipa.

    1987-01-01

    The report is based on the experience gained when visiting the Exhibition Centre at the BNFL Sellafield site and joining the hour-long coach trip round the site. The sights are recorded and a description given of the processes undertaken at Sellafield to reprocess the Magnox fuel and store the spent fuel from AGR reactors. The purpose of the main plant building, and the passage of the spent fuel through the various processes is described. Criticism is made of the safety record at Sellafield and a full and open debate on nuclear power is called for. (UK)

  6. Cask development, testing, and licensing

    International Nuclear Information System (INIS)

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

    1986-01-01

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

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

    International Nuclear Information System (INIS)

    Vos, Marcel de

    2011-01-01

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

  8. Development of joint regulatory guidance on the management of higher activity radioactive wastes on nuclear licensed sites - 16095

    International Nuclear Information System (INIS)

    Bacon, Mick; Ilett, Doug; Whittall, Andy

    2009-01-01

    In 2006 the UK Government's response (1) to recommendations by its Committee on Radioactive Waste Management (CoRWM) established, in England and Wales, that geological disposal, supported by safe and secure interim storage, is the preferred route for the long-term management of higher-activity radioactive waste (i.e. that which is not suitable for near-surface disposal). It also gave the responsibility for delivering the programme for a deep geological repository to the Nuclear Decommissioning Authority (NDA). The Scottish Government has a policy of long term, near site, near surface safe and secure interim storage. To support the open and transparent approach promised by Government, the Health and Safety Executive (HSE), the Environment Agency and the Scottish Environment Protection Agency (SEPA) are developing joint guidance on the management of higher-activity radioactive waste to explain regulatory objectives in securing safe and secure interim storage and the associated management of radioactive wastes. The guidance comes in two parts: - Guidance on the regulatory process; - Technical guidance modules. The guidance promotes a cradle to grave approach to radioactive waste management and by aligning the regulatory interests of environmental and safety regulators it delivers one of the Government's 'Better Regulation' objectives. This paper describes the process by which the joint guidance was produced with particular emphasis on stakeholder engagement. It describes the key features of the guidance, including the concept of the radioactive waste management case (RWMC). Finally the problems encountered with dissemination and implementation are discussed together with measures taken by the regulators to improve these aspects. (1) : UK Government and the devolved administrations, 'Response to the Report and Recommendations from the Committee on Radioactive Waste Management (CoRWM)', (PB 12303) October 2006. www

  9. 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

  10. EPA-developed, patented technologies related to contaminated sites and hazardous substances that are available for licensing

    Data.gov (United States)

    U.S. Environmental Protection Agency — Under the Federal Technology Transfer Act (FTTA), Federal Agencies can patent inventions developed during the course of research. These technologies can then be...

  11. Site development

    International Nuclear Information System (INIS)

    Noack, J.

    1975-01-01

    The subject of this paper is a general view over all necessary considerations to develop the site after it has been chosen and before starting with the construction of a nuclear power plant. (orig./RW) [de

  12. 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

  13. Site development

    International Nuclear Information System (INIS)

    Gaynor, R.K.

    1989-01-01

    Development of a low-level radioactive waste land disposal facility is little different than any industrial development of similar scope. Consideration must be made for normal business and operations management, security, facility maintenance, traffic control and necessary amenities for personnel. The item specific to the low-level waste site is the handling of radioactive waste materials and the regulatory and environmental protection procedures that must be planned for and accomodated in the site design and development. Each of these elements and the facility as a whole must be designed to be compatible with local land use plans, available transportation and support services, and the social and economic goals of the local community. Plans should also be made for quality control and orderly construction. This chapter deals with those aspects of the facility, its design and construction which are integral parts to the overall performance of the site

  14. The site-characterization plan and its role in resolving siting and licensing issues

    International Nuclear Information System (INIS)

    Hanlon, C.L.

    1986-01-01

    As required by the Nuclear Waste Policy Act and the Nuclear Regulatory Commission (NRC) in 10 CFR Part 60, the Department of Energy is preparing plans for conducting site characterization at three candidate sites. Prepared according to a detailed annotated outline that is based on the NRC's Regulatory Guide 4.17, these plans will present the information collected to date about the geologic, hydrologic, geochemical, geoengineering, and climatic conditions of each site; describe the design of the repository and the waste package; and discuss the site-characterization program. The most important portions of the plan will be the strategy for resolving siting and licensing issues and the description of the testing and analysis program to be followed in resolving these issues. The issues-resolution strategy consists of identifying issues and the associated information needs; allocating performance goals for various components of the repository system; developing a testing plan to gather the necessary information; gathering and analyzing the information; and documenting the results for use in site selection and licensing. The issues-resolution strategy will allow the Department to define all of the issues that must be resolved in order to demonstrate compliance with applicable regulations and to specify the information needed to resolve these issues. It will provide a consistent framework and establish priorities for the Department's site-characterization effort for the next several years

  15. Nebraska withdraws its intent to deny site license

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

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

  16. Completion of decommissioning: Monitoring for site release and license termination

    International Nuclear Information System (INIS)

    Boing, L.E.

    1997-01-01

    To request termination of a license upon completion of dismantling or decommissioning activities, documenting any residual radioactivity to show that the levels are environmentally acceptable will be necessary. When the regulators approve the decommissioning plan, they establish what the release criteria for the decommissioned site will be at the time of the site release and license termination. The criteria are numeric guidelines for direct radiation in soils and on surfaces. If the regulatory body finds that the measured on-site values are below the guidelines, the site will be acceptable for unrestricted release (no radiological controls or future use). If areas are found above those values, more decontamination or cleanup of these areas may be required unless the regulatory body grants an exemption

  17. Off-site preparedness and nuclear-power-plant licensing

    International Nuclear Information System (INIS)

    Perry, S.W.

    1983-01-01

    The first year and a half in which off-site emergency preparedness issues have been litigated before the Atomic Safety and Licensing Boards of the NRC have surfaced unique problems of proof for the applicant as well as the staff. These problems seem to be abating as the boards and the parties become more comfortable with the field and its issues, and as FEMA-NRC emergency management expertise gains credibility. Emergency preparedness presentations have also improved as the parties have become more sensitive to the seasonality of the preparedness case, and have increasingly attempted to raise it at a time when a fully developed set of facts is available for the record. Off-site preparedness issues are only now beginning to be raised on appeal to the NRC appeals board, the full commission, and the courts. Helpful guidance on what constitutes an adequate record in this area will undoubtedly be forthcoming in decisions handed down by these bodies in the months ahead

  18. The Texas concurrent characterization, licensing, and development process

    Energy Technology Data Exchange (ETDEWEB)

    Avant, R.V. Jr. [Texas Low-Level Radioactive Waste Disposal Authority, Austin, TX (United States)

    1993-03-01

    The 72nd Texas Legislature specifically delineated a 400-square-mile area in southeast Hudspeth County where siting activities would be limited. The Authority was given unprecedented powers of property access and eminent domain and expanded budget authority to conduct site selection, characterization, and licensing. In the summer of 1991, the Authority identified five general siting areas in the prescribed region, and in the fall of 1991, the Authority narrowed the siting area to one large ranch composed of about 16,000 acres--called the Faskin Ranch. Site characterization began in 1991 and will be complete by September 1993. In September 1991, Authority staff began preparing the license application and included all available information on the Faskin Ranch. At its February meeting, the Authority`s board directed staff to submit the license application to the Texas Water Commission (the new Texas radiation control agency). The license application was submitted on March 2, 1992, and on April 15, 1992, the Commission determined that the application was sufficiently complete to begin review. Discrete technical packages such as groundwater hydrology, surface water hydrology, design, etc., will be submitted to the agency for review on the completion of each package. A schedule has been developed to allow the regulators the maximum time possible to review critical technical areas while minimizing the total review period.

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

    International Nuclear Information System (INIS)

    1984-07-01

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

  20. The National Site Licensing of Electronic Resources: An Institutional Perspective

    Directory of Open Access Journals (Sweden)

    Xiaohua Zhu

    2011-06-01

    Full Text Available While academic libraries in most countries are struggling to negotiate with publishers and vendors individually or collaboratively via consortia, a few countries have experimented with a different model, national site licensing (NSL. Because NSL often involves government and large-scale collaboration, it has the potential to solve many problems in the complex licensing world. However, not many nations have adopted it. This study uses historical research approach and the comparative case study research method to explore the seemingly low level of adoption. The cases include the Canadian National Site Licensing Project (CNSLP, the United Kingdom’s National Electronic Site Licensing Initiative (NESLI, and the United States, which has not adopted NSL. The theoretical framework guiding the research design and data collection is W. Richard Scott’s institutional theory, which utilizes three supporting pillars—regulative, normative, and cultural-cognitive—to analyze institutional processes. In this study, the regulative pillar and the normative pillar of NSL adoption— an institutional construction and change—are examined. Data were collected from monographs, research articles, government documents, and relevant websites. Based on the analysis of these cases, a preliminary model is proposed for the adoption of NSL. The factors that support a country’s adoption of NSL include the need for new institutions, a centralized educational policy-making system and funding system, supportive political trends, and the tradition of cooperation. The factors that may prevent a country from adopting NSL include decentralized educational policy and funding, diversity and the large number of institutions, the concern for the “Big Deal,” and the concern for monopoly.

  1. Development and licensing of a melting plant for Chernobyl scrap

    International Nuclear Information System (INIS)

    Sappok, M.; Zunk, H.; Fashevsky, K.A.

    1998-01-01

    One decade after the accident at unit 4 of the Chernobyl nuclear power station, a melting plant for radioactively contaminated metallic materials, the so-called SURF facility, is being planned and licensed for erection in the direct neighbourhood of the NPP area. Main goal is the recycling of the material largely decontaminated by the melting process, by means of manufacturing of casks and containers for waste disposal and of shielding equipment. The melting plant will be part of the Ukrainian waste handling centre (CPPRO). The technology is based on the long-term experience gained at Siempelkamp's CARLA plant in Krefeld. Within 1995 and 1996 the licensing conditions were defined, the licensing documents prepared and the formal procedure initiated. The complex is scheduled to start operation in 2001, in case the necessary financing is allocated. To this end the proposed site of the facility has undergone the state assessment. The technical documentation for construction is at the stage of development. (author)

  2. A new approach to the nuclear power plant site licensing

    Energy Technology Data Exchange (ETDEWEB)

    Kidron, A A [Israel Electric Corp. Ltd., Haifa (Israel)

    1996-12-01

    The Israel Electric Corporation Ltd.(IEC) conducted a survey to determine the geotechnical suitability of the Shivta Site for the purpose of erecting a Nuclear Power Station and presented the results in a Preliminary Safety Analysis Report (PSAR) to the Licensing Division of the Israel Atomic Energy Commission (LD). The studies for selecting a site in the NW Negev were conducted by multi-disciplinary teams of Israeli and US professionals, beginning in 1982, over a twelve-year period. The investigations involved comprehensive geological, geophysical, geotechnical, hydrological, as well as geomorphic and pedologic evaluations of the region and the then- proposed site locale. The prior studies were completed using highly advanced and modern tools and approaches and provided a significant amount of information related to the tectonic and seismic characteristics of the NW Negev region. (author).

  3. WIPP - Pre-Licensing and Operations: Developer and Regulator Perspectives

    International Nuclear Information System (INIS)

    Peake, Tom; Patterson, R.

    2014-01-01

    The Waste Isolation Pilot Plant (WIPP) is a disposal system for defense-related transuranic (TRU) radioactive waste. Developed by the Department of Energy (DOE), WIPP is located in Southeastern New Mexico: radioactive waste is disposed of 2,150 feet underground in an ancient layer of salt with a total capacity of 6.2 million cubic feet of waste. Congress authorized the development and construction of WIPP in 1980 for the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes resulting from the defense activities and programs of the United States. This paper makes a historical review of the site development, site operations (waste disposal operations started in 1999), communications between US EPA and DOE, the chronology of pre-licensing and pre-operations, the operational phase and the regulatory challenges, and the lessons learned after 12 years of operations

  4. Hanford Site Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J. (Westinghouse Hanford Co., Richland, WA (USA)); Yancey, E.F. (Pacific Northwest Lab., Richland, WA (USA))

    1990-01-01

    The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs.

  5. Hanford Site Development Plan

    International Nuclear Information System (INIS)

    Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J.; Yancey, E.F.

    1990-01-01

    The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs

  6. Hanford Site Development Plan

    International Nuclear Information System (INIS)

    Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

    1993-05-01

    The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides an existing and future land use plan for the Hanford Site. The HSDP is updated annually in accordance with DOE Order 4320.1B, Site Development Planning, to reflect the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

  7. 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

  8. Hanford Site Development Plan

    International Nuclear Information System (INIS)

    Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

    1992-05-01

    The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides a land use plan for the Hanford Site and presents a picture of what is currently known and anticipated in accordance with DOE Order 4320.1B. Site Development Planning. The HSDP wig be updated annually as future decisions further shape the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

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

    International Nuclear Information System (INIS)

    2013-01-01

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

  10. Site suitability, selection and characterization: Branch technical position--Low-Level Waste Licensing Branch

    International Nuclear Information System (INIS)

    Siefken, D.; Pangburn, G.; Pennifill, R.; Starmer, R.J.

    1982-04-01

    The staff provides an expanded interpretation of the site suitability requirements in the proposed rule 10 CFR Part 61, a description of the anticipated site selection process, and a detailed discussion of the site characterization program needed to support a license application and environmental report. The paper provides early-on guidance to prospective applicants in these three subject areas

  11. Proceedings of the CNRA Workshop on New Reactor Siting, Licensing and Construction Experience

    International Nuclear Information System (INIS)

    2011-01-01

    This report documents the proceedings from the 'Workshop on New Reactor Siting, Licensing and Construction Experience', held in Prague, Czech Republic on 15-17 September 2010. A total of 59 specialists from 16 countries and international organisations attended. The Meeting was sponsored by the OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities and hosted by the State Office for Nuclear Safety (SUJB) in Czech Republic. The objectives of the workshop were to review and discuss recent and past construction experience lessons learned including perspectives from regulatory authorities, as well as vendors, and licensee. The workshop addressed issues associated with project management resources including: a) overall human resources, expertise, experience and organisation available to the licensee, b) capability of each potential vendor (in-house knowledge and skills versus planned subcontracting and subcontractor management). The workshop also discussed the lessons learned in the regulation of site selection, evaluation and site preparation as well as the review of regulatory practices for the licensing of new reactors, including the regulatory body infrastructure, staffing and expertise needed. The workshop provided an excellent opportunity to communicate recent experience on these topics to a wider audience, including participants from OECD member countries as well as New Entrants from non-OECD member countries. The workshop allowed the WGRNR group to introduce and discuss the current programme of work and products under development in order to gain insights from workshop participants on each of the programme of work areas, and get feedback on additional focus areas. The workshop was structured in 4 technical sessions, each followed by ample time for panel discussions. The first technical session was devoted to presentations of the licensing process for new reactors followed by different member countries. The second technical session was

  12. 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

  13. Licensing arrangements and the development of the solar energy industry

    Energy Technology Data Exchange (ETDEWEB)

    Green, M.

    1979-06-01

    The process by which technology and information related to technology are transferred within industry is explored. Property rights in technology are part of the broader field of intellectual property. The general contours of legal protection for knowledge are explored. The four basic forms of intellectual property - patents, trade secrets (or know-how), trademarks, and copyrights - are covered in varying degrees of depth, depending on their relative applicability to the development of the solar industry. Once this background has been established, the legal aspects of licensing are examined. A license is a legal arrangement whereby a party (licensor) who controls the right to use an idea, invention, etc. shares the right to use the particular intellectual property with someone else (licensee). The advantages and disadvantages of licensing are described from the point of view of potential licensees and licensors. Barriers to licensing are discussed.

  14. Development of radioactive waste management licensing review assistant

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  15. 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.)

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

    International Nuclear Information System (INIS)

    Jang, Chansu; Um, Kilsup; Choi, Jaedon

    2008-01-01

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

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  18. Nuclear power plant attempts in Turkey and the first licensed site

    International Nuclear Information System (INIS)

    Bektur, Y.; Bezdegumeli, U.

    2004-01-01

    In this paper, detailed information regarding Turkey's past attempts for the construction of a nuclear power plant (NPP) and site survey studies conducted for this plant is given. Also, some important characteristics of the first licensed site, namely Akkuyu, are summarized. There were four attempts made for the construction of an NPP in the past. However, all of them failed due to technical, economical and/or some other reasons. Akkuyu site has been selected among around 25 candidate sites for the reasons that bulky materials can be transported there by sea; it is located near the major electricity demand centers; soil-structure interaction and slab stability are suitable for the construction of an NPP; its surrounding is one of the most sparsely populated areas of Turkey; and it is seismically the most stable region in earthquake-prone Turkey, e.g. Turkish Electricity Authority (TEK) was granted a site license for the Akkuyu in 1976. (author)

  19. Magnox Electric plc's strategy for decommissioning its nuclear licensed sites

    International Nuclear Information System (INIS)

    2002-02-01

    The 1995 White Paper 'Review of Radioactive Waste Management Policy: Final Conclusions', Cm 2919, determined that the Government would ask all nuclear operators to draw up strategies for the decommissioning of their redundant plant and that the Health and Safety Executive (HSE) would review these strategies on a quinquennial basis in consultation with the environment agencies. This review has considered Magnox Electric pie (Magnox Electric) arrangements for the identification of its responsibilities for decommissioning and radioactive waste management, the quantification of the work entailed, the standards and timing of the work, and the arrangements to provide the financial resources to undertake the work. This is the second review by the HSE in response to Cm 2919 of Magnox Electric's nuclear power station decommissioning and radioactive waste management strategies and is based on the situation in April 2000. It reports the Nuclear Installations Inspectorate's (NIl) view that the strategies proposed by Magnox Electric are appropriate. The strategies are considered to be largely consistent with both national and international policy statements and guidance, and are potentially flexible enough to be able to accommodate lessons learned during ongoing decommissioning activities. During the review the Nil has considered whether Magnox Electric has identified all the tasks required to fully decommission its sites. Generally this has been found to be the case. Some additional tasks have been identified due, in part, to the reviewers' noting the changes which have recently taken place in environmental expectations. At this time, on the basis of the information presented, and with the provisos stated below, Magnox Electric's provisioning for final dismantling after 85 years is considered to be reasonable. The Nil expects Magnox Electric to further justify why a shorter timescale is not reasonably practicable before the next review. One of the purposes of this review

  20. Delivering Regulatory Consents for Decommissioning and Restoration of the Dounreay Nuclear Licensed Site

    International Nuclear Information System (INIS)

    Crawford, R.W.; Zyda, P.W.

    2006-01-01

    On behalf of the Nuclear Decommissioning Authority (NDA) the United Kingdom Atomic Energy Authority (UKAEA) has implemented a strategy to translate the near-term Dounreay restoration plan into a suite of land use documents designed to deliver the necessary planning consents to decommission and restore the Dounreay Nuclear Licensed Site. The legal consents and authorizations required to enable UKAEA to commence major projects and progress the decommissioning of the site are highlighted along with the measures taken to secure political, public and regulatory acceptance at the earliest opportunity. The approach taken by UKAEA is explained, focusing particularly on the critical need to secure planning permission and stakeholder approval well before the onset of construction works. The intention is to realize the benefits of forging a close working relationship with the land use regulator, The Highland Council. UKAEA has taken an approach to suitably inform the planning authority, in particular, the production of the Dounreay Planning Framework (DPF) document. This paper describes the role and need for the DPF, focusing on the key purpose of amending the local development plan to secure supportive planning policies and to set a land use context for the subsequent site decommissioning and restoration. This also has the advantage of securing public acceptance through an established legal process. Strategic milestones subsequent to the Highland Council's adoption of the DPF are highlighted, including the submission of phased planning applications and compliance with environmental legislation generally. The paper describes and underscores the need for early engagement of other regulators in the planning process such as the Scottish Environment Protection Agency (SEPA), and the safety regulator, the Nuclear Installations Inspectorate (NII). It describes the linkages amongst land use consents, Best Practicable Environmental Options (BPEO), radioactive substances

  1. An economic perspective on software licenses--open source, maintainers and user-developers

    DEFF Research Database (Denmark)

    Edwards, Kasper

    2005-01-01

    This paper presents a model for understanding behaviour of agents using and/or contributing to open source software. The model illustrates behaviour of agents under three licenses regimes: 1) The GPL, The BSD and 3) The Microsoft EULA. The latter license is not an open source license...... licenses induce different incentives and dynamics for maintainer and user-developer and the paper explains, from an economic standpoint, the mechanisms that ensure programs are developed and maintained under the three license regimes....

  2. The development of reactor operator license examination question bank

    International Nuclear Information System (INIS)

    Kim, In Hwan; Woo, S. M.; Kam, S. C.; Nam, K. J.; Lim, H. P.

    2001-12-01

    The number of NPP keeps increasing therefore there is more need of reactor operators. This trend requires the more efficiency in managing the license examination. Question bank system will help us to develop good quality examination materials and keep them in it. The ultimate purpose of the bank system is for selecting qualified reactor operators who are primarily responsible for the safety of reactor operation in NPP

  3. Strategy and plan for siting and licensing a Rocky Mountain low-level radioactive waste facility

    International Nuclear Information System (INIS)

    Whitman, M.

    1983-09-01

    In 1979, the States of Nevada and Washington temporarily closed their commercial low-level radioactive waste (LLW) disposal facilities and South Carolina, the only other state hosting such a facility, restricted the amount of waste it would accept. All three states then announced that they did not intend to continue the status quo of accepting all of the country's commercial low-level radioactive waste. Faced with this situation, other states began considering alternative LLW management and disposal options. In the Rocky Mountain region, this evolved into discussions for the development of an interstate compact to manage low-level waste. Inherent in this management plan was a strategy to site and license a new LLW disposal facility for the Rocky Mountain region. The Rocky Mountain Low-Level Radioactive Waste Compact was negotiated over the course of a year, with final agreement on the language of the compact agreed to in early 1982. States eligible to join the compact are Arizona, Colorado, Nevada, New Mexico, Utah, and Wyoming. Colorado adopted the compact into law in 1982, and Nevada, New Mexico and Wyoming adopted it in 1983. Utah has joined the Northwest Compact, although it may decide to join the Rocky Mountain Compact after a new disposal facility is developed for the region. Arizona has taken no action on the Rocky Mountain Compact

  4. Radioactive liquid waste discharged from Nuclear Electric licensed sites during 1991

    International Nuclear Information System (INIS)

    Austin, L.S.; Odell, K.J.

    1993-03-01

    This report presents the detailed isotopic composition of radioactive liquid waste discharged from Nuclear Electric licensed sites in 1991. Liquid discharges from those Magnox stations using pond storage of irradiated fuel contained low levels of activation and fission products, while those from Wylfa and the AGR stations contained lower levels of activation products with only traces of fission products. Discharges were similar to those observed in previous years, with any changes concordant with changes in stations' generation performance. (author)

  5. Web Site Development Support

    Science.gov (United States)

    Abdul, Hameed

    2016-01-01

    This summer I assisted the RPT Program Office in developing a design plan to update their existing website to current NASA web standards. The finished website is intended for the general public, specifically potential customers interested in learning about NASA's chemical rocket test facility capabilities and test assignment process. The goal of the website is to give the public insight about the purpose and function of the RPT Program. Working on this project gave me the opportunity to learn skills necessary for effective project management. The RPT Program Office manages numerous facilities so they are required to travel often to other sites for meetings throughout the year. Maneuvering around the travel schedule of the office and the workload priority of the IT Department proved to be quite the challenge. I overcame the travel schedule of the office by frequently communicating and checking in with my mentor via email and telephone.

  6. Nuclear power plant attempts in Turkey and the first licensed site

    International Nuclear Information System (INIS)

    Bektur, Y.; Bezdegumeli, U.

    2004-01-01

    Turkey is currently in a rapid industrialization process with a young population of 71 million. Electricity is an inevitable need for Turkey as a fast developing country. Turkey's average annual growth rates of electricity consumption have been 8% in the last two decades. The installed electricity generating capacity of Turkey reached 36 GW; the annual gross power generation was 140 TWh (23% lignite and coal, 44% natural gas, 25% hydro and 8% others); and the annual gross per capita consumption of electricity was around 2.000 kWh as of end-2003. According to forecasts prepared by the Ministry of Energy and Natural Resources (MENR), Turkey will need about 60 GW of capacity by 2010, and about 100 GW by 2020. This implies power demand growth rates of at least 8% per annum for the coming decade and at least 6% per annum for the following decade. This means that there is a need for rapid build-up of 3 GW new capacities per year for at least several years. Turkey's experience with nuclear power dates back to the 1960s - a research reactor has been operating in Istanbul since 1962 - and successive governments have had plans to introduce commercial nuclear power to the country for three decades or more. Since 1965, four attempts were made for the construction of an NPP in Turkey, but all failed. Turkish Electricity Authority (TEK, reorganized as Electricity Generation Corporation in 2002) was granted a site license for the Akkuyu site in 1976. According to the current long-term energy planning studies made by MENR, nuclear power is an important option to enhance the national energy security and reliability. In the light of this study, the Turkish Government has an intention for commencement of a nuclear power program that envisages the construction of 4500 M We nuclear power installed capacity in the next decade if the private energy sector do not make an attempt

  7. Recent developments in Canadian nuclear power plant licensing practices

    International Nuclear Information System (INIS)

    Marchildon, P.

    1985-06-01

    This paper examines the dominant factors which have influenced the safety evaluation and licensing process of current 600 MW reactors. It describes possible modifications to the process which are being considered for the licensing of a second 600 MW reactor at Point Lepreau. The key element is a firm licensing agreement covering the entire licensing cycle, to be established between the proponent and the AECB before a construction licence is issued. Progress accomplished to date in reaching such an agreement is described

  8. ITER licensing

    International Nuclear Information System (INIS)

    Gordon, C.W.

    2005-01-01

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

  9. California LLW disposal site development update: Ahead of milestone schedule

    International Nuclear Information System (INIS)

    Romano, S.A.; Gaynor, R.K.

    1987-01-01

    US Ecology has been designated by the State of California to locate, develop and operate a low-level radioactive waste disposal facility. In early 1986, the firm identified eighteen desert basins in southeastern California for siting consideration. Three candidate sites were selected for detailed field characterization work in February, 1987. A preferred site for licensing purposes will be identified in early 1988. California is currently ahead of the siting milestone schedule mandated by the Low-Level Radioactive Waste Policy Amendments Act. It is likely that a license application will be filed before the 1990 milestone date. This paper describes the process undertaken by US Ecology to identify three candidates sites for characterization, and the public involvement program supporting this decision. Future activities leading to final site development are also described

  10. THE DECISION TO RECOMMEND YUCCA MOUNTAIN AND THE NEXT STEPS TOWARD LICENSED REPOSITORY DEVELOPMENT

    International Nuclear Information System (INIS)

    Barrett, L. H.

    2002-01-01

    After more than 20 years of carefully planned and reviewed scientific field work by the U.S. Department of Energy, the U.S. Geological Survey, and numerous other organizations, Secretary of Energy Abraham concluded in January that the Yucca Mountain site is suitable, within the meaning of the Nuclear Waste Policy Act, for development as a permanent nuclear waste and spent fuel repository. In February, the Secretary recommended to the President that the site be developed for licensed disposal of these wastes, and the President transmitted this recommendation to Congress. This paper summarizes key technical and national interest considerations that provided the basis for the recommendation. It also discusses the program's near-term plans for repository development if Congress designates the site

  11. Recycling and disposal of FUSRAP materials from the Ashland 2 site at a licensed uranium mill

    International Nuclear Information System (INIS)

    Howard, B.; Conboy, D.; Rehmann, M.; Roberts, H.

    1999-01-01

    During World War II the Manhattan Engineering District (MED) used facilities near Buffalo, N.Y. to extract natural uranium from ores. Some of the byproduct material left from the ores (MED byproduct), containing low levels of uranium, thorium, and radium, was deposited on a disposal site known as Ashland 2, located in Tonawanda, NY. On behalf of the United States Army Corps of Engineers (USACE, or the Corps), ICF Kaiser Engineers (ICFKE) was tasked to provide the best value clean-up results that meet all of the criteria established in the Record of Decision for the site. International Uranium (USA) Corporation (IUC), the operator of the White Mesa Uranium Mill, a Nuclear Regulatory Commission (NRC)-licensed mill near Blanding, Utah, was selected to perform uranium extraction on the excavated materials, therefore giving the best value as it provided beneficial use of the material consistent with the Resource Conservation and Recovery Act (RCRA) intent to encourage recycling and recovery, while also providing the most cost-effective means of disposal. Challenges overcome to complete this project included (1) identifying the best-value location to accept the material; (2) meeting regulatory requirements with IUC obtaining an NRC license amendment to accept and process the material as an alternate feed; (3) excavating and preparing the material for shipment, then shipping the material to the Mill for uranium recovery; and (4) processing the material, followed by disposal of tailings from the process in the Mill's licensed uranium tailings facility. Excavation from Ashland 2 and processing of the Ashland 2 material at the White Mesa Mill resulted in a cleaner environment at Tonawanda, a cost avoidance of up to $16 million, beneficial recovery of source material, and environmentally protective disposal of byproduct material. (author)

  12. The HOR core conversion program development and licensing experiences

    International Nuclear Information System (INIS)

    Vries, J.W. de; Gibcus, H.P.M.; Leege, P.F.A. de

    1997-01-01

    This paper deals with the experiences in the development of a fuel conversion program for a 2 MW university type research reactor, the HOR. It gives an overview of the technical and administrative aspects concerning the fuel conversion program development since the eighties, including the safety review and licensing process. The overall final safety report was submitted in 1995, together with the environmental impact report, and a licence application was submitted accordingly. The licence permitting the conversion was issued in 1996, coming into force at the beginning of this year, although an appeal case is still pending. At the moment the necessary preparations for starting the actual conversion of the HOR are made. The general program characteristics are addressed. (author)

  13. 78 FR 37234 - Prospective Grant of Exclusive License: Start-Up Commercial License for the Development of...

    Science.gov (United States)

    2013-06-20

    ... the Treatment of Brain, Liver, and Pancreatic Cancers and Congestive Heart Failure AGENCY: National..., development, manufacture, distribution, sale, and use in humans for the treatment of brain cancer, liver...: Patrick McCue, Ph.D., Licensing and Patenting Manager, Office of Technology Transfer, National Institutes...

  14. UK safety and standards for radioactive waste management and decommissioning on nuclear licensed sites

    International Nuclear Information System (INIS)

    Mason, D.J.

    2001-01-01

    This paper discusses the regulation of radioactive waste and decommissioning in the United Kingdom and identifies the factors considered by HM Nuclear Installations Inspectorate in examining the adequacy arrangements for their management on nuclear licensed sites. The principal requirements are for decommissioning to be undertaken as soon as reasonably practicable and that radioactive wastes should be minimised, disposed of or contained and controlled by storage in a passively safe form. However, these requirements have to be considered in the context of major organisational changes in the UK nuclear industry and the non-availability of disposal routes for some decommissioning wastes. The legislative framework used to regulate decommissioning of nuclear facilities in the UK is described. Reference is made to radioactive waste and decommissioning strategies, quinquennial reviews criteria for delicensing and the forthcoming Environmental Impact Assessment Regulations. (author)

  15. 10 CFR 50.55 - Conditions of construction permits, early site permits, combined licenses, and manufacturing...

    Science.gov (United States)

    2010-01-01

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

  16. Development and Application of SITES

    International Nuclear Information System (INIS)

    Park, Jo Wan; Yoon; Yoon, Jeong Hyoun; Kim, Chank Lak; Cho, Sung IL

    2008-01-01

    SITES (Site Information and Total Environmental Data Management System) has been developed for the purpose of systematically managing site characteristics and environmental data produced during the pre-operational, operational, and post-closure phases of a radioactive waste disposal facility. SITES is an integration system, which consists of 4 modules, to be available for maintenance of site characteristics data, for safety assessment, and for site/environment monitoring; site environmental data management module (SECURE), integrated safety assessment module (SAINT), site/environment monitoring module (SUDAL) and geological information module for geological data management (SITES-GIS). Each module has its database with the functions of browsing, storing, and reporting data and information. Data from SECURE and SUDAL are interconnected to be utilized as inputs to SAINT. SAINT has the functions that multi-user can access simultaneously via client-server system, and the safety assessment results can be managed with its embedded Quality Assurance feature. Comparison between assessment results and environmental monitoring data can be made and visualized in SUDAL and SITES-GIS. Also, SUDAL is designed that the periodic monitoring data and information could be opened to the public via internet homepage. SITES has applied to the Wolsong low- and intermediate-level radioactive waste disposal center in Korea, and is expected to enhance the function of site/environment monitoring in other nuclear-related facilities and also in industrial facilities handling hazardous materials.

  17. Development regulation regarding with licensing of nuclear installation

    International Nuclear Information System (INIS)

    Bambang Riyono; Yudi Pramono; Dahlia Cakrawati Sinaga

    2011-01-01

    Provisions of Article 17 paragraph (3) of Law Number 10 Year 1997 on Nuclear cleary mandates for the establishment of government regulations (GR) on Nuclear licensing containing the requirements and procedure, both from the standpoint of their utilization and installation. To use has been rising GR No.29 Year 2008 on the Use of Ionizing Radiation Sources and Nuclear Materials, while for the installation has been published PP No.43 Year 2006 on Nuclear Reactor Licensing, and BAPETEN Chairman Decree No.3 Year 2006 on Non-reactor Nuclear Installation Licensing. Based on the background of the preparation of both the aforementioned are just regulate the reactor and utilization, not yet fully meet the mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear, including other nuclear installations. For these reasons, it initiated the need for a separate regulation containing provisions concerning licensing of non-reactor nuclear installations. On the other side from the understanding the legal aspects and interpretations of the Law No.10 of 2004 on the Establishment Regulation Legislation, should be in single mandate of Article 17 paragraph (3) of Law No.10 of 1997 on Nuclear would only produce one of the requirements and procedure for the use or installation, or a maximum of two (2) GR related licensing the use and installation. This is encourages conducted the assessing or studies related to how possible it is according to the legal aspect is justified to combine in one Nuclear licensing regulations regarding both the use and installation, by looking at the complexity of installation and wide scope of utilization of nuclear energy in Indonesia. The results of this paper is expected to provide input in the preparation of GR on licensing of nuclear installations. (author)

  18. Norwegian-developed carbon dioxide technology licensed to Japan

    International Nuclear Information System (INIS)

    Pettersen, Jostein

    2000-01-01

    In the late 1980s, restrictions on the use of ozone-depleting substances created increased interest in alternative working fluids in refrigerators and heat pumps. Carbon dioxide (CO2) is an incombustible, non-toxic and not ozone-depleting natural substance with low specific greenhouse effect. However, CO2 has some unusual thermodynamic properties. Thus, the pressure of a CO2 based system must be high, up to 150 bar, which means that new equipment must be developed. Research at SINTEF and the Technical University in Trondheim, Norway, in 1988-89 resulted in several patents which have later been commercialized and internationally licensed. The most important developments have been in air conditioning for cars, heat pumps for hot water and refrigeration systems for supermarkets. In Japan, a heat pump for hot water has been developed under licence. This is a 4.5 kW heat pump designed for use in detached houses and larger flats. One of the advantages of CO2 is that a high water temperature (70-90 C ) is obtained. The hot water container can then be made quite small. The heat pump is marketed by Tokyo Electric Power Company, which during the night has surplus power that can be sold for less than 25% of the daytime tariff. Compared with gas-fired water heaters, the consumption of primary energy is reduced by 30-50%. This is an important contribution to more efficient use of fossil fuel. Using CO2 also avoids the risk of fire and explosion that exists in the use of gas-fired water heaters

  19. 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.

  20. The SLOWPOKE licensing model

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-08-15

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

  1. MARSSIM guidelines for non-impacted area identification in support of partial site release prior to license termination

    International Nuclear Information System (INIS)

    Parish, D.

    1999-01-01

    Regulations are in place which allow plants undergoing decommissioning to remove obsolete requirements from their licenses. Large buffer areas to the site boundary, needed for emergency planning purposes during power operation, are not required for permanently defueled facilities. It is important that non-impacted areas be removed from license restrictions as soon as possible post shutdown to allow rapid asset recovery and return the large environmental resources these areas represent to beneficial use. License termination surveys are not required for non-impacted areas in accordance with the guidance of US Nuclear Regulatory Commission (NRC) NUREG-1575 (MARSSIM), and NRC Draft Regulatory Guide DG-4006. Thus, such areas do not fall under the license termination requirements of 10CFR50.82 (US Code of Federal Regulations). This report describes methods of classifying areas as non-impacted in accordance with MARRSIM and other NRC guidance, and the licensing options for release of non-impacted areas prior to license termination. The status of Big Rock Point's efforts toward early release of non-impacted areas also is provided. (author)

  2. Electronic licensing filing system development and implementation experience

    International Nuclear Information System (INIS)

    Walderhaug, J.

    1993-01-01

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

  3. 76 FR 79228 - Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy...

    Science.gov (United States)

    2011-12-21

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 52-018 and 52-019; NRC-2008-0170] Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy Carolinas, LLC AGENCY: Nuclear.... SUMMARY: Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Army Corps...

  4. Licensing procedures and siting problems of nuclear power stations in Japan

    International Nuclear Information System (INIS)

    Saito, Osamu.

    1981-10-01

    This paper describes the legislative and regulatory framework for nuclear power plant licensing in Japan and the different stages in the licensing procedure. The role and responsibilities of the authorities competent for the different types of nuclear facilities (power generation, ship propulsion and research) are also reviewed. The Annexes to the paper contain charts of the administrative structure for nuclear activities, the licensing procedure and nuclear facilities. (NEA) [fr

  5. Evaluation of Terminated Nuclear Material Licenses

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  6. Hanford Site sustainable development initiatives

    International Nuclear Information System (INIS)

    Sullivan, C.T.

    1994-05-01

    Since the days of the Manhattan Project of World War II, the economic well being of the Tri-Cities (Pasco, Kennewick, and Richland) of Washington State has been tied to the US Department of Energy missions at the nearby Hanford Site. As missions at the Site changed, so did the economic vitality of the region. The Hanford Site is now poised to complete its final mission, that of environmental restoration. When restoration is completed, the Site may be closed and the effect on the local economy will be devastating if action is not taken now. To that end, economic diversification and transition are being planned. To facilitate the process, the Hanford Site will become a sustainable development demonstration project

  7. 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

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

    Science.gov (United States)

    Edwards, Nancy V

    2008-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    van Erp, J B

    1977-12-01

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

  10. 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

  11. 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)

  12. EPA-developed, patented technologies available for licensing

    Data.gov (United States)

    U.S. Environmental Protection Agency — Under the Federal Technology Transfer Act (FTTA), Federal Agencies can patent inventions developed during the course of research. These technologies can then be...

  13. 77 FR 3482 - Prospective Grant of Exclusive License: Development of T Cell Receptors and Chimeric Antigen...

    Science.gov (United States)

    2012-01-24

    ... Exclusive License: Development of T Cell Receptors and Chimeric Antigen Receptors Into Therapeutics for.... 61/473,409 entitled ``Anti-epidermal growth factor receptor variant III chimeric antigen receptors... EGFRvIII chimeric antigen (CARs) and methods of using these engineered T cells to treat and/or prevent...

  14. 77 FR 22333 - Prospective Grant of Exclusive License: Development of Oncolytic Viral Cancer Therapies

    Science.gov (United States)

    2012-04-13

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Prospective Grant of Exclusive License: Development of Oncolytic Viral Cancer Therapies AGENCY: National Institutes of Health... administration of the recombinant virus to a human or animal subject, the foreign gene is expressed in vivo to...

  15. 77 FR 62521 - Prospective Grant of Exclusive License: The Development of Therapeutic Agents for the Treatment...

    Science.gov (United States)

    2012-10-15

    ... interleukin-10 (IL-10) inhibitor as a dual-biologic therapy to treat metastatic breast cancer, or ii) incorporating a p53 isoform antisense oligonucleotide as a single biologic therapy to treat T- cell lymphoma... Exclusive License: The Development of Therapeutic Agents for the Treatment of Metastatic Breast Cancer and T...

  16. Estimates of population distributions and tailings areas around licensed uranium mill sites. Final report

    International Nuclear Information System (INIS)

    Hans, J.M.; Hall, J.B.; Moore, W.E.

    1986-08-01

    Population distributions and tailings areas were estimated from aerial photography for each of 21 licensed uranium millsites. Approximately 11,600 persons live within 5 kilometers of the tailings impoundments at the millsites. About 82% of these persons live near five of the millsites. No persons were found living within 5 kilometers of six of the millsites. Tailings area measurements include the surface area of tailings in impoundments, heap-leached ore, and carryover tailings in evaporation ponds. Approximately 4,000 acres of tailings surfaces were measured for the 21 millsites. About 55% of the tailings surfaces were dry, 11% wet, and the remainder ponded. The average tailings surface area for the millsites is about 200 acres and ranges from 7 to 813 acres

  17. Improving regulatory effectiveness in federal/state siting actions: water supplies and the nuclear licensing process

    International Nuclear Information System (INIS)

    Davenport, F.S.

    1977-07-01

    The Interstate Conference on Water Problems (ICWP) is a national association of State, intrastate, and interstate officials concerned with water resources administration and related matters. The Conference was established in 1959 as an outgrowth of regional conferences on water problems as recognized in the same year by action of the General Assembly of the States. This report was produced by the Interstate Conference on Water Problems in an effort to provide a compilation and summary of the views of selected States regarding relationships of water supplies to the nuclear power plant licensing process. This publication does not represent the official position of the U.S Water Resources Council, or the U.S. Nuclear Regulatory Commission, nor does it represent the position of any single state or the ICWP

  18. Inventory of sites used to develop residual radioactivity criteria

    International Nuclear Information System (INIS)

    Ronca-Battista, M.; Hardeman, J.C. Jr.

    1986-01-01

    The US Environmental Protection Agency (EPA), in conjunction with the National Conference of Radiation Control Program Directors (CRCPD), has compiled an inventory of never licensed or otherwise poorly documented sites that may be contaminated with radioactive materials. This effort is in support of the EPA's development of radiation protection criteria for residual radioactivity at decommissioned sites. The inventory will help to establish the range of circumstances for which criteria are needed, as well as the suitability of candidate criteria for actual situations. The information will also be used to develop model sites and facilities for analyzing technical and economic feasibility of residual radioactivity criteria and to assess costs and benefits of alternate criteria. Relevant information about each site, such as radionuclides, waste forms, and quantities present will be included in the inventory when such information is available. The CRCPD has requested that each State radiation control agency furnish the information for the inventory. The inventory supplements the relatively extensive documentation of sites regulated by Federal or State agencies with information on old or unlicensed sites, such as old waste storage sites or radium ore processing facilities

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

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  20. Experience from developed and licensing an underground repository for low and intermediate level radioactive wastes

    International Nuclear Information System (INIS)

    Ebel, K.; Richter, D.

    1988-01-01

    In the German Democratic Republic an abandoned salt mine was selected and reconstructed to serve as a central repository for low and intermediate level wastes from nuclear power plants and radioisotope production and application from all over the country. The decision to establish such a repository was based on safety and technical-economic studies performed in the 1960s. The repository is owned by the main waste producer, the nuclear plant utility. It was designed, constructed and commissioned during 1972-1978. The licensing steps included a site licence (1972), a construction licence (1974), a comissioning licence and a continuous operation licence (1979). The paper reviews the overall choice of the disposal option, the responsibilities in radioactive waste management, the licensing and surveillance activities, the methods for transport and disposal, and the waste acceptance criteria established for the repository. (author)

  1. Improving regulatory effectiveness in Federal/State siting actions: Federal/State regulatory permitting actions in selected nuclear power station licensing cases

    International Nuclear Information System (INIS)

    Baroff, J.

    1977-06-01

    The Federal/State regulatory permitting actions in 12 case histories of nuclear power station licensing in nine different states are documented. General observations regarding Federal/State siting roles in the siting process are included. Eleven of the case histories are illustrated with a logic network that gives the actions of the utilities in addition to the Federal/State permits

  2. Research and development tasks of the basalt waste isolation program, and their relationship to the licensing process

    International Nuclear Information System (INIS)

    Kunkel, W.P.

    1978-06-01

    This document presents a preliminary licensing program and outlines the research and development strategy by which a license will be obtained for the repository. It addresses the base data covering the major areas of investigation and technology which will provide input to the licensing process. Basically, each facet of the program, as described in the plan, will be used as part of the documentation required for the Preliminary and Final Safety Analysis Report (PSAR and FSAR), as well as the Environmental Report

  3. Evaluation of the impact of a committed site on fusion reactor development

    International Nuclear Information System (INIS)

    Reid, R.L.; Nagy, A.

    1979-01-01

    The technical and economic merits of a committed fusion site for development of tokamak, mirror, and EBT reactor from ignition through demo phases were evaluated. Schedule compression resulting from evolving several reactor concepts and/or phases on a committed site as opposed to sequential use of independent sites was estimated. Land, water, and electrical power requirements for a committed fusion site were determined. A conceptual plot plan for siting three fusion reactors on a committed site was configured. Reactor support equipment common to the various concepts was identified as candidates for sharing. Licensing issues for fusion plants were briefly addressed

  4. Solid waste management complex site development plan

    International Nuclear Information System (INIS)

    Greager, T.M.

    1994-01-01

    The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated

  5. Solid waste management complex site development plan

    Energy Technology Data Exchange (ETDEWEB)

    Greager, T.M.

    1994-09-30

    The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated.

  6. HSE policy on decommissioning and radioactive waste management at licensed nuclear sites

    International Nuclear Information System (INIS)

    Bacon, M.

    1997-01-01

    In the UK, radioactive waste management and decommissioning on a licensed nuclear is regulated by the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to radioactive waste management and decommissioning activities. This provides a continuous but flexible safety regime until there is no danger from ionizing radiations. The regulatory policy is discussed, taking into account the implications of the 1995 White Paper reviewing radioactive waste management policy. For both radioactive waste management and decommissioning the key element of HSE policy is the need for strategic planning. This should ensure that problems are not allowed to build up and to demonstrate that, taking into account all factors, the proposed actions are the optimum in terms of safety. There is a presumption in HSE's policy towards disposal of radioactive waste as soon as possible where disposal routes exist. Where long-term storage is necessary passively safe forms are preferred over those requiring continuous monitoring or frequent intervention. (author)

  7. Development model to public hearing for environmental licensing of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Vasques, Luciana Gomes; Aquino, Afonso Rodrigues de, E-mail: lu_vasques@usp.br, E-mail: araquino@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The use of nuclear technology has always been a matter of concern from an environmental point of view. Although disputed, the generation of electricity in nuclear reactors was considered a source of clean emission in relation to emission of gases responsible for the greenhouse effect. In Brazil, nuclear activities are regulated and supervised by the Brazilian Commission of Nuclear Energy - CNEN. Environmental issues associated with nuclear activities are described by CONAMA, and the developments in this area are licensed by IBAMA, regardless of obtaining nuclear licenses issued by CNEN. Obtaining environmental licenses (prior, installation and operation) depends initially on preparing the Environmental Impact Study - EIS and the Environmental Impact Report - EIR, consisting of a presentation of EIS in language accessible to all. EIR is forwarded to bodies and entities with some connection to the enterprise, to be manifested with IBAMA about the relevance of its content. This information serves as a resource for Public Hearings, which are meetings organized by entrepreneurs, conducted by IBAMA, and rely on public participation, can be considered as a licensing step. Public Hearings are subject to subjectivity, and the model proposed in this research becomes more objective ill-defined, difficult to understand actions for the entrepreneur. (author)

  8. Development model to public hearing for environmental licensing of nuclear facilities

    International Nuclear Information System (INIS)

    Vasques, Luciana Gomes; Aquino, Afonso Rodrigues de

    2015-01-01

    The use of nuclear technology has always been a matter of concern from an environmental point of view. Although disputed, the generation of electricity in nuclear reactors was considered a source of clean emission in relation to emission of gases responsible for the greenhouse effect. In Brazil, nuclear activities are regulated and supervised by the Brazilian Commission of Nuclear Energy - CNEN. Environmental issues associated with nuclear activities are described by CONAMA, and the developments in this area are licensed by IBAMA, regardless of obtaining nuclear licenses issued by CNEN. Obtaining environmental licenses (prior, installation and operation) depends initially on preparing the Environmental Impact Study - EIS and the Environmental Impact Report - EIR, consisting of a presentation of EIS in language accessible to all. EIR is forwarded to bodies and entities with some connection to the enterprise, to be manifested with IBAMA about the relevance of its content. This information serves as a resource for Public Hearings, which are meetings organized by entrepreneurs, conducted by IBAMA, and rely on public participation, can be considered as a licensing step. Public Hearings are subject to subjectivity, and the model proposed in this research becomes more objective ill-defined, difficult to understand actions for the entrepreneur. (author)

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

    International Nuclear Information System (INIS)

    Jordan, J.

    1992-01-01

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

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

    Science.gov (United States)

    Bergen Community Coll., Paramus, NJ.

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

  11. 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...

  12. 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

  13. Cast iron transport, storage and disposal containers for use in UK nuclear licensed sites - 59412

    International Nuclear Information System (INIS)

    Viermann, Joerg; Messer, Matthias P.

    2012-01-01

    Document available in abstract form only. Full text of publication follows: Ductile Cast Iron Containers of the types GCVI (UK trademark -GNS YELLOW BOX R ) and MOSAIK R have been in use in Germany for transport, storage and disposal of intermediate level radioactive waste (ILW) for more than two decades. In 2009 a number of containers of these types were delivered to various Magnox sites as so called pathfinders to test their suitability for Magnox waste streams. The results were encouraging. Therefore the Letter of Compliance (LoC) procedure was started to prove the suitability of packages using these types of containers for the future UK Geological Disposal Facility (GDF) and a conceptual Letter of Compliance (cLoC) was obtained from RWMD in 2010. Waste stream specific applications for Interim Stage Letters of Compliance (ILoC) for a number of waste streams from different Magnox sites and from the UK's only pressurised water reactor, Sizewell B are currently being prepared and discussed with RWMD. In order to achieve a package suitable for interim storage and disposal the contents of a Ductile Cast Iron Container only has to be dried. Mobile drying facilities are readily available. Containers and drying facilities form a concerted system

  14. Architecture and Development of DCMP Web Site

    Science.gov (United States)

    Bariakhtar, Irina

    2003-03-01

    The multi-tier implementation of DCMP Web site is discussed. It is based upon newly developed PHP technology. The technology allows for creating dynamic content and scalable solutions for Web site capabilities. There are several aspects as to what type of information is to be on the site. First, it should serve the immediate needs of the researchers in the field, namely, conferences, journals, news, funds, etc. This is currently available on the site, but can be extended and improved if needed. Second, the site will reflect the connection between Condensed matter physics and the technological breakthroughs that drive the economy. Third, the site will carry an educational mission helping educate the general public, and on the other hand, help young people to start their careers in the field. The content of the DCMP Web site is under active development. It depends upon wide involvement of DCMP members.

  15. Operating experience and licensing criteria relating to on-site electric power systems in Italy

    Energy Technology Data Exchange (ETDEWEB)

    Ciattaglia, S.; Grimaldi, G. [ENEA/DISP, Via Vitaliano Brancati, 48, 00144 Roma/Rome (Italy)

    1986-02-15

    The most significant events of on-site electrical power supply degradation in Italian plants took place in coincidence with severe atmospheric conditions or with the propagation of disturbances by lightning stroke inside the plant. Essential instrumentation was lost in two cases so that, for some time, no indication of the plant status was allowed. In both cases the recovery of the plant was achieved by restoration of external power supply. Corrective actions included both improvement in immunity to disturbances, redundancy, capability and physical separation and DG's reliability demonstration. Design and safety analysis of new plants are now carried out with the help of reliability studies and probabilistic risk assessment. As a result, design changes were performed on new plants to improve the reliability of DGs start-up and the independence of the electrical emergency divisions. (authors)

  16. Operating experience and licensing criteria relating to on-site electric power systems in Italy

    International Nuclear Information System (INIS)

    Ciattaglia, S.; Grimaldi, G.

    1986-01-01

    The most significant events of on-site electrical power supply degradation in Italian plants took place in coincidence with severe atmospheric conditions or with the propagation of disturbances by lightning stroke inside the plant. Essential instrumentation was lost in two cases so that, for some time, no indication of the plant status was allowed. In both cases the recovery of the plant was achieved by restoration of external power supply. Corrective actions included both improvement in immunity to disturbances, redundancy, capability and physical separation and DG's reliability demonstration. Design and safety analysis of new plants are now carried out with the help of reliability studies and probabilistic risk assessment. As a result, design changes were performed on new plants to improve the reliability of DGs start-up and the independence of the electrical emergency divisions. (authors)

  17. Facility planning and site development

    International Nuclear Information System (INIS)

    Reisman, R.C.; Handmaker, H.

    1986-01-01

    Planning for a magnetic resonance imaging (MRI) facility should provide for the efficient operation of current and future MRI devices and must also take into consideration a broad range of general planning principles. Control of budgeted facility costs and construction schedules is of increasing importance due to the magnitude of expense of MRI facility development as well as the need to protect institutional or entrepreneurial investment. In a competitive environment facility costs may be the determining factor in a project's success

  18. 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.

  19. The developing one door licensing service system based on RESTful oriented services and MVC framework

    Science.gov (United States)

    Widiyanto, Sigit; Setyawan, Aris Budi; Tarigan, Avinanta; Sussanto, Herry

    2016-02-01

    The increase of the number of business impact on the increasing service requirements for companies and Small Medium Enterprises (SMEs) in submitting their license request. The service system that is needed must be able to accommodate a large number of documents, various institutions, and time limitations of applicant. In addition, it is also required distributed applications which is able to be integrated each other. Service oriented application fits perfectly developed along client-server application which has been developed by the Government to digitalize submitted data. RESTful architecture and MVC framework are embedded in developing application. As a result, the application proves its capability in solving security, transaction speed, and data accuracy issues.

  20. Technical guidance for siting criteria development

    Energy Technology Data Exchange (ETDEWEB)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

    1982-12-01

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

  1. Technical guidance for siting criteria development

    International Nuclear Information System (INIS)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.

    1982-12-01

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness

  2. Development of a laboratory niche Web site.

    Science.gov (United States)

    Dimenstein, Izak B; Dimenstein, Simon I

    2013-10-01

    This technical note presents the development of a methodological laboratory niche Web site. The "Grossing Technology in Surgical Pathology" (www.grossing-technology.com) Web site is used as an example. Although common steps in creation of most Web sites are followed, there are particular requirements for structuring the template's menu on methodological laboratory Web sites. The "nested doll principle," in which one object is placed inside another, most adequately describes the methodological approach to laboratory Web site design. Fragmentation in presenting the Web site's material highlights the discrete parts of the laboratory procedure. An optimally minimal triad of components can be recommended for the creation of a laboratory niche Web site: a main set of media, a blog, and an ancillary component (host, contact, and links). The inclusion of a blog makes the Web site a dynamic forum for professional communication. By forming links and portals, cloud computing opens opportunities for connecting a niche Web site with other Web sites and professional organizations. As an additional source of information exchange, methodological laboratory niche Web sites are destined to parallel both traditional and new forms, such as books, journals, seminars, webinars, and internal educational materials. Copyright © 2013 Elsevier Inc. All rights reserved.

  3. Department of Energy licensing strategy

    International Nuclear Information System (INIS)

    Frei, M.W.

    1984-01-01

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

  4. Online driver's license renewal.

    Science.gov (United States)

    2015-09-01

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

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

    International Nuclear Information System (INIS)

    Serrano R, M. L.

    2015-09-01

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

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

    International Nuclear Information System (INIS)

    Jones, H.

    1990-01-01

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

  7. 76 FR 65518 - Prospective Grant of Exclusive License: The Development of a Companion Diagnostic Kit for...

    Science.gov (United States)

    2011-10-21

    ... contemplated exclusive license should be directed to: Patrick P. McCue, Ph.D., Licensing and Patenting Manager... has been demonstrated for biliary tract, kidney, lung, and stomach cancers. The prospective exclusive...

  8. 75 FR 16490 - Prospective Grant of Exclusive License: Development of PANVAC and Tumor Associated Antigens as...

    Science.gov (United States)

    2010-04-01

    ... exclusive license should be directed to: Sabarni K. Chatterjee, Ph.D. Licensing and Patenting Associate... indicates that Brachyury is aberrantly expressed on tumors of the lung, intestine, stomach, kidney, bladder...

  9. Thematic report on community development and siting

    International Nuclear Information System (INIS)

    Vari, A.

    2002-01-01

    The paper analyses the Finnish spent fuel disposal facility siting from the perspective of community development, issues of fairness, and general factors of success. We found that anticipated positive impacts on host community development were the most important factors of local support. Second, the willingness of main stakeholders to adopt and combine several competing and changing concepts of fairness helped making legitimate decisions. Finally, we can conclude that in addition to important cultural factors which are unique in Finland, a number of siting elements have contributed to the success that are of cross-cultural nature. The paper summarises the lessons learned about the Finnish spent fuel disposal facility siting process regarding the issues of community development, fairness, and the transferability of siting approaches across cultures. It is largely based on information presented within the framework of the OECD Forum of Stakeholder Confidence Workshop held in Turku, Finland, on 15-16 November 2001. (author)

  10. 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

  11. 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.

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

    International Nuclear Information System (INIS)

    1984-05-01

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

  13. Siemens Nuclear Power Corporation methods development for BWR/PWR reactor licensing

    International Nuclear Information System (INIS)

    Pruitt, D.W.

    1992-01-01

    This presentation addresses the Siemens Nuclear Power Corporation (SNP) perspective on the primary forces driving methods development in the nuclear industry. These forces are fuel design, computational environment and industry requirement evolution. The first segment of the discussion presents the SNP experience base. SNP develops, manufactures and licenses both BWR and PWR reload fuel. A review of this experience base highlights the accelerating rate at which new fuel designs are being introduced into the nuclear industry. The application of advanced BWR lattice geometries provides an example of fuel design trends. The second aspect of the presentation is the rapid evolution of the computing environment. The final subject in the presentation is the impact of industry requirements on code or methods development

  14. Licensing issues

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  15. Idaho National Engineering Laboratory site development plan

    International Nuclear Information System (INIS)

    1994-09-01

    This plan briefly describes the 20-year outlook for the Idaho National Engineering Laboratory (INEL). Missions, workloads, worker populations, facilities, land, and other resources necessary to fulfill the 20-year site development vision for the INEL are addressed. In addition, the plan examines factors that could enhance or deter new or expanded missions at the INEL. And finally, the plan discusses specific site development issues facing the INEL, possible solutions, resources required to resolve these issues, and the anticipated impacts if these issues remain unresolved

  16. License application approach for the California LLRW disposal facility

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  17. Licensing process in Finland

    International Nuclear Information System (INIS)

    Tiippana, Petteri

    2011-01-01

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

  18. Site development and demands on infrastructure

    International Nuclear Information System (INIS)

    Nieke, K.F.

    1976-01-01

    All sub-fields are examined which form the infrastructure, the infrastructure being indispensable for the site development of a nuclear power plant. The main emphasis is put on the technical infrastructure, but the social infrastructure is dealt with, too. The most important sub-fields are: traffic connections, energy supply, external communications, foundation, building mearures. (UA) [de

  19. The dual role of local sites in assisting firms with developing technological capabilities: Evidence from China

    DEFF Research Database (Denmark)

    Wang, Yuandi; Zhou, Zhao

    2013-01-01

    .g., knowledge, human capital) and the role of motivating multinational companies (MNCs) to upgrade their local operations in developing countries so as to perform more innovation activities. Few articles are presented that examine the role of local sites in the learning and technological-capability building......, and the collaborations with local industrial community firms positively influence the relationship between firms' international inward technology licensing and technological capabilities. (C) 2012 Elsevier Ltd. All rights reserved....

  20. Highlights of the SSC Site Development Plan

    International Nuclear Information System (INIS)

    Sanford, J.R.

    1991-10-01

    This paper summarizes highlights of the Site Development Plan for the Superconducting Super Collider Laboratory. The Plan, sometimes called a Master Plan, was prepared by the architectural and engineering firm for the Laboratory: Parsons Brinckerhoff/Morrison Knudsen (PB/MK) working in association with CRSS. Their task was to interpret the SSC project needs in the context of the Ellis County, Texas site. The team effort was under the direction of Lewis May from CRSS, guided by Robert Sims from the SSC Laboratory. Conceptual drawings are presented in this report

  1. 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

  2. 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

  3. Nuclear Siting and Licensing Act of 1978. Hearings before the Subcommittee on Energy and Power, Committee on Interstate and Foreign Commerce, House of Representatives, Ninety-Fifth Congress

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The Subcommittee on Energy and Power conducted hearings on the administration proposal to revise the process by which nuclear power plants are licensed. The purpose of this proposal is to substantially reduce the amount of time needed to license and construct nuclear powerplants. The bill attempts to encourage the early selection of possible sites by separating the process by which such sites are approved fom the process by which plants are licensed. The bill would dispense with the existing requirement that all hearings be adjudicatory, and instead authorize informal hearings on certain issues, principally those which would be conducted pursuant to the National Environmental Policy Act of 1969. The bill would authorize a State which has established a program, consistent with the criteria contained in the act and regulations promulgated by the Nuclear Regulatory Commission, to determine the environmental acceptability of, and/or the need for, a proposed nuclear plant which would be located within its boundaries. Finally, the bill seeks to encourage the use of standardized design and authorizes the NRC to provide funds to intervenors under certain specified conditions

  4. Development of site specific response spectra

    International Nuclear Information System (INIS)

    Bernreuter, D.L.; Chen, J.C.; Savy, J.B.

    1987-03-01

    For a number of years the US Nuclear Regulatory Commission (NRC) has employed site specific spectra (SSSP) in their evaluation of the adequacy of the Safe Shutdown Earthquake (SSE). These spectra were developed only from the spectra of the horizontal components of the ground motion and from a very limited data set. As the data set has considerably increased for Eastern North America (ENA) and as more relevant data has become available from earthquakes occurring in other parts of the world (e.g., Italy), together with the fact that recent data indicated the importance of the vertical component, it became clear that an update of the SSSP's for ENA was desirable. The methodology used in this study is similar to the previous ones in that it used actual earthquake ground motion data with magnitudes within a certain range and recorded at distances and at sites similar to those that would be chosen for the definition of an SSE. An extensive analysis of the origin and size of the uncertainty is an important part of this study. The results of this analysis of the uncertainties is used to develop criteria for selecting the earthquake records to be used in the derivation of the SSSP's. We concluded that the SSSPs were not very sensitive to the distribution of the source to site distance of the earthquake records used in the analysis. That is, the variability (uncertainty) introduced by the range of distances was relatively small compared to the variability introduced by other factors. We also concluded that the SSSP are somewhat sensitive to the distribution of the magnitudes of these earthquakes, particularly at rock sites and, by inference, at shallow soil sites. We found that one important criterion in selecting records to generate SSSP is the depth of soil at the site

  5. 77 FR 5036 - Prospective Grant of Exclusive License: The Development of Human Anti-Mesothelin Monoclonal...

    Science.gov (United States)

    2012-02-01

    ... cancer, lung cancer, mesothelioma, and stomach/gastric cancer. The Licensed Field of Use explicitly.... Lambertson, Ph.D., Senior Licensing and Patenting Manager, Office of Technology Transfer, National Institutes... cancers, including mesothelioma, lung cancer, stomach/gastric cancer, ovarian cancer and pancreatic cancer...

  6. Problems of developing remedial strategy for the uranium ore processing legacy site Pridneprovsky Chemical Plant site (Dneprodzerginsk, Ukraine)

    International Nuclear Information System (INIS)

    Riazantsev, V.; Bugai, D.; Skalskyy, A.; Tkachenko, E.

    2014-01-01

    In this paper we present results of works and studies carried out in the frame of ongoing national and international projects aimed at developing the remedial strategy for the Soviet era legacy uranium production site Pridneprovsky Chemical Plant, Dneprodzerginsk, Ukraine. The site includes several uranium mill tailings, contaminated buildings, ore storage grounds and other contaminated facilities. Taking into account the necessity to implement provisions of the new IAEA standards (Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, No. GSR Part 3 (Interim) and others) as well as the provisions of the ICRP 103 publication, the State Nuclear Regulatory Inspectorate Ukraine developed the draft of the new licensing requirements for activities of uranium ores processing.

  7. Development of an arid site closure plan

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Barnes, F.J.

    1987-01-01

    This document describes the development of a prototype plan for the effective closure and stabilization of an arid low-level waste disposal site. This plan will provide demonstrated closure techniques for a trench in a disposal site at Los Alamos. The accuracy of modeling soil water storage by two hydrologic models, CREAMS and HELP, was tested by comparing simulation results with field measurements of soil moisture in eight experimental landfill cover systems having a range of well-defined soil profiles and vegetative covers. Regression analysis showed that CREAMS generally represented soil moisture more accurately than HELP simulations. Precautions for determining parameter values for model input and for interpreting simulation results are discussed. A specific example is presented showing how the field-validated hydrologic models can be used to develop a final prototype closure plan. 15 refs., 13 figs., 3 tabs

  8. Truncated Dual-Cap Nucleation Site Development

    Science.gov (United States)

    Matson, Douglas M.; Sander, Paul J.

    2012-01-01

    During heterogeneous nucleation within a metastable mushy-zone, several geometries for nucleation site development must be considered. Traditional spherical dual cap and crevice models are compared to a truncated dual cap to determine the activation energy and critical cluster growth kinetics in ternary Fe-Cr-Ni steel alloys. Results of activation energy results indicate that nucleation is more probable at grain boundaries within the solid than at the solid-liquid interface.

  9. Development of a chimeric Zika vaccine using a licensed live-attenuated flavivirus vaccine as backbone.

    Science.gov (United States)

    Li, Xiao-Feng; Dong, Hao-Long; Wang, Hong-Jiang; Huang, Xing-Yao; Qiu, Ye-Feng; Ji, Xue; Ye, Qing; Li, Chunfeng; Liu, Yang; Deng, Yong-Qiang; Jiang, Tao; Cheng, Gong; Zhang, Fu-Chun; Davidson, Andrew D; Song, Ya-Jun; Shi, Pei-Yong; Qin, Cheng-Feng

    2018-02-14

    The global spread of Zika virus (ZIKV) and its unexpected association with congenital defects necessitates the rapid development of a safe and effective vaccine. Here we report the development and characterization of a recombinant chimeric ZIKV vaccine candidate (termed ChinZIKV) that expresses the prM-E proteins of ZIKV using the licensed Japanese encephalitis live-attenuated vaccine SA14-14-2 as the genetic backbone. ChinZIKV retains its replication activity and genetic stability in vitro, while exhibiting an attenuation phenotype in multiple animal models. Remarkably, immunization of mice and rhesus macaques with a single dose of ChinZIKV elicits robust and long-lasting immune responses, and confers complete protection against ZIKV challenge. Significantly, female mice immunized with ChinZIKV are protected against placental and fetal damage upon ZIKV challenge during pregnancy. Overall, our study provides an alternative vaccine platform in response to the ZIKV emergency, and the safety, immunogenicity, and protection profiles of ChinZIKV warrant further clinical development.

  10. Policy development for environmental licensing and biodiversity offsets in Latin America.

    Directory of Open Access Journals (Sweden)

    Ana Villarroya

    Full Text Available Attempts to meet biodiversity goals through application of the mitigation hierarchy have gained wide traction globally with increased development of public policy, lending standards, and corporate practices. With interest in biodiversity offsets increasing in Latin America, we seek to strengthen the basis for policy development through a review of major environmental licensing policy frameworks in Argentina, Brazil, Chile, Colombia, Mexico, Peru and Venezuela. Here we focused our review on an examination of national level policies to evaluate to which degree current provisions promote positive environmental outcomes. All the surveyed countries have national-level Environmental Impact Assessment laws or regulations that cover the habitats present in their territories. Although most countries enable the use of offsets only Brazil, Colombia, Mexico and Peru explicitly require their implementation. Our review has shown that while advancing quite detailed offset policies, most countries do not seem to have strong requirements regarding impact avoidance. Despite this deficiency most countries have a strong foundation from which to develop policy for biodiversity offsets, but several issues require further guidance, including how best to: (1 ensure conformance with the mitigation hierarchy; (2 identify the most environmentally preferable offsets within a landscape context; (3 determine appropriate mitigation replacement ratios; and (4 ensure appropriate time and effort is given to monitor offset performance.

  11. Policy development for environmental licensing and biodiversity offsets in Latin America.

    Science.gov (United States)

    Villarroya, Ana; Barros, Ana Cristina; Kiesecker, Joseph

    2014-01-01

    Attempts to meet biodiversity goals through application of the mitigation hierarchy have gained wide traction globally with increased development of public policy, lending standards, and corporate practices. With interest in biodiversity offsets increasing in Latin America, we seek to strengthen the basis for policy development through a review of major environmental licensing policy frameworks in Argentina, Brazil, Chile, Colombia, Mexico, Peru and Venezuela. Here we focused our review on an examination of national level policies to evaluate to which degree current provisions promote positive environmental outcomes. All the surveyed countries have national-level Environmental Impact Assessment laws or regulations that cover the habitats present in their territories. Although most countries enable the use of offsets only Brazil, Colombia, Mexico and Peru explicitly require their implementation. Our review has shown that while advancing quite detailed offset policies, most countries do not seem to have strong requirements regarding impact avoidance. Despite this deficiency most countries have a strong foundation from which to develop policy for biodiversity offsets, but several issues require further guidance, including how best to: (1) ensure conformance with the mitigation hierarchy; (2) identify the most environmentally preferable offsets within a landscape context; (3) determine appropriate mitigation replacement ratios; and (4) ensure appropriate time and effort is given to monitor offset performance.

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

    International Nuclear Information System (INIS)

    van Erp, J.B.

    1977-12-01

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

  13. Accident consequence assessment and siting criteria development

    International Nuclear Information System (INIS)

    Kollas, J.G.

    1988-01-01

    The methodology developed is based on assessing the average over a large spectrum of meteorological conditions whole body collective dose resulting from a severe reference accident. The assessment of this dose is performed by code CRAC.GAEC, the Greek A.E.C. version of code CRAC2. The collective dose, which is chosen as a measure of the social radiation risk, is compared to the dose corresponding to a level of social risk encountered historically in energy production as a whole. The outcome of the comparison can be the determination of one or more sectors of acceptable sites for a set of specific conditions considered, such as the reactor characteristics. The present approach was aimed to deal with the problems stemming from the demographic idiomorphy of Greece, where one third of the country's population is concentrated in Athens, with the rest of the country exhibiting small population densities. One of the applications of the methodology developed concerned the identification of acceptable sites near Athens. For these sites the risk from the reference severe accident of a standard reactor to the over three millions inhabitants of Athens is less tan the risk corresponding to the same population that is due to energy production

  14. 77 FR 9678 - Prospective Grant of Exclusive License: The Development of Human Anti-CD22 Monoclonal Antibodies...

    Science.gov (United States)

    2012-02-17

    .../patent applications for the technology family, to Sanomab, Ltd. The patent rights in these inventions... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Prospective Grant of Exclusive License: The Development of Human Anti-CD22 Monoclonal Antibodies for the Treatment of Human...

  15. 77 FR 41792 - Prospective Grant of Co-Exclusive License: The Development of Human Anti-CD22 Monoclonal...

    Science.gov (United States)

    2012-07-16

    ... applications for the technology family, to Customized Therapeutics. The patent rights in these inventions have... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Prospective Grant of Co-Exclusive License: The Development of Human Anti-CD22 Monoclonal Antibodies for the Treatment of Human...

  16. 78 FR 13691 - Prospective Grant of Exclusive License: The Development of m971 and m972 Chimeric Antigen...

    Science.gov (United States)

    2013-02-28

    ... Exclusive License: The Development of m971 and m972 Chimeric Antigen Receptors (CARs) for the Treatment of B... ``M971 Chimeric Antigen Receptors'' [HHS Ref. E-291-2012/0-US-01], and (b) U.S. Patent Application 61/042... malignancies that express CD22 on their cell surface using chimeric antigen receptors which contain the m971 or...

  17. 77 FR 62520 - Prospective Grant of Exclusive License: The Development of Anti-CD22 Chimeric Antigen Receptors...

    Science.gov (United States)

    2012-10-15

    ... Exclusive License: The Development of Anti- CD22 Chimeric Antigen Receptors (CARs) for the Treatment of B... ``Anti-CD22 Chimeric Antigen Receptors'' [HHS Ref. E-265-2011/0-US-01], and (b) U.S. Patent Application... CD22 on their cell surface using chimeric antigen receptors which contain the HA22 or BL22 antibody...

  18. Oil and gas development in Greenland: A social license to operate, trust and legitimacy in environmental governance

    NARCIS (Netherlands)

    Smits, C.; Leeuwen, van J.; Tatenhove, van J.P.M.

    2017-01-01

    Since the turn of the century, Greenland has been examining the possibilities to develop its potential oil and gas resources. The large scale oil and gas activities will impact the small Greenlandic society, both positively and negatively. In this paper we employ the concept of a social license to

  19. 78 FR 50425 - Prospective Grant of Exclusive License: Development of Brachyury Tumor Associated Antigens as...

    Science.gov (United States)

    2013-08-19

    ... relating to the contemplated exclusive license should be directed to: Sabarni K. Chatterjee, Ph.D., M.B.A... target for human T-cell mediated cancer immunotherapy, such as for tumors of the lung, intestine, stomach...

  20. 78 FR 7438 - Prospective Grant of Exclusive License: Development of Human Monoclonal Antibodies Against DR4

    Science.gov (United States)

    2013-02-01

    ... receptors are not only effective in killing many types of tumors but they also synergize with traditional... evidence and argument that establishes that the grant of the license would not be consistent with the...

  1. NRC's license renewal regulations

    International Nuclear Information System (INIS)

    Akstulewicz, Francis

    1991-01-01

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

  2. Trends in nuclear licensing

    International Nuclear Information System (INIS)

    Dalton, N.W.

    1990-01-01

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

  3. Trends in nuclear licensing

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-06-01

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

  4. Idaho Chemical Processing Plant Site Development Plan

    International Nuclear Information System (INIS)

    Ferguson, F.G.

    1994-02-01

    The Idaho Chemical Processing Plant (ICPP) mission is to receive and store spent nuclear fuels and radioactive wastes for disposition for Department of Energy (DOE) in a cost-effective manner that protects the safety of Idaho National Engineering Laboratory (INEL) employees, the public, and the environment by: Developing advanced technologies to process spent nuclear fuel for permanent offsite disposition and to achieve waste minimization. Receiving and storing Navy and other DOE assigned spent nuclear fuels. Managing all wastes in compliance with applicable laws and regulations. Identifying and conducting site remediation consistent with facility transition activities. Seeking out and implementing private sector technology transfer and cooperative development agreements. Prior to April 1992, the ICPP mission included fuel reprocessing. With the recent phaseout of fuel reprocessing, some parts of the ICPP mission have changed. Others have remained the same or increased in scope

  5. Securing your Site in Development and Beyond

    Energy Technology Data Exchange (ETDEWEB)

    Akopov, Mikhail S.

    2018-01-04

    Why wait until production deployment, or even staging and testing deployment to identify security vulnerabilities? Using tools like Burp Suite, you can find security vulnerabilities before they creep up on you. Prevent cross-site scripting attacks, and establish a firmer trust between your website and your client. Verify that Apache/Nginx have the correct SSL Ciphers set. We explore using these tools and more to validate proper Apache/Nginx configurations, and to be compliant with modern configuration standards as part of the development cycle. Your clients can use tools like https://securityheaders.io and https://ssllabs.com to get a graded report on your level of compliance with OWASP Secure Headers Project and SSLLabs recommendations. Likewise, you should always use the same sites to validate your configurations. Burp Suite will find common misconfigurations and will also perform more thorough security testing of your applications. In this session you will see examples of vulnerabilities that were detected early on, as well has how to integrate these practices into your daily workflow.

  6. Sensitivity analysis using the FRAPCON-1/EM: development of a calculation model for licensing

    International Nuclear Information System (INIS)

    Chapot, J.L.C.

    1985-01-01

    The FRAPCON-1/EM is version of the FRAPCON-1 code which analyses fuel rods performance under normal operation conditions. This version yields conservative results and is used by the NRC in its licensing activities. A sensitivity analysis was made, to determine the combination of models from the FRAPCON-1/EM which yields the most conservative results for a typical Angra-1 reactor fuel rod. The present analysis showed that this code can be used as a calculation tool for the licensing of the Angra-1 reload. (F.E.) [pt

  7. Development of on-site PAFC stacks

    Energy Technology Data Exchange (ETDEWEB)

    Hotta, K.; Matsumoto, Y. [Kansai Electric Power Co., Amagasaki (Japan); Horiuchi, H.; Ohtani, T. [Mitsubishi Electric Corp., Kobe (Japan)

    1996-12-31

    PAFC (Phosphoric Acid Fuel Cell) has been researched for commercial use and demonstration plants have been installed in various sites. However, PAFC don`t have a enough stability yet, so more research and development must be required in the future. Especially, cell stack needs a proper state of three phases (liquid, gas and solid) interface. It is very difficult technology to keep this condition for a long time. In the small size cell with the electrode area of 100 cm{sup 2}, gas flow and temperature distributions show uniformity. But in the large size cell with the electrode area of 4000 cm{sup 2}, the temperature distributions show non-uniformity. These distributions would cause to be shorten the cell life. Because these distributions make hot-spot and gas poverty in limited parts. So we inserted thermocouples in short-stack for measuring three-dimensional temperature distributions and observed effects of current density and gas utilization on temperature.

  8. SMART-P MMIS Software Development by Considering the Software License for Nuclear Power Plants and the Development Cost

    International Nuclear Information System (INIS)

    Suh, Yong Suk; Park, Jae Hong; Park, Heui Youn; Son, Ki Sung; Lee, Ki Hyun; Kim, Hyeon Soo

    2005-01-01

    The acceptance criteria of software for safety system functions in NPPs (Nuclear Power Plants) are as follows: 1) acceptable plans should be prepared to control the software development activities, 2) the plans should be followed in an acceptable software life cycle, and 3) the process should produce acceptable design outputs. The KINS (Korea Institute of Nuclear Safety) recommended that the software life cycle should be established based on the IEEE Std 1074 with a supplementary requirement of a software safety analysis. The KINS emphasized that the software should be developed to show its high qualities. This paper identifies the major requirements to achieve the software license from the KINS and presents the major facts reflected in the SMART-P (System-integrated Modular Advanced ReacTor-Pilot) MMIS (Man-Machine Interface Systems) which is being developed by KAERI and targeted to start operation in 2010. This paper also addresses major concerns on the development of a safety critical software and the facts reflected in the SMART-P MMIS

  9. Savannah River Site generic data base development

    International Nuclear Information System (INIS)

    Blanchard, A.

    2000-01-01

    This report describes the results of a project to improve the generic component failure database for the Savannah River Site (SRS). Additionally, guidelines were developed further for more advanced applications of database values. A representative list of components and failure modes for SRS risk models was generated by reviewing existing safety analyses and component failure data bases and from suggestions from SRS safety analysts. Then sources of data or failure rate estimates were identified and reviewed for applicability. A major source of information was the Nuclear Computerized Library for Assessing Reactor Reliability, or NUCLARR. This source includes an extensive collection of failure data and failure rate estimates for commercial nuclear power plants. A recent Idaho National Engineering Laboratory report on failure data from the Idaho Chemical Processing Plant was also reviewed. From these and other recent sources, failure data and failure rate estimates were collected for the components and failure modes of interest. For each component failure mode, this information was aggregated to obtain a recommended generic failure rate distribution (mean and error factor based on a lognormal distribution). Results are presented in a table in this report. A major difference between generic database and previous efforts is that this effort estimates failure rates based on actual data (failure events) rather than on existing failure rate estimates. This effort was successful in that over 75% of the results are now based on actual data. Also included is a section on guidelines for more advanced applications of failure rate data. This report describes the results of a project to improve the generic component failure database for the Savannah River site (SRS). Additionally, guidelines were developed further for more advanced applications of database values

  10. Development of a low level radioactive waste disposal site in Texas - 1994 status

    International Nuclear Information System (INIS)

    Jacobi, L.R. Jr.

    1995-01-01

    The Texas Low Level Radioactive Waste Disposal Authority, an agency of the State of Texas, has been trying to develop a site for the disposal of low level radioactive waste in Texas for over ten years. Since 1991, the agency has been evaluating a site near Sierra Blanca, in far west Texas. Site characterization has been completed and a license application has been filed with the Texas Natural Resource Conservation Commission. Construction plans were completed in 1993, and the agency is prepared to begin construction and operations as soon as a license can be issued. Development costs for the site are borne by the utility companies and other major generators in Texas through the assessment of a planning and implementation fee. Total costs to date are approximately $26 million. As the project moves toward completion, state and national anti-nuclear activist groups have become more involved in attempts to thwart the Texas government's effort to solve the radioactive waste problem. To counter this increased opposition, the Texas utility companies and medical radioactive waste generators have also become more active in responding to these groups. This has been very helpful and is in keeping with the elements of building block 12 of the Nuclear Power Oversight Committee's Strategic Plan for Building New Nuclear Power Plants. This paper and poster session look at the schedule, design, and long term prospects for ultimate success of the project

  11. 78 FR 73553 - Prospective Grant of Exclusive License: Development of Cripto-1 Point of Care (POC) Tests and...

    Science.gov (United States)

    2013-12-06

    ... contemplated exclusive license should be directed to: Eggerton Campbell, Ph.D. Licensing and Patenting Manager... colon, pancreas, stomach, gallbladder, breast, lung, endometrium and cervix. Current methodologies of...

  12. 76 FR 63317 - Prospective Grant of Exclusive License: The Development of Human Anti-Mesothelin Monoclonal...

    Science.gov (United States)

    2011-10-12

    ... therapy for the treatment of pancreatic cancer, ovarian cancer, lung cancer, mesothelioma, and stomach.... Lambertson, Ph.D., Senior Licensing and Patenting Manager, Office of Technology Transfer, National Institutes... cancers, including mesothelioma, lung cancer, stomach/gastric cancer, ovarian cancer and pancreatic cancer...

  13. 77 FR 26304 - Prospective Grant of Exclusive License: Development of Ocular Therapeutics Utilizing the Peptide...

    Science.gov (United States)

    2012-05-03

    ..., Rockville, MD 20852-3804; Telephone: (301) 435- 4478; Facsimile: (301) 402-0220; Email: [email protected] (IP) to be included in this exclusive license relates to a protein designated C16Y and variations... tumor bearing mouse model (see Ponce, et al Cancer Research 63: 5060-64 (2003)). The IP covers various...

  14. Licensing and accident reviews for an HNEC

    International Nuclear Information System (INIS)

    Clark, R.G.

    1978-09-01

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

  15. 7 CFR 1948.83 - Performance of site development work.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 13 2010-01-01 2009-01-01 true Performance of site development work. 1948.83 Section 1948.83 Agriculture Regulations of the Department of Agriculture (Continued) RURAL HOUSING SERVICE... Development Assistance Program § 1948.83 Performance of site development work. Site development work will be...

  16. Developing and promoting an intranet site for a drug information service.

    Science.gov (United States)

    Costerison, Emily C; Graham, Angie S

    2008-04-01

    The development and promotion of a drug information service (DIS) intranet site are described. Stanford Hospital and Clinics (SHC) is an acute and tertiary care facility with 613 licensed inpatient beds and 48 outpatient clinics. A DIS intranet site was developed to allow better accessibility to pharmacy forms and products (e.g., drug shortage list, reference guides) and to reduce repetitive requests to the DIS. The goal was to continue to provide information to SHC health care providers but allow the drug information specialist to focus on answering clinical questions. The intranet site was completed over a four-month period. The intranet site was divided into seven webpages: DIS overview, pharmacy and therapeutics, frequently asked questions, quick drug reference guide, ask the pharmacist, drug information resources, and referral center. The preparation for and implementation of the promotional phase took approximately two months. Promotional strategies included the creation and dissemination of brochures and stickers. The intranet site went live on January 1, 2007, and the advertising campaign began one month later. The utility of the site was measured for five months by tracking the number of visits to the site, the number of visits to each webpage, and the number of downloaded files. Request volume, caller affiliation, and question types received by the DIS call center were also recorded. Establishing a DIS intranet site required a considerable time investment and a willingness to work with existing infrastructures, such as the marketing and communications department and Web marketing staff.

  17. 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.

  18. 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)

  19. 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

  20. FOSS License Selection and Code Management

    OpenAIRE

    Vescuso, Peter

    2011-01-01

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

  1. Review of a site developer's geo-scientific data and site-characterisation information to support repository certification

    International Nuclear Information System (INIS)

    Peake, R.T.; Byrum, C.; Ghose, S.

    2007-01-01

    The Waste Isolation Pilot Plant (WIPP) in New Mexico is a first-of-a-kind deep geologic facility for the disposal of transuranic (TRU) radioactive waste from weapons production in the United States. In 1993, Congress authorised the Environmental Protection Agency (EPA) to develop and implement WIPP-site-specific compliance criteria based on the general safety and environmental standards in EPA's high-level and transuranic radioactive waste regulations [1]. EPA published its site-specific regulations [2] in 1996 and certified WIPP to open in 1998. This regulatory framework set the stage for balancing diverse input data, provided a structure for document development, provided a mechanism for interaction between EPA and the Department of Energy (DOE), and provided a guide to support our review of WIPP's safety assessment. EPA's involvement continues during WIPP's operational phase. Confidence in repository site geo-scientific data enhances the regulator's ability to make a credible and defensible certification (licensing) decision and to communicate the basis for the decision to the public. Lack of confidence in the data can lead to lack of credibility about site suitability. Clear regulations and specific quality standards can enhance the quality of site-characterisation documentation and assist the regulator in its approval process of the site. In EPA's regulations, documentation is required on numerous issues, and EPA supplemented this with guidance. High-quality documentation is essential, especially for EPA. In the certification process for WIPP, the documentation in the record and our written interpretation of the record was what was used in legal proceedings that followed EPA's certification of WIPP. EPA and DOE had frequent and generally open communication. During formal regulatory proceedings, all communication had to be documented. Some decisions were made at the staff level, but major decisions were typically addressed and resolved through correspondence

  2. 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.

  3. Development of the Licensing Support Technology for Digital I and C

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, K. C.; Kim, J. Y.; Kang, H. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)] (and others)

    2008-06-15

    This research can provide the required safety and reliability of software for the use of nuclear digital safety systems, achieve the software quality sufficient to arrive at the level of the licensing agreement by the nuclear regulatory agency, and establish the rigorous software V and V procedure by the use of domestic technology. These results will provide independent safety software qualification techniques from, with the equivalent level of, the those acquired by advanced countries. The technologies obtained from this research will be able to be employed at advanced reactors such as super-critical fast reactors, high temperature gas-cooled reactors, and small modularized reactors that promote the use of digital systems.

  4. Development of the Licensing Support Technology for Digital I and C

    International Nuclear Information System (INIS)

    Kwon, K. C.; Kim, J. Y.; Kang, H. K.

    2008-06-01

    This research can provide the required safety and reliability of software for the use of nuclear digital safety systems, achieve the software quality sufficient to arrive at the level of the licensing agreement by the nuclear regulatory agency, and establish the rigorous software V and V procedure by the use of domestic technology. These results will provide independent safety software qualification techniques from, with the equivalent level of, the those acquired by advanced countries. The technologies obtained from this research will be able to be employed at advanced reactors such as super-critical fast reactors, high temperature gas-cooled reactors, and small modularized reactors that promote the use of digital systems

  5. Configuration system development of site and environmental information for radwaste disposal facility

    International Nuclear Information System (INIS)

    Park, Se-Moon; Yoon, Bong-Yo; Kim, Chang-Lak

    2005-01-01

    License for the nuclear facilities such as radioactive waste repository demands documents of site characterization, environmental assessment and safety assessment. This performance will produce bulk of the relevant data. For the safe management of radioactive waste repository, data of the site and environment have to be collected and managed systematically. Particularly for the radwaste repository, which has to be institutionally controlled for a long period after closure, the data will be collected and maintained through the monitoring programme. To meet this requirement, a new programme called 'Site Information and Total Environmental data management System (SITES)' has been developed. The scope and function of the SITES is issued in data DB, safety assessment and monitoring system. In this respect, SITES is designed with two modules of the SITES Database Module (SDM) and the Monitoring and Assesment (M and A). The SDM module is composed of three sub-modules. One is the Site Information Management System (SIMS), which manages data of site characterization such as topography, geology, hydrogeology, engineering geology, etc. The other is the ENVironmental Information management System (ENVIS) and Radioactive ENVironmental Information management System (RENVIS), which manage environmental data required for environmental assessment performance. ENVIS and RENVIS covered almost whole items of environmental assessment report required by Korean government. The SDM was constructed based on Entity Relationship Diagram produced from each item. Also using ArcGIS with the spatial characteristics of the data, it enables groundwater and water property monitoring networks, etc. To be analyzed in respect of every theme. The sub-modules of M and A called the Site and Environment Monitoring System (SEMS) and the Safety Assessment System (SAS) were developed. SEMS was designed to manage the inspection records of the individual measuring instruments and facilities, and the on

  6. The effectiveness of an intervention to reduce alcohol‐related violence in premises licensed for the sale and on‐site consumption of alcohol: a randomized controlled trial

    Science.gov (United States)

    Alam, M. Fasihul; Heikkinen, Marjukka; Hood, Kerenza; Huang, Chao; Moore, Laurence; Murphy, Simon; Playle, Rebecca; Shepherd, Jonathan; Shovelton, Claire; Sivarajasingam, Vaseekaran; Williams, Anne

    2017-01-01

    Abstract Background and Aims Premises licensed for the sale and consumption of alcohol can contribute to levels of assault‐related injury through poor operational practices that, if addressed, could reduce violence. We tested the real‐world effectiveness of an intervention designed to change premises operation, whether any intervention effect changed over time, and the effect of intervention dose. Design A parallel randomized controlled trial with the unit of allocation and outcomes measured at the level of individual premises. Setting All premises (public houses, nightclubs or hotels with a public bar) in Wales, UK. Participants A randomly selected subsample (n = 600) of eligible premises (that had one or more violent incidents recorded in police‐recorded crime data; n = 837) were randomized into control and intervention groups. Intervention and comparator Intervention premises were audited by Environmental Health Practitioners who identified risks for violence and provided feedback by varying dose (informal, through written advice, follow‐up visits) on how risks could be addressed. Control premises received usual practice. Measurements Police data were used to derive a binary variable describing whether, on each day premises were open, one or more violent incidents were evident over a 455‐day period following randomization. Findings Due to premises being unavailable at the time of intervention delivery 208 received the intervention and 245 were subject to usual practice in an intention‐to‐treat analysis. The intervention was associated with an increase in police recorded violence compared to normal practice (hazard ratio = 1.34, 95% confidence interval = 1.20–1.51). Exploratory analyses suggested that reduced violence was associated with greater intervention dose (follow‐up visits). Conclusion An Environmental Health Practitioner‐led intervention in premises licensed for the sale and on‐site consumption of alcohol resulted in an

  7. The effectiveness of an intervention to reduce alcohol-related violence in premises licensed for the sale and on-site consumption of alcohol: a randomized controlled trial.

    Science.gov (United States)

    Moore, Simon C; Alam, M Fasihul; Heikkinen, Marjukka; Hood, Kerenza; Huang, Chao; Moore, Laurence; Murphy, Simon; Playle, Rebecca; Shepherd, Jonathan; Shovelton, Claire; Sivarajasingam, Vaseekaran; Williams, Anne

    2017-11-01

    Premises licensed for the sale and consumption of alcohol can contribute to levels of assault-related injury through poor operational practices that, if addressed, could reduce violence. We tested the real-world effectiveness of an intervention designed to change premises operation, whether any intervention effect changed over time, and the effect of intervention dose. A parallel randomized controlled trial with the unit of allocation and outcomes measured at the level of individual premises. All premises (public houses, nightclubs or hotels with a public bar) in Wales, UK. A randomly selected subsample (n = 600) of eligible premises (that had one or more violent incidents recorded in police-recorded crime data; n = 837) were randomized into control and intervention groups. Intervention premises were audited by Environmental Health Practitioners who identified risks for violence and provided feedback by varying dose (informal, through written advice, follow-up visits) on how risks could be addressed. Control premises received usual practice. Police data were used to derive a binary variable describing whether, on each day premises were open, one or more violent incidents were evident over a 455-day period following randomization. Due to premises being unavailable at the time of intervention delivery 208 received the intervention and 245 were subject to usual practice in an intention-to-treat analysis. The intervention was associated with an increase in police recorded violence compared to normal practice (hazard ratio = 1.34, 95% confidence interval = 1.20-1.51). Exploratory analyses suggested that reduced violence was associated with greater intervention dose (follow-up visits). An Environmental Health Practitioner-led intervention in premises licensed for the sale and on-site consumption of alcohol resulted in an increase in police recorded violence. © 2017 The Authors. Addiction published by John Wiley & Sons Ltd on behalf of Society for the Study of

  8. 78 FR 20671 - Prospective Grant of A Start-Up Commercialization Exclusive License: The Development of Fenoterol...

    Science.gov (United States)

    2013-04-05

    ... Brain and Hepatocellular Cancers AGENCY: National Institutes of Health, HHS. ACTION: Notice. SUMMARY..., and use in humans for the treatment of brain cancer or hepatocellular cancer within the Licensed... contemplated exclusive commercialization license should be directed to: Patrick McCue, Ph.D., Licensing and...

  9. Radiation Protection training WEB site to hold pedagogical material for developing courses a distance way

    International Nuclear Information System (INIS)

    Marco, M.; Rodriguez, M.; Hernando, E.; Falcon, S.; Rodriguez, M.; Villarroel, R.

    2003-01-01

    Radiation Protection Training (RPT) System in Spain are is well defined in the local local regulations related to radioactive facilities licensing and radiation protection. A system of personnel licenses is established considering two levels of required radiation protection training-supervisor and operator according to responsibilities assigned during the operation of the radioactive facilities. This paper present the major advances already done in the educational web site maintained on the CIEMAT server and accessible through the CSN web. The project includes training material for sixteen applied courses and the design of a educational web site to hold pedagogical material for developing distant learning courses. The main objective of this project is to provide training materials for course organisers, trainers and for professional participants and to promote the exchange of expertise between workers involved in all activities using radiation sources. The project also aims to provide necessary mechanism for standardisation of the radiation protection knowledge made available to the exposed workers, including theoretical and practical training. The developed training material included in the project will cover all uses of radioactive sources including medical diagnosis. The web site is being developed of provide educational material on a modular design and in Spanish. The paper presents the initial results of this useful tool for practitioners. Courses are based on core modules with basic and specific modules involving different targets groups, and the contents can be easily adapted for other target groups. For each one of the modules should be included in the web site: objectives, syllabus, lessons and practical sessions, demo and lab exercises, etc. The project includes training tools for sixteen courses based in the standard syllabus content in the Spanish legal framework. In the next future complete materials for trainers will be available to case courses

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

    International Nuclear Information System (INIS)

    Hahn, F.J.

    1976-01-01

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

  11. Licensing of New Nuclear Power Plants in Canada

    International Nuclear Information System (INIS)

    Schwarz, Garry; Miller, Doug

    2011-01-01

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

  12. Developing a workable public input process for aesthetics and recreational needs during hydropower licensing

    International Nuclear Information System (INIS)

    Howe, D.; Stimac, M.

    1993-01-01

    Aesthetics and recreation are becoming increasingly important issues during hydropower licensing. A variety of regulations and legislation mandate the protection of instream flows for aesthetic and recreational resources. These have provided impetus for determining the effects of instream flows on recreation and aesthetic resources. A public survey designed for a proposed small hydropower project, located in a heavily used recreation area, attempts to determine the aesthetic and recreational preferences for instream flows. The major components in designing the survey are discussed. The public input process is still underway, however, preliminary results indicate lower flows in the river are generally preferable by visitors of the area. This is likely because of the types of users and the recreation activities performed

  13. The Reactor Analysis Support Package (RASP): Volume 10, Guidelines for developing a reload licensing capability:Final report

    International Nuclear Information System (INIS)

    Diamond, D.J.

    1988-08-01

    The EPRI Reactor Analysis Support Package (RASP) consists of computer codes and documentation for calculating core performance and plant transients. This report was written to help a utility to use these tools properly for reload design and safety evaluations. The emphasis is on the steps that the utility can take to develop a methodology that is approved by the Nuclear Regulatory Commission for reload licensing submittals. The report treats both the planning and the implementation of this type of calculational capability. With regard to planning, there is discussion defining objectives, resource requirements, organization and scheduling. In order to help the engineering staff implement the plan there is discussion of the development of a methodology for event analysis, qualification of the methods, and the writing of design control procedures and topical reports. The experience of utilities, and especially of GPU Nuclear Corporation (GPUN), in developing a reload licensing capability is cited throughout the report and extracts from GPUN design control procedures are included in the appendices. 16 refs., 23 figs., 9 tabs

  14. Nuclear facilities licensing

    International Nuclear Information System (INIS)

    Carvalho, A.J.M. de.

    1978-01-01

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

  15. The Clinch Bend Regional Industrial Site and economic development opportunities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    This effort focuses initially on the Clinch Bend site. Other sites and developable tracts of land are identified with the assistance of communities in proximity to Oak Ridge, the State of Tennessee, and others, and compared with the projected site requirements for large industrial facilities.

  16. Part 2: Conserving and Planting Trees at Development Sites

    Science.gov (United States)

    Karen Cappiella; Tom Schueler; Tiffany Wright

    2006-01-01

    This manual presents specific ways to enable developers, engineers or landscape architects to incorporate more trees into a development site. The proposed approach focuses on protecting existing trees, planting trees in storm water treatment practices, and planting trees in other open spaces at the development site. This manual introduces conceptual designs for storm...

  17. Use of modeling in repository licensing

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  18. Development in France of nuclear safety technical regulations and standards used in the licensing procedure

    International Nuclear Information System (INIS)

    Lebouleux, P.

    1983-04-01

    Initially, the Commissariat a l'Energie Atomique was the overall structure which encompassed all nuclear activities in France, including those connected with radiological protection and nuclear safety. As other partners appeared, the Authorities have laid down national regulations relative to nuclear installations since 1963. These regulations more particularly provide for the addition of prescriptions with which the applicant must comply to obtain the necessary licenses and the establishment of General Technical Regulations pertaining to nuclear safety. The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operation of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. A RFS, or a letter, can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

  19. Hydrogeological Site Descriptive Model - a strategy for its development during Site Investigations

    Energy Technology Data Exchange (ETDEWEB)

    Rhen, Ingvar [SWECO VIAK AB, Goeteborg (Sweden); Follin, Sven [SF GeoLogic AB, Stockholm (Sweden); Hermanson, Jan [Golder Associates, Stockholm (Sweden)

    2003-04-01

    The report is to present a strategy for the development of the Site Descriptive Hydrogeological Model within the SKB Site Investigation Programme. The report, and similar reports from the Geology, Rock Mechanics, Thermal properties, Hydrogeochemistry, Transport Properties and Surface Ecosystem disciplines are intended to guide SKB Site Descriptive Modelling but also to provide the authorities with an overview of how the modelling should be performed. Thus the objectives of this report are to: provide guidelines for the modelling of different sites resulting in consistent handling of modelling issues during the Site Investigations, provide a structure for the modelling sequence that is suitable for the establishment of a Site Descriptive model and provide some necessary details that should be considered in a Site Descriptive model.

  20. Hydrogeological Site Descriptive Model - a strategy for its development during Site Investigations

    International Nuclear Information System (INIS)

    Rhen, Ingvar; Follin, Sven; Hermanson, Jan

    2003-04-01

    The report is to present a strategy for the development of the Site Descriptive Hydrogeological Model within the SKB Site Investigation Programme. The report, and similar reports from the Geology, Rock Mechanics, Thermal properties, Hydrogeochemistry, Transport Properties and Surface Ecosystem disciplines are intended to guide SKB Site Descriptive Modelling but also to provide the authorities with an overview of how the modelling should be performed. Thus the objectives of this report are to: provide guidelines for the modelling of different sites resulting in consistent handling of modelling issues during the Site Investigations, provide a structure for the modelling sequence that is suitable for the establishment of a Site Descriptive model and provide some necessary details that should be considered in a Site Descriptive model

  1. Site-specific development plan: Carlin, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Fiore, J.H.

    1980-01-01

    The conditions for developing the geothermal resource near Carlin appear favorable. The resource has a favorable temperature range for direct applications (174/sup 0/F or 79/sup 0/C), the geothermal fluid has low total dissolved solids, no objectionable constituents that would result in costly scaling or corrosion problems and the resource is conveniently located within two miles from town. Direct space heating is the most realistic application and is recommended. Several clusters of homes are located less than 2 miles away. The project could be developed on a larger scale than this study proposes. The engineering and economic models are proposed on a small scale here for simplicity in evaluating the feasibility of pursuing development. Conceivably the producing well will provide sufficient hot water to accommodate more homes than the models include. The town of Carlin seems receptive to development and there does not appear to be any major barriers to exploration or development. The regulatory climate in both the state and county is conducive to geothermal development at this level. No major regulatory or environmental obstacles are noted which would severely curtail utilization for space heating. The prospect of replacing natural gas heat with geothermal heat for 60 or more homes is economically attractive. Geothermal rates for hot water are not expected to increase as rapidly as the price of natural gas to the consumer over the next 10 years. The increases for hot water from geothermal are primarily a function of power costs for the pumps plus inflation affecting maintenance costs. Individual homeowners can expect payback on retrofitting costs within two to three years.

  2. 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

  3. Site map | IDRC - International Development Research Centre

    International Development Research Centre (IDRC) Digital Library (Canada)

    Livestock Vaccine Innovation Fund · Open Data for Development · Safe and Inclusive Cities · Science Granting Councils Initiative in Sub-Saharan Africa · Think Tank Initiative · Funding · Graduate Student Awards · Grants · Subscribe to funding alerts · In their own words: IDRC awardees share their experiences · Resources.

  4. The probabilistic approach in the licensing process and the development of probabilistic risk assessment methodology in Japan

    International Nuclear Information System (INIS)

    Togo, Y.; Sato, K.

    1981-01-01

    The probabilistic approach has long seemed to be one of the most comprehensive methods for evaluating the safety of nuclear plants. So far, most of the guidelines and criteria for licensing are based on the deterministic concept. However, there have been a few examples to which the probabilistic approach was directly applied, such as the evaluation of aircraft crashes and turbine missiles. One may find other examples of such applications. However, a much more important role is now to be played by this concept, in implementing the 52 recommendations from the lessons learned from the TMI accident. To develop the probabilistic risk assessment methodology most relevant to Japanese situations, a five-year programme plan has been adopted and is to be conducted by the Japan Atomic Research Institute from fiscal 1980. Various problems have been identified and are to be solved through this programme plan. The current status of developments is described together with activities outside the government programme. (author)

  5. 1994 Site Development Plan: A plan with vision

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The 1994 Lawrence Livermore National Laboratory Site Development Plan has been developed during a period of great change and uncertainty. Our goal is to make possible the best use of the Laboratory`s resources to meet shifting national priorities in the post-Cold War world. Site Planning is an important component of the overall Laboratory strategic planning process. This plan focuses on opportunities for the Laboratory as well as on key site development issues including facility construction, redevelopment and reuse, site accessibility, and security. A major challenge is to achieve sufficient stability in the site planning and execution so that the processes of construction can occur efficiently while at the same time providing sufficient flexibility in site facilities so that a range of changing national needs can be accommodated. We are closely coupled to the DOE strategic planning process to meet this challenge.

  6. Development and Assessment of the Appendix K Version of RELAP5-3D for LOCA Licensing Analysis

    International Nuclear Information System (INIS)

    Liang, Thomas K.S.; Chang, C.-J.; Hung, H.-J.

    2002-01-01

    In light water reactors, particularly the pressurized water reactor (PWR), the severity of a loss-of-coolant accident (LOCA) would limit how high the reactor power can operate. Although the best-estimate LOCA licensing methodology can provide the greatest margin on the peak cladding temperature (PCT) evaluation during a LOCA, it generally takes much more resources to develop. Instead, implementation of evaluation models required by Appendix K of 10CFR50 on an advanced thermal-hydraulic platform such as RELAP5, TRAC, etc., also can gain significant margin for the PCT calculation. Through compliance evaluation against Appendix K of 10CFR50, all of the required evaluation models have been implemented in RELAP5-3D. To verify and assess the development of the Appendix K version of RELAP5-3D, nine kinds of separate-effects experiments and eight sets of LOCA integral experiments were adopted. Through the assessments against separate-effects experiments, the success of the code modification in accordance with Appendix K of 10CFR50 was demonstrated. Besides, one set of a typical integral large-break LOCA from Loss-of-Fluid Test Facility experiments (L2-5) has also been applied to preliminarily evaluate the integral performance of the Appendix K version of RELAP5-3D. The PCT predicted by the evaluation models is greater than the one from best-estimate calculation in the whole LOCA history with the conservatism of 150 K, and the measured PCTs of L2-5 are also well bounded by the evaluation model calculation. Another seven sets of integral-effect experiments will be further applied in the next step to ensure the reasonable integral conservatism of the newly developed LOCA licensing analysis code (RELAP5-3DK/INER), which can cover all the phases of both large- and small LOCA in one code

  7. Development of software tools for supporting building clearance and site release at UKAEA

    International Nuclear Information System (INIS)

    Jessop, G.; Pearl, M.

    2002-01-01

    UKAEA sites generally have complex histories and have been subject to a diverse range of nuclear operations. Most of the nuclear reactors, laboratories, workshops and other support facilities are now redundant and a programme of decommissioning works in accordance with IAEA guidance is in progress. Decommissioning is being carried out in phases with post- operative activities, care and maintenance and care and surveillance periods between stages to allow relatively short-lived radioactivity to decay. This reduces dose levels to personnel and minimises radioactive waste production. Following on from these stages is an end point phase which corresponds to the point at which the risks to human health and the environment are sufficiently low so that the buildings / land can be released for future use. Unconditional release corresponds to meeting the requirement for 'de-licensing'. Although reaching a de-licensable end point is the desired aim for UKAEA sites, it is recognised that this may take hundreds of years for parts of some UKAEA sites, or may never be attainable at a reasonable cost to the UK taxpayer. Thus on these sites, long term risk management systems are in place to minimise the impact on health, safety and the environment. In order to manage these short, medium and long term liabilities, UKAEA has developed a number of software tools based on good practice guidance. One of these tools in particular is being developed to address building clearance and site release. This tool, IMAGES (Information Management and Geographical Information System) integrates systematic data capture, with database management and spatial assessment (through a Geographical Information System). Details of IMAGES and its applications are discussed in the paper. This paper outlines the approach being adopted by UKAEA for building and site release and the integrated software system, IMAGES, being used to capture, collate, interpret and report results. The key to UKAEA's strategy for

  8. Paraho oil shale module. Site development plan, Task 4

    Energy Technology Data Exchange (ETDEWEB)

    1981-10-01

    A management plan and schedule which covers all requirements for gaining access to the site and for conducting a Paraho Process demonstration program have been prepared. The oil shale available should represent a regional resource of suitable size and quality for commercial development. Discussed in this report are: proof of ownership; requirements for rights-of-way for access to the site; local zoning restrictions; water rights; site availability verification; and other legal requirements. (DMC)

  9. The partnership approach to siting and developing radioactive waste management facilities

    International Nuclear Information System (INIS)

    2010-03-01

    History shows that the search for sites for radioactive waste management facilities has been marred by conflicts and delays. Affected communities have often objected that their concerns and interests were not addressed. In response, institutions have progressively turned away from the traditional 'decide, announce and defend' model, and are learning to 'engage, interact and co-operate'. This shift has fostered the emergence of partnerships between the proponent of the facility and the potential host community. Working in partnership with potential host communities enables pertinent issues and concerns to be raised and addressed, and creates an opportunity for developing a relationship of mutual understanding and mutual learning, as well as for developing solutions that will add value to the host community and region. Key elements of the partnership approach are being incorporated into waste management strategies, leading increasingly to positive outcomes. National radioactive waste management programmes are in various phases of siting facilities and rely on different technical approaches for the various categories of waste. In all cases, it is necessary for institutional actors and the potential or actual host community to build a meaningful, workable relationship. Partnership approaches are effective in achieving a desirable combination of licensable site and management concept while meeting the sometimes competing requirements of fair representation and competent participation. Partnership arrangements facilitate reaching agreement on measures for local control, financial support and future development

  10. Development and maintenance of the Hanford Site Radiological Control Manual

    International Nuclear Information System (INIS)

    Munson, L.H.; Selby, J.M.; Vargo, G.J.; Clark, D.L.

    1993-04-01

    In June 1992 the US Department of Energy (DOE) issued DOE N5480.6, Radiological Control, which set forth DOE's Radiological Control Program and established the framework for its implementation at sites nationwide. Accompanying the Order was the DOE Radiological Control Manual (DOE RCM), which provided the detailed requirements for the program. The Order also mandated Field Office issuance of site-specific radiological control manuals by December 1, 1992. This paper presents the approach taken to develop, review, approve, implement, and subsequently maintain the site-specific manual for the DOE Richland Field Office (RL) at Hanford Site

  11. Even Faster Web Sites Performance Best Practices for Web Developers

    CERN Document Server

    Souders, Steve

    2009-01-01

    Performance is critical to the success of any web site, and yet today's web applications push browsers to their limits with increasing amounts of rich content and heavy use of Ajax. In this book, Steve Souders, web performance evangelist at Google and former Chief Performance Yahoo!, provides valuable techniques to help you optimize your site's performance. Souders' previous book, the bestselling High Performance Web Sites, shocked the web development world by revealing that 80% of the time it takes for a web page to load is on the client side. In Even Faster Web Sites, Souders and eight exp

  12. Emergency preparedness source term development for the Office of Nuclear Material Safety and Safeguards-Licensed Facilities

    International Nuclear Information System (INIS)

    Sutter, S.L.; Mishima, J.; Ballinger, M.Y.; Lindsey, C.G.

    1984-08-01

    In order to establish requirements for emergency preparedness plans at facilities licensed by the Office of Nuclear Materials Safety and Safeguards, the Nuclear Regulatory Commission (NRC) needs to develop source terms (the amount of material made airborne) in accidents. These source terms are used to estimate the potential public doses from the events, which, in turn, will be used to judge whether emergency preparedness plans are needed for a particular type of facility. Pacific Northwest Laboratory is providing the NRC with source terms by developing several accident scenarios for eleven types of fuel cycle and by-product operations. Several scenarios are developed for each operation, leading to the identification of the maximum release considered for emergency preparedness planning (MREPP) scenario. The MREPP scenarios postulated were of three types: fire, tornado, and criticality. Fire was significant at oxide fuel fabrication, UF 6 production, radiopharmaceutical manufacturing, radiopharmacy, sealed source manufacturing, waste warehousing, and university research and development facilities. Tornadoes were MREPP events for uranium mills and plutonium contaminated facilities, and criticalities were significant at nonoxide fuel fabrication and nuclear research and development facilities. Techniques for adjusting the MREPP release to different facilities are also described

  13. Development of a site analysis tool for distributed wind projects

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, Shawn [The Cadmus Group, Inc., Waltham MA (United States)

    2012-02-28

    The Cadmus Group, Inc., in collaboration with the National Renewable Energy Laboratory (NREL) and Encraft, was awarded a grant from the Department of Energy (DOE) to develop a site analysis tool for distributed wind technologies. As the principal investigator for this project, Mr. Shawn Shaw was responsible for overall project management, direction, and technical approach. The product resulting from this project is the Distributed Wind Site Analysis Tool (DSAT), a software tool for analyzing proposed sites for distributed wind technology (DWT) systems. This user-friendly tool supports the long-term growth and stability of the DWT market by providing reliable, realistic estimates of site and system energy output and feasibility. DSAT-which is accessible online and requires no purchase or download of software-is available in two account types; Standard: This free account allows the user to analyze a limited number of sites and to produce a system performance report for each; and Professional: For a small annual fee users can analyze an unlimited number of sites, produce system performance reports, and generate other customizable reports containing key information such as visual influence and wind resources. The tool’s interactive maps allow users to create site models that incorporate the obstructions and terrain types present. Users can generate site reports immediately after entering the requisite site information. Ideally, this tool also educates users regarding good site selection and effective evaluation practices.

  14. Biosphere reserves – learning sites of sustainable development?

    Czech Academy of Sciences Publication Activity Database

    Kušová, Drahomíra; Těšitel, Jan; Bartoš, Michael

    2008-01-01

    Roč. 14, č. 3 (2008), s. 221-234 ISSN 1211-7420 Institutional research plan: CEZ:AV0Z60870520 Keywords : nature protection * learning sites * biosphere reserves * sustainable development Subject RIV: DO - Wilderness Conservation

  15. Selecting Suitable Sites for Wind Energy Development in Ghana ...

    African Journals Online (AJOL)

    Selecting Suitable Sites for Wind Energy Development in Ghana. ... In the event of shortages in petroleum products, these power plants will have ... Layers of these criteria setting were combined using the overlay function in a GIS environment.

  16. A GIS connection between brownfield sites, transportation and economic development.

    Science.gov (United States)

    2011-08-01

    "This report outlines the design and development of a web-based data distribution system for brownfield site redevelopment in Toledo-Lucas County, Ohio. The system is designed to advance smart growth initiatives by creating the link between transport...

  17. A future for nuclear sites beyond their service life. Nuclear site value development

    International Nuclear Information System (INIS)

    2008-01-01

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites in built

  18. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 9, Index

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules.

  19. EPA-developed, patented technologies related to water monitoring and remediation that are available for licensing

    Data.gov (United States)

    U.S. Environmental Protection Agency — Under the Federal Technology Transfer Act (FTTA), Federal Agencies can patent inventions developed during the course of research. These technologies can then be...

  20. EPA-developed, patented technologies related to pollution prevention that are available for licensing.

    Data.gov (United States)

    U.S. Environmental Protection Agency — Under the Federal Technology Transfer Act (FTTA), Federal Agencies can patent inventions developed during the course of research. These technologies can then be...

  1. EPA-developed, patented technologies related to air quality that are available for licensing

    Data.gov (United States)

    U.S. Environmental Protection Agency — Under the Federal Technology Transfer Act (FTTA), Federal Agencies can patent inventions developed during the course of research. These technologies can then be...

  2. EPA-developed, patented technologies related to waste that are available for licensing

    Data.gov (United States)

    U.S. Environmental Protection Agency — Under the Federal Technology Transfer Act (FTTA), Federal Agencies can patent inventions developed during the course of research. These technologies can then be...

  3. Geothermal energy in Washington: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    Bloomquist, R.G.

    1979-04-01

    This is an attempt to identify the factors which have affected and will continue to affect geothermal assessment and development in the state. The eight potential sites chosen for detailed analysis include: Indian Heaven KGRA, Mount St. Helens KGRA, Kennedy Hot Springs KGRA, Mount Adams PGRA (Potential Geothermal Resource Area), Mount Rainier PGRA, Mount Baker PGRA, Olympic-Sol Duc Hot Springs, and Yakima. The following information is included for each site: site data, site location and physical description, geological/geophysical description, reservoir characteristics, land ownership and leasing, geothermal development status, institutional characteristics, environmental factors, transportation and utilities, and population. A number of serious impediments to geothermal development were identified which can be solved only by legislative action at the state or federal level and/or changes in attitudes by regulatory agencies. (MHR)

  4. Development of a comprehensive management site evaluation methodology

    International Nuclear Information System (INIS)

    Rodgers, J.C.; Onishi, Y.

    1981-01-01

    The Nuclear Regulatory Commission is in the process of preparing regulations that will define the necessary conditions for adequate disposal of low-level waste (LLW) by confinement in an LLW disposal facility. These proposed regulations form the context in which the motivation for the joint Los Alamos National Laboratory Battelle Pacific Northwest Laboratory program to develop a site-specific, LLW site evaluation methodology is discussed. The overall effort is divided into three development areas: land-use evaluation, environmental transport modelling, and long term scenario development including long-range climatology projections. At the present time four steps are envisioned in the application of the methodology to a site: site land use suitability assessment, land use-ecosystem interaction, contaminant transport simulation, and sensitivity analysis. Each of these steps is discussed in the paper. 12 refs

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

    Directory of Open Access Journals (Sweden)

    William Cross

    2016-09-01

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

  6. COMPULSORY LICENSE IN BIODIVERSITY BASED PATENT: PUBLIC HEALTH CONCERN AND BENEFIT SHARING FOR DEVELOPING COUNTRIES

    OpenAIRE

    Dr.Ranti Fauza Mayana, SH.*1 & Tisni Santika, SH.2

    2018-01-01

    It is certainly true that when it comes to high-quality medicines, most of which are produced by international pharmaceutical companies - people have to pay premium prices. The prices are unaffordable for most of society in developing and under developed countries. With some 80 % of the world’s biological diversity lying in the tropical and sub tropical regions of the south (Velasquez G. and Boulet P, 1999), accompanied by the fact that 56 % of the top 150 prescribed drugs in the United Sta...

  7. 48 CFR 227.7203-4 - License rights.

    Science.gov (United States)

    2010-10-01

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

  8. Support in the development of Regulatory Procedures for licensing Lepse Waste Management Operations

    International Nuclear Information System (INIS)

    2001-05-01

    This report describes a project intended to assist Gosatomnadzor of Russia develop a set of documents defining the regulatory requirements for information to be submitted to Gosatomnadzor in support of any application for a licence relating to the removal of spent nuclear fuel from the depot ship Lepse. The project resulted in the development of three regulatory documents covering the documentation required in support of a licence application, the requirements for quality assurance arrangements and the safety analysis report. The working method adopted involved staged development of draft material and review at workshops involving a wide variety of relevant Russian and western organizations. The input and output of the workshops was fully documented to provide an audit trail for the document development and the rationale for what has been included and what is excluded and why. The availability of the regulatory documents in English should significantly assist in the use of the documents by western partners in the actual industrial project. Important experience and information was exchanged among participants in the project. The developing understanding is an important element in providing confidence, from a western perspective, that appropriate regulatory supervision can be applied to industrial projects supported by organizations such as the European Commission and national agencies. The same working methods could be used in the next phase of Lepse regulatory support, i.e., support in development of the procedures for the regulatory review of licence applications, and, subsequently, support in the application of the regulatory inspection process to ensure licence conditions are being complied with. Similarly, these working methods could be used in providing regulatory support for nuclear and radiation safety related to other industrial projects involving radioactive waste management. The participants in this sub-project described in this report were Norwegian

  9. Licensing procedures for Low-Level Waste disposal facilities

    International Nuclear Information System (INIS)

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

    1985-09-01

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

  10. Licensing procedures for Low-Level Waste disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

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

    1985-09-01

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

  11. International developments in uranium mining and mill site remediation

    International Nuclear Information System (INIS)

    Quarch, H.; Kuhlmann, J.; Daroussin, J.L.; Poyser, R.W.

    1993-01-01

    At the end of production, mine sites, mill sites, tailings ponds, heap leaching residues in uranium mining districts world-wide have to be remediated in a responsible and sustainable manner in order to minimize long term environmental impacts. Current practice, regulatory environments and rehabilitation objectives in some of the most important uranium producing countries are briefly characterized as well as applicable radioprotection and geotechnical criteria. Important local and regional variables are outlined which determine optimal site specific solutions. Examples from Europe and North America are shown. Monitoring and control requirements as well as areas of current and necessary research and development are identified

  12. Development of site-specific soil cleanup criteria: New Brunswick Laboratory, New Jersey site

    Energy Technology Data Exchange (ETDEWEB)

    Veluri, V.R.; Moe, H.J.; Robinet, M.J.; Wynveen, R.A.

    1983-03-01

    The potential human exposure which results from the residual soil radioactivity at a decommissioned site is a prime concern during D and D projects. To estimate this exposure, a pathway analysis approach is often used to arrive at the residual soil radioactivity criteria. The development of such a criteria for the decommissioning of the New Brunswick Laboratory, New Jersey site is discussed. Contamination on this site was spotty and located in small soil pockets spread throughout the site area. Less than 1% of the relevant site area was contaminated. The major contaminants encountered at the site were /sup 239/Pu, /sup 241/Am, normal and natural uranium, and natural thorium. During the development of the pathway analysis to determine the site cleanup criteria, corrections for the inhomogeneity of the contamination were made. These correction factors and their effect upon the relevant pathway parameters are presented. Major pathways by which radioactive material may reach an individual are identified and patterns of use are specified (scenario). Each pathway is modeled to estimate the transfer parameters along the given pathway, such as soil to air to man, etc. The transfer parameters are then combined with dose rate conversion factors (ICRP 30 methodology) to obtain soil concentration to dose rate conversion factors (pCi/g/mrem/yr). For an appropriate choice of annual dose equivalent rate, one can then arrive at a value for the residual soil concentration. Pathway modeling, transfer parameters, and dose rate factors for the three major pathways; inhalation, ingestion and external exposure, which are important for the NBL site, are discussed.

  13. Latest development in project site radwaste treatment facility (SRTF) Sanmen

    International Nuclear Information System (INIS)

    Mennicken, K.; Lohmann, P.

    2015-01-01

    Westinghouse Electric Germany GmbH (WEG) was successful in being awarded a contract as to the planning, delivery, installation and commissioning of radwaste treatment systems for the AP1000 units at Sanmen site, PR China. Operational low and intermediate level radioactive waste will be processed in the Site Radwaste Treatment Facility (SRTF). This paper explains the latest developments of the project, especially the experience with customer-hired Chinese planning partners, installation companies and Customer operating personnel. (authors)

  14. Geothermal energy in Montana: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    Brown, K.E.

    1979-11-01

    A short description of the state's geothermal characteristics, economy, and climate is presented. More specific information is included under the planning regions and site specific data summaries. A brief discussion of the geothermal characteristics and a listing of a majority of the known hot springs is included. The factors which influence geothermal development were researched and presented, including: economics, financing, state leasing, federal leasing, direct-use technology, water quality laws, water rights, and the Major Facility Siting Act. (MHR)

  15. Development of an Owner Engineer's independent capability in NPP safety and licensing

    International Nuclear Information System (INIS)

    Auglaire, M.; Bayart, D.; D'Eer, A.; Polet, F.; Vanhoenacker, L.; Zhang, J.

    2002-01-01

    As Owner's Engineer to Electrabel, the Belgian utility which owns and operates the 7 NPPs in Belgium, Tractebel Energy Engineering has gained considerable experience in the field of ten-yearly safety overhauls of NPPs since 1983. It has developed a methodology leading to proposing corrective actions by means of a global and integrated approach in which safety improvement costs are optimized. Safety issues addressed during those projects encompass the writing of Probabilistic Safety Assessment studies, post-TMI recommendations implementation, the installation of autocatalytic recombiners, accident studies, protection against pressurized thermal shock, impact of flooding of internal or external origin, implementation of severe accident management guidelines, re-evaluation of the environment, verification of extreme climate conditions, updating of the Safety Analysis Reports, operation review. (author)

  16. DEVELOPING SITE-SPECIFIC DERIVED CONCENTRATION GUIDELINE LEVELS FOR MULTIPLE MEDIA AT THE CONNECTICUT YANKEE HADDAM NECK PLANT

    International Nuclear Information System (INIS)

    Taylor, S.W.; Smith, L.C.; Carr, R.K.; Carson, A.; Darois, E.

    2003-01-01

    As part of the license termination process, site-specific Derived Concentration Guideline Levels for the Haddam Neck Plant site are developed for soil, groundwater, concrete left standing, and concrete demolished that satisfy the radiological criteria for unrestricted use as defined in 10 CFR 20.1402. Background information on the license termination process and characteristics of the Haddam Neck Plant site are presented. The dose models and associated resident farmer and building occupancy scenarios, applicable pathways, and critical groups developed to establish the Derived Concentration Guideline Levels are described. A parameter assignment process is introduced wherein general population values are used to establish behavioral and metabolic parameters representative of an average member of the critical group, while the uncertainty associated with important physical parameters is considered. A key element of the parameter assignment process is the use of sensitivity analysis to identify the dose sensitive physical parameters and to ensure that such parameters are assigned conservative values. Structuring the parameter assignment process, completing the formal sensitivity analyses, and assigning conservative values to the sensitive physical parameters in a consistent way establishes a calculation framework that lead to Derived Concentration Guideline Levels with a uniform level of conservatism across all media and all radionuclides

  17. Development of an integrated condition monitoring system for meeting license renewal criteria

    International Nuclear Information System (INIS)

    Jarrell, D.B.; Stratton, R.C.

    1991-01-01

    A project for developing a methodology that facilitates an artificial intelligence (AI) approach to the integration of component condition monitoring, fault diagnostics, and component failure root cause analysis is in progress at PNL. Using model-based reasoning with an object oriented schematic representation, these combined elements provide a real-time interactive means to systematically investigate, understand and auto-document the mitigation of age-related component degradation. A common Data Acquisition System contains component parameter and machinery history data as well as a knowledge of the plant system configuration. The unique aspect of this system is that it integrates this component parametric, diagnostic, and failure history knowledge to determine a more complete computerized specification of the component condition than was previously possible. This condition specification is then compared to degradation process models for behavioral similitude, thereby identifying the active degradation mechanism. Based on the monitored trends and the degradation model, an accurate estimate of projected equipment service life can then be projected. (author)

  18. A developing chronology for prehistoric 'moated sites' in northeast Thailand

    International Nuclear Information System (INIS)

    McGrath, R.J.; Boyd, W.E.

    1999-01-01

    Full text: Many mounded Iron Age occupation sites in the Mun River Valley,N.E. Thailand are characterised by distinctive encircling earthworks, these are commonly known as 'moated sites'. The first excavations of any significance within the moats themselves at six sites -Noen U-Loke, Non Muang Khao, Ban Non Khrua Chut, Ban Non Ngiu, Ban Makham Thae and Ban Non Wat - in the form of long trenches have been carried out to enable detailed examination of their structure. Significantly, the surficial morphology of the moats, and the notable regularity of shape and patterning of the moats in plan, usually does not accurately reflect the buried sectional morphology of incised channel features, which are in no way expressed on the surface. Buried channels beneath the edge of the mounds as well as the surrounding moat banks have also been revealed. Stratigraphic and geomorphic relationships of the buried features imply critical chronological relationships which need to be tested to allow full development of a model for the evolution of the archaeological sites. Extremely small quantities of charcoal and shells obtained from the buried features has necessitated the need for AMS dating to develop the chronology for the development, use and decline of the moated features and channels. The dating is an ongoing process, however, results thus far obtained supports the development of older channels towards the archaeological mounds, and yet older buried channels under the sites

  19. Developing pipeline risk methodology for environmental license permit; Metodologia para avaliacao do risco em dutos, no licenciamento ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Arruda, Paulo; Naime, Andre [Instituto Brasileiro do Meio Ambiente e dos Recursos Naturais Renovaveis (IBAMA), Brasilia, DF (Brazil). Diretoria de Licenciamento e Qualidade Ambiental; Serpa, Ricardo [Companhia de Tecnologia de Saneamento Ambiental (CETESB), Sao Paulo, SP (Brazil). Setor de Analise de Riscos; Mendes, Renato F. [PETROBRAS Engenharia, RJ (Brazil); Ventura, Gilmar [TRANSPETRO - PETROBRAS Transportes, Rio de Janeiro, RJ (Brazil)

    2005-07-01

    Some new pipelines undertakings aim to establish connection between gas provinces in the Southeast and consumers in the Northeast of Brazil, in order to supply medium consuming centers and regions with minor potential of development. Consulting companies are carrying out Environmental Assessments studies and among them is the Risk Analyses of these pipeline transmission systems, in order to receive environmental permits by IBAMA, the Federal Brazilian Environmental Agency. In addition, existing interstate pipeline systems which are under IBAMA regulation will also require the same attention. For the purpose of defining a Pipeline Risk Analysis Protocol with methodology and risk criteria, with minimum risk analysis information on a comprehensive process, it has been decided for a 'tour de force' formed by experts from IBAMA and PETROBRAS engineers. The risk assessment protocol is focus on the risk to communities in the neighborhood of these pipelines and on the potential damage to the environment near and far from the ROW. The joined work ended up in two protocols, which attempt to provide environmental license permits for oil pipeline and gas pipelines with minimum contents for risk analysis studies. Another aspect is the environmental risk that has been focused on the contingency plan approach, since there are no consolidated environmental risk criteria for application as a common worldwide sense. The environmental risk mapping - MARA methodology will indicate areas with potential to be affected by leakages along a pipeline system. (author)

  20. Development of corrective measures and site stabilization technologies for shallow land burial facilities at semiarid sites

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Abeele, W.V.

    1986-01-01

    The overall purpose of the corrective measures task performed for the National Low-Level Waste Management Program has been to develop and test methods that can be used to correct any actual or anticipated problems with new and existing shallow land burial (SLB) sites in a semiarid environment. These field tests have not only evaluated remedial actions, but have also investigated phenomena suspected of being a possible problem at semiarid SLB sites. The approach we have taken in developing remedial action and site closure technologies for low-level waste sites is to recognize that physical and biological processes affecting site integrity are interdependent, and therefore, cannot be treated as separate problems. The field experiments performed for this task were to identify, evaluate, and model erosion control technologies, field test second generation biointrusion barriers, determine by field experiments the extent of upward radionuclide migration due to moisture cycling, and measure the effects of subsidence on remedial action of other system components. Progress made in each of these research areas is described

  1. Geothermal energy in Idaho: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    McClain, D.W.

    1979-07-01

    Detailed site specific data regarding the commercialization potential of the proven, potential, and inferred geothermal resource areas in Idaho are presented. To assess the potential for geothermal resource development in Idaho, several kinds of data were obtained. These include information regarding institutional procedures for geothermal development, logistical procedures for utilization, energy needs and forecasted demands, and resource data. Area reports, data sheets, and scenarios were prepared that described possible geothermal development at individual sites. In preparing development projections, the objective was to base them on actual market potential, forecasted growth, and known or inferred resource conditions. To the extent possible, power-on-line dates and energy utilization estimates are realistic projections of the first events. Commercialization projections were based on the assumption that an aggressive development program will prove sufficient known and inferred resources to accomplish the projected event. This report is an estimate of probable energy developable under an aggressive exploration program and is considered extremely conservative. (MHR)

  2. A future for nuclear sites beyond their service life. Nuclear site value development; Un avenir pour les sites nucleaires en fin de cycle. Valorisation des sites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites

  3. Geothermal energy in Idaho: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    McClain, D.V.

    1979-07-01

    A summary of known information about the nature of the resource, its potential for development, and the infrastructure of government which will guide future development is presented. Detailed site specific data regarding the commercialization potential of the proven, potential, and inferred geothermal resource areas in Idaho are included. Leasing and development status, institutional parameters, and a legal overview of geothermal resources in Idaho are given. (MHR)

  4. Developments in modelling the economic impact of Off-site accident consequences

    International Nuclear Information System (INIS)

    Haywood, S.M.; Robinson, C.A.; Faude, D.

    1991-01-01

    Models for assessing the economic consequences of accidental releases of radioactivity have application both in accident consequence codes and in decision aiding computer systems for use in emergency response. Such models may be applied in emergency planning, and studies in connection with the siting, design and licensing of nuclear facilities. Several models for predicting economic impact have been developed, in Europe and the US, and these are reviewed. A new model, called COCO-1 (Cost of Consequences Off-site), has been developed under the CEC MARIA programme and the features of the model are summarised. The costs calculated are a measure of the benefit foregone as a result of the accident, and in addition to tangible monetary costs the model attempts to include costs arising from the effect of the accident on individuals, for instance the disruption caused by the loss of homes. COCO-1 includes the cost of countermeasures, namely evacuation, relocation, sheltering, food restrictions and decontamination, and also the cost of health effects in the exposed population. The primary quantity used in COCO-1 to measure the economic value of land subject to restrictions on usage is Gross Domestic Product (GDP). Examples of default data included in the model are presented, as are the results of an illustrative application. The limitations of COCO-1 are discussed, and areas where further data are needed are identified

  5. The need for legislative framework (licensing)

    International Nuclear Information System (INIS)

    Krech, H.

    1977-01-01

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

  6. Assessment of the licensing aspects of HTGR in Yugoslavia

    International Nuclear Information System (INIS)

    Varazdinec, Z.

    1990-01-01

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

  7. Assessment of the licensing aspects of HTGR in Yugoslavia

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-07-01

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

  8. 10 CFR 781.51 - Nonexclusive licenses.

    Science.gov (United States)

    2010-01-01

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

  9. Licensed Healthcare Facilities

    Data.gov (United States)

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

  10. 2015 Business Licenses

    Data.gov (United States)

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

  11. Overview of software development at the parabolic dish test site

    Science.gov (United States)

    Miyazono, C. K.

    1985-01-01

    The development history of the data acquisition and data analysis software is discussed. The software development occurred between 1978 and 1984 in support of solar energy module testing at the Jet Propulsion Laboratory's Parabolic Dish Test Site, located within Edwards Test Station. The development went through incremental stages, starting with a simple single-user BASIC set of programs, and progressing to the relative complex multi-user FORTRAN system that was used until the termination of the project. Additional software in support of testing is discussed including software in support of a meteorological subsystem and the Test Bed Concentrator Control Console interface. Conclusions and recommendations for further development are discussed.

  12. License - PSCDB | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...wnload License Update History of This Database Site Policy | Contact Us License - PSCDB | LSDB Archive ...

  13. License - SSBD | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...thout notice. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - SSBD | LSDB Archive ...

  14. License - ASTRA | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ... notice. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - ASTRA | LSDB Archive ...

  15. License - JSNP | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - JSNP | LSDB Archive ...

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

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...out This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - KOME | LSDB Archive ...

  17. License - RGP gmap | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...nged without notice. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - RGP gmap | LSDB Archive ...

  18. License - DMPD | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...ownload License Update History of This Database Site Policy | Contact Us License - DMPD | LSDB Archive ...

  19. License - SAHG | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...ut notice. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - SAHG | LSDB Archive ...

  20. License - GRIPDB | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...e Database Description Download License Update History of This Database Site Policy | Contact Us License - GRIPDB | LSDB Archive ...

  1. License - GETDB | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...se Database Description Download License Update History of This Database Site Policy | Contact Us License - GETDB | LSDB Archive ...

  2. License - RPSD | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...thout notice. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - RPSD | LSDB Archive ...

  3. License - RMOS | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...out This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - RMOS | LSDB Archive ...

  4. A survey of collection development for United States Medical Licensing Examination (USMLE) and National Board Dental Examination (NBDE) preparation material.

    Science.gov (United States)

    Hendrix, Dean; Hasman, Linda

    2008-07-01

    The research sought to ascertain medical and dental libraries' collection development policies, evaluation methods, purchase decisions, and issues that relate to print and electronic United States Medical Licensing Examination (USMLE) and National Board Dental Examination (NBDE) preparation materials. The investigators surveyed librarians supporting American Association of Medical Colleges (AAMC)-accredited medical schools (n = 58/125) on the USMLE and librarians supporting American Dental Association (ADA)-accredited dental schools (n = 23/56) on the NBDE. The investigators analyzed the data by cross-tabulating and filtering the results using EFM Continuum web survey software. Investigators also surveyed print and electronic USMLE and NBDE preparation materials from 2004-2007 to determine the number of publications and existence of reviews. A majority of responding AAMC libraries (62%, n = 58) provide at least 1 electronic or online USMLE preparation resource and buy an average of 11.6 print USMLE titles annually. Due to a paucity of NBDE print and electronic resources, ADA libraries bought significantly fewer print resources, and only 1 subscribed to an electronic resource. The most often reported evaluation methods for both populations were feedback from medical or dental students, feedback from medical or dental faculty, and online trials. Some AAMC (10%, n = 58) and ADA libraries (39%, n = 23) libraries reported that no evaluation of these materials occured at their libraries. From 2004-2007, publishers produced 45 USMLE preparation resources (total n = 546) to every 1 NBDE preparation resource (total n = 12). Users' needs, institutional missions and goals, financial status, and official collection policies most often underlie decisions to collect or not collect examination preparation materials. Evaluating the quality of examination preparation materials can be problematic due to lack of published reviews, lack of usability testing by libraries, and

  5. The Monticello license renewal project

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  6. Environmental licensing issues for cogeneration plants

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  7. The strategy of experimental power reactor licensing in Indonesia

    International Nuclear Information System (INIS)

    Moch Djoko Birmano

    2015-01-01

    Currently, BATAN has being planned to develop Experimental Power Reactor (EPR), that is the research nuclear reactor that can generate power (electricity or heat). The EPR is planned will be built in the National Center for Research of Science and Technology (Puspiptek) area at Serpong, South Tangerang, Banten Province, with the choice of reactor types is HTGR with the power size of 10 MWth. As stated in the Act No. 10 year 1997 on Nuclear Power, that every construction and operation of nuclear reactors and other nuclear installations and decommissioning of nuclear reactors required to have a permit. Furthermore, the its implementation arrangements is regulated in Government Regulation (GR) No. 2 year 2014 on Licensing of Nuclear Installations and Nuclear Material Utilization, which contains the requirements and procedures for the licensing process since site, construction, commissioning, operation, and decommissioning, it means licensing is implemented during the activity of construction, operation and decommissioning of NPPs.While, for the more detailed licensing arrangements available in the guidelines of BAPETEN Chairman Regulation (BCR). This study was conducted to understand the legal and institutional aspects, types and stages, and the licensing process of RDE, and identify licensing strategy so that timely as planned. Methodologies used include the literature study, consultation with experts in BAPETEN, discussions in the national seminar including FGD. (author)

  8. Law no. 10.308 of 20th November, 2001 on radioactive waste repositories siting, construction, licensing, operation, inspection, costs, indemnity, civil liability and guarantees concerning to the radioactive wastes repositories and other provisions

    International Nuclear Information System (INIS)

    2001-01-01

    This Act was published on November 20, 2001 and set forth regulations on the final disposal of radioactive wastes produced in Brazil, including siting, construction, licensing, operation, inspection, costs, indemnities, civil liability and guarantees concerning to the radioactive wastes repositories. This act allows for installation and operation of initial, intermediary and final repositories in accordance with the criteria established by the Brazilian Nuclear Energy National Commission - CNEN. The person or organization granted with CNEN authorization for operation of the initial repositories shall be liable for personal, patrimony and environmental radiological damages. The civil liability of CNEN is concerned to the radioactive waste intermediary and final disposals and transportation

  9. SITE-94. Discrete-feature modelling of the Aespoe site: 2. Development of the integrated site-scale model

    Energy Technology Data Exchange (ETDEWEB)

    Geier, J.E. [Golder Associates AB, Uppsala (Sweden)

    1996-12-01

    A 3-dimensional, discrete-feature hydrological model is developed. The model integrates structural and hydrologic data for the Aespoe site, on scales ranging from semi regional fracture zones to individual fractures in the vicinity of the nuclear waste canisters. Hydrologic properties of the large-scale structures are initially estimated from cross-hole hydrologic test data, and automatically calibrated by numerical simulation of network flow, and comparison with undisturbed heads and observed drawdown in selected cross-hole tests. The calibrated model is combined with a separately derived fracture network model, to yield the integrated model. This model is partly validated by simulation of transient responses to a long-term pumping test and a convergent tracer test, based on the LPT2 experiment at Aespoe. The integrated model predicts that discharge from the SITE-94 repository is predominantly via fracture zones along the eastern shore of Aespoe. Similar discharge loci are produced by numerous model variants that explore uncertainty with regard to effective semi regional boundary conditions, hydrologic properties of the site-scale structures, and alternative structural/hydrological interpretations. 32 refs.

  10. SITE-94. Discrete-feature modelling of the Aespoe site: 2. Development of the integrated site-scale model

    International Nuclear Information System (INIS)

    Geier, J.E.

    1996-12-01

    A 3-dimensional, discrete-feature hydrological model is developed. The model integrates structural and hydrologic data for the Aespoe site, on scales ranging from semi regional fracture zones to individual fractures in the vicinity of the nuclear waste canisters. Hydrologic properties of the large-scale structures are initially estimated from cross-hole hydrologic test data, and automatically calibrated by numerical simulation of network flow, and comparison with undisturbed heads and observed drawdown in selected cross-hole tests. The calibrated model is combined with a separately derived fracture network model, to yield the integrated model. This model is partly validated by simulation of transient responses to a long-term pumping test and a convergent tracer test, based on the LPT2 experiment at Aespoe. The integrated model predicts that discharge from the SITE-94 repository is predominantly via fracture zones along the eastern shore of Aespoe. Similar discharge loci are produced by numerous model variants that explore uncertainty with regard to effective semi regional boundary conditions, hydrologic properties of the site-scale structures, and alternative structural/hydrological interpretations. 32 refs

  11. Geothermal resources in Oregon: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    Justus, D.L.

    1979-04-01

    An inventory of resources based on available information is presented. Potential for utilization and the legal and institutional environment in which development is likely to occur were also considered. Sites selected for this investigation include the 13 identified KGRA's, one PGRA which was chosen because of substantial local interest expressed in favor of development, and one major geologic fault zone which shows indications of high potential. Each chapter represents a planning region and is introduced by a regional overview of the physical setting followed by a narrative summary statement of the specific resource location and characteristics, existing utilization and potential end-uses for future development. Detailed site information in the form of data sheets follows each narrative. (MHR)

  12. The USNCR license renewal process

    International Nuclear Information System (INIS)

    Kuo, Pao-Tsin

    2002-01-01

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

  13. Comparative Analysis of Hydraulic Fracturing Wastewater Practices in Unconventional Shale Development: Newspaper Coverage of Stakeholder Concerns and Social License to Operate

    OpenAIRE

    Joel Gehman; Dara Y. Thompson; Daniel S. Alessi; Diana M. Allen; Greg G. Goss

    2016-01-01

    In this article we review prior literature regarding the concept of social license to operate, and related concepts, including corporate social responsibility, sustainable development, stakeholder management and cumulative effects. Informed by these concepts, we search for newspaper articles published in North American provinces and states where the Barnett, Duvernay, Marcellus and Montney shale plays are located. Using these data, we tabulate coverage of stakeholder concerns related to hydra...

  14. Preliminary report for the license of a hot cell that will be use in the technology development for the obtention of Mo-99

    International Nuclear Information System (INIS)

    Fucugauchi, L.A.; Millan S, S.; Lopez M, A.E.; Lopez C, R; Sanchez M, V.; Reynoso V, R.; Vera, A.

    1991-05-01

    A preliminary report for the license of a hot cell that will be used in the development of the technology for the obtaining of Mo-99 is presented. The following topics are also included: objective of the project, technical description, description of the prototype cell, handling of radioactive wastes, lists of equipment that will be used, risk analysis, curricula, quality assurance plan and an annex with the report on handling of radioactive wastes presented to the PAGD-IAEA. (Author)

  15. Nevada National Security Site: Site-Directed Research and Development (SDRD) Fiscal Year 2015 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Bender, Howard A. [National Security Technologies, LLC. (NSTec), Mercury, NV (United States). Site-Directed Research and Development Program

    2016-04-01

    This report presents results of multiple research projects, new and ongoing, funded under the Site-Directed Research and Development Program for the Nevada National Security Site during federal fiscal year 2015. The Site's legacy capabilities in remote sensing combined with new paradigms for emergency response and consequence management help drive the need to develop advanced aerial sensor platforms. Likewise, dynamic materials science is a critical area of scientific research for which basic physics issues are still unresolved. New methods of characterizing materials in extreme states are vitally needed, and these efforts are paving the way with new knowledge. Projects selected in FY 2015 for the Exploratory Research portfolio exhibit a strong balance of NNSS mission relevance. Geoscience, seismology, and techniques for detecting underground nuclear events are still essential focus areas. Many of the project reports in the second major section of this annual report are ongoing continuations in multi-year lifecycles. Diagnostic techniques for stockpile and nuclear security science figured prominently as well, with a few key efforts coming to fruition, such as phase transition detection. In other areas, modeling efforts toward better understanding plasma focus physics has also started to pay dividends for major program needs.

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

    International Nuclear Information System (INIS)

    Albrecht, E.; Ballhaus, S.

    1975-01-01

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

  17. Hydrogeochemical site descriptive model - a strategy for the model development during site investigations

    International Nuclear Information System (INIS)

    Smellie, John; Laaksoharju, Marcus; Tullborg, Eva-Lena

    2002-12-01

    In 2002, SKB commenced site characterisation investigations using deep boreholes at different sites. As an integral part of the planning work SKB has prepared a strategy to develop a Hydrogeochemical Site Descriptive Model; similar strategies have been developed for the other major geoscience disciplines. The main objectives of the Hydrogeochemical Site Descriptive Model are to describe the chemistry and distribution of the groundwater in the bedrock and overburden and the hydrogeochemical processes involved in its origin and evolution. This description is based primarily on measurements of the groundwater composition but incorporates the use of available geological and hydrogeological site descriptive models. The SKB hydrogeochemistry programme is planned to fulfil two basic requirements: 1) to provide representative and quality assured data for use as input parameter values in calculating long-term repository safety, and 2) to understand the present undisturbed hydrogeochemical conditions and how these conditions will change in the future. Parameter values for safety analysis include pH, Eh, S, SO 4 , HCO 3 , HPO 4 and TDS (mainly cations), together with colloids, fulvic and humic acids, other organics, bacteria and nitrogen. These values will be used to characterise the groundwater environment at, above and below repository depths. In the hydrogeochemical site investigation programme the number and location of the sampling points will be constrained by: a) geology (e.g. topography, overburden types, bedrock structures etc), b) hydrogeology (e.g. groundwater recharge/discharge areas, residence times), c) reliability (e.g. undisturbed vs disturbed groundwater chemical conditions), and d) resources (e.g. number and type of samples, and also available personnel, may be restricted by budgetary and schedule concerns). Naturally a balance is required between these constraints and the scientific aims of the programme. The constraints should never detrimentally affect

  18. Safety and licensing requirements in the Republic of South Africa

    International Nuclear Information System (INIS)

    Simpson, D.M.; Langford, E.L.

    1986-01-01

    The principles for licensing of nuclear installations in South Africa are based on the control of mortality risk to the operators of an installation and the population resident in the vicinity of the site. This paper describes the development of this safety philosophy, and the nuclear licensing process used in this country. The structure of the nuclear regulatory function is briefly described, including the respective roles of the Atomic Energy Corporation, Licencing Branch and the Council for Nuclear Safety. The development of risk criteria and quantitative release magnitude-probability criteria for radioactive material is outlined. Tasks that have to be undertaken by a potential waste disposal site licensee before a site licence is issued are described. Once the facility is commissioned periodic monitoring procedures will have to be adopted throughout the lifetime of the facility. The scope of typical monitoring activities is outlined and the ongoing analyses to be performed and the records to be kept are discussed

  19. FY 2016 Site-Directed Research & Development Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Bender, Howard [National Security Technologies, LLC. (NSTec), Mercury, NV (United States)

    2017-04-01

    As the Nevada National Security Site (NNSS) continues to evolve and transition its mission to a broader scope, significant challenges lie ahead that present unique opportunities for our research and development (R&D) enterprise. At the juncture, we are poised to create a different future investment strategy. Our decisions at the beginning of a new tri-decade span must be guided as expertly as possible given the greater complexity and multifaceted nature of our work.

  20. New Developments in 1,4 Dioxane Site Management

    Science.gov (United States)

    2016-11-01

    developed biomarkers to assess aerobic 1,4-dioxane degradation because it may be an important contributor to site-specific natural attenuation capacity...survey corroborate the results of the lab-based research showing that 1,4-dioxane degradation is favored under aerobic conditions but is inhibited by...oxidative attack. In situ oxidation technologies (e.g., chemical oxidation, enhanced aerobic biodegradation) should degrade 1,4-dioxane but each has

  1. Geothermal energy in Alaska: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    Markle, D.

    1979-04-01

    The following are presented: the history of geothermal energy in Alaska; a history of Alaska land ownership; legal and institutional barriers; and economics. Development, the socio-economic and physical data concerning geothermal energy are documented by regions. The six regions presented are those of the present Alaska State Planning Activities and those of the Federal Land Use Commission. Site data summaries of the one hundred and four separate geothermal spring locations are presented by these regions. (MHR)

  2. Geothermal energy in Montana: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    Brown, K.E.

    1979-11-01

    A short description of the state's geothermal characteristics, economy, and climate is presented. A listing of the majority of the known hot springs is included. A discussion of present and projected demand is included. The results of the site specific studies are addressed within the state energy picture. Possible uses and process requirements of geothermal resources are discussed. The factors which influence geothermal development were researched and presented according to relative importance. (MHR)

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  4. SiteGuide: An example-based approach to web site development assistance

    NARCIS (Netherlands)

    Hollink, V.; de Boer, V.; van Someren, M.; Filipe, J.; Cordeiro, J.

    2009-01-01

    We present ‘SiteGuide’, a tool that helps web designers to decide which information will be included in a new web site and how the information will be organized. SiteGuide takes as input URLs of web sites from the same domain as the site the user wants to create. It automatically searches the pages

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

    International Nuclear Information System (INIS)

    Snellings, D.D. Jr.

    1975-01-01

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

  6. Geological evolution, palaeoclimate and historical development of the Forsmark and Laxemar-Simpevarp areas. Site descriptive modelling SDM-Site

    Energy Technology Data Exchange (ETDEWEB)

    Soederbaeck, Bjoern [ed.

    2008-06-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterization at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The site investigations started in 2002 and were completed in 2007. The analysis and modelling of data from the site investigations, which have taken place during and after these investigations, provide a foundation for the development of an integrated, multidisciplinary site descriptive model (SDM) for each of the two sites. A site descriptive model constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere, as well as those natural processes that affect or have affected their long-term development. Hitherto, a number of reports presenting preliminary site descriptive models for Forsmark and Laxemar-Simpevarp have been published. In these reports, the evolutionary and historical aspects of the site were included in a separate chapter. The present report comprises a further elaboration of the evolutionary and historical information included in the preliminary SDM reports, but presented here in a separate, supplementary report to the final site description, SDM-Site. The report is common to the two investigated areas, and the overall objective is to describe the long-term geological evolution, the palaeoclimate, and the post-glacial development of ecosystems and of the human population at the two sites. The report largely consists of a synthesis of information derived from the scientific literature and other sources not related to the site investigations. However, considerable information from the site investigations that has contributed to our understanding of the past development at each site is also included. This unique synthesis of both published information in a regional perspective and new site-specific information breaks new ground in our understanding

  7. Geological evolution, palaeoclimate and historical development of the Forsmark and Laxemar-Simpevarp areas. Site descriptive modelling SDM-Site

    International Nuclear Information System (INIS)

    Soederbaeck, Bjoern

    2008-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterization at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The site investigations started in 2002 and were completed in 2007. The analysis and modelling of data from the site investigations, which have taken place during and after these investigations, provide a foundation for the development of an integrated, multidisciplinary site descriptive model (SDM) for each of the two sites. A site descriptive model constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere, as well as those natural processes that affect or have affected their long-term development. Hitherto, a number of reports presenting preliminary site descriptive models for Forsmark and Laxemar-Simpevarp have been published. In these reports, the evolutionary and historical aspects of the site were included in a separate chapter. The present report comprises a further elaboration of the evolutionary and historical information included in the preliminary SDM reports, but presented here in a separate, supplementary report to the final site description, SDM-Site. The report is common to the two investigated areas, and the overall objective is to describe the long-term geological evolution, the palaeoclimate, and the post-glacial development of ecosystems and of the human population at the two sites. The report largely consists of a synthesis of information derived from the scientific literature and other sources not related to the site investigations. However, considerable information from the site investigations that has contributed to our understanding of the past development at each site is also included. This unique synthesis of both published information in a regional perspective and new site-specific information breaks new ground in our understanding

  8. Development testing of grouting and liner technology for humid sites

    International Nuclear Information System (INIS)

    Vaughan, N.D.

    1981-01-01

    Shallow land burial, although practiced for many years, has not always secured radionuclides from the biosphere in humid environments. To develop and demonstrate improved burial technology the Engineered Test Facility was implemented. An integral part of this experiment was site characterization, with geologic and hydrologic factors as major the components. Improved techniques for burial of low-level waste were developed and tested in the laboratory before being applied in the field. The two techniques studied were membrane trench liner and grouting void spaces

  9. Impact analysis and community development needs at the salt site

    International Nuclear Information System (INIS)

    Gray, S.; Boryczka, M.; Hines, B.

    1984-01-01

    The Office of Nuclear Waste Isolation (ONWI) has developed a socioeconomic program for a nuclear waste repository constructed in salt. The program is comprised of three elements: impact assessment, impact mitigation, and impact monitoring. The first element, impact assessment, is the focus of ONWI's current activities. Socioeconomic data has been collected for seven salt sites in Texas, Utah, Mississippi and Louisiana. Demographic, economic, community service, governmental and social structure information has been assembled into data base reports for each site area. These socioeconomic reports will be the basis for analyzing community-related impacts. Socioeconomic effects are currently being evaluated for the environmental assessment document required by the Nuclear Waste Policy Act. The approach to evaluating socioeconomic impacts for the environmental assessment impact includes developing the data base necessary for evaluation; assessing impacts of baseline population projected by the states; assessing project-related impacts through the use of an inmigration model and responding to socioeconomic issues raised in public meetings and hearings. The siting, construction, and operation of nuclear repositories will involve an extended period of time and an increased workforce, which can result in some impacts similar to those of other large development projects. The communities affected by a repository site will face increased demands for housing, community services (transportation, sewer and water, schools, etc.) and land, as well as a desire to maintain the community's ''character''. The management of this expansion and other related community impacts should be structured to meet community needs and goals. The management process should include the formation of an impact management comment, a public participation program, and a technical assistance program

  10. Development of a site-wide accident management center for the Savannah River Site

    International Nuclear Information System (INIS)

    Heal, D.W.; Britt, T.E.

    1992-01-01

    In 1990, the Safety Analysis Group at the Savannah River Site (SRS) began development of an Accident Management program. The program was designed to provide a total system which would meet the Department of Energy (DOE) Safety Performance Criteria, in regard to severe accident management, in the most effective manner. This paper will present two significant changes in the current SRS Accident Management program which will be used to meet these expanded needs. The first and most significant change will be to expand the diversity of the groups involved in the Accident Management process. In the future, organizations such as Environmental Safety, Health ampersand Quality Assurance, Emergency Planning, Site Management, Human Factors, Risk Assessment, and many others will work as an integrated team to solve facility problems. Organizations such as Materials Technology, Equipment Engineering and many of the laboratories on site will be utilized as support groups to increase the technical capability for specific accident analyses. This phase of the program is currently being structured, and should be operational by January of 1993

  11. Development of METAL-ACTIVE SITE and ZINCCLUSTER tool to predict active site pockets.

    Science.gov (United States)

    Ajitha, M; Sundar, K; Arul Mugilan, S; Arumugam, S

    2018-03-01

    The advent of whole genome sequencing leads to increasing number of proteins with known amino acid sequences. Despite many efforts, the number of proteins with resolved three dimensional structures is still low. One of the challenging tasks the structural biologists face is the prediction of the interaction of metal ion with any protein for which the structure is unknown. Based on the information available in Protein Data Bank, a site (METALACTIVE INTERACTION) has been generated which displays information for significant high preferential and low-preferential combination of endogenous ligands for 49 metal ions. User can also gain information about the residues present in the first and second coordination sphere as it plays a major role in maintaining the structure and function of metalloproteins in biological system. In this paper, a novel computational tool (ZINCCLUSTER) is developed, which can predict the zinc metal binding sites of proteins even if only the primary sequence is known. The purpose of this tool is to predict the active site cluster of an uncharacterized protein based on its primary sequence or a 3D structure. The tool can predict amino acids interacting with a metal or vice versa. This tool is based on the occurrence of significant triplets and it is tested to have higher prediction accuracy when compared to that of other available techniques. © 2017 Wiley Periodicals, Inc.

  12. Geological Site Descriptive Model. A strategy for the model development during site investigations

    International Nuclear Information System (INIS)

    Munier, Raymond; Stenberg, Leif; Stanfors, Roy; Milnes, Allan Geoffrey; Hermanson, Jan; Triumf, Carl-Axel

    2003-04-01

    methodology should also be compliant to the toolbox of software used by SKB. Munier and Hermanson have earlier described a methodology for geometrically presenting and administering interpreted deformation zones, and the rock masses between, in a site descriptive model to be used in site investigations. That work, written in Swedish, has for practical purposes been partly incorporated into the present report. However, slight departures from the methodology proposed there have been necessary, partly due to experiences gained in the Laxemar project, in which the methodology was applied, and partly due to advances in the development of the CAD-based RVS tool. The present report is structured to take account of the different levels of interpretation, outlined above. After a short clarification of the main terms which will be used in the report, the first of the three main chapters outlines the data requirements for 3D geological modelling, together with the main investigation methods and the degree of method-specific interpretation in each. This chapter concerns the production of the primary data sets which are stored in SICADA or SDE, which will be later used in the modelling process. The second of the main chapters concerns the combination of some of the primary data sets to provide a usable input into the 3D model, with the main emphasis on the process of integrative interpretation. There are two aspects which are particularly important in this context, the analysis and synthesis of geo-scientific cartographic data and single borehole data. The third main chapter presents the central theme of the report, 3D geological modelling and the process of interdisciplinary interpretation which this involves. In a final chapter, the treatment of uncertainty and confidence will be discussed in relation to the proposed modelling procedures

  13. Geological Site Descriptive Model. A strategy for the model development during site investigations

    Energy Technology Data Exchange (ETDEWEB)

    Munier, Raymond; Stenberg, Leif [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Stanfors, Roy [Roy Stanfors Consulting, Lund (Sweden); Milnes, Allan Geoffrey [GEA Consulting, Uppsala (Sweden); Hermanson, Jan [Golder Associates, Stockholm (Sweden); Triumf, Carl-Axel [Geovista, Luleaa (Sweden)

    2003-04-01

    promoted. The methodology should also be compliant to the toolbox of software used by SKB. Munier and Hermanson have earlier described a methodology for geometrically presenting and administering interpreted deformation zones, and the rock masses between, in a site descriptive model to be used in site investigations. That work, written in Swedish, has for practical purposes been partly incorporated into the present report. However, slight departures from the methodology proposed there have been necessary, partly due to experiences gained in the Laxemar project, in which the methodology was applied, and partly due to advances in the development of the CAD-based RVS tool. The present report is structured to take account of the different levels of interpretation, outlined above. After a short clarification of the main terms which will be used in the report, the first of the three main chapters outlines the data requirements for 3D geological modelling, together with the main investigation methods and the degree of method-specific interpretation in each. This chapter concerns the production of the primary data sets which are stored in SICADA or SDE, which will be later used in the modelling process. The second of the main chapters concerns the combination of some of the primary data sets to provide a usable input into the 3D model, with the main emphasis on the process of integrative interpretation. There are two aspects which are particularly important in this context, the analysis and synthesis of geo-scientific cartographic data and single borehole data. The third main chapter presents the central theme of the report, 3D geological modelling and the process of interdisciplinary interpretation which this involves. In a final chapter, the treatment of uncertainty and confidence will be discussed in relation to the proposed modelling procedures.

  14. Novel approaches for an enhanced geothermal development of residential sites

    Science.gov (United States)

    Schelenz, Sophie; Firmbach, Linda; Shao, Haibing; Dietrich, Peter; Vienken, Thomas

    2015-04-01

    An ongoing technological enhancement drives an increasing use of shallow geothermal systems for heating and cooling applications. However, even in areas with intensive shallow geothermal use, planning of geothermal systems is in many cases solely based on geological maps, drilling databases, and literature references. Thus, relevant heat transport parameters are rather approximated than measured for the specific site. To increase the planning safety and promote the use of renewable energies in the domestic sector, this study investigates a novel concept for an enhanced geothermal development of residential neighbourhoods. This concept is based on a site-specific characterization of subsurface conditions and the implementation of demand-oriented geothermal usage options. Therefore, an investigation approach has been tested that combines non-invasive with minimum-invasive exploration methods. While electrical resistivity tomography has been applied to characterize the geological subsurface structure, Direct Push soundings enable a detailed, vertical high-resolution characterization of the subsurface surrounding the borehole heat exchangers. The benefit of this site-specific subsurface investigation is highlighted for 1) a more precise design of shallow geothermal systems and 2) a reliable prediction of induced long-term changes in groundwater temperatures. To guarantee the financial feasibility and practicability of the novel geothermal development, three different options for its implementation in residential neighbourhoods were consequently deduced.

  15. Development of site remediation technologies in European countries

    International Nuclear Information System (INIS)

    Nunno, T.J.; Hyman, J.A.; Pheiffer, T.

    1988-01-01

    Site remediation is a pressing issue in European countries due to limited availability of land. Therefore, much progress is being made in the development of effective technologies for remediating contaminated sites. The purpose of this program was to investigate the most successful and innovative technologies for potential application into US markets. This EPA-sponsored project was based on a 9-month research effort which identified 95 innovative technologies in use or being researched in foreign countries. The most promising technologies were studied in-depth through personal interviews with the engineers who research and apply these technologies, and tours of laboratory models and full-scale installations. The most successful full-scale technologies investigated were developed in Holland, West Germany and Belgium. These technologies include vacuum extraction of hydrocarbons from soil, in situ washing of cadmium-polluted soil, rotating biocontractors for treating pesticides in ground water, high-temperature slagging incineration of low-level radioactive wastes, in situ steam stripping, and a number of landfarming and soil washing operations. The paper provides description of 13 site remediation techniques that have shown such promise in laboratory studies or in practice to warrant consideration of their use in the US

  16. In situ gamma spectrometry development for site mapping

    International Nuclear Information System (INIS)

    Panza, F.

    2012-01-01

    The high-resolution gamma spectrometry currently provides a powerful analytical tool for performing environmental measurements. In the context of radiological characterization of a site (natural or artificial radioactivity) and for the dismantling of nuclear installations, mapping of radionuclides is an important asset. The idea is to move a HPGe spectrometer to study the site and from nuclear and position data, to identify, to locate and to quantify the radionuclides present in the soil. The development of this tool follows an intercomparison (ISIS 2007) where an intervention/crisis exercise showed the limits of current tools. The main part of this research project has focused on mapping of nuclear data. Knowledge of the parameters of an in situ spectrum helped to create a simulator, modeling the response of a spectrometer moving over contaminated soil. The simulator itself helped to develop algorithms for mapping and to test them in extreme situations and not realizable. A large part of this research leads to the creation of a viable prototype providing real-time information concerning the identity and locality as possible radionuclides. The work performed on the deconvolution of data can make in post processing a map of the activity of radionuclide soil but also an indication of the depth distribution of the source. The prototype named OSCAR was tested on contaminated sites (Switzerland and Japan) and the results are in agreement with reference measurements. (author)

  17. Hydrogeochemical site descriptive model - a strategy for the model development during site investigations

    Energy Technology Data Exchange (ETDEWEB)

    Smellie, John [Conterra AB, Uppsala (Sweden); Laaksoharju, Marcus [GeoPoint AB, Sollentuna (Sweden); Tullborg, Eva-Lena [Terralogica AB, Graabo (Sweden)

    2002-12-01

    In 2002, SKB commenced site characterisation investigations using deep boreholes at different sites. As an integral part of the planning work SKB has prepared a strategy to develop a Hydrogeochemical Site Descriptive Model; similar strategies have been developed for the other major geoscience disciplines. The main objectives of the Hydrogeochemical Site Descriptive Model are to describe the chemistry and distribution of the groundwater in the bedrock and overburden and the hydrogeochemical processes involved in its origin and evolution. This description is based primarily on measurements of the groundwater composition but incorporates the use of available geological and hydrogeological site descriptive models. The SKB hydrogeochemistry programme is planned to fulfil two basic requirements: 1) to provide representative and quality assured data for use as input parameter values in calculating long-term repository safety, and 2) to understand the present undisturbed hydrogeochemical conditions and how these conditions will change in the future. Parameter values for safety analysis include pH, Eh, S, SO{sub 4}, HCO{sub 3}, HPO{sub 4} and TDS (mainly cations), together with colloids, fulvic and humic acids, other organics, bacteria and nitrogen. These values will be used to characterise the groundwater environment at, above and below repository depths. In the hydrogeochemical site investigation programme the number and location of the sampling points will be constrained by: a) geology (e.g. topography, overburden types, bedrock structures etc), b) hydrogeology (e.g. groundwater recharge/discharge areas, residence times), c) reliability (e.g. undisturbed vs disturbed groundwater chemical conditions), and d) resources (e.g. number and type of samples, and also available personnel, may be restricted by budgetary and schedule concerns). Naturally a balance is required between these constraints and the scientific aims of the programme. The constraints should never

  18. Perspectives of investigation and development of Semipalatinsk Test Site

    International Nuclear Information System (INIS)

    Kadyrzhanov, K.K.; Lukashenko, S.N.

    2008-01-01

    Full text: Since the Semipalatinsk Test Site has been stopped and up until now, National Nuclear Center of the Republic of Kazakhstan (NNC RK) in cooperation with other specialist from Kazakhstan and international scientific community have accumulated large scope of information about current radiological situation at Semipalatinsk Nuclear Test Site (SNTS) and adjacent territories. There were revealed all important spots of radioactive contamination, identified main pathways and mechanisms for present and potential proliferation of radioactive substances. Obtained data assure us that present-day SNTS provides no negative impact on population on adjacent to the Site territories excluding people in the water basin of the river Shagan. Compliance with regulatory requirements and special rules for SNTS territory assures radiation safety at commercial activities on the Site. At the same time, the radiological situation does not remain stable; there were revealed the processes of radionuclide migration what requires regular monitoring of radiological situation at SNTS. Taking into account the scale of the Site and the variety of tests performed there, the information available about SNTS can not be completely exhaustive but enables us to propose a scientifically grounded plan for further research and practical measures aimed at remediation and reclamation of lands. implementation of such measures should return up to 80% of the lands to commercial use. SNTS is one of the world largest nuclear test sites with decisive contribution to creation and development of nuclear weapon. To considerable extent, these were works at SNTS which established nuclear parity between the superpowers one of the crucial factors in the history of human civilization in the 20 century. Also taking into account the interest to SNTS paid by international organizations, it is reasonable to initiate a procedure and recognize SNTS as a landmark including it in the UNESCO List of Cultural and Nature

  19. 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

  20. The development of an on-site container

    International Nuclear Information System (INIS)

    Glass, R.E.; McAllaster, M.E.; Jones, P.L.; McKinney, A.L.

    1992-01-01

    Sandia National Laboratories (SNL) has developed a package for the on-site transport of chemical munitions for the US Army. This package was designed to prevent the release of lethal quantities of chemical agents during transportation of munitions to the demilitarization facilities on-site. The packaging prevents auto-ignition of the munitions by limiting the thermal and structural assault on the munitions during an accident. This package, with some modifications to account for contents, may be suitable for the on-site transport of mixed wastes at United States Department of Energy facilities. This paper discusses the design and verification testing of the package. The safety criteria for the package were modeled after the International Atomic Energy Agency (IAEA) hypothetical accident sequence and modified to take credit for operational controls. The modified accident sequence consisted of drop, puncture, and thermal events. The post-accident leak rate was established to prevent harm to an exposed worker. The packaging has a mass of 8600 kg and can accommodate up to 3600 kg of contents. The interior of the package is 188 cm in diameter and 232 cm long. Two sample ports can be used to sample the interior of the package prior to opening the closure and an o-ring test port can be used to determine the leak rates prior to and after transport

  1. Development of Onsite Transportation Safety Documents for Nevada Test Site

    International Nuclear Information System (INIS)

    Frank Hand; Willard Thomas; Frank Sciacca; Manny Negrete; Susan Kelley

    2008-01-01

    Department of Energy (DOE) Orders require each DOE site to develop onsite transportation safety documents (OTSDs). The Nevada Test Site approach divided all onsite transfers into two groups with each group covered by a standalone OTSD identified as Non-Nuclear and Nuclear. The Non-Nuclear transfers involve all radioactive hazardous material in less than Hazard Category (HC)-3 quantities and all chemically hazardous materials. The Nuclear transfers involve all radioactive material equal to or greater than HC-3 quantities and radioactive material mated with high explosives regardless of quantity. Both OTSDs comply with DOE O 460.1B requirements. The Nuclear OTSD also complies with DOE O 461.1A requirements and includes a DOE-STD-3009 approach to hazard analysis (HA) and accident analysis as needed. All Nuclear OTSD proposed transfers were determined to be non-equivalent and a methodology was developed to determine if 'equivalent safety' to a fully compliant Department of Transportation (DOT) transfer was achieved. For each HA scenario, three hypothetical transfers were evaluated: a DOT-compliant, uncontrolled, and controlled transfer. Equivalent safety is demonstrated when the risk level for each controlled transfer is equal to or less than the corresponding DOT-compliant transfer risk level. In this comparison the typical DOE-STD-3009 risk matrix was modified to reflect transportation requirements. Design basis conditions (DBCs) were developed for each non-equivalent transfer. Initial DBCs were based solely upon the amount of material present. Route-, transfer-, and site-specific conditions were evaluated and the initial DBCs revised as needed. Final DBCs were evaluated for each transfer's packaging and its contents

  2. 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

  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. 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

  5. Licensing reform in the USA

    International Nuclear Information System (INIS)

    1991-01-01

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

  6. Experience acquired by Furnas for licensing nuclear power plants

    International Nuclear Information System (INIS)

    Silva, A.J.C. da; Xavier, E.E.

    1986-01-01

    The system for licensing of Almirante Alvaro Alberto Nuclear Power Plant-Unit 1 is presented. The process phases for reactor construction and operation are described: preliminary site approval; bases for safety review; partial construction permits; final construction permits; emission of final report of safety analysis; initial operation license and permanent operation license. (M.C.K.) [pt

  7. Nevada National Security Site. Site-Directed Research and Development FY 2011 Annual Report

    International Nuclear Information System (INIS)

    Bender, Howard

    2012-01-01

    This fiscal year 2011 annual report of the Site-Directed Research and Development program, the 10th anniversary edition, recognizes a full decade of innovative R and D accomplishments in support of the Nevada National Security Site (NNSS). Last year the NNSS itself was renamed to reflect a diversifying mission, and our R and D program has contributed significantly to shape emerging missions that will continue to evolve. New initiatives in stockpile stewardship science, nonproliferation, and treaty verification and monitoring have had substantial successes in FY 2011, and many more accomplishments are expected. SDRD is the cornerstone on which many of these initiatives rest. Historically supporting our main focus areas, SDRD is also building a solid foundation for new, and non-traditional, emerging national security missions. The program continues its charter to advance science and technology for a broad base of agencies including the U.S. Department of Energy (DOE), U.S. Department of Defense (DoD), U.S. Department of Homeland Security (DHS), and many others.

  8. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs.

  9. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs

  10. Source removal strategy development for manufactured gas plant sites

    International Nuclear Information System (INIS)

    Golchin, J.; Nelson, S.

    1994-01-01

    A source removal action plan was developed by Midwest Gas and the Iowa Department of Natural Resources to address the source coal tar contamination within the underground gas holder basin at former Manufactured Gas Plant (MGP) sites. The procedure utilizes a mixture of coal, contaminated soil and coal rat sludge to provide a material that had suitable material handling characteristics for shipment and burning in high efficiency utility boilers. Screening of the mixture was required to remove oversized debris and ferrous metal. The resulting mixture did not exhibit toxic characteristics when tested under the Toxicity Characteristics Leaching Procedure (TCLP). Test results on the coal tar sludges have indicated that the more pure coal tar materials may fail the TCLP test and be classified as a RCRA hazardous waste. The processing procedure was designed to stabilize the coal tar sludges and render those sludges less hazardous and, as a result, able to pass the TCLP test. This procedure was adopted by the Edison Electric Institute to develop a national guidance document for remediation of MGP sites. The EPA Office of Solid Waste and Emergency Response recommended this strategy to the Regional Waste Management Directors as a practical tool for handling wastes that may exhibit the RCRA characteristics

  11. Conceptual framework for using 'Best Estimate plus Uncertainty' as a basis for licensing activities for fuels developed for an advanced reactor

    International Nuclear Information System (INIS)

    McClure, P.; Unal, C.; Boyack, B.

    2010-01-01

    Closing the fuel cycle is one of the major technical challenges to expanding the use of nuclear energy to meet the world's need for benign, environmentally safe electrical power. 'Closing the fuel cycle ' means getting the maximum amount of energy possible out of uranium fuel while minimizing the amount of high-level waste that must be stored. The U.S. Dept. of Energy's Fuel Cycle Research and Development (FCRD) program is investigating the recycling of transuranic isotopes contained in spent nuclear fuel. Recycling minimizes the amount of high-level waste that would require storage in repositories. Developing new fuels and the advanced reactors that burn them is a long process typically spanning two decades from concept to final licensing. A unique challenge to meeting the FCRD objectives in this area is the fact that the experimental database is incomplete. Thus, using a traditional, heavily empirical approach to develop and qualify fuels for an advanced reactor plant will be very challenging. To address this concern, FCRD has launched an advanced modeling and simulation (M and S) approach to revolutionize fuel development and advanced reactor design. This new approach depends on transferring recent advances in the computational sciences and computer technologies into the development of these program elements. The licensing process that historically has been used by the U.S. Nuclear Regulatory Commission (NRC) for fuels qualification is based on using a large body of experimental work to qualify and license a new fuel. If an M and S approach with more directed experimentation is to be considered as an alternative approach for licensing, a framework needs to be developed early in the process. Using M and S with limited experiments as a basis for demonstrating that a design can meet NRC requirements is not new and has precedence in the NRC. The method is generically referred to as a 'Best Estimate plus Uncertainty' (BE+U) approach because the goal of the

  12. Thermal Site Descriptive Model. A strategy for the model development during site investigations. Version 1.0

    International Nuclear Information System (INIS)

    Sundberg, Jan

    2003-04-01

    Site investigations are in progress for the siting of a deep repository for spent nuclear fuel. As part of the planning work, strategies are developed for site descriptive modelling regarding different disciplines, amongst them the thermal conditions. The objective of the strategy for a thermal site descriptive model is to guide the practical implementation of evaluating site specific data during the site investigations. It is understood that further development may be needed. The model describes the thermal properties and other thermal parameters of intact rock, fractures and fracture zones, and of the rock mass. The methodology is based on estimation of thermal properties of intact rock and discontinuities, using both empirical and theoretical/numerical approaches, and estimation of thermal processes using mathematical modelling. The methodology will be used and evaluated for the thermal site descriptive modelling at the Aespoe Hard Rock Laboratory

  13. Development of cholecystokinin binding sites in rat upper gastrointestinal tract

    International Nuclear Information System (INIS)

    Robinson, P.H.; Moran, T.H.; Goldrich, M.; McHugh, P.R.

    1987-01-01

    Autoradiography using 125 I-labeled Bolton Hunter-CCK-33 was used to study the distribution of cholecystokinin binding sites at different stages of development in the rat upper gastrointestinal tract. Cholecystokinin (CCK) binding was present in the distal stomach, esophagus, and gastroduodenal junction in the rat fetus of gestational age of 17 days. In the 20-day fetus, specific binding was found in the gastric mucosa, antral circular muscle, and pyloric sphincter. Mucosal binding declined during postnatal development and had disappeared by day 15. Antral binding declined sharply between day 10 and day 15 and disappeared by day 50. Pyloric muscle binding was present in fetal stomach and persisted in the adult. Pancreatic CCK binding was not observed before day 10. These results suggest that CCK may have a role in the control of gastric emptying and ingestive behavior in the neonatal rat

  14. Development of cholecystokinin binding sites in rat upper gastrointestinal tract

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, P.H.; Moran, T.H.; Goldrich, M.; McHugh, P.R.

    1987-04-01

    Autoradiography using /sup 125/I-labeled Bolton Hunter-CCK-33 was used to study the distribution of cholecystokinin binding sites at different stages of development in the rat upper gastrointestinal tract. Cholecystokinin (CCK) binding was present in the distal stomach, esophagus, and gastroduodenal junction in the rat fetus of gestational age of 17 days. In the 20-day fetus, specific binding was found in the gastric mucosa, antral circular muscle, and pyloric sphincter. Mucosal binding declined during postnatal development and had disappeared by day 15. Antral binding declined sharply between day 10 and day 15 and disappeared by day 50. Pyloric muscle binding was present in fetal stomach and persisted in the adult. Pancreatic CCK binding was not observed before day 10. These results suggest that CCK may have a role in the control of gastric emptying and ingestive behavior in the neonatal rat.

  15. Development of the web-based site investigation flow diagram in repository development program

    International Nuclear Information System (INIS)

    Yamamoto, Shuichi; Yoshimura, Kimitaka; Ohuchi, Jin; Tsuboya, Takao; Ando, Kenichi

    2005-01-01

    In siting a repository for high level radioactive wastes (HLW), it is essential for consensus building intelligibly and visually present why and how the area is selected as a suitable site. However 'information asymmetry' exists especially between society and an implementation body because various types of investigation, analysis and assessment are implemented in site characterization on the basis of a wide variety of advanced science and technology. Communication between experts (e.g. surveyors and modelers) is also important for efficient and reliable site investigation/ characterization. The Web-based Site Investigation Flow Diagram (SIFD) has been developed as a tool for information sharing among stake holders and society-jointed decision making. To test applicability of the SIFD, virtual site characterization ('dry run') is performed using the existing site investigation data. It is concluded that the web-based SIFD enhance traceability and transparency of the site investigation/ characterization, and therefore it would be a powerful communication tool among experts for efficient and reliable site investigation/characterization and among stake holders for consensus building

  16. Technology licensing in China

    DEFF Research Database (Denmark)

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

    2015-01-01

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

  17. State Licenses & Permits

    Data.gov (United States)

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

  18. Validation, acceptance and licensing

    International Nuclear Information System (INIS)

    Wene, C.O.

    1992-01-01

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

  19. An introduction to intellectual property licensing for technology companies

    Science.gov (United States)

    Meier, Lawrence H.

    2001-05-01

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

  20. Hanford Site Protective Barrier Development Program: Fiscal year 1990 highlights

    International Nuclear Information System (INIS)

    Cadwell, L.L.

    1991-09-01

    The Hanford Site Protective Barrier Development Program was jointly developed by Pacific Northwest Laboratory (PNL) and Westinghouse Hanford Company (WHC) to design and test an earthen cover system(s) that can be used to inhibit water infiltration; plant, animal, and human intrusion; and wind and water erosion. The joint PNL/WHC program was initiated in FY 1986. To date, research findings support the initial concepts of barrier designs for the Hanford Site. A fine-soil surface is planned to partition surface water into runoff and temporary storage. Transpiration by vegetation that grows in the fine-soil layer will return stored water to the atmosphere as will surface evaporation. A capillary break created by the interface of the fine-soil layer and coarser textured materials below will further limit the downward migration of surface water, making it available over a longer period of time for cycling to the atmosphere. Should water pass the interface, it will drain laterally through a coarse textured sand/gravel layer. Tested barrier designs appear to work adequately to prevent drainage under current and postulated wetter-climate (added precipitation) conditions. Wind and water erosion tasks are developing data to predict the extent of erosion on barrier surfaces. Data collected during the last year confirm the effectiveness of small burrowing animals in removing surface water. Water infiltrating through burrows of larger mammals was subsequently lost by natural processes. Natural analog and climate change studies are under way to provide credibility for modeling the performance of barrier designs over a long period of time and under shifts in climate. 10 refs., 30 figs

  1. Hanford Site Protective Barrier Development Program: Fiscal year 1990 highlights

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, L.L. (ed.)

    1991-09-01

    The Hanford Site Protective Barrier Development Program was jointly developed by Pacific Northwest Laboratory (PNL) and Westinghouse Hanford Company (WHC) to design and test an earthen cover system(s) that can be used to inhibit water infiltration; plant, animal, and human intrusion; and wind and water erosion. The joint PNL/WHC program was initiated in FY 1986. To date, research findings support the initial concepts of barrier designs for the Hanford Site. A fine-soil surface is planned to partition surface water into runoff and temporary storage. Transpiration by vegetation that grows in the fine-soil layer will return stored water to the atmosphere as will surface evaporation. A capillary break created by the interface of the fine-soil layer and coarser textured materials below will further limit the downward migration of surface water, making it available over a longer period of time for cycling to the atmosphere. Should water pass the interface, it will drain laterally through a coarse textured sand/gravel layer. Tested barrier designs appear to work adequately to prevent drainage under current and postulated wetter-climate (added precipitation) conditions. Wind and water erosion tasks are developing data to predict the extent of erosion on barrier surfaces. Data collected during the last year confirm the effectiveness of small burrowing animals in removing surface water. Water infiltrating through burrows of larger mammals was subsequently lost by natural processes. Natural analog and climate change studies are under way to provide credibility for modeling the performance of barrier designs over a long period of time and under shifts in climate. 10 refs., 30 figs.

  2. Nuclear power stations licensing

    International Nuclear Information System (INIS)

    Solito, J.

    1978-04-01

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

  3. Nevada Test Site-Directed Research, Development, and Demonstration

    International Nuclear Information System (INIS)

    Will Lewis, Compiler

    2006-01-01

    The Nevada Test Site-Directed Research, Development, and Demonstration (SDRD) program completed a very successful year of research and development activities in FY 2005. Fifty new projects were selected for funding this year, and five FY 2004 projects were brought to conclusion. The total funds expended by the SDRD program were $5.4 million, for an average per project cost of just under $100,000. Two external audits of SDRD accounting practices were conducted in FY 2005. Both audits found the program's accounting practices consistent with the requirements of DOE Order 413.2A, and one included the observation that the NTS contractor ''did an exceptional job in planning and executing year-start activities.'' Highlights for the year included: the filing of 18 invention disclosures for intellectual property generated by FY 2005 projects; programmatic adoption of 17 FY 2004 SDRD-developed technologies; participation in the tri-lab Laboratory Directed Research and Development (LDRD) and SDRD program review that was broadly attended by NTS, NNSA, LDRD, and U.S. Department of Homeland Security representatives; peer reviews of all FY 2005 projects; and the successful completion of 55 R and D projects, as presented in this report

  4. The development of surface barriers at the Hanford Site

    International Nuclear Information System (INIS)

    Wing, N.R.; Gee, G.W.

    1994-03-01

    Engineered barriers are being developed to isolate wastes disposed of near the earth's surface at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. Much of the waste that would be disposed of by in-place stabilization currently is located in relatively shallow subsurface structures such as solid waste burial grounds, tanks, vaults, and cribs. Unless protected in some way, the wastes could be transported to the accessible environment via the following pathways: plant, animal, and human intrusion; water infiltration; erosion; and the exhalation of noxious gases. Permanent isolation surface barriers have been proposed to protect wastes disposed of ''in place'' from the transport pathways identified previously (Figure 1). The protective barrier consists of a variety of different materials (e.g., fine soil, sand, gravel, riprap, asphalt, etc.) placed in layers to form an above-grade mound directly over the waste zone. Surface markers are being considered for placement around the periphery of the waste sites to inform future generations of the nature and hazards of the buried wastes. In addition, throughout the protective barrier, subsurface markers could be placed to warn any inadvertent human intruders of the dangers of the buried wastes (Figure 2)

  5. The development of an on-site container

    International Nuclear Information System (INIS)

    Glass, R.E.; McAllaster, M.E.; Jones, P.L.; McKinney, A.L.

    1993-01-01

    This paper describes the results of the development of a packaging designed for on-site transportation of chemical munitions. The criteria for the package were patterned after the requirements for Type B packagings, but were modified to take credit for the operational controls that could be applied on-site. The design phase has been completed and a contract has been placed for fabrication of 165 units. In addition to the tests completed during the design phase, a complete sequence of verification tests will be performed on the first fleet unit. This sequence will consist of: (1) a 22,700-kg load placed on the packaging for 24 hours, (2) the flat side free drop, (3) the center-of-gravity over closure joint puncture test, and (4) a 15-min all-engulfing JP-4 pool-fire test. At the completion of the test sequence, the package will be required to meet the less than 1 x 10 -1 std cc/s leak test. (J.P.N.)

  6. Means for improving state participation in the siting, licensing, and development of Federal nuclear waste facilities. A report to Congress

    International Nuclear Information System (INIS)

    1979-03-01

    This report is based on the premise that State involvement in any national nuclear waste management program is important in making the program work. The following issues are discussed: national planning process, technical review capability, state participation in the Federal processes, grant programs, transportation, and consultation and concurrence. Recommendations are given

  7. Biologic Agents for Periodontal Regeneration and Implant Site Development

    Directory of Open Access Journals (Sweden)

    Fernando Suárez-López del Amo

    2015-01-01

    Full Text Available The advancement of molecular mediators or biologic agents has increased tremendously during the last decade in periodontology and dental implantology. Implant site development and reconstruction of the lost periodontium represent main fields in which these molecular mediators have been employed and investigated. Different growth factors trigger different reactions in the tissues of the periodontium at various cellular levels. Proliferation, migration, and differentiation constitute the main target areas of these molecular mediators. It was the purpose of this comprehensive review to describe the origin and rationale, evidence, and the most current understanding of the following biologic agents: Recombinant Human Platelet-Derived Growth Factor-BB (rhPDGF-BB, Enamel Matrix Derivate (EMD, Platelet-Rich Plasma (PRP and Platelet-Rich Fibrin (PRF, Recombinant Human Fibroblast Growth Factor-2 (rhFGF-2, Bone Morphogenic Proteins (BMPs, BMP-2 and BMP-7, Teriparatide PTH, and Growth Differential Factor-5 (GDF-5.

  8. Growing up wired: social networking sites and adolescent psychosocial development.

    Science.gov (United States)

    Spies Shapiro, Lauren A; Margolin, Gayla

    2014-03-01

    Since the advent of social networking site (SNS) technologies, adolescents' use of these technologies has expanded and is now a primary way of communicating with and acquiring information about others in their social network. Overall, adolescents and young adults' stated motivations for using SNSs are quite similar to more traditional forms of communication-to stay in touch with friends, make plans, get to know people better, and present oneself to others. We begin with a summary of theories that describe the role of SNSs in adolescents' interpersonal relationships, as well as common methodologies used in this field of research thus far. Then, with the social changes that occur throughout adolescence as a backdrop, we address the ways in which SNSs intersect with key tasks of adolescent psychosocial development, specifically peer affiliation and friendship quality, as well as identity development. Evidence suggests that SNSs differentially relate to adolescents' social connectivity and identity development, with sociability, self-esteem, and nature of SNS feedback as important potential moderators. We synthesize current findings, highlight unanswered questions, and recommend both methodological and theoretical directions for future research.

  9. Mechanisation and automation technologies development in work at construction sites

    Science.gov (United States)

    Sobotka, A.; Pacewicz, K.

    2017-10-01

    Implementing construction work that creates buildings is a very complicated and laborious task and requires the use of various types of machines and equipment. For years there has been a desire for designers and technologists to introduce devices that replace people’s work on machine construction, automation and even robots. Technologies for building construction are still being developed and implemented to limit people’s hard work and improve work efficiency and quality in innovative architectonical and construction solutions. New opportunities for improving work on the construction site include computerisation of technological processes and construction management for projects and processes. The aim of the paper was to analyse the development of mechanisation, automation and computerisation of construction processes and selected building technologies, with special attention paid to 3D printing technology. The state of mechanisation of construction works in Poland and trends in its development in construction technologies are presented. These studies were conducted on the basis of the available literature and a survey of Polish construction companies.

  10. Nuclear reactor operator licensing

    International Nuclear Information System (INIS)

    Bursey, R.J.

    1978-01-01

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

  11. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    1987-05-01

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

  12. Licensing of simple digital devices

    International Nuclear Information System (INIS)

    Jackson, T. W.

    2008-01-01

    The inability to guarantee error-free software gave rise to the potential for common-cause failure of digital safety systems in nuclear power plants. To address this vulnerability, the U. S. Nuclear Regulatory Commission (NRC) required a quality software development process and a defense-in-depth and diversity analysis for digital safety systems. As a result of recent interim [NRC] staff guidance in the digital instrumentation and control (I and C) area, licensing of simple digital devices decreases some regulatory burden with respect to demonstrating a quality software development process and defense-in-depth and diversity analysis. This paper defines simple digital devices and addresses the interim staff guidance that applies to such devices. The paper also highlights the technical aspects that affect the licensing of such devices and incorporates licensing experience in the U.S. to date. (authors)

  13. Thermal site descriptive model. A strategy for the model development during site investigations - version 2

    Energy Technology Data Exchange (ETDEWEB)

    Back, Paer-Erik; Sundberg, Jan [Geo Innova AB (Sweden)

    2007-09-15

    This report presents a strategy for describing, predicting and visualising the thermal aspects of the site descriptive model. The strategy is an updated version of an earlier strategy applied in all SDM versions during the initial site investigation phase at the Forsmark and Oskarshamn areas. The previous methodology for thermal modelling did not take the spatial correlation fully into account during simulation. The result was that the variability of thermal conductivity in the rock mass was not sufficiently well described. Experience from earlier thermal SDMs indicated that development of the methodology was required in order describe the spatial distribution of thermal conductivity in the rock mass in a sufficiently reliable way, taking both variability within rock types and between rock types into account. A good description of the thermal conductivity distribution is especially important for the lower tail. This tail is important for the design of a repository because it affects the canister spacing. The presented approach is developed to be used for final SDM regarding thermal properties, primarily thermal conductivity. Specific objectives for the strategy of thermal stochastic modelling are: Description: statistical description of the thermal conductivity of a rock domain. Prediction: prediction of thermal conductivity in a specific rock volume. Visualisation: visualisation of the spatial distribution of thermal conductivity. The thermal site descriptive model should include the temperature distribution and thermal properties of the rock mass. The temperature is the result of the thermal processes in the repository area. Determination of thermal transport properties can be made using different methods, such as laboratory investigations, field measurements, modelling from mineralogical composition and distribution, modelling from density logging and modelling from temperature logging. The different types of data represent different scales, which has to be

  14. Thermal site descriptive model. A strategy for the model development during site investigations - version 2

    International Nuclear Information System (INIS)

    Back, Paer-Erik; Sundberg, Jan

    2007-09-01

    This report presents a strategy for describing, predicting and visualising the thermal aspects of the site descriptive model. The strategy is an updated version of an earlier strategy applied in all SDM versions during the initial site investigation phase at the Forsmark and Oskarshamn areas. The previous methodology for thermal modelling did not take the spatial correlation fully into account during simulation. The result was that the variability of thermal conductivity in the rock mass was not sufficiently well described. Experience from earlier thermal SDMs indicated that development of the methodology was required in order describe the spatial distribution of thermal conductivity in the rock mass in a sufficiently reliable way, taking both variability within rock types and between rock types into account. A good description of the thermal conductivity distribution is especially important for the lower tail. This tail is important for the design of a repository because it affects the canister spacing. The presented approach is developed to be used for final SDM regarding thermal properties, primarily thermal conductivity. Specific objectives for the strategy of thermal stochastic modelling are: Description: statistical description of the thermal conductivity of a rock domain. Prediction: prediction of thermal conductivity in a specific rock volume. Visualisation: visualisation of the spatial distribution of thermal conductivity. The thermal site descriptive model should include the temperature distribution and thermal properties of the rock mass. The temperature is the result of the thermal processes in the repository area. Determination of thermal transport properties can be made using different methods, such as laboratory investigations, field measurements, modelling from mineralogical composition and distribution, modelling from density logging and modelling from temperature logging. The different types of data represent different scales, which has to be

  15. To License or Not to License Remanufacturing Business?

    Directory of Open Access Journals (Sweden)

    Zu-Jun Ma

    2018-01-01

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

  16. Site characterization plan overview: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Consultation Draft

    International Nuclear Information System (INIS)

    1988-01-01

    The consultation draft of the site characterization plan is a lengthy document that describes in considerable detail the program that will be conducted to characterize the geologic, hydrologic, and other conditions relevant to the suitability of the site for a repository. The overview presented here consists of brief summaries of important topics covered in the consultation draft of the site-characterization plan; it is not a substitute for the site-characterization plan. The arrangement of the overview is similar to that of the plan itself, with brief descriptions of the disposal system -- the site, the repository, and the waste package -- preceding the discussion of the characterization program to be carried out at the Yucca Mountain site. It is intended primarily for the management staff of organizations involved in the DOE's repository program -- staff who might wish to understand the general scope of the site-characterization program, the activities to be conducted, and the facilities to be constructed rather than the technical details of site characterization. 22 figs., 1 tab

  17. Regulatory systems-based licensing guidance documentation

    International Nuclear Information System (INIS)

    Delligatti, M.S.

    1991-01-01

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

  18. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

  19. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 4

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package; and to present the plans for obtaining the geologic information necessary to demonstate the suitability of the site for a repository, to desin the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next; it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

  20. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended by the Secretary of Energy and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared by the US Department of Energy (DOE) in accordance with the requirements of the Nulcear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of the site characterization plan are oulined, and compliance with applicable regulations is discussed

  1. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  2. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  3. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package; and to present the plans for obtaining the geologic information necessary to demonstate the suitability of the site for a repository, to desin the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next; it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  4. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended by the Secretary of Energy and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared by the US Department of Energy (DOE) in accordance with the requirements of the Nulcear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of the site characterization plan are oulined, and compliance with applicable regulations is discussed.

  5. Licensing aspects regarding the RBMN project

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  6. Development of subsurface characterization method for decommissioning site remediation

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sang Bum; Nam, Jong Soo; Choi, Yong Suk; Seo, Bum Kyoung; Moon, Jei Kwon; Choi, Jong Won [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    In situ measurement of peak to valley method based on the ratio of counting rate between the full energy peak and Compton region was applied to identify the depth distribution of 137Cs. The In situ measurement and sampling results were applied to evaluate a residual radioactivity before and after remediation in decommissioning KRR site. Spatial analysis based on the Geostatistics method provides a reliable estimating the volume of contaminated soil with a graphical analysis, which was applied to the site characterization in the decommissioning KRR site. The in situ measurement and spatial analysis results for characterization of subsurface contamination are presented. The objective of a remedial action is to reduce risks to human health to acceptable levels by removing the source of contamination. Site characterization of the subsurface contamination is an important factor for planning and implementation of site remediation. Radiological survey and evaluation technology are required to ensure the reliability of the results, and the process must be easily applied during field measurements. In situ gamma-ray spectrometry is a powerful method for site characterization that can be used to identify the depth distribution and quantify radionuclides directly at the measurement site. The in situ measurement and Geostatistics method was applied to the site characterization for remediation and final status survey in decommissioning KRR site.

  7. Comparative Analysis of Hydraulic Fracturing Wastewater Practices in Unconventional Shale Development: Newspaper Coverage of Stakeholder Concerns and Social License to Operate

    Directory of Open Access Journals (Sweden)

    Joel Gehman

    2016-09-01

    Full Text Available In this article we review prior literature regarding the concept of social license to operate, and related concepts, including corporate social responsibility, sustainable development, stakeholder management and cumulative effects. Informed by these concepts, we search for newspaper articles published in North American provinces and states where the Barnett, Duvernay, Marcellus and Montney shale plays are located. Using these data, we tabulate coverage of stakeholder concerns related to hydraulic fracturing and wastewater practices, and compare the extent to which these concerns vary over place and time. Our vocabulary analyses identify differences in the types and quantities of newspaper coverage devoted to concerns regarding hydraulic fracturing activities in general and wastewater practices in particular. We interpret these differences as suggesting that obtaining a social license to operate is likely not a one size fits all proposition. By understanding which stakeholder concerns are most salient in particular places and times, oil and gas operators and regulators can better tailor their strategies and policies to address local concerns. In other words, the findings from this study indicate that conventional understandings of risk as a technical or economic problem may not be adequate for dealing with unconventional resource challenges such as hydraulic fracturing. Operators and regulators may also need to manage social and cultural risks.

  8. Site development in the Central Midwest Compact Region

    International Nuclear Information System (INIS)

    Lash, T.R.

    1986-01-01

    Illinois and Kentucky, the two members of the Central Midwest Interstate Low-Level Radioactive Waste Compact, are well along in fulfilling their responsibility to provide new low-level radioactive waste (LLW) disposal capacity, which has been delegated to states and regions by federal law. The host state for facilities under the compact will be Illinois, and thus the focus of this paper is on Illinois' siting process. Illinois has both the statutory authority for LLW management and a cabinet-level agency, the Illinois Department of Nuclear Safety (IDNS), which has the responsibility for implementing the state management act. Based on activities to date, the Central Midwest Region expects to meet the milestones established by the federal Low-Level Radioactive Waste Policy Amendments Act of 1985. Illinois, however, cannot take further progress toward managing and disposing of our LLW for granted. IDNS and the Central Midwest Compact Commission (CMCC) must continue vigorously to press ahead to assure timely development of new disposal capacity. This paper provides background information on (1) the laws under which new facilities will be established in the Central Midwest Region, (2) the activities of IDNS and CMCC, and (3) planned activities by both IDNS and the CMCC

  9. Selecting Suitable Sites for Wind Energy Development in Ghana*

    African Journals Online (AJOL)

    Michae O. Mensah

    2016-06-01

    Jun 1, 2016 ... Ghana's wind power potential both on-shore and off-shore. ..... such as forest and game reserves, tourist sites, etc. (iv) Siting in lakes is restricted. (v) Slopes greater than 30° ... Atlantic coastline that stretches 560 km along the.

  10. Systematic analysis of transcription start sites in avian development.

    Directory of Open Access Journals (Sweden)

    Marina Lizio

    2017-09-01

    Full Text Available Cap Analysis of Gene Expression (CAGE in combination with single-molecule sequencing technology allows precision mapping of transcription start sites (TSSs and genome-wide capture of promoter activities in differentiated and steady state cell populations. Much less is known about whether TSS profiling can characterize diverse and non-steady state cell populations, such as the approximately 400 transitory and heterogeneous cell types that arise during ontogeny of vertebrate animals. To gain such insight, we used the chick model and performed CAGE-based TSS analysis on embryonic samples covering the full 3-week developmental period. In total, 31,863 robust TSS peaks (>1 tag per million [TPM] were mapped to the latest chicken genome assembly, of which 34% to 46% were active in any given developmental stage. ZENBU, a web-based, open-source platform, was used for interactive data exploration. TSSs of genes critical for lineage differentiation could be precisely mapped and their activities tracked throughout development, suggesting that non-steady state and heterogeneous cell populations are amenable to CAGE-based transcriptional analysis. Our study also uncovered a large set of extremely stable housekeeping TSSs and many novel stage-specific ones. We furthermore demonstrated that TSS mapping could expedite motif-based promoter analysis for regulatory modules associated with stage-specific and housekeeping genes. Finally, using Brachyury as an example, we provide evidence that precise TSS mapping in combination with Clustered Regularly Interspaced Short Palindromic Repeat (CRISPR-on technology enables us, for the first time, to efficiently target endogenous avian genes for transcriptional activation. Taken together, our results represent the first report of genome-wide TSS mapping in birds and the first systematic developmental TSS analysis in any amniote species (birds and mammals. By facilitating promoter-based molecular analysis and genetic

  11. Developing Hydrogeological Site Characterization Strategies based on Human Health Risk

    Science.gov (United States)

    de Barros, F.; Rubin, Y.; Maxwell, R. M.

    2013-12-01

    In order to provide better sustainable groundwater quality management and minimize the impact of contamination in humans, improved understanding and quantification of the interaction between hydrogeological models, geological site information and human health are needed. Considering the joint influence of these components in the overall human health risk assessment and the corresponding sources of uncertainty aid decision makers to better allocate resources in data acquisition campaigns. This is important to (1) achieve remediation goals in a cost-effective manner, (2) protect human health and (3) keep water supplies clean in order to keep with quality standards. Such task is challenging since a full characterization of the subsurface is unfeasible due to financial and technological constraints. In addition, human exposure and physiological response to contamination are subject to uncertainty and variability. Normally, sampling strategies are developed with the goal of reducing uncertainty, but less often they are developed in the context of their impacts on the overall system uncertainty. Therefore, quantifying the impact from each of these components (hydrogeological, behavioral and physiological) in final human health risk prediction can provide guidance for decision makers to best allocate resources towards minimal prediction uncertainty. In this presentation, a multi-component human health risk-based framework is presented which allows decision makers to set priorities through an information entropy-based visualization tool. Results highlight the role of characteristic length-scales characterizing flow and transport in determining data needs within an integrated hydrogeological-health framework. Conditions where uncertainty reduction in human health risk predictions may benefit from better understanding of the health component, as opposed to a more detailed hydrogeological characterization, are also discussed. Finally, results illustrate how different dose

  12. Transition to e-government in Developing countries: The Case of Driver and Vehicle Licensing Authority (DVLA) e-Service Smart City Initiatives in Ghana

    DEFF Research Database (Denmark)

    Kofi Wireko, Joseph; Skouby, Knud Erik

    2016-01-01

    Most developing countries, especially in Africa are fighting corruption as a major barrier to development, and e-government is seen as a new way of addressing it. Besides generally being recognized as cost-efficient, e-government is thought to reduce corruption through increased transparency......, better accountability and, the disappearance of the “middle-man” in the acquisition of public services by the citizenry. This paper discusses the extent to which this has been achieved in Ghana by analyzing the implementation of e-government service of the Driver and Vehicle Licensing Authority (DVLA......) of Ghana using the “stages of growth” mode from a sociotechnical perspective. The outcome of the analysis suggests that the e-government service implementation by DVLA is still at its basic and rudimentary stage (Catalogue stage) and continuous presence of the “middle-man,” high level of corruption, lack...

  13. License renewal demonstration program: NRC observations and lessons learned

    International Nuclear Information System (INIS)

    Prato, R.J.; Kuo, P.T.; Newberry, S.F.

    1996-12-01

    This report summarizes the Nuclear Regulatory Commission staff's observations and lessons learned from the five License Renewal Demonstration Program (LRDP) site visits performed by the staff from March 25, 1996, through August 16, 1996. The LRDP was a Nuclear Energy Institute (NEI) program intended to assess the effectiveness of the guidance provided by NEI 95-10, Revision 0, open-quotes Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule,close quotes to implement the requirements of Title 10 of the Code of Federal Regulations, Part 54 (10 CFR Part 54), open-quotes Requirements for Renewal of Operating Licenses for Nuclear Power Plants.close quotes In general, NEI 95-10 appeared to contain the basic guidance needed for scoping, screening, identifying aging effects, developing aging management programs, and performing time-limited aging analyses. However, inconsistent implementation of this guidance in some areas was an indication that clarification of existing guidance and/or the inclusion-of some new guidance may be needed for applicants to develop a license renewal program that is consistent with the intent of the rule

  14. Grimsel Test Site. Further Development of Seismic Tomography

    International Nuclear Information System (INIS)

    Albert, W.; Buehnemann, J.; Holliger, K.; Maurer, H.R.; Pratt, G.; Stekl, I.

    1999-03-01

    Experience gained by NAGRA and its partner organisations in the Grimsel underground rock laboratory has led to the identification of two main areas of investigation: The first part of the present project deals with the evaluation and testing of underground seismic sources suitable for large measurement distances. Various high-frequency seismic sources have been tested at the Grimsel Test Site (GTS) (Buehnemann, 1996; Buehnemann and Holliger, 1998). The tests were designed to facilitate future tomographic studies of potential radioactive waste disposal sites. A key objective was to identify borehole and tunnel seismic sources capable of generating and sustaining high-frequency signals over distances of up to 1000 m. Seismic sources were located in both water-filled boreholes (sparker, two piezo-electric sources, explosives) and at the tunnel wall (accelerated weight drop, minivibrator, bolt gun, buffalo gun, explosives). The second focal point of the project was dealing with improvement (and development) of analysis techniques in terms of stability, quality and resolution. 3 inversion techniques were tested and developed using the dataset US85 (Gelbke, 1988). Two travel time inversions - anisotropic velocity tomography - AVT (Pratt and Chapman, 1992) and coupled inversion - CI (Maurer, 1996; Maurer and Green, 1997) - and a wave field inversion (WFI Song et al., 1995) were used. Several problems occurred in the first inversion of the US85 dataset using the Simultaneous Iterative Reconstruction Technique (SIRT); these were due to the velocity anisotropy of the rock, the triggering inaccuracy of the shots and uncertainties regarding the source/receiver locations in the boreholes. In the AVT, the velocity anisotropy of the rock is taken into account as a free parameter. In addition to an 'isotropic' velocity image, this involves producing tomograms of anisotropy. Taking into account the anisotropy of the rock allows the artefacts of the SIRT inversion to be explained

  15. 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

  16. Libraries and licensing

    Directory of Open Access Journals (Sweden)

    Maja Žumer

    2001-01-01

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

  17. Technology Licensing Strategy for Network Product in a Service Industry

    Directory of Open Access Journals (Sweden)

    Xianpei Hong

    2015-01-01

    Full Text Available Technology licensing has gained significant attention in literature and practice as a rapid and effective way to improve firm’s capability of technology innovation. In this paper, we investigate a duopolistic service provider competition market, where service providers develop and sell a kind of network product. In this setting, we analyze the innovating service provider’s four licensing strategies: no licensing, fixed fee licensing, royalty licensing, and two-part tariff licensing. The literature suggests that when the network products can be completely substituted, two-part tariff licensing is the optimal strategy of the innovating service provider. We find that when the network products cannot be completely substituted, two-part tariff licensing is not always optimal. The degree of the product differentiation, the intensity of the network effects, and the R&D cost of the potential licensee play a key role in determining the innovating service provider’s optimal licensing strategies.

  18. 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)

  19. Licensing Support Network: An Electronic Discovery System

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  20. Site characterization plan overview: Yucca Mountain site, Nevada Research and Development Area, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    To help the public better understand both the SCP and the site characterization program, the DOE has prepared this overview and the SCP Public Handbook. The overview presents summaries of selected topics covered in the SCP; it is not a substitute for the SCP. The organization of the overview is similar to that of the SCP itself, with brief descriptions of the Yucca Mountain site, the repository, and the containers in which the waste would be packaged, followed by a discussion of the characterization program to be carried out at the Yucca Mountain site. This overview is intended primarily for those persons who want to understand the general scope and basis of the site-characterization program, the activities to be conducted, and the facilities to be constructed without spending the time necessary to become familiar with all of the technical details presented in the SCP. For the readers of the SCP, the overview will be useful as a general guide to the plan. The SCP Public Handbook is a short document that contains brief descriptions of the SCP process and the contents of the SCP. It also explains how the public can submit comments on the SCP and lists the libraries and reading rooms at which the SCP is available. 9 refs., 18 tabs.

  1. Site characterization plan overview: Yucca Mountain site, Nevada Reserch and Development Area, Nevada

    International Nuclear Information System (INIS)

    1988-12-01

    To help the public better understand both the SCP and the site characterization program, the DOE has prepared this overview and the SCP Public Handbook. The overview presents summaries of selected topics covered in the SCP; it is not a substitute for the SCP. The organization of the overview is similar to that of the SCP itself, with brief descriptions of the Yucca Mountain site, the repository, and the containers in which the waste would be packaged, followed by a discussion of the characterization program to be carried out at the Yucca Mountain site. This overview is intended primarily for those persons who want to understand the general scope and basis of the site-characterization program, the activities to be conducted, and the facilities to be constructed without spending the time necessary to become familiar with all of the technical details presented in the SCP. For the readers of the SCP, the overview will be useful as a general guide to the plan. The SCP Public Handbook is a short document that contains brief descriptions of the SCP process and the contents of the SCP. It also explains how the public can submit comments on the SCP and lists the libraries and reading rooms at which the SCP is available. 9 refs., 18 tabs

  2. 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)

  3. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 3, Part A: Chapters 6 and 7

    International Nuclear Information System (INIS)

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 218 figs., 50 tabs

  4. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 1, Part A: Chapters 1 and 2

    International Nuclear Information System (INIS)

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 750 refs., 123 figs., 42 tabs

  5. Site Characterization Plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 3, Part A: Chapters 6 and 7

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 218 figs., 50 tabs.

  6. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 1, Part A: Chapters 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 750 refs., 123 figs., 42 tabs.

  7. SITE-94. Scenario development FEP audit list preparation: methodology and presentation

    International Nuclear Information System (INIS)

    Stenhouse, M.; Chapman, N.; Sumerling, T.

    1993-04-01

    This report concerns a study which is part of the SKI performance assessment project SITE-94. SITE-94 is a performance assessment of a hypothetical repository at a real site. The main objective of the project is to determine how site specific data should be assimilated into the performance assessment process and to evaluate how uncertainties inherent in site characterization will influence performance assessment results. Other important elements of SITE-94 are the development of a practical and defensible methodology for defining, constructing and analyzing scenarios, the development of approaches for treatment of uncertainties , evaluation of canister integrity, and the development and application of an appropriate quality assurance plan for performance assessments

  8. Recommendations: Procedure to develop a preliminary safety report as part of the radioactive waste repository construction licensing process

    International Nuclear Information System (INIS)

    2003-01-01

    The structure of a preliminary safety report for the title purpose should be as follows: A. Textual part: 1. General (Introduction, Basic information about the construction, Timetable); 2. Site information (Siting, Geography and demography, Meteorology and climatic situation, Hydrology, Geology and hydrogeology); 3. Repository design description (Basic function and performance requirements, Design, Auxiliary systems, Fire prevention/protection, Emergency plans); 4. Operation of the repository (Waste acceptance and inspection, Waste handling and interim storage, Waste disposal, Operating monitoring), 5. Health and environmental impact assessment (Radionuclide inventory, Radionuclide transport paths and mechanisms of release into the environment, Radionuclide release in normal and emergency situations, Radiation protection - health impact assessment and regulatory compliance, Draft operating limits and conditions, Proposed ways of assuring physical protection, Uncertainty assessment), 6. Safe repository shutdown/decommissioning concept, 7 Quality assurance assessment, 8. List of selected equipment. B. Annexes: Maps, Drawings, Diagrams, Miscellaneous; C. Documentation: Previous safety report amendments, Protocols, Miscellaneous. (P.A.)

  9. Source term development for tritium at the Sheffield disposal site

    International Nuclear Information System (INIS)

    MacKenzie, D.R.; Barletta, R.E.; Smalley, J.F.; Kempf, C.R.; Davis, R.E.

    1984-01-01

    The Sheffield low-level radioactive waste disposal site, which ceased operation in 1978, has been the focus of modeling efforts by the NRC for the purpose of predicting long-term site behavior. To provide the NRC with the information required for its modeling effort, a study to define the source term for tritium in eight trenches at the Sheffield site has been undertaken. Tritium is of special interest since significant concentrations of the isotope have been found in groundwater samples taken at the site and at locations outside the site boundary. Previous estimates of tritium site inventory at Sheffield are in wide disagreement. In this study, the tritium inventory in the eight trenches was estimated by reviewing the radioactive shipping records (RSRs) for waste buried in these trenches. It has been found that the tritium shipped for burial at the site was probably higher than previously estimated. In the eight trenches surveyed, which amount to roughly one half the total volume and activity buried at Sheffield, approximately 2350 Ci of tritium from non-fuel cycle sources were identified. The review of RSRs also formed the basis for obtaining waste package descriptions and for contacting large waste generators to obtain more detailed information regarding these waste packages. As a result of this review and the selected generator contacts, the non-fuel cycle tritium waste was categorized. The tritium releases from each of these waste categories were modeled. The results of this modeling effort are presented for each of the eight trenches selected. 3 references, 2 figures

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    Dverstorpand, Bjoern; Stroemberg, Bo

    2014-01-01

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

  12. 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

  13. Licensing of MAPLE reactors in Canada

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  14. 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

  15. 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

  16. Development of site index curves for Pinus kesiya in the Philippines ...

    African Journals Online (AJOL)

    Development of site index curves for Pinus kesiya in the Philippines. RIC Lumbres, YJ Lee, YO Seo, FG Calora JR. Abstract. This study was conducted to develop a height–age growth model and site index curves for site quality evaluation of old secondary-growth stands of Pinus kesiya in the northern Philippines.

  17. Social Network Sites: A Starting Point for Career Development Practitioners

    Science.gov (United States)

    Strehlke, Christina

    2010-01-01

    This action research study explores the career influence of social network sites (SNSs) by examining 14 web-based articles that consider the risks and opportunities of SNSs from a job search perspective. Three themes are discussed: user visibility, self-presentation, and network connections. Practical strategies are identified to help career…

  18. Thymus: The site for Development of Cellular Immunity

    Indian Academy of Sciences (India)

    The immune system protects our bodies against infectionsand cancers. This review introduce readers to the thymus. – a primary lymphoid organ – which is the site of developmentand maturation of functional T lymphocytes. Progenitorstem cells arise from the bone marrow and undergo sequentialdevelopment in the thymus ...

  19. Developing Classroom Web Sites for 21st Century Learning

    Science.gov (United States)

    Tingen, Jennifer; Philbeck, Lauren; Holcomb, Lori B.

    2011-01-01

    Classroom Web sites have the potential to support and enhance student learning by targeting 21st century skills, such as collaboration among teachers, students, parents, and other teachers, media literacy, and interpersonal and self-directional skills, as well as thinking and problem-solving skills. Web 2.0 tools such as blogs, vokis, and podcasts…

  20. 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)

  1. Geothermal energy in Alaska: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    Markle, D.R.

    1979-04-01

    The various factors affecting geothermal resource development are summarized for Alaska including: resource data base, geological description, reservoir characteristics, environmental character, base and development status, institutional factors, economics, population and market, and development potential. (MHR)

  2. Geothermal energy in Idaho: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    1979-07-01

    The various factors affecting geothermal resource development are summarized for Idaho, including: resource data base, geological description, reservoir characteristics, environmental character, lease and development status, institutional factors, legal aspects, population and market, and development. (MHR)

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

    International Nuclear Information System (INIS)

    Kadak, Andrew C.

    2001-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-15

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

  5. A study on development of monitoring and assessment module for sites

    International Nuclear Information System (INIS)

    Park, Se Moon; Yoon, Bong Yo; Kim, Dae Jung; Park, Joo Wan; Kim, Chang Lak

    2006-01-01

    As the development of total management systems for sites along with site environmental information is becoming standard, the system known as the Site Information and Total Environmental database management System (SITES) has been developed over the last two years. The first result was a database management system for storing data obtained from facilities, and a site characterization in addition to an environmental assessment of a site. The SITES database is designed to be effective and practical for use with facility management and safety assessment in relation to Geographic Information Systems. SITES is a total management program, which includes its database, its data analysis system required for site characterization, a safety assessment modeling system and an environment monitoring system. I can contribute to the institutional management of the facility and to its safety reassessment. SITES is composed of two main modules: the SITES Database Module (SDM) and the Monitoring and Assessment (M and A) module. The M and A module is subdivided into two sub-modules: the Safety Assessment System (SAS) and the Site Environmental Monitoring System (SEMS). SAS controls the data (input and output) from the SITES DB for the site safety assessment, whereas SEMS controls the data obtained from the records of the measuring sensors and facilities. The on-line site and environmental monitoring data is managed in SEMS. The present paper introduces the procedure and function of the M and A modules

  6. 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

  7. Understanding Licensing Behavior

    DEFF Research Database (Denmark)

    Cabaleiro, Goretti; Moreira, Solon; Reichstein, Toke

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

  8. EPA-developed, patented technologies related to miscellaneous areas of environmental experties and invention that are available for licensing

    Data.gov (United States)

    U.S. Environmental Protection Agency — Under the Federal Technology Transfer Act (FTTA), Federal Agencies can patent inventions developed during the course of research. These technologies can then be...

  9. License Agreements | NCI Technology Transfer Center | TTC

    Science.gov (United States)

    NCI Technology Transfer Center (TTC) licenses the discoveries of NCI and nine other NIH Institutes so new technologies can be developed and commercialized, to convert them into public health benefits.

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

    International Nuclear Information System (INIS)

    Jamieson, T.

    2009-01-01

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

  11. Development of corrective measures and site stabilization technologies for shallow land burial facilities at semiarid sites: summary paper

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Abeele, W.V.

    1987-01-01

    The overall purpose of the corrective measures task performed for the national Low-Level Waste Management Program (NLLWMP) has been to develop and test methods that can be used to correct any actual or anticipated problems with new and existing shallow land burial (SLB) sites in a semiarid environment. These field tests have not only evaluated remedial actions, but have also investigated phenomena suspected of being a possible problem at semiarid SLB sites. The approach the authors have taken in developing remedial action and site closure technologies for low-level waste sites is to recognize the physical and biological processes affecting site integrity are interdependent, and therefore, cannot be treated as separate problems. More specifically the field experiments performed for this task were to identify, evaluate, and model erosion control technologies, field test second generation biointrusion barriers, determine by field experiments the extent of upward radionuclide migration due to moisture cycling, and measure the effects of subsidence on remedial action of other system components. In the following sections of this final task summary report, the authors describe the progress made in establishing the facility in which many of these field experiments were performed, the Los Alamos Experimental Engineered Test Facility (EETF), as well as a brief description of the four research areas encompassed by this task. 45 references, 4 figures

  12. License - Q-TARO | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...thout notice. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - Q-TARO | LSDB Archive ...

  13. License - ClEST | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...License Update History of This Database Site Policy | Contact Us License - ClEST | LSDB Archive ...

  14. License - dbQSNP | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...escription Download License Update History of This Database Site Policy | Contact Us License - dbQSNP | LSDB Archive ...

  15. License - eSOL | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...iption Download License Update History of This Database Site Policy | Contact Us License - eSOL | LSDB Archive ...

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

    International Nuclear Information System (INIS)

    Stoyanova-Todorova, P.

    2004-01-01

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

  17. Allegheny County Dog Licenses

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — A list of dog license dates, dog breeds, and dog name by zip code. Currently this dataset does not include City of Pittsburgh dogs.

  18. Credentialing, Licensing, and Education

    Science.gov (United States)

    ... V W X Y Z Credentialing, Licensing, and Education Share: On This Page The Bottom Line Credentials, ... and practices that chiropractors are allowed to perform. Education and Training Professional organizations in some complementary health ...

  19. License to build

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  20. 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

  1. Status of the Texas low-level radioactive waste disposal site - construction sequencing and staffing patterns

    International Nuclear Information System (INIS)

    Jacobi, L.R. Jr.

    1996-01-01

    The Texas Low-Level Radioactive Waste Disposal Authority, an agency of the State of Texas, has been attempting to develop a site for the disposal of low-level radioactive waste in Texas for more than fourteen years. Since 1991, the agency has been evaluating a site near Sierra Blanca, in far west Texas. Site characterization was completed in 1992, and a license application was filed that year. Construction plans were completed in 1993. In April 1996, the licensing agency, the Texas Natural Resource Conservation Commission, completed its review and proposed to issue a license. The administrative hearings on the proposed license should be completed by July 1997. The Authority is prepared to begin construction and operations as soon as a final license can be issued

  2. The development and site investigation of fume diluter

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Bok Youn; Kang, Chang Hee; Jo, Young Do; Lim, Sang Taek [Korea Institute of Geology Mining and Materials, Taejon (Korea, Republic of)

    1996-12-01

    It is third project year on `Application of mobile diesel equipment in underground mines` for providing appropriate measures to improve underground working environment contaminated by the diesel exhaust pollutants. For reducing the exhaust temperature bellow 70 deg. C to prevent production of the governing pollutant (NO{sub 2}), the fume diluter is verified the most effective device through the site investigation. Therefore, the fume diluter is strongly recommended instead of catalytic converter which is employed presently. The performances derived from the tests are as follows; 1) This device increased air flow to 6.7-8.4 times of the original exhaust, 2) Exhaust temperature can be reduced to 66 deg. C from 161 deg. C, 3) All the pollutants can be reduced to bellow than 30 % of exhaust concentration, 4) This device requires less cost and no maintenance. (author). 4 tabs., 4 figs.

  3. Off-site shipment request development and review plan

    International Nuclear Information System (INIS)

    1992-05-01

    On May 17, 1991, Department of Energy Headquarters (DOE-HQ) imposed a moratorium on the shipment of all Resource Conservation and Recovery Act (RCRA) hazardous and Toxic Substances Control Act (TSCA) waste to commercial treatment, storage and disposal facilities. The moratorium was imposed after it was discovered that some shipments of RCRA and TSCA waste from Department of Energy (DOE) sites contained small quantities of radioactive and special nuclear material (SNM). The shipment of these wastes has been attributed to inconsistent and possibly erroneous interpretation of DOE Orders and guidance. In an effort to clarify existing DOE Orders and guidance and establish throughout the DOE complex, June 21, 1991, DOE-HQ issued in draft the Performance Objective for Certification of Non-Radioactive Hazardous Waste. This Performance Objective was subsequently approved on November 15, 1991. The Performance Objective contains specific requirements that must be net to allow the shipment of RCRA and TSCA waste for commercial treatment, storage and disposal. On July 16, 1991, based on the initial draft of the Performance Objective, Martin Marietta Energy Systems (MMES) issued a directive which applies the Performance Objective requirements to all wastes and materials. In addition, this MMES directive imposed the requirement for a review by a Central Waste Management (CWM) Readiness Review Board (RRB). Additional DOE and MMES guidance and directives have been issued since May 17, 1991. This plan applies to all waste destined for shipment from the Portsmouth Gaseous Diffusion Plant (PORTS) to off-site commercial treatment, storage and disposal facilities, and to all materials destined for recycle, surplus and salvage

  4. PBMR-SA licensing project organization

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  5. Development of on-site spent fuel transfer system designs

    International Nuclear Information System (INIS)

    Lambert, R.W.; Pennington, C.W.; Guerra, G.V.

    1993-01-01

    The Electric Power Research Institute (EPRI) of the United States has sponsored development of conceptual designs for accomplishing spent fuel transfer from spent fuel pools to casks and from one cask to another. Under an EPRI research contract, transnuclear has developed several concepts for spent fuel transfer systems. (J.P.N.)

  6. License - AT Atlas | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ... might be changed without notice. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - AT Atlas | LSDB Archive ...

  7. License - RED | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ...ts might be changed without notice. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - RED | LSDB Archive ...

  8. License - TP Atlas | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data ... might be changed without notice. About This Database Database Description Download License Update History of This Database Site Policy | Contact Us License - TP Atlas | LSDB Archive ...

  9. License - FANTOM5 | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data List Contact us FANTOM....0 International . If you use data from this database, please be sure attribute this database as follows: FANTOM...se Database Description Download License Update History of This Database Site Policy | Contact Us License - FANTOM5 | LSDB Archive ...

  10. PTIP chromatin regulator controls development and activation of B cell subsets to license humoral immunity in mice

    DEFF Research Database (Denmark)

    Su, Dan; Vanhee, Stijn; Soria, Rebeca

    2017-01-01

    B cell receptor signaling and downstream NF-κB activity are crucial for the maturation and functionality of all major B cell subsets, yet the molecular players in these signaling events are not fully understood. Here we use several genetically modified mouse models to demonstrate that expression...... of the multifunctional BRCT (BRCA1 C-terminal) domain-containing PTIP (Pax transactivation domain-interacting protein) chromatin regulator is controlled by B cell activation and potentiates steady-state and postimmune antibody production in vivo. By examining the effects of PTIP deficiency in mice at various ages during...... ontogeny, we demonstrate that PTIP promotes bone marrow B cell development as well as the neonatal establishment and subsequent long-term maintenance of self-reactive B-1 B cells. Furthermore, we find that PTIP is required for B cell receptor- and T:B interaction-induced proliferation, differentiation...

  11. CONFIRMATORY SURVEY RESULTS FOR PORTIONS OF THE ABB COMBUSTION ENGINEERING SITE IN WINDSOR, CONNECTICUT DURING THE FALL OF 2011

    Energy Technology Data Exchange (ETDEWEB)

    Wade C. Adams

    2011-12-09

    From the mid-1950s until mid-2000, the Combustion Engineering, Inc. (CE) site in Windsor, Connecticut (Figure A-1) was involved in the research, development, engineering, production, and servicing of nuclear fuels, systems, and services. The site is currently undergoing decommissioning that will lead to license termination and unrestricted release in accordance with the requirements of the License Termination Rule in 10 CFR Part 20, Subpart E. Asea Brown Boveri Incorporated (ABB) has been decommissioning the CE site since 2001.

  12. Confirmatory Survey Results For Portions Of The ABB Combustion Engineering Site In Windsor, Connecticut During The Fall Of 2011

    International Nuclear Information System (INIS)

    Adams, Wade C.

    2011-01-01

    From the mid-1950s until mid-2000, the Combustion Engineering, Inc. (CE) site in Windsor, Connecticut (Figure A-1) was involved in the research, development, engineering, production, and servicing of nuclear fuels, systems, and services. The site is currently undergoing decommissioning that will lead to license termination and unrestricted release in accordance with the requirements of the License Termination Rule in 10 CFR Part 20, Subpart E. Asea Brown Boveri Incorporated (ABB) has been decommissioning the CE site since 2001.

  13. Research and development and related capabilities for safety and licensing of nuclear power reactors: a regulatory perspective

    International Nuclear Information System (INIS)

    Newland, D.B.

    2001-01-01

    In today's increasingly competitive environment within the electrical power generation industry, the nuclear power utilities are constantly striving for greater efficiency and lower operating costs. Economic de-regulation costs. Economic de-regulation of the electrical market is occurring in a number of countries, including Canada, and this places additional pressure on utilities to be economically competitive. The industry examines all its business activities critically to determine if they provide benefit and good value for money. In these circumstances there can be a tendency for the longer term strategic activities to be treated as lower priority and have reduced funding. Such activities include research and development, design authority, corporate knowledge, and technical expertise, and their associated infrastructure. This paper discusses how the situation with regard to funding of research and development (R and D) has evolved in Canada over the past 5 years, and how the Canadian Nuclear Safety Commission (CNSC) has responded to the changing environment. Of particular interest is a R and D capability review that the industry undertook, the results of which are briefly described. Other related infrastructure aspects such as technical expertise, design authority, education and their inter-relationship with R and D. are also discussed. There are a number of important elements that are needed for a successful way forward: recognition of the depth of the problem by stakeholders; clarification of the roles and responsibilities of these stakeholders; strong leadership within the power reactor industry; improved co-ordinating amongst the industry partners; effective international co-operation; and succession planning in the broadest sense. It is finally concluded that the issue of R and D funding and expertise maintenance is one that will not go away and will inevitably worsen. It is a difficult issue to tackle and there are no simple solutions. The situation has

  14. Development of a method to rate the primary safety of vehicles using linked New Zealand crash and vehicle licensing data.

    Science.gov (United States)

    Keall, Michael D; Newstead, Stuart

    2016-01-01

    Vehicle safety rating systems aim firstly to inform consumers about safe vehicle choices and, secondly, to encourage vehicle manufacturers to aspire to safer levels of vehicle performance. Primary rating systems (that measure the ability of a vehicle to assist the driver in avoiding crashes) have not been developed for a variety of reasons, mainly associated with the difficult task of disassociating driver behavior and vehicle exposure characteristics from the estimation of crash involvement risk specific to a given vehicle. The aim of the current study was to explore different approaches to primary safety estimation, identifying which approaches (if any) may be most valid and most practical, given typical data that may be available for producing ratings. Data analyzed consisted of crash data and motor vehicle registration data for the period 2003 to 2012: 21,643,864 observations (representing vehicle-years) and 135,578 crashed vehicles. Various logistic models were tested as a means to estimate primary safety: Conditional models (conditioning on the vehicle owner over all vehicles owned); full models not conditioned on the owner, with all available owner and vehicle data; reduced models with few variables; induced exposure models; and models that synthesised elements from the latter two models. It was found that excluding young drivers (aged 25 and under) from all primary safety estimates attenuated some high risks estimated for make/model combinations favored by young people. The conditional model had clear biases that made it unsuitable. Estimates from a reduced model based just on crash rates per year (but including an owner location variable) produced estimates that were generally similar to the full model, although there was more spread in the estimates. The best replication of the full model estimates was generated by a synthesis of the reduced model and an induced exposure model. This study compared approaches to estimating primary safety that could mimic

  15. Integrated site investigation procedure for environment protection toward sustainable development

    International Nuclear Information System (INIS)

    Omar, R C; Roslan, R; Baharuddin, I N Z

    2013-01-01

    The spatial configuration of cities and their relationship to the urban environment has recently been the subject of empirical, theoretical and policy research. An awareness of environmental issues can assist policy makers, planners, developers and others to recognize the constraints imposed upon development due the physical environment especially in areas, which are susceptible to erosion, flooding and landslide. This paper highlights the key requirements for considering an assessment to protect our urban environment by incorporating three main factor i.e. policy practice, planning process and engineering investigation. Base on this three main factor the framework of the assessment is carried out. The assessment can be divided into three different categories, namely as investigation for planning, investigation for urban development and specialized investigation and mitigation. The minimum requirements for the planning and urban development investigation are listed. These guidelines suggest the level at which the various types of investigation should be carried out as well as the range of application, the scope and methodology to be used for different investigation. It is hoped that this procedure will provide guidance in the establishment and protection of urban ecosystem toward sustainable development.

  16. TWRS tank waste pretreatment process development hot test siting report

    International Nuclear Information System (INIS)

    Howden, G.F.; Banning, D.L.; Dodd, D.A.; Smith, D.A.; Stevens, P.F.; Hansen, R.I.; Reynolds, B.A.

    1995-02-01

    This report is the sixth in a series that have assessed the hot testing requirements for TWRS pretreatment process development and identified the hot testing support requirements. This report, based on the previous work, identifies specific hot test work packages, matches those packages to specific hot cell facilities, and provides recommendations of specific facilities to be employed for the pretreatment hot test work. Also identified are serious limitations in the tank waste sample retrieval and handling infrastructure. Recommendations are provided for staged development of 500 mL, 3 L, 25 L and 4000 L sample recovery systems and specific actions to provide those capabilities

  17. Development of Alternative Technology to PWHT in Site Welding

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ho Jin; Lee, B. S.; Jang, J. S.; Kim, K. H.; Park, S. D.; Yoon, J. H.; Kim, M. C.; Kim, K. B.; Sung, K. W

    2007-04-15

    ASME Section IX added requirements for qualification when using temper bead welding in the 2004 edition. The temper bead welding techniques which can satisfy the requirements of the Code are needed to use them in the site repair welding. The optimized welding parameters can be obtained when controlling the process to supercritically-reheat and to subcritically-reheat the coarse grain region sequently. The microstructures of SCFGCG obtained from the Gleegle simulated specimens and those of post weld heat treated coarse grain region are compared. The obtained both microstructures showed almost similar patterns. mid bead deposition technique Suggested in this study has a technical concept that the mid beads are deposited between the deposited initial beads repeatedly in a bead layer, which gives a lot of reheating effects on brittle microstructure in HAZ. This newly suggested technique is considered to have more effective tempering effect than the conventional temper bead technique which has concept to deposit one type of beads in a bead layer. The suggested modeling in this study can simulate well the SMAW process. Hence this modeling was used in analyzing the more complicated welding process of multi-layer welding. The modeling was used to analyze the tempering effect on the microstructures of HAZ by considering the patterns of overlapping of the reheating regions under the consequently deposited beads. When considering the crack path in the ever-matched weld metal condition, the interface may have a resistance against the crack propagation. A182 filler and A625 filler were used to make the weld specimens which have different weld metal conditions. The crack directed toward the under-matched weld metal may propagate across the fusion line easier than that of the even-matched weld metal condition.

  18. Development of Alternative Technology to PWHT in Site Welding

    International Nuclear Information System (INIS)

    Lee, Ho Jin; Lee, B. S.; Jang, J. S.; Kim, K. H.; Park, S. D.; Yoon, J. H.; Kim, M. C.; Kim, K. B.; Sung, K. W.

    2007-04-01

    ASME Section IX added requirements for qualification when using temper bead welding in the 2004 edition. The temper bead welding techniques which can satisfy the requirements of the Code are needed to use them in the site repair welding. The optimized welding parameters can be obtained when controlling the process to supercritically-reheat and to subcritically-reheat the coarse grain region sequently. The microstructures of SCFGCG obtained from the Gleegle simulated specimens and those of post weld heat treated coarse grain region are compared. The obtained both microstructures showed almost similar patterns. mid bead deposition technique Suggested in this study has a technical concept that the mid beads are deposited between the deposited initial beads repeatedly in a bead layer, which gives a lot of reheating effects on brittle microstructure in HAZ. This newly suggested technique is considered to have more effective tempering effect than the conventional temper bead technique which has concept to deposit one type of beads in a bead layer. The suggested modeling in this study can simulate well the SMAW process. Hence this modeling was used in analyzing the more complicated welding process of multi-layer welding. The modeling was used to analyze the tempering effect on the microstructures of HAZ by considering the patterns of overlapping of the reheating regions under the consequently deposited beads. When considering the crack path in the ever-matched weld metal condition, the interface may have a resistance against the crack propagation. A182 filler and A625 filler were used to make the weld specimens which have different weld metal conditions. The crack directed toward the under-matched weld metal may propagate across the fusion line easier than that of the even-matched weld metal condition

  19. Remote experimental site concept development, LDRD final report

    International Nuclear Information System (INIS)

    Casper, T.A.; Meyer, W.; Butner, D.

    1995-01-01

    Scientific research is now often conducted on large and expensive experiments that utilize collaborative efforts on a national or international scale to explore physics and engineering issues. This is particularly true for the current US magnetic fusion energy program where collaboration on existing facilities has increased in importance and will form the basis for future efforts. As fusion energy research approaches reactor conditions, the trend is towards fewer large and expensive experimental facilities, leaving many major institutions without local experiments. Since the expertise of various groups is a valuable resource, it is important to integrate these teams into an overall scientific program. To sustain continued involvement in experiments, scientists are now often required to travel frequently, or to move their families, to the new large facilities. This problem is common to many other different fields of scientific research. The next-generation tokamaks, such as the Tokamak Physics Experiment (TPX) or the International Thermonuclear Experimental Reactor (ITER), will operate in steady-state or long pulse mode and produce fluxes of fusion reaction products sufficient to activate the surrounding structures. As a direct consequence, remote operation requiring robotics and video monitoring will become necessary, with only brief and limited access to the vessel area allowed. Even the on-site control room, data acquisition facilities, and work areas will be remotely located from the experiment, isolated by large biological barriers, and connected with fiber-optics. Current planning for the ITER experiment includes a network of control room facilities to be located in the countries of the four major international partners; USA, Russian Federation, Japan, and the European Community

  20. Site-Directed Research and Development FY 2014 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Bender, H. A. [Nevada Test Site/National Security Technologies, LLC (United States)

    2015-04-22

    The reports contained herein are for project activities that occurred from October 2013 through September 2014. Project life cycle is indicated under the title as well as the original proposal number (in the following format: site abbreviation--ID #--originating fiscal year; e.g., STL-03-14). Each of the reports describes in detail the discoveries, achievements, and challenges encountered by our principal investigators. As SDRD, by definition, invests in “high-risk” and hopefully “high-payoff” research, the element of uncertainty is inherent. While many of our efforts are “successful” and result in positive outcomes or technology utilization, some fall short of expectations, but cannot be construed as “failure” in the negative sense. The latter is a natural and valid part of the process of advanced research and often leads to unforeseen new pathways to future discovery. Regardless, either result advances our knowledge base and increases our ability to identify solutions and/or avoid costly and unwarranted paths for future challenges. In summary, the SDRD program continues to provide an unfettered mechanism for innovation that returns multifold to our customers, to national security, and to the general public. The program is a vibrant R&D innovation engine, benefited by its discretionary pedigree, enhanced mission spectrum, committed resources, and sound competitiveness to yield maximum taxpayer benefit. The 25 projects described exemplify the creativity and ability of a diverse scientific and engineering talent base. The efforts also showcase an impressive capability and resource that can be brought to find solutions to a broad array of technology needs and applications relevant to the NNSS mission and national security. Further SDRD performance metrics can be found in the appendix at the end of this report.

  1. Site investigation equipment developed by Teollisuuden Voima Oy

    International Nuclear Information System (INIS)

    Oehberg, A.

    1991-02-01

    Teollisuuden Voima Oy (TVO) carries out site investigations in Finland for final disposal of nuclear high level waste during 1987-2000. In order to carry out the investigations some essential equipment have been designed and constructed. The biggest insufficiency among different measuring methods was among water sampling and hydraulic testing. There are some common specifications which all of these equipment has to fulfil. The two most important are that they have to be operatable in deep slim boreholes down to 1000 meters depth with 56 mm in diameter. The main purpose of the Hydraulic Testing Unit is to determine hydraulic conductivity in crystalline rock, where water can flow primarily through fractures. In most commonly used configurations, measurement range is from 10 - 11 to 10 - 5 m/s with constant-head method. Although constant-head method is principally used, almost any known hydraulic method is possible with existing hardware. Most functions are controlled by the computer. The whole system is built into an electrically heated trailer. The system consists of inflatable packers, stainless steel rods, pressure transducers and datalogging devices. The maximum number of monitoring sections is seven. In addition to that as many blind sections as is needed to prevent vertical flow in boreholes can be installed. Water sampling is possible either with a double packer method or in conjunction with the hydraulic head monitoring equipment. The first possibility involves using the laboratory trailer and the second one using a separate pumping unit plus the laboratory trailer in a later phase when sampling is to be conducted. In the laboratory trailer there are all the measuring devices needed to control different chemical parameters (pH, Eh, pS, O 2 , conductivity and temperature) during pumping

  2. Improving the Business Trade Licensing Reform Environment

    OpenAIRE

    Gamser, Matthew

    2003-01-01

    This case study of Kenyan business trade licensing shows that red-tape costs can be cut if reform is championed strongly and there is a strong case in terms of costs and benefits. The reform of business registration, trade licensing and other business entry procedures is a cost effective and progressive way to promote indigenous private sector development. But, reform needs more than good cost-benefit analysis and legal drafting; it also requires building constituencies and continuous advocacy.

  3. Identification of sites for the low-level waste disposal development and demonstration program

    International Nuclear Information System (INIS)

    Ketelle, R.H.; Lee, D.W.

    1988-04-01

    This report presents the results of site selection studies for potential low-level radioactive waste disposal sites on the Oak Ridge Reservation (ORR). Summaries of the site selection procedures used and results of previous site selection studies on the ORR are included. This report includes recommendations of sites for demonstration of shallow land burial using engineered trench designs and demonstration of above-grade disposal using design concepts similar to those used in tumulus disposal. The site selection study, like its predecessor (ORNL/TM-9717, Use of DOE Site Selection Criteria for Screening Low-Level Waste Disposal Sites on the Oak Ridge Reservation), involved application of exclusionary site screening criteria to the region of interest to eliminate unacceptable areas from consideration. Also like the previous study, the region of interest for this study was limited to the Oak Ridge Department of Energy Reservation. Reconnaissance-level environmental data were used in the study, and field inspections of candidate sites were made to verify the available reconnaissance data. Five candidate sites, all underlain by Knox dolomite residuum and bedrock, were identified for possible development of shallow land burial facilities. Of the five candidate sites, the West Chestnut site was judged to be best suited for deployment of the shallow land burial technology. Three candidate sites, all underlain by the Conasauga Group in Bear Creek Valley, were identified for possible development of above-grade disposal technologies. Of the three sites identified, the Central Bear Creek Valley site lying between State Route 95 and Gum Hollow Road was ranked most favorable for deployment of the above-grade disposal technology

  4. Older People as a Developing Market for Cultural Heritage Sites

    Science.gov (United States)

    Hansen, Anna; Zipsane, Henrik

    2014-01-01

    Is it morally acceptable for the heritage sector to see the growing population of senior citizens as a developing market? Jamtli is an open air museum in the north of Sweden. The main target group is families with children, but an increasing number of activities for older adults are being offered. The growing population of older people is a…

  5. Design issues in adaptive web-site development

    NARCIS (Netherlands)

    De Bra, P.M.E.; Brusilovsky, P.; De Bra, P.M.E.

    1999-01-01

    For almost a decade people have been developing hypertext or hypermedia applications that adapt to some "features" of their users, like knowledge or preferences [Brusilovsky, 1996]. Recently some adaptive application environments have become available that use World Wide Web technology. Examples of

  6. Geothermal energy in Wyoming: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    James, R.W.

    1979-04-01

    An overview of geothermal energy and its current and potential uses in Wyoming is presented. Chapters on each region are concluded with a summary of thermal springs in the region. The uniqueness of Yellowstone is discussed from both an institutional point of view and a natural one. The institutional situation at the federal and state level is discussed as it applies to geothermal development in Wyoming. (MHR)

  7. Waste site characterization and remediation: Problems in developing countries

    Energy Technology Data Exchange (ETDEWEB)

    Kalavapudi, M. [ENVIROSYS, Gaithersburg, MD (United States); Iyengar, V. [Biomineral Sciences International Inc., Bethesda, MD (United States)

    1996-12-31

    Increased industrial activities in developing countries have degraded the environment, and the impact on the environment is further magnified because of an ever-increasing population, the prime receptors. Independent of the geographical location, it is possible to adopt effective strategies to solve environmental problems. In the United States, waste characterization and remediation practices are commonly used for quantifying toxic contaminants in air, water, and soil. Previously, such procedures were extraneous, ineffective, and cost-intensive. Reconciliation between the government and stakeholders, reinforced by valid data analysis and environmental exposure assessments, has allowed the {open_quotes}Brownfields{close_quotes} to be a successful approach. Certified reference materials and standard reference materials from the National Institute of Standards (NIST) are indispensable tools for solving environmental problems and help to validate data quality and the demands of legal metrology. Certified reference materials are commonly available, essential tools for developing good quality secondary and in-house reference materials that also enhance analytical quality. This paper cites examples of environmental conditions in developing countries, i.e., industrial pollution problems in India, polluted beaches in Brazil, and deteriorating air quality in countries, such as Korea, China, and Japan. The paper also highlights practical and effective approaches for remediating these problems. 23 refs., 7 figs., 1 tab.

  8. Stability in licensing requirements: a technical perspective

    International Nuclear Information System (INIS)

    Szalay, R.A.

    1978-01-01

    The serious difficulties encountered in the licensing procedure for nuclear power plants in the United States have resulted in the elaboration of a Bill on the siting and licensing of nuclear installations for the purpose of reforming the present system. The author fears, however, that this Bill will not reduce the complexity of present regulations and will be unable to reach the object sought which is to reduce the length of the procedure; he analyses the technical and political reasons underlying this situation, and in particular the role of the staff of the Nuclear Regulatory Commission. (NEA) [fr

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

    International Nuclear Information System (INIS)

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

    1998-07-01

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

  10. Development of Tsunami PSA method for Korean NPP site

    International Nuclear Information System (INIS)

    Kim, Min Kyu; Choi, In Kil; Park, Jin Hee

    2010-01-01

    A methodology of tsunami PSA was developed in this study. A tsunami PSA consists of tsunami hazard analysis, tsunami fragility analysis and system analysis. In the case of tsunami hazard analysis, evaluation of tsunami return period is major task. For the evaluation of tsunami return period, numerical analysis and empirical method can be applied. The application of this method was applied to a nuclear power plant, Ulchin 56 NPP, which is located in the east coast of Korean peninsula. Through this study, whole tsunami PSA working procedure was established and example calculation was performed for one of real nuclear power plant in Korea

  11. Nuclear licensing in Slovenia

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  12. Software licenses: Stay honest!

    CERN Multimedia

    Computer Security Team

    2012-01-01

    Do you recall our article about copyright violation in the last issue of the CERN Bulletin, “Music, videos and the risk for CERN”? Now let’s be more precise. “Violating copyright” not only means the illegal download of music and videos, it also applies to software packages and applications.   Users must respect proprietary rights in compliance with the CERN Computing Rules (OC5). Not having legitimately obtained a program or the required licenses to run that software is not a minor offense. It violates CERN rules and puts the Organization at risk! Vendors deserve credit and compensation. Therefore, make sure that you have the right to use their software. In other words, you have bought the software via legitimate channels and use a valid and honestly obtained license. This also applies to “Shareware” and software under open licenses, which might also come with a cost. Usually, only “Freeware” is complete...

  13. Licensing of the Ignalina NPP

    International Nuclear Information System (INIS)

    Kutas, S.

    1999-01-01

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

  14. The United States nuclear regulatory commission license renewal process

    International Nuclear Information System (INIS)

    Holian, B.E.

    2009-01-01

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

  15. 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

  16. The Role of Adolescent Development in Social Networking Site Use: Theory and Evidence

    Directory of Open Access Journals (Sweden)

    Drew P. Cingel

    2014-03-01

    Full Text Available Using survey data collected from 260 children, adolescents, and young adults between the ages of 9 and 26, this paper offers evidence for a relationship between social networking site use and Imaginary Audience, a developmental variable in which adolescents believe others are thinking about them at all times. Specifically, after controlling for a number of variables, results indicate a significant, positive relationship between social networking site use and Imaginary Audience ideation. Additionally, results indicate a positive relationship between Imaginary Audience ideation and Facebook customization practices. Together, these findings provide evidence, based on Vygotskian developmental theory, for a general consideration of the role that currently available tools, in this case social networking sites, can have on development. Thus, findings implicate both the role of development on social networking site use, as well as the role of social networking site use on development. Overall, these findings have important implications for the study of media and human development, which are discussed in detail.

  17. Licensing in an international triopoly

    Science.gov (United States)

    Ferreira, Fernanda A.; Ferreira, Flávio

    2011-12-01

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

  18. Site-Directed Research and Development FY 2012 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    ,

    2013-04-01

    The reports included in this report are for project activities that occurred from October 2011 through September 2012. These reports describe in detail the discoveries, achievements, and challenges encountered by our talented and enthusiastic principal investigators (PIs). Many of the reports describe R&D efforts that were “successful” in their pursuits and resulted in a positive outcome or technology realization. As we’ve stated before, and continue to stress, in some cases the result is a “negative” finding, for instance a technology is currently impractical or out of reach. This can often be viewed erroneously as a “failure,” but is actually a valid outcome in the pursuit of high-risk research, which often leads to unforeseen new paths of discovery. Either result advances our knowledge and increases our ability to identify solutions and/or likewise avoid costly paths not appropriate for the challenges presented. The SDRD program continues to provide an unfettered mechanism for innovation and development that returns multifold to the NNSS mission. Overall the program is a strong R&D innovation engine, benefited by an enhanced mission, committed resources, and sound competitiveness to yield maximum benefit. The 23 projects described exemplify the creativity and ability of a diverse scientific and engineering talent base. The efforts also showcase an impressive capability and resource that can be brought to find solutions to a broad array of technology needs and applications relevant to the NNSS mission and national security.

  19. A case of bacillary angiomatosis developed at a burn site

    Directory of Open Access Journals (Sweden)

    Ayse Albayrak

    2012-01-01

    Full Text Available Bacillary Angiomatosis (BA is frequently seen in patients with human immunodeficiency virus (HIV-induced immunodeficiency. Our patient was a case that developed granuloma-like lesions in the area of a burn, 8 days after being burnt on the upper right arm by scalding water. No indication of immune deficiency was observed and no history of direct contact with cats was evident. By the sixth day of the patient′s admission to our clinic, some of the lesions had reached a diameter of 2.5 cm. An excision biopsy was carried out from the lesions present on the patient. Electron microscopy revealed solitary bacilli located close to the capillary wall. Oral erythromycin treatment was implemented at 250 mg, 4 times a day for 2.5 months. Within this period of treatment, the lesions regressed completely, and a complete cure was achieved. This case demonstrates that BA must be considered in the differential diagnosis of both HIV-infected and immunocompetent patients.

  20. Development of site suitability criteria for the high level waste repository for Lawrence Livermore Laboratories

    International Nuclear Information System (INIS)

    1977-06-01

    Results of our mining, geological and geotechnical studies provided in support of the development of site suitability criteria for the high level waste repository are presented. The primary purpose of the work was the identification and development of appropriate geotechnical descriptors and coefficients required for the Site Suitability Repository Model. This model was developed by The Analytic Sciences Corporation (TASC) of Reading, Massachusetts and is not described in this report

  1. Development of site suitability criteria for the high level waste repository for Lawrence Livermore Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    1977-06-01

    Results of our mining, geological and geotechnical studies provided in support of the development of site suitability criteria for the high level waste repository are presented. The primary purpose of the work was the identification and development of appropriate geotechnical descriptors and coefficients required for the Site Suitability Repository Model. This model was developed by The Analytic Sciences Corporation (TASC) of Reading, Massachusetts and is not described in this report.

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

    International Nuclear Information System (INIS)

    Gray, P.L.

    1980-01-01

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

  3. Soil contamination by brominated flame retardants in open waste dumping sites in Asian developing countries.

    Science.gov (United States)

    Eguchi, Akifimi; Isobe, Tomohiko; Ramu, Karri; Tue, Nguyen Minh; Sudaryanto, Agus; Devanathan, Gnanasekaran; Viet, Pham Hung; Tana, Rouch Seang; Takahashi, Shin; Subramanian, Annamalai; Tanabe, Shinsuke

    2013-03-01

    In Asian developing countries, large amounts of municipal wastes are dumped into open dumping sites each day without adequate management. This practice may cause several adverse environmental consequences and increase health risks to local communities. These dumping sites are contaminated with many chemicals including brominated flame retardants (BFRs) such as polybrominated diphenyl ethers (PBDEs) and hexabromocyclododecanes (HBCDs). BFRs may be released into the environment through production processes and through the disposal of plastics and electronic wastes that contain them. The purpose of this study was to elucidate the status of BFR pollution in municipal waste dumping sites in Asian developing countries. Soil samples were collected from six open waste dumping sites and five reference sites in Cambodia, India, Indonesia, Malaysia, and Vietnam from 1999 to 2007. The results suggest that PBDEs are the dominant contaminants in the dumping sites in Asian developing countries, whereas HBCD contamination remains low. Concentrations of PBDEs and HBCDs ranged from ND to 180 μg/kg dry wt and ND to 1.4 μg/kg dry wt, respectively, in the reference sites and from 0.20 to 430 μg/kg dry wt and ND to 2.5 μg/kg dry wt, respectively, in the dumping sites. Contamination levels of PBDEs in Asian municipal dumping sites were comparable with those reported from electronic waste dismantling areas in Pearl River delta, China. Copyright © 2012 Elsevier Ltd. All rights reserved.

  4. Licensing the Sun

    Science.gov (United States)

    Demski, Jennifer

    2013-01-01

    The University of San Diego (USD) and Point Loma Nazarene University (PLNU) are licensing the sun. Both California schools are generating solar power on campus without having to sink large amounts of capital into equipment and installation. By negotiating power purchasing agreements (PPAs) with Amsolar and Perpetual Energy Systems, respectively,…

  5. Trends in CANDU licensing

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  6. Future of nuclear licensing

    International Nuclear Information System (INIS)

    Denton, H.R.

    1984-01-01

    The following topics are outlined: Comparison of US and best foreign experience in nuclear power plant construction and operation; Status of licensing and construction; Observed attributes; Reduced construction time; Fewer reactor trips; Higher capacity factor; Diesel generator reliability; Steam generator tube leakage; and US regulatory initiatives: NRC efforts and industry efforts

  7. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requirements of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs.

  8. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1988-01-01

    Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requiremenrs of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs

  9. 76 FR 60941 - Policy Regarding Submittal of Amendments for Processing of Equivalent Feed at Licensed Uranium...

    Science.gov (United States)

    2011-09-30

    ... Processing of Equivalent Feed at Licensed Uranium Recovery Facilities AGENCY: Nuclear Regulatory Commission... State-licensed uranium recovery site, either conventional, heap leach, or in situ recovery. DATES... Regarding Submittal of Amendments for Processing of Equivalent Feed at Licensed Uranium Recovery Facilities...

  10. 76 FR 63330 - Policy Regarding Submittal of Amendments for Processing of Equivalent Feed at Licensed Uranium...

    Science.gov (United States)

    2011-10-12

    ... Processing of Equivalent Feed at Licensed Uranium Recovery Facilities AGENCY: Nuclear Regulatory Commission... NRC and Agreement State-licensed uranium recovery site. This action is necessary to correct several... read ``(see Page A2 of SECY-99-011, ``Draft Rulemaking Plan: Domestic Licensing of Uranium and Thorium...

  11. The Influence of Social Networking Sites on High School Students' Social and Academic Development

    Science.gov (United States)

    Ahn, June

    2010-01-01

    This dissertation examines the effects of social network sites on youth social and academic development. First, I provide a critical analysis of the extant research literature surrounding social network sites and youth. I merge scholarly thought in the areas of Internet studies, digital divides, social capital theory, psychological well-being,…

  12. Evaluation of afforestation development and natural colonization on a reclaimed mine site

    Science.gov (United States)

    Diana Laarmann; Henn Korjus; Allan Sims; Ahto Kangur; Andres Kiviste; John Stanturf

    2015-01-01

    Post-mining restoration sites often develop novel ecosystems as soil conditions are completely new and ecosystem assemblage can be spontaneous even on afforested sites. This study presents results from long-term monitoring and evaluation of an afforested oil-shale quarry in Estonia. The study is based on chronosequence data of soil and vegetation and comparisons are...

  13. 31 CFR 596.309 - Specific license.

    Science.gov (United States)

    2010-07-01

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

  14. 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

  15. Site Management Guide (Blue Book)

    International Nuclear Information System (INIS)

    2014-01-01

    The U.S. Department of Energy (Department) Office of Legacy Management (LM), established in 2003, manages the Department's postclosure responsibilities and ensures the future protection of human health and the environment. During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over 100 sites. Since 1989, the Department has taken an aggressive accelerated cleanup approach to reduce risks and cut costs. At most Departmental sites undergoing cleanup, some residual hazards will remain at the time cleanup is completed due to financial and technical impracticality. However, the Department still has an obligation to protect human health and the environment after cleanup is completed. LM fulfills DOE's postclosure obligation by providing long-term management of postcleanup sites which do not have continuing missions. LM is also responsible for sites under the Formerly Utilized Sites Remedial Action Program (FUSRAP). Currently, the U.S. Army Corps of Engineers (USACE) is responsible for site surveys and remediation at FUSRAP sites. Once remediation is completed, LM becomes responsible for long-term management. LM also has responsibility for uranium processing sites addressed by Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA). UMTRCA Title II sites are sites that were commercially owned and are regulated under a U.S. Nuclear Regulatory Commission (NRC) license. For license termination, the owner must conduct an NRC-approved cleanup of any on-site radioactive waste remaining from former uranium ore-processing operations. The site owner must also provide full funding for inspections and, if necessary, ongoing maintenance. Once site

  16. NPP License Renewal and Aging Management: Revised Guidance

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  17. NPP License Renewal and Aging Management: Revised Guidance

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  18. Phase 2 environmental site investigation procedures and technologies for property transfer and PS and E development

    Science.gov (United States)

    1999-05-01

    The purpose of this project is to provide TxDOT with an improved procedure for conducting environmental site investigations at various stages during transportation infrastructure development. The project seeks to identify modern assessment technologi...

  19. Development of emergency response training program for on-site commanders (1)

    International Nuclear Information System (INIS)

    Hikono, Masaru; Matsui, Yuko; Kanayama, Masaki

    2017-01-01

    Since the Great East Japan Earthquake of 2011, there have been increasing calls for developing the leadership capabilities of managers who are in charge of command and control of the on-site emergency response center at nuclear power plants. Training programs to improve non-technical skills are being developed and introduced. The authors developed an active learning exercise that can be repeatedly performed on-site, targeting on-site commander teams in charge of the initial response in an emergency situation. The exercise forms the core element of a non-technical skills training curriculum. This paper outlines the developed exercise, evaluates the stress on the participants caused by the exercise, and identifies any issues before actually introducing it to a site. (author)

  20. District-Scale Green Infrastructure Scenarios for the Zidell Development Site, City of Portland

    Science.gov (United States)

    The report outlines technical assistance to develop green infrastructure scenarios for the Zidell Yards site consistent with the constraints of a recently remediated brownfield that can be implemented within a 15-20 year time horizon.

  1. IAEA news: • Newcomer countries face common challenges in nuclear infrastructure development. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators. • IAEA reaches milestone in disposal of radioactive sources

    International Nuclear Information System (INIS)

    Kollar, Lenka; Dyck, Elisabeth; Dixit, Aabha; Gaspar, Miklos; Gil, Laura

    2016-01-01

    • Newcomer countries face common challenges in nuclear infrastructure development: Countries embarking on a nuclear power programme need to make sure that the development of their legal, regulatory and support infrastructure keeps pace with the construction of the power plant itself. This is the only way to ensure that the programme proceeds in a safe, secure and sustainable way, concluded participants of a workshop on nuclear power infrastructure development hosted at the IAEA last February. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators: A new generation of advanced, prefab nuclear power reactors called small modular reactors (SMRs) could be licensed and hit the market as early as 2020, and the IAEA is helping regulators prepare for their debut. In a series of workshops that began earlier this year, the IAEA is working closely with regulators on approaches to safety and licensing ahead of potential SMR deployment worldwide. • IAEA reaches milestone in disposal of radioactive sources: Successful tests of a promising technology for moving and storing low level radioactive sealed sources are paving the way for a new disposal method for dealing with small volumes of radioactive waste around the world. The method, which involves placing and covering sealed sources in a narrow hole a few hundred metres deep, would allow countries to safely and securely take charge of their own disused radioactive sources. The proof of concept for the technology was tested in Croatia late last year — without the use of actual radioactive material.

  2. 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.

  3. Licensing in an International Market

    Science.gov (United States)

    Ferreira, Fernanda A.

    2008-09-01

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

  4. 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

  5. A guide to the licensing of uranium and thorium mine and mill waste management systems

    International Nuclear Information System (INIS)

    1986-01-01

    This document is issued to assist industry and the public in understanding the licensing process used by the Canadian Atomic Energy Control Board (AECB), and do describe and consolidate the requirements, criteria and guidelines the AECB uses in the regulation of uranium and thorium mine and mill waste management systems. All phases of these systems are addressed, including pre-development activities, siting and construction, operation, and decommissioning and abandonment

  6. AECL strategy for surface-based investigations of potential disposal sites and the development of a geosphere model for a site

    International Nuclear Information System (INIS)

    Whitaker, S.H.; Brown, A.; Davison, C.C.; Gascoyne, M.; Lodha, G.S.; Stevenson, D.R.; Thorne, G.A.; Tomsons, D.

    1994-05-01

    The objective of this report is to summarize AECL's strategy for surface-based geotechnical site investigations used in screening and evaluating candidate areas and candidate sites for a nuclear fuel waste repository and for the development of geosphere models of sites. The report is one of several prepared by national nuclear fuel waste management programs for the Swedish Nuclear Fuel and Waste Management Co. (SKB) to provide international background on site investigations for SKB's R and D programme on siting.The scope of the report is limited to surface-based investigations of the geosphere, those done at surface or in boreholes drilled from surface. The report discusses AECL's investigation strategy and the methods proposed for use in surface-based reconnaissance and detailed site investigations at potential repository sites. Site investigations done for AECL's Underground Research Laboratory are used to illustrate the approach. The report also discusses AECL's strategy for developing conceptual and mathematical models of geological conditions at sites and the use of these models in developing a model (Geosphere Model) for use in assessing the performance of the disposal system after a repository is closed. Models based on the site data obtained at the URL are used to illustrate the approach. Finally, the report summarizes the lessons learned from AECL's R and D program on site investigations and mentions some recent developments in the R and D program. 120 refs, 33 figs, 7 tabs

  7. AECL strategy for surface-based investigations of potential disposal sites and the development of a geosphere model for a site

    Energy Technology Data Exchange (ETDEWEB)

    Whitaker, S H; Brown, A; Davison, C C; Gascoyne, M; Lodha, G S; Stevenson, D R; Thorne, G A; Tomsons, D [AECL Research, Whiteshell Labs., Pinawa, MB (Canada)

    1994-05-01

    The objective of this report is to summarize AECL`s strategy for surface-based geotechnical site investigations used in screening and evaluating candidate areas and candidate sites for a nuclear fuel waste repository and for the development of geosphere models of sites. The report is one of several prepared by national nuclear fuel waste management programs for the Swedish Nuclear Fuel and Waste Management Co. (SKB) to provide international background on site investigations for SKB`s R and D programme on siting.The scope of the report is limited to surface-based investigations of the geosphere, those done at surface or in boreholes drilled from surface. The report discusses AECL`s investigation strategy and the methods proposed for use in surface-based reconnaissance and detailed site investigations at potential repository sites. Site investigations done for AECL`s Underground Research Laboratory are used to illustrate the approach. The report also discusses AECL`s strategy for developing conceptual and mathematical models of geological conditions at sites and the use of these models in developing a model (Geosphere Model) for use in assessing the performance of the disposal system after a repository is closed. Models based on the site data obtained at the URL are used to illustrate the approach. Finally, the report summarizes the lessons learned from AECL`s R and D program on site investigations and mentions some recent developments in the R and D program. 120 refs, 33 figs, 7 tabs.

  8. The nuclear licensing procedure

    International Nuclear Information System (INIS)

    Wagner, H.

    1976-01-01

    To begin with, the present nuclear licensing procedure is illustrated by a diagram. The relationship between the state and the Laender, the various experts (GRS - IRS + LRA -, TUEV, DWD, university institutes, firms of consulting engineers, etc), participation of the public, e.g. publication of the relevant documents, questions, objections (made by individuals or by groups such as citizens' initiatives), public discussion, official notice, appeals against the decision, the right of immediate execution of the decision are shortly dealt with. Finally, ways to improve the licensing procedure are discussed, from the evaluation of the documents to be submitted, published, and examined by the authorities (and their experts) up to an improvement of the administrative procedure. An improved licensing procedure should satisfy the well-founded claims of the public for more transparency as well as the equally justifiable claims of industry and utilities in order to ensure that the citizens' legal right to have safe and adequate electric power is guaranteed. The updated energy programme established by the Federal Government is mentioned along with the effectiveness of dealing with nuclear problems on the various levels of a Land government. (orig.) [de

  9. Licensing activities for advanced reactors in NNC

    International Nuclear Information System (INIS)

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

    2001-01-01

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

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

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  11. INTEGRATED REMOTE SENSING AND GIS FOR MODELING ECONOMIC REHABILITATION DEVELOPMENT OF EX-MINE SITES

    Directory of Open Access Journals (Sweden)

    Junaidi Junaidi

    2017-11-01

    Full Text Available The potential environmental impacts of mining, increasing environmental legislation and public awareness have received increased attention world-wide in the last two decades. The focus of concern by the industry, environmental regulatory agencies and members of the public is the systematic rehabilitation of ex-mine sites to improve the quality at site for potential future commercial land use. The minerals extracted from these mine/quarry sites are essential in the construction, semiconductor, high-technology, ceramic and other manufacturing sectors for further industrial development. However, efficient engineering design and systematic economic evaluation of mine sites for site rehabilitation are required in maintaining the expected standards of environmental compliance.  With escalating production costs and the keen competitiveness of the mining industry world-wide, the necessity to increase the efficiency in site rehabilitation is getting more prominence.  A coordinated environmental protection and rehabilitation programme is essential if the environmental awareness of the community and the demands of the respective planning authorities are to be accommodated. There is thus a need to increase the base of knowledge for efficient planning in the systematic and progressive rehabilitation of current and future ex-mine sites. An efficient modeling tool is required for the systematic planning and design of potential economic land development of ex-mine sites. The applicability of Remote Sensing and Geographic Information System (GIS technology is a useful tool to acquire spatial information for the systematic design and planning of potential development of ex-mine sites. This research was conducted to detect the trends in the suitability of land cover changes via land cover change detection of ex-mine sites and validated with reality. The findings are useful to assist in the development of a tool for efficient modeling and design of potential

  12. Siting a low-level radioactive waste disposal facility in California

    International Nuclear Information System (INIS)

    Romano, S.A.; Gaynor, R.K.

    1991-01-01

    US Ecology is the State of California's designee to site, develop and operate a low-level radioactive waste disposal facility. In March 1988, a site in the Ward Valley of California's Mojave Desert was chosen for development. Strong local community support has been expressed for the site. US Ecology anticipates licensing and constructing a facility to receive waste by early 1991. This schedule places California well ahead of the siting milestones identified in Federal law. (author) 1 fig., 2 refs

  13. 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)

  14. 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

  15. Creating Virtual Fieldwork Experiences of Geoheritage Sites as Educator Professional Development (Invited)

    Science.gov (United States)

    Duggan-Haas, D.

    2013-12-01

    Geoheritage sites are identified as such because they include excellent examples of geologic features or processes, or they have played an important role in the development of geologic understandings. These characteristics also make them excellent sites for teaching in the field, for teaching educators about the nature of fieldwork, and for making Virtual Fieldwork Experiences (VFEs, multimedia representations of field sites). Through the NSF-funded Regional and Local Earth (ReaL) Earth Inquiry Project, we have engaged educators in these practices. The nature of geoheritage sites is anomalous -- if this were not the case, the sites would not gain recognition. Anomalous features or processes can be powerful learning tools when placed into comparison with the more mundane, and the Earth system science of sites local to schools is likely to be mundane. By comparing the mundane and the extraordinary, it is hoped we can learn more about both. The professional development (PD) in ReaL Earth Inquiry begins with a face-to-face workshop within the teachers' region at a site that is interesting from an Earth system science perspective. Though we recognize and emphasize that all sites are interesting from an ESS perspective if you know how to look, the sites typically have features worthy of geoheritage designation. PD does not end with the end of the workshop but continues with online study groups where teachers work together to complete the workshop site VFE, and transition to work on VFEs of sites local to their schools. Throughout the program, participants engage in: - mentored fieldwork that pays attention to the skills and knowledge needed to lead fieldwork; - instruction in and use of a wide range of technologies for making VFEs; - study of a coherent conceptual framework connected to the project's driving question: Why does this place look the way it does? - and, use of resources for supporting all of the above The resources include templates for making VFEs and a

  16. Summary of NRR future licensing activities

    International Nuclear Information System (INIS)

    2001-01-01

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

  17. Evaluation of the Potential for Agricultural Development at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Robert G.; Hattendorf, Mary J.; Kincaid, Charles T.

    2000-02-25

    By 2050, when cleanup of the Hanford Site is expected to be completed, large worldwide demands to increase the global production of animal and fish protein, food, and fiber are anticipated, despite advancements in crop breeding, genetic engineering, and other technologies. The most likely large areas for expanded irrigation in the Pacific Northwest are the undeveloped East High areas of the Columbia Basin Project and non-restricted areas within the Hanford Site in south-central Washington State. The area known as the Hanford Site has all the components that favor successful irrigated farming. Constraints to agricultural development of the Hanford Site are political and social, not economic or technical. Obtaining adequate water rights for any irrigated development will be a major issue. Numerous anticipated future advances in irrigation and resource conservation techniques such as precision agriculture techniques, improved irrigation systems, and irrigation system controls will greatly minimize the negative environmental impacts of agricultural activities.

  18. Feasibility determination of low head hydroelectric power development at existing sites: Mousam River Project

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    The technical and economic feasibility of low head hydroelectric power development at existing sites along the Mousam River in southeastern Maine was studied. The following areas were investigated: determination of available energy; development of restoration concepts; environmental studies; historical and archeological studies; assessment of civil construction requirements; geotechnical and geologic assessment of existing dams; assessment of turbine alternatives; assessment of generator and utility interface alternatives; economic analysis; and restoration concept evaluation and selection. The results of the hydropower evaluation showed that: of the seven sites evaluated, only four can be considered economically feasible for refurbishment at this time; the use of used and/or rebuilt equipment is more economically attractive than new equipment; the cost of equipment at each site was of the same order as the cost of the dam reconstruction; and the cost of fuel prices will be the determining feature of whether the sites should be reconstructed.

  19. Strategy for safety case development: impact of a volunteering approach to siting a japanese HLW repository

    International Nuclear Information System (INIS)

    Kitayama, K.; Ishiguro, K.; Takeuchi, M.; Tsuchi, H.; Kato, T.; Sakabe, Y.; Wakasugi, K.

    2008-01-01

    NUMO strategy for safety case development is constrained by a staged siting approach, which has been initiated by a call for volunteer municipalities to host the HLW repository. For each site, the safety case is an important factor to be considered at the selection steps which narrow down towards the preferred repository location. This is particularly challenging, however, as every site requires a tailored repository concept, with associated performance assessment and an individual site evaluation programme all of which evolve with gradually increasing understanding of the host environment. In order to maintain flexibility without losing focus, NUMO has developed a formalized tailoring procedure, termed the NUMO Structured Approach (NSA). The NSA guides the interaction of the key site characterisation, repository design and performance assessment groups and is facilitated by tools to help the decision making associated with the tailoring process (e.g. a requirements management system) and with comparison of siting and design options (e.g. multi-attribute analysis). Pragmatically, the post-closure safety case will initially emphasize near-field processes and a robust engineering barrier system, considering the limited geological information at early stages. This will be complemented by a more realistic assessment of total system performance, as needed to compare options. In addition, efforts to rigorously assess operational phase safety and the practicality of assuring quality of the constructed engineered barriers are components of the total safety case which are receiving particular attention now, as they may better discriminate between sites while information is still limited. (authors)

  20. Development of the on-site power supply in German nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Simon, M. [Gesellschaft fuer Reaktorsicherheit - GRS mbH, Schwertnergasse 1, D-5000 Koeln 1, Cologne (Germany)

    1986-02-15

    The design of the on-site power supply is different in German Nuclear Power Plants, depending on age and size of the plant. The cause for this is the evolution of the safety requirements. The general development of the design of safety Systems, which resulted in a strict separation of redundant trains is also reflected in the design of the emergency power system and even the complete on-site power supply System. This will be demonstrated by different examples. The advantages of this design with respect to the availability of on-site power will be explained and verified by means of operating experience. (author)

  1. 1000kW on-site PAFC power plant development and demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Satomi, Tomohide; Koike, Shunichi [Phosphoric Acid Fuel Cell Technology Research Association (PAFC-TRA), Osaka (Japan); Ishikawa, Ryou [New Energy and Industrial Technology Development Organization (NEDO), Tokyo (Japan)

    1996-12-31

    Phosphoric Acid Fuel Cell Technology Research Association (PAFC-TRA) and New Energy and Industrial Technology Development Organization (NEDO) have been conducting a joint project on development of a 5000kW urban energy center type PAFC power plant (pressurized) and a 1000kW on-site PAFC power plant (non-pressurized). The objective of the technical development of 1000kW on-site PAFC power plant is to realize a medium size power plant with an overall efficiency of over 70% and an electrical efficiency of over 36%, that could be installed in a large building as a cogeneration system. The components and system integration development work and the plant design were performed in 1991 and 1992. Manufacturing of the plant and installation at the test site were completed in 1994. PAC test was carried out in 1994, and generation test was started in January 1995. Demonstration test is scheduled for 1995 and 1996.

  2. Priority Determination of Underwater Tourism Site Development in Gorontalo Province using Analytical Hierarchy Process (AHP)

    Science.gov (United States)

    Rohandi, M.; Tuloli, M. Y.; Jassin, R. T.

    2018-02-01

    This research aims to determine the development of priority of underwater tourism in Gorontalo province using the Analytical Hierarchy Process (AHP) method which is one of DSS methods applying Multi-Attribute Decision Making (MADM). This method used 5 criteria and 28 alternatives to determine the best priority of underwater tourism site development in Gorontalo province. Based on the AHP calculation it appeared that the best priority development of underwater tourism site is Pulau Cinta whose total AHP score is 0.489 or 48.9%. This DSS produced a reliable result, faster solution, time-saving, and low cost for the decision makers to obtain the best underwater tourism site to be developed.

  3. The JINR Tier1 Site Simulation for Research and Development Purposes

    Directory of Open Access Journals (Sweden)

    Korenkov V.

    2016-01-01

    A system for grid and cloud services simulation is developed at LIT (JINR, Dubna. This simulation system is focused on improving the effciency of the grid/cloud structures development by using the work quality indicators of some real system. The development of such kind of software is very important for making a new grid/cloud infrastructure for such big scientific experiments like the JINR Tier1 site for WLCG. The simulation of some processes of the Tier1 site is considered as an example of our application approach.

  4. Development of policies for Natura 2000 sites: a multi-criteria approach to support decision makers.

    Science.gov (United States)

    Cortina, Carla; Boggia, Antonio

    2014-08-01

    The aim of this study is to present a methodology to support decision makers in the choice of Natura 2000 sites needing an appropriate management plan to ensure a sustainable socio-economic development. In order to promote sustainable development in the Natura 2000 sites compatible with nature preservation, conservation measures or management plans are necessary. The main issue is to decide when only conservation measures can be applied and when the sites need an appropriate management plan. We present a case study for the Italian Region of Umbria. The methodology is based on a multi-criteria approach to identify the biodiversity index (BI), and on the development of a human activities index (HAI). By crossing the two indexes for each site on a Cartesian plane, four groups of sites were identified. Each group corresponds to a specific need for an appropriate management plan. Sites in the first group with a high level both of biodiversity and human activities have the most urgent need of an appropriate management plan to ensure sustainable development. The proposed methodology and analysis is replicable in other regions or countries by using the data available for each site in the Natura 2000 standard data form. A multi-criteria analysis is especially suitable for supporting decision makers when they deal with a multidimensional decision process. We found the multi-criteria approach particularly sound in this case, due to the concept of biodiversity itself, which is complex and multidimensional, and to the high number of alternatives (Natura 2000 sites) to be assessed. Copyright © 2014 Elsevier Ltd. All rights reserved.

  5. Inventory of geoheritage sites: The base of geotourism development in Montenegro

    Directory of Open Access Journals (Sweden)

    Đurović Predrag

    2010-01-01

    Full Text Available The main principles and methodology of establishing the inventory of geoheritage sites are analyzed. Special attention is given to theoretical and practical problems related to application of the established principles. Geoheritage sites in Montenegro, classified according to international standards (ProGeo were presented, including their valorization based on the aspects of tourism valorization. Possibilities and limitations of geotourism development in Montenegro were emphasized, too. .

  6. Development and assessment of closure technology for liquid-waste disposal sites

    International Nuclear Information System (INIS)

    Phillips, S.J.; Relyea, J.F.; Seitz, R.R.; Cammann, J.W.

    1990-01-01

    Discharge of low-level liquid wastes into soils was practiced previously at the Hanford Site. Technologies for long-term confinement of subsurface contaminants are needed. Additionally, methods are needed to assess the effectiveness of confinement technologies in remediating potentially diverse environmental conditions. Recently developed site remediation systems and assessment methods for in situ stabilization and isolation of radioactive and other contaminants within and below low-level liquid-waste disposal structures are summarized

  7. Development of new low level radioactive waste disposal sites: A progress report

    International Nuclear Information System (INIS)

    Anderson, Robert T.; Antonucci, George J.; Ryan, Michael T.

    1992-01-01

    The status of the development of three new low level radioactive waste disposal facilities for the Central Midwest (Illinois), Southeastern (North Carolina) and Appalachian (Pennsylvania) compacts is presented. These three sites will dispose of about 50-65 percent of the commercial low-level waste (LLW) generated in the U.S. annually. Chem-Nuclear, as developer and proposed operator of all three sites has used a common approach to site development. This approach has been based on their twenty-plus years of operating experience and a standard technical approach. The technology employed is an above-grade, multiple engineered barrier design. The paper also contrasts actual progress at each site with a generalized project schedule. Areas of schedule delays are noted along with the steps being taken to accelerate schedule. Finally, we note that continued progress and timely start-up of operations of these new sites is critical on a national basis. This is due to the possibility of near-term closure of the existing LLW disposal sites. (author)

  8. Raptor nest-site use in relation to the proximity of coalbed methane development

    Science.gov (United States)

    Carlile, J.D.; Sanders, Lindsey E.; Chalfoun, Anna D.; Gerow, K.G.

    2018-01-01

    Raptor nest–site use in relation to the proximity of coalbed–methane development. Energy development such as coalbed–methane (CBM) extraction is a major land use with largely unknown consequences for many animal species. Some raptor species may be especially vulnerable to habitat changes due to energy development given their ecological requirements and population trajectories. Using 12,977 observations of 3,074 nests of 12 raptor species across nine years (2003–2011) in the Powder River Basin, Wyoming, USA, we evaluated relationships between raptor nest–site use and CBM development. Our objectives were to determine temporal trends in nest–use rates, and whether nest–site use was related to the proximity of CBM development. Across the study area, nest–use rates varied across species and years in a non–linear fashion. We developed a novel randomization test to assess differences in use between nests at developed and undeveloped sites, while controlling for annual variation in nest–site use. Red–tailed hawks (Buteo jamaicensis), burrowing owls (Athene cunicularia), and long–eared owls (Asio otus) used nests in undeveloped areas more than nests in developed areas (i.e. nests near CBM development). Differences between development groups were equivocal for the remaining nine species; however, we caution that we likely had lower statistical power to detect differences for rarer species. Our findings suggest potential avoidance of nesting in areas near CBM development by some species and reveal that CBM effects may be fairly consistent across distances between 400–2,415 m from wells. Future work should consider habitat preferences and fitness outcomes, and control for other key factors such as local prey availability, raptor densities, and weather.

  9. 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)

  10. 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)

  11. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in acordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and eveloping a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing prinicples, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed. 880 refs., 130 figs., 25 tabs.

  12. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-11-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the errata page

  13. License to Learn

    DEFF Research Database (Denmark)

    Leone, Maria Isabella; Boccardelli, Paolo; Reichstein, Toke

    2016-01-01

    the technology. Drawing on a sample of 133 licensees and an equal number of matched nonlicensees, we present empirical evidence that thick contracts propel the licensees' likelihood of introducing new inventions. It is also found that thick contracts act as a substitute for licensees' absorptive capacity....... Licensees that are more familiar with the licensed technology are in less need of assistance from the licensors to assimilate and integrate the knowledge. However, this substitution effect is neutralized once the hurdle of invention has been overcome, meaning that the licensees have succeeded to ignite...... the invention process, suggesting the exploitation of the learning curve, triggered by their mutual understanding....

  14. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-04-01

    The Operating Units Status Report --- Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff on NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non- power reactors in the US

  15. License agreement, employee work

    OpenAIRE

    Poncová, Veronika

    2012-01-01

    The rigorous thesis is focused on license agreement and employee work. The aim of the thesis is not only an analysis of the use of a copyrighted work by a person different from the author of the work, but also an analysis of the performance of copyright by a person different from the author of the work. The thesis consists of five chapters. The opening chapter provides a summary of the notion of copyright, its sources at the national and international levels, but also the European Union legis...

  16. Developing a Hierarchical Decision Model to Evaluate Nuclear Power Plant Alternative Siting Technologies

    Science.gov (United States)

    Lingga, Marwan Mossa

    A strong trend of returning to nuclear power is evident in different places in the world. Forty-five countries are planning to add nuclear power to their grids and more than 66 nuclear power plants are under construction. Nuclear power plants that generate electricity and steam need to improve safety to become more acceptable to governments and the public. One novel practical solution to increase nuclear power plants' safety factor is to build them away from urban areas, such as offshore or underground. To date, Land-Based siting is the dominant option for siting all commercial operational nuclear power plants. However, the literature reveals several options for building nuclear power plants in safer sitings than Land-Based sitings. The alternatives are several and each has advantages and disadvantages, and it is difficult to distinguish among them and choose the best for a specific project. In this research, we recall the old idea of using the alternatives of offshore and underground sitings for new nuclear power plants and propose a tool to help in choosing the best siting technology. This research involved the development of a decision model for evaluating several potential nuclear power plant siting technologies, both those that are currently available and future ones. The decision model was developed based on the Hierarchical Decision Modeling (HDM) methodology. The model considers five major dimensions, social, technical, economic, environmental, and political (STEEP), and their related criteria and sub-criteria. The model was designed and developed by the author, and its elements' validation and evaluation were done by a large number of experts in the field of nuclear energy. The decision model was applied in evaluating five potential siting technologies and ranked the Natural Island as the best in comparison to Land-Based, Floating Plant, Artificial Island, and Semi-Embedded plant.

  17. PC-based car license plate reader

    Science.gov (United States)

    Hwang, Chung-Mu; Shu, Shyh-Yeong; Chen, Wen-Yu; Chen, Yie-Wern; Wen, Kuang-Pu

    1992-11-01

    A car license plate reader (CLPR) using fuzzy inference and neural network algorithm has been developed in Industrial Technology Research Institute (ITRI) and installed in highway toll stations to identify stolen cars. It takes an average of 0.7 seconds to recognize a car license plate by using a PC with 80486-50 CPU. The recognition rate of the system is about 97%. The techniques of CLPR include vehicle sensing, image grab control, optic pre- processing, lighting, and optic character recognition (OCR). The CLPR can be used in vehicle flow statistics, the checking of stolen vehicles, automatic charging systems in parking lots or garage management, and so on.

  18. Licensing procedure and requirements in the FRG

    International Nuclear Information System (INIS)

    Brosche, D.

    1981-01-01

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

  19. Procurement Specifications Templates for On-Site Solar Photovoltaic: For Use in Developing Federal Solicitations

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, G. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2017-01-16

    With the increasing adaption of on-site renewable energy systems designed to feed site loads, there is a critical need to develop tools that allow the federal sector to become a mature and sophisticated consumer. This document is intended to reduce project development and operational risks while increasing the speed at which projects are completed; two necessary components to reach the scale required to meet mandates and achieve cost savings for taxpayers. This guide is intended to act as a living document where lessons learned from the increasing number of projects can be incorporated and provide guidance for efforts. While additional guides will be developed to cover other renewable technologies, this guide covers on-site solar photovoltaic systems with an emphasis on third-party designed, financed, owned, and operated systems.

  20. License - Plabrain DB | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available switchLanguage; BLAST Search Image Search Home About Archive Update History Data List Contact us Plabrain... Alike 2.1 Japan . If you use data from this database, please be sure attribute this database as follows: Plabrain...of this database (http://dbarchive.lifesciencedb.jp/english/en/plabrain-db/desc.html) in the article or pape...se Description Download License Update History of This Database Site Policy | Contact Us License - Plabrain DB | LSDB Archive ...

  1. Legal questions concerning the licensing procedure of nuclear power plants

    International Nuclear Information System (INIS)

    Boerner, B.

    1978-01-01

    The publication contains 4 articles which deal with legal practice and problems of the licensing procedure in the Federal Republic of Germany: 1) Actions brought by joint boards from the constitutional point of view (Burmeister, J.); 2) court review of the assessment of technical and economic questions concerning the licensing of power plant construction (Ossenbuehl, F.); 3) the site plan approval procedure as a legal problem (Friauf, K.H.); 4) legal questions concerning the immediate enforceability (Papier, H.J.). (HP) [de

  2. Development of probabilistic seismic hazard analysis for international sites, challenges and guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez Ares, Antonio, E-mail: antonio.fernandez@rizzoassoc.com [Paul C. Rizzo Associates, Inc., 500 Penn Center Boulevard, Penn Center East, Suite 100, Pittsburgh, PA 15235 (United States); Fatehi, Ali, E-mail: ali.fatehi@rizzoassoc.com [Paul C. Rizzo Associates, Inc., 500 Penn Center Boulevard, Penn Center East, Suite 100, Pittsburgh, PA 15235 (United States)

    2013-06-15

    Research highlights: ► Site-specific seismic hazard study and suggestions for overcoming those challenges that are inherent to the significant amounts of epistemic uncertainty for sites at remote locations. ► Main aspects of probabilistic seismic hazard analysis (PSHA). ► Regional and site geology in the context of a probabilistic seismic hazard analysis (PSHA), including state-of-the-art ground motion estimation methods, and geophysical conditions. ► Senior seismic hazard analysis (SSHAC) as a mean to incorporate the opinions and contributions of the informed scientific community. -- Abstract: This article provides guidance to conduct a site-specific seismic hazard study, giving suggestions for overcoming those challenges that are inherent to the significant amounts of epistemic uncertainty for sites at remote locations. The text follows the general process of a seismic hazard study, describing both the deterministic and probabilistic approaches. Key and controversial items are identified in the areas of recorded seismicity, seismic sources, magnitude, ground motion models, and local site effects. A case history corresponding to a seismic hazard study in the Middle East for a Greenfield site in a remote location is incorporated along the development of the recommendations. Other examples of analysis case histories throughout the World are presented as well.

  3. Development of site profiles for dose reconstruction used in worker compensation claims.

    Science.gov (United States)

    Kenoyer, Judson L; Scalsky, Edward D; Taulbee, Timothy D

    2008-07-01

    For the purpose of dose reconstruction, personal dosimeter data and measured intakes through bioassay analysis (i.e., in-vivo and in-vitro measurements) should be used whenever possible and given precedence over area monitoring data, survey data, or source term data. However, this is not always possible. A worker's exposure record may be incomplete or missing, or, based on directives and guidelines at the time, a worker may not have been monitored during his or her time of employment. In an effort to recognize, analyze, and incorporate all possible considerations of potential exposures, the National Institute for Occupational Safety and Health Radiation Dose Reconstruction Program developed "site profiles" for all of the major U.S. Department of Energy sites and Atomic Weapons Employer sites. Site profiles are technical documents that (1) provide a brief, general overview of the site; (2) identify the facilities on site with a brief description of the processes and radionuclides used in these processes; (3) contain detailed information on the historical detection limits for film, thermoluminescent dosimeter, and bioassay measurements that are used by the dose reconstructor to interpret a worker's available monitoring records; and (4) provide important supporting information for the dose reconstructor to use if the monitoring data are inadequate or unavailable. When a complete set of monitoring data for an individual is unavailable, it is the parameters in the site profile that are of the most use to the dose reconstructor. These parameters include facility monitoring data (by radionuclide, mechanism of intake, year of exposure, location within a facility); occupational medical x rays and techniques used; environmental measurements (by area on site, radiation type, energy range); minimum detectable activities of the types and kinds of instruments used to detect the different radionuclides; specific source terms (quantities of material and their molecular form

  4. Quality assurance of nursing web sites: development and implications of the ALEU method.

    Science.gov (United States)

    Cambil-Martín, Jacobo; Flynn, Maria; Villaverde-Gutiérrez, Carmen

    2011-09-01

    This article presents a study that evaluated the physical accessibility, readability, and usability of Spanish nursing Web sites and discusses the quality assurance issues raised, which are relevant to the wider nursing community. The Internet is recognized as an important source of health information for both nurses and the general public. Although it makes health-related information universally available, the wide variation in the overall quality of health Web sites is problematic. This raises many questions for the nursing profession: about what constitutes a good-quality Web site, about the nature of the information that nurses are finding and using to support their professional education, research, and clinical practice, and about the impact that Internet information ultimately has on health interactions and nursing care. The process of completing this small study showed that it is possible to usefully assess dimensions of Web site quality and suggested that it may be feasible to develop tools to help nurses evaluate national and international nursing Web sites. More research is needed to understand how nurses use the Internet to support their everyday professional practices, but the development and application of international Web site quality assurance tools may be important for maintaining professional nursing standards in the Internet age.

  5. Development and validation of the Single Item Trait Empathy Scale (SITES).

    Science.gov (United States)

    Konrath, Sara; Meier, Brian P; Bushman, Brad J

    2018-04-01

    Empathy involves feeling compassion for others and imagining how they feel. In this article, we develop and validate the Single Item Trait Empathy Scale (SITES), which contains only one item that takes seconds to complete. In seven studies (N=5,724), the SITES was found to be both reliable and valid. It correlated in expected ways with a wide variety of intrapersonal outcomes. For example, it is negatively correlated with narcissism, depression, anxiety, and alexithymia. In contrast, it is positively correlated with other measures of empathy, self-esteem, subjective well-being, and agreeableness. The SITES also correlates with a wide variety of interpersonal outcomes, especially compassion for others and helping others. The SITES is recommended in situations when time or question quantity is constrained.

  6. Using a risk assessment protocol to develop soil cleanup criteria for petroleum contaminated sites

    International Nuclear Information System (INIS)

    Asante-Duah, D.K.

    1991-01-01

    Petroleum contaminated site may prose significant risks to the public because of potential health and environmental effects, and to Potentially Responsible Parties (PRPs) because of financial liabilities that could result from such effects. The effective management of petroleum contaminated sites has therefore become an important environmental priority and will be a growing challenge for years to come. It has also become evident that the proper management of such sites poses great challenges. Risk assessment seems to be one of the fastest evolving tools for developing appropriate management decisions, including those relating to the levels of cleanup warranty under specific scenarios. This paper reports that the U.S. Environmental Protection Agency (U.S. EPA) recognizes the use of risk assessment to facilitate decisions on whether or not remedial actions are needed to abate site-related risks, and also in the enforcement of regulatory standards. Risk assessment techniques have been used in various regulatory programs employed by federal, state, and local agencies

  7. Site characterization progress report, April 1, 1994--September 30, 1994: Yucca Mountain, Nevada. Volume 11

    International Nuclear Information System (INIS)

    1995-03-01

    The Civil Radioactive Waste Management Program was restructured to provide a new approach to the evaluation of the site for development as a repository and to its licensing. Funding was increased for FY 95, with most of the increase going to the Yucca Mountain site characterization project. During this period, significant progress was made in surface-based testing, advanced conceptual design, performance assessment, planning, licensing support system development activities, and construction of the Exploratory Studies Facility. The report is divided into the following sections: introduction, programmatic activities, site programs, repository design, waste package, performance assessment, and exploratory studies facility design/construction

  8. Public participation and regional development at a nuclear waste disposal site

    International Nuclear Information System (INIS)

    Ipsen, D.

    2005-01-01

    The propositions brought forward in this article try to implement sociological aspects into the search for nuclear waste disposal sites based on two theses: Firstly without the willingness of public participation in the search and inspection processes the success of the process is severly put into question in a democratic state. Secondly the potential disposal site must not block the further economic development of the region. These two theses lead to socio-economic criteria for consideration or debarment, to a concept of active and intensive participation, and to considerations about long-term regional development. (orig.)

  9. Development of portal web site for fostering of risk literacy 'risk information navigator'

    International Nuclear Information System (INIS)

    Shobu, Nobuhiro; Mitsui, Seiichiro; Nakamura, Hirofumi

    2004-01-01

    Risk communication activities are important for promoting mutual understanding between local communities and Japan Nuclear Cycle Development Institutes (JNC). In addition to conventional public relation activities, the risk communication study team of JNC Tokai Works has started practical studies to promote further mutual understanding with its local communities. This paper reports the design and concept of a web site for the fostering of risk literacy, the 'Risk Information Navigator', that was developed as one of the risk communication methods, and surveys the web site from the user's perspective. (author)

  10. Development of spectral shapes and attenuation relations from accelerograms recorded on rock and soil sites

    International Nuclear Information System (INIS)

    Ghosh, A.K.; Rao, K.S.; Kushwaha, H.S.

    1998-06-01

    Earthquake accelerograms recorded on rock and soil sites have been analysed. Site-specific response spectra and peak ground acceleration attenuation relations have been developed. This report presents the normalised pseudo-absolute acceleration spectra for various values of damping and for various confidence levels. Scaling laws have been developed for the response spectra. The present results are based on a large database and comparison has been made with earlier results. These results will be useful in the earthquake resistant design of structures. (author)

  11. Development of spectral shapes and attenuation relations from accelerograms recorded on rock and soil sites

    Energy Technology Data Exchange (ETDEWEB)

    Ghosh, A K; Rao, K S; Kushwaha, H S [Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)

    1998-06-01

    Earthquake accelerograms recorded on rock and soil sites have been analysed. Site-specific response spectra and peak ground acceleration attenuation relations have been developed. This report presents the normalised pseudo-absolute acceleration spectra for various values of damping and for various confidence levels. Scaling laws have been developed for the response spectra. The present results are based on a large database and comparison has been made with earlier results. These results will be useful in the earthquake resistant design of structures. (author) 22 refs., 7 figs., 5 tabs.

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

    Science.gov (United States)

    California State Dept. of Motor Vehicles, Sacramento.

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

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

    International Nuclear Information System (INIS)

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

    1982-01-01

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

  14. Exporting the Canadian licensing program

    International Nuclear Information System (INIS)

    Whelan, D.J.

    1981-06-01

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

  15. Community Involvement in Tourism Development: A Case Study of Lenggong Valley World Heritage Site

    Directory of Open Access Journals (Sweden)

    A. Khadar Nur Zafirah

    2014-01-01

    Full Text Available This paper examines the empirical relationship between the economic impact and community involvement in the Lenggong Valley. Recommendations for improvement in development effectiveness through the development of a community centre for economic and social activities, with specific attention given to types of activity and community involvement stimulating the economic development in the Lenggong Valley. Heritage tourism development is a tourism in which arts, culture and heritage form a key attraction for visitors and it can be represented as an area of significant economic benefit to heritage sites. The tourism industry in Hulu Perak became more widespread after Lenggong Valley is recognized as a World Heritage Site. There is shown a positive effect on the development and economic prosperity.

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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