WorldWideScience

Sample records for aseismic design licensings

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-03-01

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

  2. Aseismic design and testing of nuclear facilities

    International Nuclear Information System (INIS)

    Earthquake possibility is a main problem faced by certain countries concerning nuclear reactor siting and safety. To assist in finding solutions to earthquake problems, a Panel on Aseismic Design and Testing of Nuclear Facilities was held from 12 to 16 June 1967 in Tokyo. Paper presented in the Panel are condensed into recommendations that comprise this report. Topics discussed in this report are (i) basic philosophy of aseismic design (ii) site selection or evaluation (iii) aseismic design and (iv) future action including investigations and research problems. Tabs

  3. Technical guidelines for aseismic design of nuclear power plants

    International Nuclear Information System (INIS)

    This document is a translation, in its entirety, of the Japan Electric Association (JEA) publication entitled open-quotes Technical Guidelines for Aseismic Design of Nuclear Power Plants - JEAG 4601-1987.close quotes This guideline describes in detail the aseismic design techniques used in Japan for nuclear power plants. It contains chapters dealing with: (a)the selection of earthquake ground motions for a site, (b) the investigation of foundation and bedrock conditions, (c) the evaluation of ground stability and the effects of ground movement on buried piping and structures, (d) the analysis and design of structures, and (e) the analysis and design of equipment and distribution systems (piping, electrical raceways, instrumentation, tubing and HVAC duct). The guideline also includes appendices which summarize data, information and references related to aseismic design technology

  4. Development of aseismic designing normative base of Russia

    International Nuclear Information System (INIS)

    Russian NPP are designed in according with aseismic designing normative base of documentation, including Federal Norms and Rules, guidelines of branch and institutes, recommendations of IAEA and other direction and recommendations documents. Aseismic designing normative base is being developed in order to improve the degree of NPP safety, to take into account last investigations in this field and appropriate international recommendations. Two new main Federal Guidelines for aseismic designing of NPP were worked out by work group of leading specialists, were submited to leading institutes of Minatom of Russia and were approved in 2001 by Federal Regulatory Body of Russia: Aseismic designing Norms of NPP (Hfl-03 1-01), was approved 19.10.01 by decision No.9, Location of NPP. The main safety criterions and demands, approved 08.11.01 by decision X210. 'Aseismic designing Norms of NPP' establishes the demands of safety assurance of on-ground NPP after seismic influence, assignments of seismic category of NPP components, assignments of seismic influence parameters, assurance of seismic reliability of construction, technological and electrical equipment, control and regulation systems of NPP. The document contains: 1. he document assignment and area of utilization; 2. The main contents; 3. efinition of seismic conditions of NPP location region and NPP site; 4. onstructions and fundaments; 5. echnological equipment and pipelines; 6. lectrical, control and regulation equipment; 7. Aseismic and defence measures. The following items are enclosed: Consideration of ground conditions influence on defmition of seismic conditions of NPP site; tandard work program for elaboration of geo-dynamic and seismic conditions of NPP site; tandard seismic influence; Definition of constructions components strength during line method calculations; The main contents of liquid container seismic conditions calculations; The main contents of length constructions

  5. The influence of soil behaviour on the aseismic design of nuclear power plants

    International Nuclear Information System (INIS)

    Extensive measurements of the dynamic mechanical properties of soils and rocks have indicated their essentially non-linear behaviour. A review is given of these properties and their relevance to aseismic design in the UK is discussed. In addition, current methods of modeling soil amplification and soil-structure interaction and ways in which these methods may be used to represent non-linear material effects are described. (author)

  6. Aseismic design of the Heysham II Nuclear Power Station

    International Nuclear Information System (INIS)

    A brief description of the seismic criteria established for use with the Steam Generating Heavy Water Reactor (SCHWR) and taken for the Heysham II Project is given. The qualification strategy adopted for Heysham II is described, and a brief overview is given of some of the more important design changes required for seismic purposes on that station

  7. Experimental and analytical studies on aseismic design of ventilation ducts

    International Nuclear Information System (INIS)

    For seismic resistant design of the ventilation ducts, it is the most popular and convenient way to idealize duct as a simple beam model and to compute maximum support spacing which makes duct rigid enough. However, few practical data are available to assume the precise stiffness of thinwalled duct on which accurate prediction of dynamic properties depends essentially. In this paper, the experimental study including the vibration tests and the static load tests with regard to two full scale duct models is described and a comparison between experimental and analytical results on the dynamic properties, the deflections and the stress distributions is discussed. Also, the mode of failure of the ducts due to vertically applied static load with negative internal pressure is observed. (orig.)

  8. Some difference of concepts between design guideline for FBR base isolation system and aseismic design guideline of LWR in Japan

    International Nuclear Information System (INIS)

    This paper deals with the concept and the relation of 'the Base Isolation System and FBR' to the Safety Criteria and the Guideline of the Aseismic Design of LWR in Japan. The Central Research Institute of Electric Power Industries have been working for FBR last several years. The author has been contribute to their works, and this is one of the subjects. He described his own idea obtained through the cooperative work with CRIEPI. (author)

  9. Latur earthquake and its impact on the aseismic design of structures in India

    International Nuclear Information System (INIS)

    The Latur earthquake occurred on September 30, 1995. The epicentre was located near the Killari village of Latur District which is situated in the stable continental region of Southern Peninsular India. The earthquake caused a wide range of damage though its magnitude (MS) was 6.4. Intensive damage survey was carried out and a number of geophysical and seismological studies had been undertaken. It has been concluded from the results, available so far from these studies, that the hypocentre of the earthquake was on the lineament dipping NW-SE. The rock matrix in the hypocentral region was weakened due to the presence of fluid and rupture of this weak region caused the event. The ground motion produced by the earthquake was of complex nature comprising of horizontal and vertical component. The ground acceleration in the epicentral region was estimated as 0.2 g. Latur earthquake raised several issues with respect to aseismic design of structures in India which need further deliberation. These issues are related to seismic zoning of India, determination of design basis ground motion, design/detailing of structures, etc. (author)

  10. Evaluation of earthquake vibration on aseismic design of nuclear power plant judging from recent earthquakes

    International Nuclear Information System (INIS)

    The Regulatory Guide for Aseismic Design of Nuclear Reactor Facilities was revised on 19th September, 2006. Six factors for evaluation of earthquake vibration are considered on the basis of the recent earthquakes. They are 1) evaluation of earthquake vibration by method using fault model, 2) investigation and approval of active fault, 3) direct hit earthquake, 4) assumption of the short active fault as the hypocentral fault, 5) locality of the earthquake and the earthquake vibration and 6) remaining risk. A guiding principle of revision required new evaluation method of earthquake vibration using fault model, and evaluation of probability of earthquake vibration. The remaining risk means the facilities and people get into danger when stronger earthquake than the design occurred, accordingly, the scattering has to be considered at evaluation of earthquake vibration. The earthquake belt of Hyogo-Nanbu earthquake and strong vibration pulse in 1995, relation between length of surface earthquake fault and hypocentral fault, and distribution of seismic intensity of off Kushiro in 1993 are shown. (S.Y.)

  11. Recent advances and design options of the aseismic bearing pad concept for reduction of seismic loading

    International Nuclear Information System (INIS)

    The intent of this paper is to: briefly review the developed concepts from a mechanics standpoint; summarize the results of recent testing and applications; discuss the complexities and subtleties of differences between concepts, and highlight the effectiveness of each within selected frequency ranges. On this basis, the paper will provide a forum for application of each concept within the nuclear design community. The potential licensing implications of incorporating the ABP concept into nuclear plant design are be discussed in light of actual experience extrapolated to several dominant regulatory processes; namely the French, German, Japanese, Canadian and American. The intent is to identify potential licensing issues, spur additional research and development in these areas, and continue to bring the concept to the attention of the nuclear community to facilitate acceptance and application. (orig./HP)

  12. Licensing Teachers: Design for a Teaching Profession.

    Science.gov (United States)

    Wise, Arthur E.; And Others

    This report presents a new comprehensive design for licensing teachers. The design would require beginning teachers to complete a supervised internship as the penultimate step in the licensing process. Local school districts, operating under state guidelines, would be expected to make carefully planned internships available to all beginning…

  13. Analytical procedure in aseismic design of eccentric structure using response spectrum

    International Nuclear Information System (INIS)

    In this paper, the response are evaluated by the following two methods by the use of the typical torsional analytical models in which masses, rigidities, eccentricities between the centers thereof and several actual earthquake waves are taken as the parameters: (1) the root mean square of responses by using the response spectra derived from the earthquake waves, (2) the time history analysis by using the earthquake wave. The earthquake waves used are chosen to present the different frequency content and magnitude of the response spectra. The typical results derived from the study are as follows: (a) the response accelerations of mass center in the input earthquake direction by the (1) method coincide comparatively well with those by the (2) method, (b) the response accelerations perpendicular to the input earthquake direction by (1) method are 2 to 3 times as much as those by the (2) method, (c) the amplification of the response accelerations at arbitrary points distributed on the spread mass to those of center of the lumped mass by the (1) method are remarkably large compared with those by the (2) method in both directions respectively. These problems on the response spectrum analysis for the above-mentioned eccentric structure are discussed, and an improved analytical method applying the amplification coefficients of responses derived from this parametric time history analysis is proposed to the actual seismic design by the using of the given design ground response spectrum with root mean square technique

  14. Aseismic design of structure-equipment systems using variable frequency pendulum isolator

    International Nuclear Information System (INIS)

    Sliding isolation systems have emerged as very useful vibration control technique that incorporate isolation, energy dissipation and restoring mechanism in one unit. However, most currently available systems such as friction pendulum system (FPS) and pure friction (PF) system have practical limitations and are of limited effectiveness when input excitation level is significantly different from its design level. To overcome these limitations while preserving the advantages, a new system called the variable frequency pendulum isolator (VFPI) has been developed by the authors. The isolation period of VFPI continuously decreases with increase in horizontal sliding displacement which results in a more robust isolation system. The VFPI also limits the maximum force transmitted to the structure by providing a restoring force-softening mechanism. In this paper, it has been shown that isolating a structure using VFPI is very effective for vibration control of structure-equipment and other primary-secondary systems. An example five-storey structure with equipment mounted at its top has been analysed to demonstrate the effectiveness of VFPI. It is shown that VFPI provides better vibration control properties compared to other friction isolation systems, and excellent response reduction is observed for a wide range of equipment properties and excitation characteristics. The performance of the example structure with VFPI has been compared with the other frictional systems such as FPS and PF system

  15. New nuclear plant design and licensing process

    International Nuclear Information System (INIS)

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

  16. NUCLEAR SAFETY DESIGN BASES FOR LICENSE APPLICATION

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-03-08

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

  17. Nuclear Safety Design Base for License Application

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-09-29

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

  18. Design, implementation and licensing of improvement measures

    International Nuclear Information System (INIS)

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

  19. ASEISMIC DESIGN OF RESERVOIR FACED WHOLLY WITH ASPHALT CONCRETE%全库铺设沥青混凝土面板水库的抗震设计

    Institute of Scientific and Technical Information of China (English)

    方火浪; 田代幸英; 大内周; 森二郎

    2006-01-01

    介绍在建中日本最大规模的全库铺设沥青混凝土面板水库的抗震设计.基于水库所处的地形、地质及堤体填筑条件,首先对水库整体进行三维有限元动力分析,从总体上掌握水库的地震反应特性;然后对变形较大的断面进行详细的二维动力分析,获得面板的最大动应变.同时,通过大量室内试验,确定满足施工要求的沥青混凝土配合比及其物理力学特性.根据面板的材料特性及其构造特点,提出二级抗震设防的极限状态设计法,并对该水库面板的抗震性能进行校核.%The aseismic design of the reservoir faced wholly with asphalt concrete under construction is addressed, which is the largest one in Japan for this type of reservoir. Due to the complex geomorphologic features and geological structures of the site as well as the complicated construction processes of embankments, general response characteristics of the entire reservoir were firstly investigated by 3D dynamic analyses, and then the maximum strains of the asphalt concrete facing for typical cross-sections of the reservoir with potentially great deformation were determined by detailed 2D dynamic analyses. The results show as follows: (1) both acceleration and strain are with a similar distribution character independent on the direction of the seismic excitation, concentrating in the high banking areas of the main dam, the left-side bank, and from the subsidiary dam to the right-side bank; (2) maximum values of acceleration and strain occur in the main dam although they slightly vary with the excitation direction of the seismic motion; (3) a 2D analytical result is slightly greater than that of a 3D analytical result; and (4) maximum strains of the facing for Levels 1 and 2 seismic waves considering the regional factors of this reservoir site are 0.019% and 0.030%, respectively. At the same time, a series of material tests of asphalt concrete mixtures, including mix design and

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

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    Hastings, C.R.

    1999-08-30

    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

  2. Handling of design and licensing changes in Hungary

    International Nuclear Information System (INIS)

    Regulatory and licensing matters related to the siting, construction, commissioning, operation and decommissioning of NPPs are within the remits of several different authorities in Hungary, as describing in the following: — Nuclear regulation, licensing and regulatory oversight are within the responsibilities of the Hungarian Atomic Energy Authority (HAEA), as stated in the Atomic Energy Act CXVI, 1996; — Environmental protection aspects of the use of nuclear energy are within the realm of the National Inspectorate for the Environment, Nature and Water, as stipulated by the Environmental Protection Act LIII, 1995; — Production and commercial aspects of power generation are within the responsibilities of the Hungarian Energy Office, on the basis of the Electric Energy Act LXXXVI, 2007; — Health physics aspects are under the responsibility of the National Public Health and Medical Officer Service, on the basis of a government directive. In addition, several government and ministerial directives have included regulations related to NPP operation. The nuclear safety regulation is the most significant of these for the handling of design and licensing changes

  3. Handling of design and licensing changes in China

    International Nuclear Information System (INIS)

    In China, two nuclear safety requirements published by NNSA in 2004 are regarded as fundamental safety regulations: — HAF 102, Design Safety Requirement for Nuclear Power Plants; — HAF 103, Operation Safety Requirements for Nuclear Power Plants. General safety requirements, including design and licensing changes, are stipulated in the two regulations. They are the equivalent of IAEA requirements Safety of Nuclear Power Plants: Design, SSR-2/1 and Safety of Nuclear Power Plants: Commissioning and Operation, SSR-2/2, respectively. Modifications for NPPs are regulated by the following procedures: — Procedure for SSC modification; — Procedure for operational limits and conditions modification; — Procedure for instruction and control system modification; — Procedure for organization modification

  4. The design of licensing contracts: Chemicals, Pharmaceuticals, and Electrical Engineering in Imperial Germany

    OpenAIRE

    Burhop, Carsten; Lübbers, Thorsten

    2011-01-01

    We investigate a sample of 180 technology licensing contracts closed by German chemical, pharmaceutical, and electrical engineering companies between 1880 and 1913. Our empirical results suggest that strategic behaviour seems to be relevant for the design of licensing contracts, whereas inventor moral hazard and risk aversion of licensor or licensee seem to be irrelevant. Moreover, our results suggest that uncertainty regarding the profitability of licensed technology influenced the design of...

  5. Handling of design and licensing changes in India

    International Nuclear Information System (INIS)

    system to be made available at all coastal NPPs; — An automatic reactor trip on seismic events at all NPPs (this already exists at two nuclear generating stations); — The capability of all NPPs to cope with extended station blackout conditions; —Guidelines on how to handle beyond design basis accidents and completion of a comprehensive severe accident management guidelines document. In parallel, the implications from a comparison of the plant conditions with that of modern safety requirements should be analysed and, in turn, the unit safety justified to the licensing authority. The regulatory body in India completed special inspections of all NPPs in order to assess their capability to deal with natural events and station blackouts

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-01-01

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

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

    International Nuclear Information System (INIS)

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

  8. Handling of design and licensing changes in the Republic of Korea

    International Nuclear Information System (INIS)

    Various design and licensing changes may be implemented throughout the operating life of NPPs to improve safety and reliability of SSCs. They may involve adding, deleting or modifying the SSCs, and changes may also affect the plant configuration management. All documentation related to design and licensing changes should be updated to address not just the change itself but also what impact the changes will have on the current operation and maintenance practices

  9. Evaluation of aseismic integrity in HTTR core-bottom structure. Pt. 1. Aseismic test for core-bottom structure

    International Nuclear Information System (INIS)

    The aseismic tests were carried out using (1)/(5)-scale and (1)/(3)-scale models of the core-bottom structure of the HTTR to quantitatively evaluate the response of acceleration, strain, impact load etc. The following conclusions are obtained. (i) The frequency response of the keyway strain is correlative with that of the impact acceleration on the hot plenum block. (ii) It was confirmed through (1)/(5)-scale and (1)/(3)-scale model tests that the applied similarity law is valid to evaluate the seismic response characteristics of the core-bottom structure. (ii) The stress of graphite components estimated from the scale model test using S2-earthquake excitation was sufficiently lower than the allowable stress used as the design criterion. ((orig.))

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

    International Nuclear Information System (INIS)

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

  11. ITER licensing

    International Nuclear Information System (INIS)

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

  12. Some applications of understanding of transient fuel failure mechanisms in design and licensing of LMFBRs

    International Nuclear Information System (INIS)

    Some applications of fuel failure technology in reactor design and licensing efforts are discussed. Topics covered include failures in transient overpower accidents, failures in loss-of-flow accidents, off-normal transients, and applications to inherently safe fuel design. (U.S.)

  13. Handling of design and licensing changes in the Czech Republic

    International Nuclear Information System (INIS)

    Knowledge of the current NPP design basis is a fundamental starting point for any LTO programme. The design changes and assessments of SSC ageing effects on their performance and functions need to be supported by easily accessible design basis information to prevent undesirable infringements on NPP safety. The safety design bases reconstitution project started in 2003. The central data gathering process was completed in 2006. In 2007, the reconstitution of the design basis parameters started. Both the design basis functions and parameters were assembled. The reconstitution was prioritized according to the needs and requirements of the recommended modifications

  14. Seismicity triggered by fluid injection-induced aseismic slip

    Science.gov (United States)

    Guglielmi, Yves; Cappa, Frédéric; Avouac, Jean-Philippe; Henry, Pierre; Elsworth, Derek

    2015-06-01

    Anthropogenic fluid injections are known to induce earthquakes. The mechanisms involved are poorly understood, and our ability to assess the seismic hazard associated with geothermal energy or unconventional hydrocarbon production remains limited. We directly measure fault slip and seismicity induced by fluid injection into a natural fault. We observe highly dilatant and slow [~4 micrometers per second (μm/s)] aseismic slip associated with a 20-fold increase of permeability, which transitions to faster slip (~10 μm/s) associated with reduced dilatancy and micro-earthquakes. Most aseismic slip occurs within the fluid-pressurized zone and obeys a rate-strengthening friction law μ=0.67+0.045ln(vv0) with v0 = 0.1 μm/s. Fluid injection primarily triggers aseismic slip in this experiment, with micro-earthquakes being an indirect effect mediated by aseismic creep.

  15. License Application Design Selection Feature Report Canistered Assemblies

    International Nuclear Information System (INIS)

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

  16. Presentation summary, safety design aspects and U.S. licensing challenges of the pebble bed modular reactor

    International Nuclear Information System (INIS)

    This presentation consists of three sections: An overview of the status of the PBMR project in South Africa, a review of the design features and philosophy being utilized to design the PBMR, and a summary of the key licensing issues that Exelon has identified in assessing the licensability of the PBMR for application in this country

  17. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App.N Appendix N to...

  18. Field investigation on severely damaged aseismic buildings in 2014 Ludian earthquake

    Science.gov (United States)

    Lin, Xuchuan; Zhang, Haoyu; Chen, Hongfu; Chen, Hao; Lin, Junqi

    2015-03-01

    The 2014 magnitude 6.5 Ludian earthquake caused a death toll of 617, many landslides and tens of thousands of collapsed buildings. A field investigation to evaluate the damage to buildings was carried out immediately after the occurrence of the earthquake. Severely damaged aseismic buildings, which were basically observed in the downtown of Longtoushan Town, were carefully examined one by one with the aim to improve design codes. This paper summarizes the damage observed to the investigated aseismic buildings in both the structural and local levels. A common failure mode was observed that most of the aseismic buildings, such as RC frame structures and confined masonry structures, were similarly destroyed by severe damage or complete collapse of the first story. The related strong ground motion, which was recorded at the nearby station, had a short duration of less than 20 s but a very large PGA up to 1.0 g. The RC frames based on the new design codes still failed to achieve the design target for "strong column, weak beam". Typical local failure details, which were related to the interaction between RC columns and infill walls and between constructional columns and masonry walls, are summarized with preliminary analyses.

  19. Handling of design and licensing changes in the Russian Federation

    International Nuclear Information System (INIS)

    Design changes in NPP units that aim at eliminating or minimizing the effects of ageing mechanisms are usually the result of complex analyses and of R&D conclusions. Design changes can also be the result of feedback, both positive and negative, from OE in similar units. Design changes are implemented taking into account the recommendations from international organizations (including the IAEA), and lessons learned from events and accidents around the world. These usually require preventive and compensatory measures in order to remove weaknesses and avoid analogous situations in the future. For example, as a result of experience accumulated from the operating steam generators PGV-1000 and PGV-1000M in WWER-1000 units, some abnormal hydrodynamic regimes deviating from the design were observed in the heat exchange section, and increased damage to the steam generator pipe nozzles was observed. High stresses (including residual stresses) in the piping joints were noted. As a result, the steam generator design was altered, and these changes either reduced or completely eradicated the degradation phenomena, thereby increasing steam generator reliability and serviceability

  20. Design, Licensing and Construction of the Turbine Island

    International Nuclear Information System (INIS)

    Olivier Mandement, Business Development Director of Alstom Thermal Power, presented the different specificities of turbine and explained to the audience the different steps of the construction of the Turbine Island. He made a focus on the ARABELLE turbine design that is used for the Flamanville 3 EPR reactor

  1. Handling of design and licensing changes in Canada

    International Nuclear Information System (INIS)

    Design changes required at the time of an LTO application may stem from various sources, such as new regulatory requirements, modernization programmes, obsolescence, the introduction or expansion of environmental qualification programmes, motorized valve and driver upgrade programmes, changes dictated by operation feedback or lessons learned from the Fukushima Daiichi accident (which has prompted various degrees of intervention in plants around the world). The original design life of a plant is driven by the design life of its major components. However, service life, the time during which the plant can operate safely and reliably, may exceed the design life when conditions warrant it. This is because the actual operation in terms of, for example, fatigue cycles and ageing factors such as erosion–corrosion, among other things, for most components may be considerably lower than their design targets. When possible, selected components are replaced to re-establish margins and full operability. In CANDU reactors, the core components that require replacement in order to extend plant life are primarily the fuel channels at about 30 years of operation. Removal and replacement of fuel channel components in a CANDU unit is usually an economically viable option and has been a pivotal milestone in the life management of CANDU units. Extensive analysis and studies of fuel channels have been undertaken over the years and lessons learned summarized in a number of publications. Bulk lower feeder replacement is another significant activity that may be required in older plants for LTO. Replacing feeders during the large scale fuel channel replacement (LSFCR) outage may actually reduce the duration of the LSFCR by improving access to the fuel channels

  2. Handling of design and licensing changes in Spain

    International Nuclear Information System (INIS)

    Changes to the design and licence basis are analysed to ensure that AMPs and TLAA both include and justify them during LTO. Analysis of the impact of design changes on ageing management may be done as part of the configuration control process, or be managed, for example, by the ageing management coordinator. This is the case for the SMG plant. Changes to the licence are reviewed at least every two years. Those related to ageing management or LTO are evaluated through the scoping criteria. For those changes that meet the selection criteria in 10 CFR 54.4, an ageing management review is performed and new scope added to the AMPs. With respect to active equipment, the maintenance rule scope is periodically updated as changes in safety functions are analysed. These changes are considered in the review of the licence scope

  3. Salt repository project waste package design and licensing strategy

    International Nuclear Information System (INIS)

    The objective of this project is to develop design concepts that are expected to satisfy the waste package design and regulatory requirements based on available engineering expertise and judgment and on preliminary analysis, evaluations, and data. The waste package includes the waste form and all components between the waste form and the host rock. The conceptual design of the waste package was developed to accommodate three different waste forms, defense high-level waste, intact spent fuel, and consolidated spent fuel. Defense high-level waste is borosilicate glass incorporating highly radioactive waste sludge. The vitrified waste is cast into cylindrical stainless steel canisters. Spent fuel from commercial pressurized water reactors (PWR) and boiling water reactors (BWR) arrives at the repository as intact assemblies. The two main requirements of the Nuclear Regulatory Commission that must be satisfied are: (1) to provide substantially complete containment of the radionuclides for up to 1,000 years after repository closure and (2) to provide controlled release of radionuclides to a small fraction of their 1,000-year inventory for the period from 1,000 to 10,000 years after repository closure

  4. Handling of design and licensing changes in the United States of America

    International Nuclear Information System (INIS)

    Since NPPs are subject to ongoing design and licensing basis changes throughout the operating term, the AMPs and activities also need to be modified and updated as part of the change process. When SSCs are added, deleted or modified as part of the change process, the impact of the change on the ageing management activities also need to be addressed. The modification process should include consideration of the operating term, maintenance and inspection requirements during the operating term and ageing management activities for the SSC. Once a plant has decided to operate beyond the original design life, the modification process should incorporate the new operating term (e.g. 60 years) into the basic assumptions for subsequent modifications. This will ensure that design and licensing basis changes include appropriate consideration of ageing management activities for the remaining operating term

  5. Risk-informed design and licensing - A new approach for future reactors such as the IRISTM design

    International Nuclear Information System (INIS)

    The application of risk-based design and licensing procedures to new reactor designs demonstrates the potential for future nuclear plant designs that can provide high levels of safety as well as reliable and economical performance. Results of the US DOE's Nuclear Energy Research Initiative project on risk-based design and licensing methods have shown that it is possible to utilize today's technology, current performance data, and licensing experience while at the same time making a new design that is safe as well as economical. In the new process, the traditional design methods and safety principles such as defense-in-depth and conservatism would still be employed, but the logic governing their use would be reversed from that of the traditional design methods. In the risk-based approach, probabilistic risk analysis would be used as the paramount decision support tool, taking advantage of its ability to integrate all of the elements of system performance and to model uncertainties. The traditional design tools and principles would still be used, but only in the context of the probabilistic risk analysis. The US DOE is also sponsoring the development of Generation IV reactors that are aimed at resource sustain ability, enhanced safety, and improved economics. The IRISTM (International Reactor Innovative and Secure) design is being developed by an international consortium with a goal of design certification by 2008. The IRIS design is an integral, light-water-reactor design where all primary system components are enclosed within the reactor vessel. The IRIS design features a four- to five-year-life straight-burn core with less than 5% enriched fuel, a 48-month interval between maintenance shutdowns, and safety- by-design whereby postulated accidents are either eliminated or their probability of occurring is lessened and their consequences are reduced. The application of risk-based methods is especially appropriate for new reactors such as the IRIS design because the

  6. Design of an Automated Secure Garage System Using License Plate Recognition Technique

    OpenAIRE

    Afaz Uddin Ahmed; Taufiq Mahmud Masum; Mohammad Mahbubur Rahman

    2014-01-01

    Modern technologies have reached our garage to secure the cars and entrance to the residences for the demand of high security and automated infrastructure. The concept of intelligent secure garage systems in modern transport management system is a remarkable example of the computer interfaced controlling devices. License Plate Recognition (LPR) process is one of the key elements of modern intelligent garage security setups. This paper presents a design of an automated secure garage system fea...

  7. Design of an Automated Secure Garage System Using License Plate Recognition Technique

    Directory of Open Access Journals (Sweden)

    Afaz Uddin Ahmed

    2014-01-01

    Full Text Available Modern technologies have reached our garage to secure the cars and entrance to the residences for the demand of high security and automated infrastructure. The concept of intelligent secure garage systems in modern transport management system is a remarkable example of the computer interfaced controlling devices. License Plate Recognition (LPR process is one of the key elements of modern intelligent garage security setups. This paper presents a design of an automated secure garage system featuring LPR process. A study of templates matching approach by using Optical Character Recognition (OCR is implemented to carry out the LPR method. We also developed a prototype design of the secured garage system to verify the application for local use. The system allows only a predefined enlisted cars or vehicles to enter the garage while blocking the others along with a central-alarm feature. Moreover, the system maintains an update database of the cars that has left and entered into the garage within a particular duration. The vehicle is distinguished by the system mainly based on their registration number in the license plates. The tactics are tried on several samples of license plate’s image in both indoor and outdoor setting.

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

    Energy Technology Data Exchange (ETDEWEB)

    MacBeth, M. J.; Hemmings, R. L. [Canatom-NPM, Ontario (Canada)

    2002-04-15

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

  9. Aspects of Safety Analysis for Sodium Cooled Fast Reactor Design and Licensing

    International Nuclear Information System (INIS)

    This paper discusses aspects of safety analysis of a sodium cooled fast reactor (SFR) that are necessary for nuclear plant design and licensing. In the last two decades, SFR safety analysis has focused mostly on anticipated transients without scram (or unprotected transients). These include unprotected loss of flow, unprotected transient over power and unprotected loss of heat sink. While these transients provide a bounding safety assessment, other more probable transients need to be assessed to support SFR design and licensing efforts. Using a representative traveling wave reactor (TWR) reactor core, different aspects of safety analysis are discussed with example results from SASSYS-1/SAS4A calculations and their implications on SFR design. First, transient event classification is presented. Then, the effects of protected transients (where the reactor scrams) on various design parameters (scram set-points, delay time, peak cladding temperature limit etc.) are demonstrated. Third, the effects of uncertainties of various parameters are demonstrated. Finally, sensitivity analyses and their implications on the reactor design and safety profiles are discussed. (author)

  10. Industrial Pollution Control and Efficient Licensing Processes: The Case of Swedish Regulatory Design

    Directory of Open Access Journals (Sweden)

    Maria Pettersson

    2014-08-01

    Full Text Available Industrial pollution accounts for a large proportion of global pollution, and in the European Union, an integrated pollution and prevention approach based on individual performance standards has been implemented to regulate emissions from industrial plants. Crucial for the assessment of the licensing conditions are the Best Available Technique (BAT requirements, which should be set in accordance with the recently introduced Industrial Emissions Directive (IED. In this paper, we review and assess the licensing of industrial plants in one of the Member States, namely Sweden. Specifically, we discuss how the existing regulations (including the IED manage to address potential trade-offs between important regulatory design issues, such as flexibility, predictability and the need to provide continuous incentives for environmental improvements. The analysis indicates that while the EU regulations provide flexibility in terms of the choice of compliance measures, in Sweden, it enters an existing regulatory framework that adds a lot of uncertainty with respect to the outcome of the licensing processes. An important challenge for the implementation of the IED is to implement performance standards that lead to continuous incentives to improve environmental performance in industrial sectors without, at the same time, adding new uncertainties. While standards ideally should be both flexible and predictable, achieving one of these criteria may often come at the expense of the other.

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-09-01

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

  15. An Earthquake Swarm Search Implemented at Major Convergent Margins to Test for Associated Aseismic Slip

    Science.gov (United States)

    Holtkamp, S. G.; Pritchard, M. E.; Lohman, R. B.; Brudzinski, M. R.

    2009-12-01

    Recent geodetic analysis indicates earthquake swarms may be associated with slow slip such that earthquakes may only represent a fraction of the moment release. To investigate this potential relationship, we have developed a manual search approach to identify earthquake swarms from a seismicity catalog. Our technique is designed to be insensitive to spatial and temporal scales and the total number of events, as seismicity rates vary in different fault zones. Our first application of this technique on globally recorded earthquakes in South America detects 35 possible swarms of varying spatial scale, with 18 in the megathrust region and 8 along the volcanic arc. Three swarms in the vicinity of the arc appear to be triggered by the Mw=8.5 2001 Peru earthquake, and are examined for possible triggering mechanisms. Coulomb stress modeling suggests that static stress changes due to the earthquake are insufficient to trigger activity, so a dynamic or secondary triggering mechanism is more likely. Volcanic swarms are often associated with ground deformation, either associated with fluid movement (e.g. dike intrusion or chamber inflation or deflation) or fault movement, although these processes are sometimes difficult to differentiate. The only swarm along the arc with sufficient geodetic data that we can process and model is near Ticsani Volcano in Peru. In this case, a swarm of events southeast of the volcano precedes a more typical earthquake sequence beneath the volcano, and evidence for deformation is found in the location of the swarm, but there is no evidence for aseismic slip. Rather, we favor a model where the swarm is associated with deflation of a magma body to the southeast that triggered the earthquake sequence by promoting movement on a fault beneath Ticsani. Since swarms on the subduction interface may indicate aseismic moment release, with a direct impact on hazard, we examine potential relations between swarms and megathrust ruptures. We find evidence that

  16. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Science.gov (United States)

    2010-01-01

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

  17. Design of Intelligent Parking Management System Based on License Plate Recognition

    Directory of Open Access Journals (Sweden)

    Qing Tian

    2014-06-01

    Full Text Available License Plate Recognition (LPR which has been extensively studied recently is becoming one important part of Intelligent Transportation Systems (ITS. It is not only applied to public security monitoring, but also applied to a red light shot, speeding violation paparazzi, parking system and so on. The present paper introduces an intelligent parking management system based on LPR, recognizing license plate automatically at the parking lot access and realizing vehicle information integrated management conveniently. The software part is developed with VC++, QT and Microsoft Office Access Database. In the system, LPR is carried out through video streaming frame by frame to choose the best result with a high speed. After accurate LPR, the vehicle information, such as LP number, LP color, car type and access time, will be stored in system database. In addition, the system interface is designed very friendly and simple for administrators to operate, which can largely improve the whole performance of LPR system. Experimental results show that this parking management system can achieve high correct rate at 95%, and can be applied to real-time implementation

  18. Licensing design basis source term update for the Evolutionary Advanced Light Water Reactor

    International Nuclear Information System (INIS)

    The purpose of this report is to document the technical basis for a licensing source term update for the Evolutionary Advanced Light Water Reactor (ALWR) which will make the source term more physically realistic. While TID [Technical Information Document] 14844 and related regulatory guidance have served the industry well, much has been learned about source term over the last 30 years, and the ALWR Requirements Document provides an opportunity to incorporate this experience by updating the licensing source term. Further, the source term update will provide an improved basis for evolutionary ALWR accident mitigation design. Results of this work indicate that the fission product release magnitude to containment is slightly less than TID 14844 for noble gas, iodine, and semi and low volatiles, but somewhat higher for cesium and tellurium. Release timing is delayed by one hour or more after the accident initiation. The chemical form of iodine is largely aerosol with significantly less organic iodine compared to regulatory guidance which specifies mostly elemental and a relatively large fraction of organic. Containment spray aerosol removal rate was determined to be significantly higher than specified in regulatory guidance. Finally, BWR suppression pool decontamination factor was determined to be less effective than allowed by regulatory guidance early in the accident (due to the delayed release noted above) and more effective than that allowed by regulatory guidance later in the accident. It is recognized by the ALWR program that the source term update could be taken further in the direction of a physically-based source term. 47 refs., 4 figs., 11 tabs

  19. License-Exempt Child Care Providers: A Needs Assessment for Designing an Implementation Model

    Science.gov (United States)

    Roseburr, Linda Joyce

    2008-01-01

    Many children from low-income families appear to be not receiving quality child care from their license-exempt subsidized child-care providers. The purpose of this qualitative case study was to obtain data from a sample of license-exempt providers/caregivers and parents from a mailed self-administered survey and telephone interview. Four research…

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  2. Design of Intelligent Parking Management System Based on License Plate Recognition

    OpenAIRE

    Qing Tian; Teng Guo; Shuai Qiao; Yun Wei; Wei-wei Fei

    2014-01-01

    License Plate Recognition (LPR) which has been extensively studied recently is becoming one important part of Intelligent Transportation Systems (ITS). It is not only applied to public security monitoring, but also applied to a red light shot, speeding violation paparazzi, parking system and so on. The present paper introduces an intelligent parking management system based on LPR, recognizing license plate automatically at the parking lot access and realizing vehicle information integrated ma...

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

    International Nuclear Information System (INIS)

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

  4. Preliminary decision and construction design approval in the nuclear licensing procedure from the view of the energy supply enterprises

    International Nuclear Information System (INIS)

    From the point of view of the supply enterprises, a site plan approval procedure for nuclear facilities is a pressing need for long-term site provision, because the preliminary decision has not proven useful as a means of clarifying the site situation. Construction design approval, based on nuclear law, from the point of view of the supply enterprises, is a very desirable instrument for standardizing nuclear facilities and thus for speeding up the licensing procedures. (orig.)

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

    International Nuclear Information System (INIS)

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

  6. Repository program licensing approach

    International Nuclear Information System (INIS)

    Yucca Mountain, Nevada is currently being studied by the US Department of Energy (DOE) as a potential site for a mined geologic repository for high-level nuclear waste. DOE has the responsibility to determine the suitability of the site and to develop a license application (LA) for authorization to construct the potential repository. If the site is suitable, the license application would be submitted to the US Nuclear Regulatory Commission (NRC). The repository program licensing approach is focused on the timely acquisition of information needed in licensing and the resolution of potential licensing issues with the NRC staff. Licensing involves an iterative process requiring refinements as data are acquired, analyzed, and evaluated. The repository licensing approach presented in this paper ensures that the information is available when needed to facilitate the licensing process. Identifying the information needed to evaluate compliance with the performance objectives in 10 CFR 60, monitoring the acquisition of such information, and developing a successful license application are integral elements of DOE's repository program licensing approach. Activities to characterize the site are being systematically conducted as planned in the Site Characterization Plan (SCP). In addition, DOE is implementing the issue resolution initiative, the license application annotated outline (LAAO) process, and interim licensability evaluations to update the early planning in the SCP and to focus site characterization, design, and performance assessment activities on the acquisition of information needed for a site suitability determination and licensing. Collectively, the issue resolution initiative, LAAO process, and interim licensability evaluations are key elements of a transition to the iterative process to answer the question: open-quotes When do we have enough data to support licensing?close quotes

  7. INDUCED SEISMICITY. Seismicity triggered by fluid injection-induced aseismic slip.

    Science.gov (United States)

    Guglielmi, Yves; Cappa, Frédéric; Avouac, Jean-Philippe; Henry, Pierre; Elsworth, Derek

    2015-06-12

    Anthropogenic fluid injections are known to induce earthquakes. The mechanisms involved are poorly understood, and our ability to assess the seismic hazard associated with geothermal energy or unconventional hydrocarbon production remains limited. We directly measure fault slip and seismicity induced by fluid injection into a natural fault. We observe highly dilatant and slow [~4 micrometers per second (μm/s)] aseismic slip associated with a 20-fold increase of permeability, which transitions to faster slip (~10 μm/s) associated with reduced dilatancy and micro-earthquakes. Most aseismic slip occurs within the fluid-pressurized zone and obeys a rate-strengthening friction law μ = 0.67 + 0.045ln(v/v₀) with v₀ = 0.1 μm/s. Fluid injection primarily triggers aseismic slip in this experiment, with micro-earthquakes being an indirect effect mediated by aseismic creep. PMID:26068845

  8. Industrial Pollution Control and Efficient Licensing Processes: The Case of Swedish Regulatory Design

    OpenAIRE

    Maria Pettersson; Patrik Söderholm

    2014-01-01

    Industrial pollution accounts for a large proportion of global pollution, and in the European Union, an integrated pollution and prevention approach based on individual performance standards has been implemented to regulate emissions from industrial plants. Crucial for the assessment of the licensing conditions are the Best Available Technique (BAT) requirements, which should be set in accordance with the recently introduced Industrial Emissions Directive (IED). In this paper, we review and a...

  9. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    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

  10. Onset of aseismic creep on major strike-slip faults

    KAUST Repository

    Çakir, Ziyadin

    2012-10-02

    Time series analysis of spaceborne synthetic aperture radar (SAR) data, GPS measurements, and fi eld observations reveal that the central section of the Izmit (Turkey) fault that slipped with a supershear rupture velocity in the A.D. 1999, Mw7.4, Izmit earthquake began creeping aseismically following the earthquake. Rapid initial postseismic afterslip decayed logarithmically with time and appears to have reached a steady rate comparable to the preearthquake full fault-crossing rate, suggesting that it may continue for decades and possibly until late in the earthquake cycle. If confi rmed by future monitoring, these observations identify postseismic afterslip as a mechanism for initiating creep behavior along strike-slip faults. Long-term afterslip and/or creep has signifi cant implications for earthquake cycle models, recurrence intervals of large earthquakes, and accordingly, seismic hazard estimation along mature strike-slip faults, in particular for Istanbul which is believed to lie adjacent to a seismic gap along the North Anatolian fault in the Sea of Marmara. © 2012 Geological Society of America.

  11. The NCS 45 cask family: an updated design replaces an old design. Lessons learned during design, testing and licensing

    International Nuclear Information System (INIS)

    The NCS 45 cask family is intended to replace the cask types R52, TN6/1 and TN6/3. These packagings - country of origin France - were in operation worldwide since mid 1970. In the late nineties prolongations of the certificates of package approval became more and more difficult and time consuming. Finally only special arrangements for restricted contents were issued by the competent French authority which caused considerable problems when validations in other countries were applied for. To guarantee the availability of such a cask in the future for its customers NCS decided to replace the old casks by an updated design, the NCS 45 cask family

  12. Regularized Deterministic Annealing Hidden Markov Models for Identificationand Analysis of Seismic and Aseismic events.

    Science.gov (United States)

    Granat, R. A.; Clayton, R.; Kedar, S.; Kaneko, Y.

    2003-12-01

    modified optimization procedure based on the application of statistical priors. These priors induce a regularized learning strategy that is designed to avoid the located sub-optimal points in the parameter space. The end result is a robust technique for estimating the optimal parameters of an HMM and thereby the statistical properties of the data. We compare this method to the method of deterministic annealing as applied to hidden Markov models, and discuss a combined algorithm that employs both techniques simultaneously to the advantage of each. We present preliminary results of the technique as applied to the TriNet data set, with particular emphasis on location and recognition of seismic and aseismic signals with a period of minutes to hours.

  13. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    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

  14. Hidden Markov Models for Detecting Aseismic Events in Southern California

    Science.gov (United States)

    Granat, R.

    2004-12-01

    demonstrates that in the case of most events we can rule out the possibility of the event being the result of regional transients such as weather phenomena. As a result, the implication is that these regionally observed mode changes are either the result of small-scale seismic activity or of unknown episodic aseismic activity.

  15. From Geodetic Imaging of Seismic and Aseismic Fault Slip to Dynamic Modeling of the Seismic Cycle

    Science.gov (United States)

    Avouac, Jean-Philippe

    2015-05-01

    Understanding the partitioning of seismic and aseismic fault slip is central to seismotectonics as it ultimately determines the seismic potential of faults. Thanks to advances in tectonic geodesy, it is now possible to develop kinematic models of the spatiotemporal evolution of slip over the seismic cycle and to determine the budget of seismic and aseismic slip. Studies of subduction zones and continental faults have shown that aseismic creep is common and sometimes prevalent within the seismogenic depth range. Interseismic coupling is generally observed to be spatially heterogeneous, defining locked patches of stress accumulation, to be released in future earthquakes or aseismic transients, surrounded by creeping areas. Clay-rich tectonites, high temperature, and elevated pore-fluid pressure seem to be key factors promoting aseismic creep. The generally logarithmic time evolution of afterslip is a distinctive feature of creeping faults that suggests a logarithmic dependency of fault friction on slip rate, as observed in laboratory friction experiments. Most faults can be considered to be paved with interlaced patches where the friction law is either rate-strengthening, inhibiting seismic rupture propagation, or rate-weakening, allowing for earthquake nucleation. The rate-weakening patches act as asperities on which stress builds up in the interseismic period; they might rupture collectively in a variety of ways. The pattern of interseismic coupling can help constrain the return period of the maximum- magnitude earthquake based on the requirement that seismic and aseismic slip sum to match long-term slip. Dynamic models of the seismic cycle based on this conceptual model can be tuned to reproduce geodetic and seismological observations. The promise and pitfalls of using such models to assess seismic hazard are discussed.

  16. 车牌视频跟踪识别系统的设计%Design of video tracking and recognition system for license plates

    Institute of Scientific and Technical Information of China (English)

    黄宝生; 黄海波

    2013-01-01

    The video automatic recognition technology for license plates is the core technology of intelligent traffic system (ITS). It is the main means and development direction of highway and urban traffic management. License plate recognition sys⁃tem is composed of license plate localization,license plate character segmentation and license plate character recognition. Direct⁃Show filter is used in this system to capture video frame. The median filtering is used to reduce the image noise and the trans⁃verse Sobel operator is used for edge detection. The license plate area and license plate similarity template matching are calculated by means of the measure function to search for license plate location. A license plate positioning algorithm applied to image threshold selection was designed. The back⁃propagation neural network is adopted to recognize the text which is segmented from the binary image. Experiments results indicate that the system achieved a fairly good effect in the process of license plate tracking and recognition.%  车牌视频自动跟踪识别技术是智能交通系统(ITS)中的核心技术,是公路交通和城市交通管理的主要手段和发展方向。车牌识别系统可由车牌定位、车牌字符分割和车牌字符识别组成,在此使用DirectShow滤镜截取视频帧。采用中值滤波进行图像的降噪和横向的Sobel算子作边沿检测,利用测度函数计算车牌区域与一个车牌相似度的模板匹配法寻找车牌位置,设计了用于图像临界值选取的车牌定位算法,最后采用BP神经网络对切割后的车牌文字进行识别。经过实际测试,系统在车牌跟踪识别方面取得了较好的效果。

  17. Re-licensing fort ST. Vrain: How the HTGR design basis was rediscovered - HTR2008-58030

    International Nuclear Information System (INIS)

    Over its 1968-1988 life, PSCo re-licensed the Fort St. Vrain (FSV) High-temperature Gas Reactor (HTGR) for light water reactor (LWR) technology requirements. Estimates of the financial losses associated with the plant range from $500 million to $2 billion in 1980 dollars. Colorado ratepayers, the shareholders of Gulf General Atomics and its corporate successors - General Atomics, GA Technologies or just GA and Public Service Company of Colorado (PSCo) bore these losses. Two critical plant issues required solution for the plant's economic success - (1) the high-cost of 93% enriched uranium fuel and (2) low unit availability. While fuel costs were beyond utility control, low availability was controllable, yet remained unresolved. Commercially isolated for twenty years, PSCo shut the plant down in 1988. Economic success of future HTGRs depends upon avoiding similar complications. This paper examines the issues that made FSV uneconomic, including those fundamental to HTGR technology and others attributable to the utility operator and its culture. Knowing the history of FSV and HTGR design, designers should anticipate reasonable challenges. Preparations will help manage future HTGR risks, costs, and assure operating success. Regulators and industry can assure more effective, economic operations in the next round of HTGR designs. (authors)

  18. 77 FR 16091 - Order Modifying Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design...

    Science.gov (United States)

    2012-03-19

    ... accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires... 48166 Fort Calhoun Station Omaha Public Power District, Docket No. 50-285, License No. DPR-40 Mr. David..., License Nos. NPF-2 and NPF-8 Mr. Tom Lynch, Vice President--Farley, Southern Nuclear Operating...

  19. Aseismic deep subduction of the Philippine Sea plate and slab window

    Science.gov (United States)

    Huang, Zhouchuan; Zhao, Dapeng; Hasegawa, Akira; Umino, Norihito; Park, Jung-Ho; Kang, Ik-Bum

    2013-10-01

    We have made great efforts to collect and combine a large number of high-quality data from local earthquakes and teleseismic events recorded by the dense seismic networks in both South Korea and West Japan. This is the first time that a large number of Korean and Japanese seismic data sets are analyzed jointly. As a result, a high-resolution 3-D P-wave velocity model down to 700-km depth is determined, which clearly shows that the Philippine Sea (PHS) plate has subducted aseismically down to ˜460 km depth under the Japan Sea, Tsushima Strait and East China Sea. The aseismic PHS slab is visible in two areas: one is under the Japan Sea off western Honshu, and the other is under East China Sea off western Kyushu. However, the aseismic PHS slab is not visible between the two areas, where a slab window has formed. The slab window is located beneath the center of the present study region where many teleseismic rays crisscross. Detailed synthetic tests were conducted, which indicate that both the aseismic PHS slab and the slab window are robust features. Using the teleseismic data recorded by the Japanese stations alone, the aseismic PHS slab and the slab window were also revealed (Zhao et al., 2012), though the ray paths in the Japanese data set crisscross less well offshore. The slab window may be caused by the subducted Kyushu-Palau Ridge and Kinan Seamount Chain where the PHS slab may be segmented. Hot mantle upwelling is revealed in the big mantle wedge above the Pacific slab under the present study region, which may have facilitated the formation of the PHS slab window. These novel findings may shed new light on the subduction history of the PHS plate and the dynamic evolution of the Japan subduction zone.

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

    International Nuclear Information System (INIS)

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

  1. US licensing process and ABWR certification

    International Nuclear Information System (INIS)

    The Part 50 licensing process establishes a two-step licensing process whereby the U.S. Nuclear Regulatory Commission (NRC) authorizes construction through issuance of a construction permit and authorizes operation by issuance of an operating license. At each stage, the NRC staff conducts technical reviews, and there is potential for public hearings. The purpose of the Part 52 licensing process is to provide a regulatory framework that brings about early resolution of licensing issues in comparison with the Part 50 process. Because issues are not resolved early in the Part 50 licensing process, approval of an operating license is not assured until after a significant investment has been made in the plant. Part 52 increases the stability and certainty of the licensing process by providing for the early resolution of safety and environmental issues. The Part 52 licensing process features early site permits, design certification, and combined construction permits and operating licenses

  2. Licensing of a Type B(U) package design for the transport of industrial 60Co sealed sources and the use as irradiator facility in Argentina

    International Nuclear Information System (INIS)

    This paper points out the relevant regulatory issues related to the licensing process of a Type B(U) package design, EMI-9 model, approved for the transport and the use as irradiator facility. The radioactive contents is 60Co sealed sources of up to 2,96 PBq, as a special form radioactive material for industrial use. The correspondent Approval Certificate was issued by the Nuclear Regulatory Authority of Argentina in accordance with the Regulatory Standard AR 10.16.1 that is coincident with the 1985 Edition (As Amended 1990) of the IAEA Regulations. It is described the most significant activities performed during the licensing process as well as brief comments are made on the experience gained from previous Type B(U) package design developments. (author)

  3. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    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

  4. Seismicity Variations Associated with Aseismic Transients in Guerrero, Mexico, 1995-2006

    OpenAIRE

    Liu, Yajing; Rice, James R.; Larson, Kristine M.

    2007-01-01

    Primarily aseismic deformation transients in subduction zones, sometimes associated with tremors and low-frequency earthquakes, are a newly recognized mode of deformation. Stressing in the up-dip seismogenic zone is increased episodically due to down-dip transient slips, and each event may make it more prone to failure in a large thrust earthquake. It is important for seismic hazard assessment to search and identify patterns of seismicity variation associated with transients. The Guerrero, Me...

  5. Mineral carbonation of serpentinite in the San Andreas Fault: Implications for aseismic creep

    Science.gov (United States)

    Klein, F.; Goldsby, D. L.; Lin, J.

    2013-12-01

    Here we present a new model that highlights the impact of peridotite-water-CO2 interactions on aseismic creep in the San Andreas Fault (SAF) zone. Serpentinization of peridotite is commonly invoked as the cause of aseismic slip (creep) observed in the SAF of central and northern California, as the creeping section coincides with the mapped extent of the Coast Range ophiolite (Irwin and Barnes, 1975). However, more recently it has been demonstrated that serpentinization alone cannot account for the high rates of aseismic slip (Moore et al., 1996). Moore and Rymer (2007) hypothesized that the reaction of silica-rich fluids with serpentinite causes the formation of mechanically weak talc, which is presently held responsible for fault-zone weakening in this area. While silica-metasomatism can transform serpentinite into steatite (talc rock), the common and widespread occurrence of CO2-rich springs in the fault zone, and silica-carbonate altered serpentinite, points to carbonation (i.e., CO2-metasomatism) of serpentinite as the major cause of fault-zone weakening in central and northern California. Initial results of our field program, mineralogical analyses and friction experiments will be presented, which highlight the evolution in shear strength from serpentine, to soapstone (talc-magnesite rock), to listvenite (quartz-magnesite rock), the final product of CO2-metasomatism.

  6. CANDU 9 enhancements and licensing

    International Nuclear Information System (INIS)

    The CANDU 9 design has followed the evolutionary product development approach that has characterized the CANDU family of nuclear power plants. In addition to utilizing proven equipment and systems from operating stations, the CANDU 9 design has looked ahead to incorporate design and safety enhancements necessary to meet evolving utility and licensing requirements. With the requirement that the CANDU 9 design should be licensable for both domestic and foreign potential users, the pre-project Basic Design Engineering program included a two year formal extensive review by the Canadian Regulatory Agency, the Atomic Energy Control Board . Documentation submitted for the licensing review included the licensing basis, safety requirements and safety analyses necessary to demonstrate compliance with regulations and to assess system design and performance

  7. Trends in CANDU licensing

    International Nuclear Information System (INIS)

    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

  8. Spontaneous aseismic and seismic slip on evolving faults in a continuum-mechanics framework

    Science.gov (United States)

    Herrendörfer, Robert; van Dinther, Ylona; Gerya, Taras

    2016-04-01

    The convergent plate motion in subduction zones is accommodated both by seismic events as well as by aseismic transients and steady slip. To better understand the long-term conditions in subduction zones that govern which portion of convergence is released through seismic or aseismic slip, we need to simulate self-consistently these slip processes and the faults along which they occur. For this purpose, we extended our continuum-based, visco-elasto-plastic numerical model in which cycles of earthquake-like ruptures were simulated through a purely slip rate-dependent friction, albeit at very low slip rates (van Dinther et al., JGR, 2013). To model a wider slip spectrum and to approach seismic slip rates, we implemented an adaptive time-stepping scheme (Lapusta and Rice, JGR, 2001) and an innovative invariant reformulation of conventional rate-and state dependent friction (RSF). In a simplified subduction setup, we validate our new implementations by comparing our simulated stability transitions to those of conventional seismic cycle models. We show a general agreement of the transitions between the occurrence of decaying oscillations towards stable sliding, periodic aseismic events, complex periodic behaviour and seismic events. To demonstrate the advantages of this continuum approach, we simulate the spatiotemporal evolution of a complex fault system beyond the megathrust within an otherwise visco-elastically deforming layered upper plate. Using the common assumption of zero cohesion in RSF applications, deformation localizes in fault-like shear bands, while the degree of localization depends on the choice of RSF parameters. Deformation strongly localizes for rate-weakening friction within the usual laboratory-determined range (a-b~ -1e-2), whereas for rate-strengthening friction it only localizes clearly outside of this range (a-b~1e-4). Furthermore, the existence of these faults is short-lived, because RSF describes only transient changes in fault strength. In

  9. Transition from cataclastic flow to aseismic brittle failure in Carrarra marble

    Science.gov (United States)

    Walker, E.; Schubnel, A.; Thompson, B.; Fortin, J.; Nasseri, M.; Young, R.

    2004-12-01

    Interest in the brittle-ductile transition has increased considerably in recent years, in large part due to the fact that the maximum depth of seismicity corresponds to a transition in the crust and in the upper mantle from seismogenic brittle failure to aseismic cataclastic flow, i.e. from localized to homogeneous deformation. The mechanics of the transition depends both on some extrinsic variable (state of solid stress, pore pressure, temperature, fluid chemistry and strain rate) and intrinsic parameters (crack and dislocation density, modal composition of the rock or porosity for example). In the present study, two triaxial experiments were performed on Carrara marble at room temperature. The rock samples were first deformed in the cataclastic domain (up to ˜5% axial strain) until they exhibited severe damage accumulation, i.e. wavespeed attenuation. Damaged samples were then brought back at constant differential stress into the the brittle field by solely reducing the effective mean stress. Throughout both experiments, compressional wave velocities were measured along several raypaths. Acoustic Emissions, when any, were monitored and localized after testing. A complete 2 minutes failure recordings of failure (12 channels at 10MHz sampling frequency) was also obtained using ESG's Hyperion gigarecorder during one of the experiment. Our new set of data shows that during cataclastic deformation, elastic wave velocities show large variations, but only a small degree of elastic anisotropy when compared to what is generally observed in typical brittle materials such as granite or sandstones. After sufficient damage accumulation and when reducing the mean stress, both samples exhibited a fast acceleration in axial strain. Tertiary creep was followed by the nucleation of a brittle failure. Observed differential stress drops during rupture propagation were of the order of 150 MPa. Although failure occurred with large slip and stress drop, only very few AEs could be

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

    International Nuclear Information System (INIS)

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

  11. WNA Licensing and Permitting Survey

    International Nuclear Information System (INIS)

    This presentation treats of licensing and permitting practices - views of the international nuclear industry. It provides an overview of a survey by WNA on licensing that was completed in September 2012. It explains that responses to the survey were received from utilities, vendors and architect engineer firms across 4 continents. It notes that all nuclear stakeholders agree that safety and security is paramount in any licensing process. It also notes that the survey focuses the interaction of regulatory process with the industry's commercial activities, such as procurement, contracting, and finance. The results of the survey indicate that one licensing model does not fit all and that the regulatory, political and economic environments are very diverse across countries. The presentation highlights differences and some pros and cons for one-step and two-or multi-step licensing. It also highlights the importance of pre-licensing activities. It notes that vendor and site selection are also different and can be commercial or government influenced. Regarding contracting, the survey indicates that it is not practical to develop or advocate for standardization because of the diversity of factors driving commercial considerations. Regarding financing, it highlights the importance of a clear and predictable licensing regime to the availability of financing. It concludes by noting that international harmonization of safety requirements and standardization of designs would greatly facilitate licensing, although there still remains a long way to go in that regard

  12. Advanced reactor licensing issues

    International Nuclear Information System (INIS)

    In July 1986 the US Nuclear Regulatory Commission issued a Policy Statement on the Regulation of Advanced Nuclear Power Plants. As part of this policy advanced reactor designers were encouraged to interact with NRC early in the design process to obtain feedback regarding licensing requirements for advanced reactors. Accordingly, the staff has been interacting with the Department of Energy (DOE) and its contractors on the review of three advanced reactor conceptual designs: one modular High Temperature Gas-Cooled Reactor (MHTGR) and two Liquid Metal Reactors (LMRs). As a result of these interactions certain safety issues associated with these advanced reactor designs have been identified as key to the licensability of the designs as proposed by DOE. The major issues in this regard are: (1) selection and treatment of accident scenarios; (2) selection of siting source term; (3) performance and reliability of reactor shutdown and decay heat removal systems; (4) need for conventional containment; (5) need for conventional emergency evacuation; (6) role of the operator; (7) treatment of balance of plant; and (8) modular approach. This paper provides a status of the NRC review effort, describes the above issues in more detail and provides the current status and approach to the development of licensing guidance on each

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

    International Nuclear Information System (INIS)

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

  14. Licensing and Business Models

    OpenAIRE

    Onetti Alberto; Verma Sameer

    2008-01-01

    License affects software companies’ business activities. While proprietary software vendors create custom licenses, open source companies have less flexibility. The Open Source Initiative (OSI) defines a list of 72 licenses as open source (“OSI approved”). For a project to follow open source licensing, it has to pick licenses from this set. Logically, we expect that an open source company defines its business model around the license that it selects. Thus, we can assume that business model de...

  15. Nursing: Licensed Practical and Licensed Vocational Nurses

    Science.gov (United States)

    ... LPNs) and licensed vocational nurses (LVNs) provide basic nursing care. They work under the direction of registered ... licensed vocational nurses work in many settings, including nursing homes and extended care facilities, hospitals, physicians’ offices, ...

  16. Licensed Healthcare Facilities

    Data.gov (United States)

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

  17. Introduction to special section on phenomenology, underlying processes, and hazard implications of aseismic slip and nonvolcanic tremor

    Science.gov (United States)

    Gomberg, Joan

    2010-01-01

    This paper introduces the special section on the "phenomenology, underlying processes, and hazard implications of aseismic slip and nonvolcanic tremor" by highlighting key results of the studies published in it. Many of the results indicate that seismic and aseismic manifestations of slow slip reflect transient shear displacements on the plate interface, with the outstanding exception of northern Cascadia where tremor sources have been located on and above the plate interface (differing models of the plate interface there also need to be reconciled). Slow slip phenomena appear to result from propagating deformation that may develop with persistent gaps and segment boundaries. Results add to evidence that when tectonic deformation is relaxed via slow slip, most relaxation occurs aseismically but with seismic signals providing higher-resolution proxies for the aseismic slip. Instead of two distinct slip modes as suggested previously, lines between "fast" and "slow" slip more appropriately may be described as blurry zones. Results reported also show that slow slip sources do not coincide with a specific temperature or metamorphic reaction. Their associations with zones of high conductivity and low shear to compressional wave velocity ratios corroborate source models involving pore fluid pressure buildup and release. These models and spatial anticorrelations between earthquake and tremor activity also corroborate a linkage between slow slip and frictional properties transitional between steady state and stick-slip. Finally, this special section highlights the benefits of global and multidisciplinary studies, which demonstrate that slow phenomena are not confined to beneath the locked zone but exist in many settings.

  18. Streamlining the license renewal review process

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  1. PBMR-SA licensing project organization

    International Nuclear Information System (INIS)

    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)

  2. Validation, acceptance and licensing

    International Nuclear Information System (INIS)

    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

  3. Current status of the PBMR licensing project

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  5. Postseismic deformation following the Mw 7.2, 23 October 2011 Van earthquake (Turkey): Evidence for aseismic fault reactivation

    KAUST Repository

    Dogan, Ugur

    2014-04-16

    Geodetic measurements following the 23 October 2011, Mw = 7.2 Van (eastern Turkey) earthquake reveal that a fault splay on the footwall block of the coseismic thrust fault was reactivated and slipped aseismically for more than 1.5 years following the earthquake. Although long-lasting aseismic slip on coseismic ruptures has been documented following many large earthquakes, long-lasting, triggered slip on neighboring faults that did not rupture during the earthquake has not been reported previously. Elastic dislocation and Coulomb stress modeling indicate that the postseismic deformation can be adequately explained by shallow slip on both the coseismic and splay fault and is likely driven mostly by coseismic stress changes. Thus, the slip deficit on the shallow section of the coseismic fault indicated by interferometric synthetic aperture radar-based models has been partially filled by aseismic slip, suggesting a lower likelihood for a large earthquake on the shallow section of the Van fault than suggested by previous studies.

  6. Reproducibility of spatial and temporal distribution of aseismic slips in Hyuga-nada of southwest Japan

    Science.gov (United States)

    Nakata, Ryoko; Miyazaki, Shin'ichi; Hyodo, Mamoru; Hori, Takane

    2014-09-01

    The Hyuga-nada region of southwest Japan, which is located off the east coast of Kyushu Island, may have the potential to generate great interplate earthquakes along the Nankai trough in the future. In this area, thrust earthquakes of M = 6.7-7.2 have occurred with recurrence intervals of approximately 30 years. In association with these earthquakes, possible local heterogeneities of plate coupling may be expected within 100 km from the coast in the Hyuga-nada region. We investigate numerical experiments to determine the spatial and temporal resolution of slip on the plate interface beneath the Hyuga-nada offshore region. For this purpose, we calculated synthetic displacement data from the result of numerical simulation conducted for the afterslip following an Mw 6.8 earthquake, for existing global positioning system stations on land and planned ocean floor seismic network stations. The spatial and temporal distribution of fault slip is then estimated using a Kalman filter-based inversion. The slip distribution estimated by using ocean floor stations demonstrates that the heterogeneity of plate coupling is resolved approximately within 50 km from the coastal area. This heterogeneity corresponds to the coseismic area of an Mw 6.8 earthquake with a radius of 10 km. Our study quantitatively evaluates the spatial resolution of aseismic slip in the Hyuga-nada region. Analysis based on continuous ocean floor data is useful for resolving the spatial variations of heterogeneities in plate couplings.

  7. 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....

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

    International Nuclear Information System (INIS)

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

  9. Operating reactors licensing actions summary. Volume 5, No. 3

    International Nuclear Information System (INIS)

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

  10. Licensing reform in the USA

    International Nuclear Information System (INIS)

    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)

  11. Human Factors Guidance for Control Room and Digital Human-System Interface Design and Modification. Guidelines for Planning, Specification, Design, Licensing, Implementation, Training, Operation and Maintenance

    International Nuclear Information System (INIS)

    Nuclear plant operators face a significant challenge designing and modifying control rooms. This report provides guidance on planning, designing, implementing and operating modernized control rooms and digital human-system interfaces

  12. Human Factors Guidance for Control Room and Digital Human-System Interface Design and Modification, Guidelines for Planning, Specification, Design, Licensing, Implementation, Training, Operation and Maintenance

    Energy Technology Data Exchange (ETDEWEB)

    R. Fink, D. Hill, J. O' Hara

    2004-11-30

    Nuclear plant operators face a significant challenge designing and modifying control rooms. This report provides guidance on planning, designing, implementing and operating modernized control rooms and digital human-system interfaces.

  13. Nuclear power stations licensing

    International Nuclear Information System (INIS)

    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 n0 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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  16. IRIS Licensing Status

    Energy Technology Data Exchange (ETDEWEB)

    Kling, Charles L.; Carelli, Mario D. [Westinghouse Electric Company, Windsor (United States)

    2006-04-15

    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{sup TM} intrinsically eliminates and/or significantly reduces the consequences of traditional LWR accidents. In addition, the fewer passive safety systems are similar in principle to those of the US NRC approved AP1000 design. For these reasons, the IRIS testing program only needs to include those features unique to the IRIS design. NRC feedback was that the planned test program appeared to be complete and could generate sufficient information to support a Design Certification (DC) submittal. The US NRC has also stated that a DC application must include complete information regarding the test program. On this basis the IRIS team has initiated an aggressive program to conduct IRIS testing to support a DC submittal by the end of 2008. Subsequent US NRC review should be expeditious because of the AP1000 precedent, allowing IRIS to obtain its Final Design Approval (FDA) in 2012; thereby, maintaining its goal of deployment in the 2015-2017 time frame. The next steps in the pre-application review process will be to provide the US NRC with a road map of the anticipated IRIS licensing process, a review of current licensing requirements showing that IRIS meets or exceeds all current criteria and information to support the long term goal of redefining the Emergency Planning Zone (EPZ)

  17. Design change management in regulation of nuclear fleets: World nuclear association's working groups on Cooperation in Reactor Design Evaluation and Licensing (CORDEL)

    International Nuclear Information System (INIS)

    The 60 year life of a reactor means that a plant will undergo change during its life. To ensure continuing safety, changes must be made with a full understanding of the design intent. With this aim, regulators require that each operating organisation should have a formally designated entity responsible for complete design knowledge in regard to plant safety. INSAG-19 calls such an entity 'Design Authority'. This requirement is difficult to achieve, especially as the number of countries and utilities operating plants increases. Some of these operating organisations will be new, and some will be small. For Gen III plants sold on a turnkey basis, it is even more challenging for the operating company to develop and retain the full knowledge needed for this role. CORDEL's Task Force entitled 'Design Change Management' is investigating options for effective design change management with the aim to support design standardization throughout a fleet's lifetime by means of enhanced international cooperation within industry and regulators. This paper starts with considering the causes of design change and identifies reasons for the increased beneficial involvement of the plant's original vendor in the design change process. A key central theme running through the paper is the definition of responsibilities for design change. Various existing mechanisms of vendor-operator interfaces over design change and how they are managed in different organisational and regulatory environments around the world are considered, with the functionality of Owners Groups and Design Authority being central. The roles played in the design change process by vendors, utilities, regulators, owners' groups and other organisations such as WANO are considered The aerospace industry approach to Design Authority has been assessed to consider what lessons might be learned. (authors)

  18. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    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

  19. A safety licensable computing architecture

    CERN Document Server

    Halang, WA; Jung, S-K; Scheepstra, JJ

    1993-01-01

    This book describes the design of a low complexity, fault-detecting computer architecture for utilisation in programmable logic controllers (PLCs) for process control purposes. The cyclic operating mode of PLCs and a specification level graphical programming paradigm based on interconnecting application-oriented standard software function modules are architecturally supported. Thus, by design, there is no semantic gap between the specification, programming and machine execution levels enabling the safety licensing of application software by diverse back translation, an extremely simple but rig

  20. Impact of power spectral density function licensing requirement on PVRC damping response spectra for replicate piping design

    International Nuclear Information System (INIS)

    In November 1989, the USNRC issued Revision 2 of the Standard Review Plan (SRP), Section 3.7.1. The revision requires acceleration time histories (ATH) used in the seismic analysis of nuclear power plant (NPP) structures meet a target power spectral density function (PSDF) in addition to meeting the USNRC Regulatory Guide 1.60 design ground response spectrum (DGRS). Three statistically independent ATH (Original ATH) developed prior to 1989 do not fully envelop the new SRP target PSDF. Consequently, these Original ATH were numerically modified to meet the target PSDF (Modified ATH). At the same time, a new set of artificial ATH was also developed (New ATH). A three-dimensional seismic analysis of a NPP containment structure is performed using each of the three sets of ATH. Three sets of in-structure response spectra are developed at a representative location. From which ASME Code Case N-411-1 damping (PVRC damping) response spectra are developed. The three sets of PVRC damping response spectra are used as inputs to response spectrum analyses of four typical piping systems and the resulting responses compared and discussed

  1. CANDU 9 safety enhancements and licensability

    International Nuclear Information System (INIS)

    The CANDU 9 design has followed the evolutionary product development approach that has characterized the CANDU family of nuclear power plants. In addition to utilizing proven equipment and systems from operating stations, the CANDU 9 design has looked ahead to incorporate design and safety enhancements necessary to meet evolving utility and regulatory requirements both in Canada and overseas. To demonstrate licensability in Canada, and to assure overseas customers that the design had independent regulatory review in the country of origin, the pre-project Basic Engineering Program included an extensive two year formal review by the Canadian regulatory authority, the Atomic Energy Control Board (AECB). Documentation submitted for this licensing review included the licensing basis, safety requirements and safety analysis necessary to demonstrate compliance with regulations as well as to assess system design and performance. The licensing review was successfully completed in 1997 January. In addition, to facilitate licensability in Korea, CANDU 9 incorporates feedback from the application of Korean licensing requirements to the CANDU 6 reactors at Wolsong site. (author)

  2. Microstructural study of the partition between seismic and aseismic deformation along the North Anatolian Fault zone, Turkey

    Science.gov (United States)

    Kaduri, M.; Gratier, J. P.; Renard, F.; Cakir, Z.; Lasserre, C.

    2014-12-01

    Along the North Anatolian Fault (Turkey), fault sliding is accommodated both by earthquakes and by aseismic creep. The creep processes develop either as transient (post-seismic or interseismic) sliding or as permanent sliding along zones localized on specific segments of the fault. Creep processes relax the stress and contribute to stress redistribution within the seismogenic zone. They participate to the deformation budget during the seismic cycle, sometimes delaying or on the contrary helping triggering the occurrence of large earthquakes. Identifying the mechanisms controlling creep and their evolution with time and space represents a major challenge for predicting the mechanical evolution of active faults. Our goal is to answer three main questions: How to identify at the outcrop scale permanent creep from transient creep? Is aseismic creep controlled by lithology? How does creep evolve before and after earthquakes? The challenge is to understand which key parameters control the shift from seismic to aseismic deformation, such as the effect of fabric, rock lithology, fault roughness, strain-rate, fluid pressure or stress.We collected samples from a dozen of fresh and well-preserved fault outcrops along creeping and locked segments of the North Anatolian Fault. We used various methods such as microscopic and geological observations, SEM, XRD analysis, strain measurements from image processing approaches in order to quantitatively characterize the amount of deformation and the mechanisms involved. Results show different relationships between lithology and mechanisms of deformation: (i) Along the locked segments of the North Anatolian Fault, in massive limestone, we found evidence of large earthquakes followed by pre- or post-seismic (i.e. afterslip) creep. (ii) Along some creeping segments, we observed gouges with weak clay (saponite) that could accommodate (or have accommodated in the past) large permanent creep. (iii) Along other creeping segments, we observed

  3. Trends in nuclear licensing

    International Nuclear Information System (INIS)

    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. Aseismic Slip Events along the Southern San Andreas Fault System Captured by Radar Interferometry

    Energy Technology Data Exchange (ETDEWEB)

    Vincent, P

    2001-10-01

    A seismic slip is observed along several faults in the Salton Sea and southernmost Landers rupture zone regions using interferometric synthetic aperture radar (InSAR) data spanning different time periods between 1992 and 1997. In the southernmost Landers rupture zone, projecting south from the Pinto Mountain Fault, sharp discontinuities in the interferometric phase are observed along the sub-parallel Burnt Mountain and Eureka Peak Faults beginning three months after the Landers earthquake and is interpreted to be post-Landers after-slip. Abrupt phase offsets are also seen along the two southernmost contiguous 11 km Durmid Hill and North Shore segments of the San Andreas Fault with an abrupt termination of slip near the northern end of the North Shore Segment. A sharp phase offset is seen across 20 km of the 30 km-long Superstition Hills Fault before phase decorrelation in the Imperial Valley along the southern 10 km of the fault prevents coherent imaging by InSAR. A time series of deformation interferograms suggest most of this slip occurred between 1993 and 1995 and none of it occurred between 1992 and 1993. A phase offset is also seen along a 5 km central segment of the Coyote Creek fault that forms a wedge with an adjoining northeast-southwest trending conjugate fault. Most of the slip observed on the southern San Andreas and Superstition Hills Faults occurred between 1993 and 1995--no slip is observed in the 92-93 interferograms. These slip events, especially the Burnt Mountain and Eureka Peak events, are inferred to be related to stress redistribution from the June, 1992 M{sub w} = 7.3 Landers earthquake. Best-fit elastic models of the San Andreas and Superstition Hills slip events suggest source mechanisms with seismic moments over three orders of magnitude larger than a maximum possible summation of seismic moments from all seismicity along each fault segment during the entire 4.8-year time interval spanned by the InSAR data. Aseismic moment releases of this

  5. Licensed bases management for advanced nuclear plants

    International Nuclear Information System (INIS)

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

  6. Universal Licensing System (ULS)

    Data.gov (United States)

    Federal Communications Commission — The Universal Licensing System allows electronic filing of applications processed by the Commission. The ULS allows you to indicate the application purpose and...

  7. Licensing, supervision, retrofitting

    International Nuclear Information System (INIS)

    The lecture deals in detail with questions on the systematization and coordination of the elements the Atomic Energy Act defines as relevant to licensing; discretion to deny a licence for safety reasons - other licensing reservations under environmental law - protection of third parties - provisions for waste disposal and compliance with international obligations - protective aim of the law; questions on a concentrating effect in licensing and other administrative decisions; introduction of a plan approval procedure or site assessment and procedure; staged licensing procedure, dynamization of provisions against damage; subsequent obligations; introduction of periodical safety checks; abolition of the indemnification obligation pursuant to Paragraph 18 Section 3 of the Atomic Energy Act. (HSCH)

  8. Operator licensing examiner standards

    International Nuclear Information System (INIS)

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

  9. Licensing of HTGRs in the United States

    International Nuclear Information System (INIS)

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

  10. Licensing of the construction permit of the NHR-200

    International Nuclear Information System (INIS)

    The nuclear heating reactor (NHR) was developed by the Institute of Nuclear Energy Technology (INET), Tsinghua University. The main design features and safety concepts of the NHR-200, the criteria and principles that were followed in licensing the construction permit of the NHR-200 are discussed. Licensing activities and procedures are described. Some of the main licensing safety issues including accident analysis, secondary containment design, the requirements for the Diesel generators and the safety classification of systems and components are briefly addressed

  11. Evolution of Shallow Aseismic Slip Around the MW 7.6 September 5th 2012 Nicoya Megathrust Earthquake

    Science.gov (United States)

    Malservisi, R.; Jiang, Y.; Dixon, T. H.; Protti, M.; Gonzalez, V.; Newman, A. V.

    2013-12-01

    A dense continuous GPS (CGPS) network on the Nicoya Peninsula of northern Costa Rica is uniquely located above the seismogenic zone of the Cocos-Caribbean subduction boundary. This location has allowed sensitivity to measure deformation from aseismic slip on the plate interface both updip and downdip of the locked subduction interface. On September 5, 2012, after years of slow-slip event observations, a large moment magnitude (MW) 7.6 megathrust earthquake occurred directly within the CGPS network. In this study, we compare the spatial distribution and temporal occurrence of the pre-seismic slow slip with the coseismic and early post-seismic slip in the first 24 hours after the earthquake. We focus on evaluating the cumulative aseismic slip and its relation to the early-postseismic deformation, including the sensitivity of solutions to the modeling assumptions. One year out, the CGPS network continues to record strong post-seismic deformation after the event. Here we evaluate the relaxation time associated with such event showing that multiple relaxation times are necessary to fit the data. Our results clearly indicate that observation of slip on the shallow part of the fault is very important to fully understand the subduction earthquake cycle. CGPS coseismic deformation and fault plane slip inversion computed as difference between the position the day before and the position the day after (left) and the position 120sec after the event and the position the day after (right).

  12. 50 CFR 260.50 - Suspension or revocation of license of licensed sampler or licensed inspector.

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 7 2010-10-01 2010-10-01 false Suspension or revocation of license of... Licensing of Samplers and Inspectors § 260.50 Suspension or revocation of license of licensed sampler or... or evidence that he may wish to offer as to why his license should not be suspended or revoked....

  13. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    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

  14. Review of revised Japanese seismic guidelines for NPP design

    International Nuclear Information System (INIS)

    From new knowledge in recently aseismic design studies, some of the conventional design methods we understood to be conservative, and review for guideline of private sector and preparation for by-laws of administrative office thereby have been promoted since 1984. This paper presents the state-of-arts and trends of current aseismic design methods and the guideline and the by-laws thereof for Japanese NPP, including items on determination of the design basis earthquake, investigation of ground condition and seismic stability, treatment of soil-structure interaction, limitation for uplift of building basement, evaluation of non-linear characteristics and response, and provision of design basis damping. (orig.)

  15. 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.

  16. Development of licensing process of nuclear power plants (NPPs) for Kenya

    Energy Technology Data Exchange (ETDEWEB)

    Shadrack, A. K. [Radiation Protection Board, Mombasa (Kenya)

    2012-03-15

    This research paper presents the findings of a comprehensive survey and analysis of the licensing procedures of six leading countries with nuclear power technology. The main objective of this study was to develop a generic reference licensing procedure of nuclear power plants for Kenya based on the best practices from the licensing procedures of six countries such as US, republic of Korea Canada, Japan, UK, France and Japan. Based on the analysis results, a generic reference licensing process for Kenya was developed and two future research areas significant for the establishment of nuclear regulation infrastructure for Kenya recommended. The analysis process classified the licensing process according to licensing stages, licensing steps, and levels of authorization. Finally, a two - step licensing procedures for Kenya was established comprising of 3 licensing stages, 3 licensing steps, and 3 levels of authorization. This research paper is useful as a draft for legislation process for nuclear power plants sitting, design, construction, commissioning, operation, and decommissioning in Kenya.

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

    International Nuclear Information System (INIS)

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

  18. 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.

  19. Seismic and aseismic deformations and impact on reservoir permeability: The case of EGS stimulation at The Geysers, California, USA

    Science.gov (United States)

    Jeanne, Pierre; Rutqvist, Jonny; Rinaldi, Antonio Pio; Dobson, Patrick F.; Walters, Mark; Hartline, Craig; Garcia, Julio

    2015-11-01

    In this paper, we use the Seismicity-Based Reservoir Characterization approach to study the spatiotemporal dynamics of an injection-induced microseismic cloud, monitored during the stimulation of an enhanced geothermal system, and associated with the Northwest Geysers Enhanced Geothermal System (EGS) Demonstration project (California). We identified the development of a seismically quiet domain around the injection well surrounded by a seismically active domain. Then we compare these observations with the results of 3-D Thermo-Hydro-Mechanical simulations of the EGS, which accounts for changes in permeability as a function of the effective normal stress and the plastic strain. The results of our modeling show that (1) the aseismic domain is caused by both the presence of the injected cold water and by thermal processes. These thermal processes cause a cooling-stress reduction, which prevent shear reactivation and favors fracture opening by reducing effective normal stress and locally increasing the permeability. This process is accompanied by aseismic plastic shear strain. (2) In the seismic domain, microseismicity is caused by the reactivation of the preexisting fractures, resulting from an increase in injection-induced pore pressure. Our modeling indicates that in this domain, permeability evolves according to the effective normal stress acting on the shear zones, whereas shearing of preexisting fractures may have a low impact on permeability. We attribute this lack of permeability gain to the fact that the initial permeabilities of these preexisting fractures are already high (up to 2 orders of magnitude higher than the host rock) and may already be fully dilated by past tectonic straining.

  20. Nuclear facilities licensing

    International Nuclear Information System (INIS)

    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.)

  1. Operator licensing examiner standards

    International Nuclear Information System (INIS)

    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

  2. 7 CFR 52.32 - Suspension or revocation of license of licensed sampler or licensed inspector.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 2 2010-01-01 2010-01-01 false Suspension or revocation of license of licensed... Inspection and Certification Licensing of Samplers and Inspectors § 52.32 Suspension or revocation of license..., with the Secretary supported by any argument or evidence that he may wish to offer as to why...

  3. AP1000R licensing and deployment in the United States

    International Nuclear Information System (INIS)

    In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two new nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing actions directed

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  9. ABWR certification work brings US licensing stability nearer

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  11. Gamma irradiation facility: License and authorization processes

    International Nuclear Information System (INIS)

    National and international regulations demand that the competent authority should issue licenses to authorize users of ionizing radiation after satisfactory completion of the conditions set by the authority in line with international standards. In the process five (5) licenses (Site selection, Design, Construction, Importation and Transportation of Radioactive sources and Commissioning) were requested for by the management of SHESTCO and were issued by the Nigeria Nuclear Regulatory Authority (NNRA) after going through the rigorous and laborious process. Despite the fact that the installations of the major components of the facility were completed before the establishment of the NNRA, it took close to 2 years to secure all the licenses. The licenses for site selection, design and construction were issued retroactively after proper review of the compliance with the national and international regulations by experts from Nigeria and International Atomic Energy Agency (IAEA), Vienna, Austria. It was tough, to say the least, to secure the licenses for the importation of radioactive sources, and the Hot Commissioningwith the radioactive sources already installed but unused

  12. GOVERNOR ORGANIZATIONS ACTIVITY LICENSING

    Directory of Open Access Journals (Sweden)

    Maslennikova L. V.

    2015-03-01

    Full Text Available The author analyses the licensing of governor organizations activity in connection with amendments to the Housing Code of the Russian Federation by adoption of a Federal law of 21.07.2014 N 255-FZ «On amendments to the Housing Code of the Russian Federation, some legislative acts of the Russian Federation and on declare force Certain Provisions of Legislative Acts of the Russian Federation void » and the Government Resolution adoption of the of 28.10.2014г. N 1110 «On entrepreneur activity in apartment buildings’ government licensing». The urgency of the issue of the apartment buildings licensing activity is associated with the modernization of housing and communal services and legal regulation in this area. Introduction of the governor organizations activity licensing without securing in law the concept of "governor organizations" is a significant flaw of the legislator. As a result, the author gives the concept of governor organizations based on the analysis of scientific papers and current legislation. In addition, the article analyzes the introduction of licensing control, assesses the established order of the three registers on the governor organizations activity. The presented paper examines the experience of foreign countries associated with the activities on the apartment building common property management as well, and the state control over such activity. The authors examine violations of housing legislation that may cause the governor organizations and their officials’ administrative responsibility

  13. Decree of the Czechoslovak Atomic Energy Commission No. 2 as of 27 October 1978 on securing nuclear safety during the designing, licensing, and implementation of constructions that involve nuclear power facilities

    International Nuclear Information System (INIS)

    The Decree lays down requirements aimed at securing nuclear safety of constructions involving nuclear power facilities during their designing, licensing and implementation. The basic requirements include (i) quality assurance; (ii) in-service inspection; (iii) radiation protection in the surroundings of the nuclear facility; (iv) radiation protection within the nuclear facility buildings; (v) protection against facility failures; (vi) heat removal; (vii) fire protection; (viii) protection against external natural or man-made effects; (ix) protection against adverse activities; (x) conditions for the use of common facilities. Design requirements are specified for the reactor core, instrumentation and control systems, reactor cooling systems, power supply systems, containment system, and radiation protection. The Decree entered into force on 1 January 1979. (J.B.)

  14. Nuclear licensing in Slovenia

    International Nuclear Information System (INIS)

    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)

  15. 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...

  16. License to Learn

    DEFF Research Database (Denmark)

    Leone, Maria Isabella; Boccardelli, Paolo; Reichstein, Toke;

    2016-01-01

    . 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......This article introduces the distinction between thin and thick contracts to the investigation of licensing-in as a mechanism for technological learning. Thick contracts include a clause specifying that the licensors are obligated to assist the licensees in assimilating and integrating the...

  17. New Reactor Licensing Status and Lessons Learned

    International Nuclear Information System (INIS)

    This presentation deals with new reactor licensing status and lessons learned in the USA. The presentation covers a status of licensing for large light water reactors in the USA and insights and lessons learned from licensing reviews and on-going construction activities. In the area of lessons learned, the presentation highlights the importance of pre-application interactions between applicants and the regulator. It notes that early interactions and reviews are important for major policy and technical issues and areas where research may be needed. It highlights the importance of communication, the success of on-sight audits of detailed calculations and analyses, and the importance for applicants and regulators to be aware of issues arising on similar applications domestically and internationally. It next discusses the importance of translation of design into construction documents as well as the need to ensure that construction is conducted in accordance with the licensing basis, especially under the U.S. one-step licensing process. The presentation also provides a discussion on new processes being implemented to address the need for changes during construction. These include a preliminary amendment request process by which the licensee could seek a no objection letter from the regulator to proceeding with installing and testing a proposed change pending U.S.NRC's review of the license amendment request. It also discusses the use of pre-submittal meetings with licensees on draft amendment requests in order to provide feedback and expedite the review of the amendments when submitted. It notes the ongoing work to address Fukushima lessons learned. It concludes by noting that the U.S.NRC has initiated a comprehensive review to identify best practices and potential enhancements to its new reactor licensing processes and that a report should be published in early 2013

  18. Cask development, testing, and licensing

    International Nuclear Information System (INIS)

    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

  19. Safety and Licensing of Spent Fuel Storage Facilities

    International Nuclear Information System (INIS)

    All operating nuclear power reactors in the United States (U.S.) are storing spent fuel on-site in spent fuel pools licensed by the U.S. Nuclear Regulatory Commission (NRC). Spent fuel pools at U.S. reactors were not designed to store the full amount of spent fuel generated during the lifetime of plant operation. Consequently, most utilities expanded their storage capacity by the use of high-density storage racks. Even with the high density racks, most utilities will need additional storage capacity. When it became apparent that nuclear power plants were going to need additional spent fuel storage space, the NRC amended its regulations in 1980 to provide nuclear power plants with alternate spent fuel storage in an independent spent fuel storage installation (ISFSI). NRC provides for a 20-year specific license with the option to renew the license for additional 20-year terms. In 1990, the NRC implemented the General License option to ease the burden on nuclear power plants that have a license to either operate or possess fuel. The general license for each storage cask terminates 20 years after the storage cask is first used by the licensee. The first storage cask using a general license was loaded in 1994. This paper discusses NRC experiences and its knowledge gained in licensing over the past 30 years and renewing the licenses for three ISFSIs and how this knowledge has driven the NRC to revise its guidance and thought processes for dry storage. (author)

  20. A BWR licensing experience in the USA

    International Nuclear Information System (INIS)

    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)

  1. NRC materials licensing business process reengineering

    International Nuclear Information System (INIS)

    The United States Nuclear Regulatory Commission (NRC) has issued 6550 active licenses that authorize possession and use of byproduct, source, and special nuclear material. In October 1994, the NRC staff began to examine the process used to issue these licenses to identify ways to improve the process. In addition to examining the current process, the staff was directed to develop a new process design that would accomplish the following goals: (1) Maintain or raise the level of public safety achieved by the current process, (2) Perform licensing reviews and associated tasks an order of magnitude faster than the current process, (3) Exploit modern information technology as a fundamental part of the new process, and (4) Reduce the resources needed to carry out the licensing program to meet the projected 1997-1999 staffing levels. The method used for this examination is called Business Process Reengineering (BPR). BPR is the process of fundamentally changing the way work is performed so as to achieve radical performance improvements in speed, cost, and quality. Features of the new licensing process, scheduled to begin in 1996, are outlined in this paper

  2. 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)

  3. Understanding Licensing Behavior

    DEFF Research Database (Denmark)

    Cabaleiro, Goretti; Moreira, Solon; Reichstein, Toke

    The potential for rent dissipation has been argued to be the main cause of firms? licensing out behavior being stifled.However, this aspect has been scarcely studied empirically. We draw on rent dissipation arguments, and hypothesize that firms suffering from the not-invented-here (NIH) syndrome...

  4. A License To Deal.

    Science.gov (United States)

    Sanville, Tom

    1999-01-01

    Discusses consortium-based licensing as a means of meeting libraries' information resources needs. Topics include information needs, the need for more affordable information, requirements for libraries and for vendors, competition across disciplines, saving money, pricing and market practices, experiences at OhioLINK, and future possibilities.…

  5. High variability of stress accumulation, seismic and aseismic release mode along the Peru-Ecuador subduction zone (Invited)

    Science.gov (United States)

    Nocquet, J.; Villegas, J. C.; Chlieh, M.; Mothes, P. A.; Rolandone, F.; Jarrín, P.; Cisneros, D.; Vallee, M.

    2013-12-01

    Most geodetic measurements of interseismic strain along subduction zones have led to the view of coupled asperities of variable size usually separated by narrower zones of low coupling. Along the western margin of South America, fast convergence of the oceanic Nazca plate has repeatedly produced M>8 earthquakes and three of the ten largest megathrust earthquakes since 1900. Contrasting with this behavior, the segment comprised between central Peru and central Ecuador has not experienced any great earthquake for at least five centuries. New GPS measurements in Peru and Ecuador first highlight that a along a ~1000km long segment, convergence is predominantly accommodated by aseismic creep along the plate interface, with possible coupling occurring at shallow depth, close to the trench. This area is bounded by highly locked segments, which produced M>8.5 earthquakes in central Peru and northern Ecuador. While the observed low interseismic coupling explains the lack of great earthquakes, this area has experienced two earthquakes that share the characteristics of tsunamigenic earthquakes, indicating a correlation between the mode of stress accumulation along the plate interface and its release. Finally, we have observed several episodes of slow slip, sometimes associated with intense, micro to moderate seismicity. These observations suggest a specific behavior for this segment, which contrasts with the behavior of the neighboring segments.

  6. Licensing Trends for Construction of New Nuclear Plants

    International Nuclear Information System (INIS)

    Currently in Korea, an SFR (Sodium-cooled Fast Reactor) technology proving stage reactor called PGSFR (Prototype Gen-IV SFR) is being developed by KAERI and KEPCO E and C to be constructed by 2028. After the accident of the Fukushima nuclear power plants, how to regulate and license newly developing nuclear reactors requiring higher safety goals has been issued. As a result, in leading nuclear nations developing new reactors, the close cooperation between the developer and the regulator is becoming very important. In this study, the licensing processes of leading nuclear countries were surveyed and compared with that of Korea, and a new licensing direction for PGSFR was suggested. Reviewing licensing processes for newly developing reactors of other countries, the first step of the licensing process is the pre-safety review, which is to review the reactor design. This process is not legally binding, but is a review process for a better understanding of newly applied technologies by regulators prior to starting the legally binding licensing process as the construction and operation licensing. This process provides an opportunity for the reactor developer to adopt the regulator's licensing direction and a goal to designing newly developing reactors to meet the safety requirements

  7. Establishment of regulatory framework for the development reactor licensing

    International Nuclear Information System (INIS)

    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. The Licensing of New Nuclear Power Plants in Europe

    International Nuclear Information System (INIS)

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

  9. Automatic Licenses Plate Recognition

    OpenAIRE

    Ronak P Patel; Narendra M Patel; Keyur Brahmbhatt

    2013-01-01

    This paper describes the Smart Vehicle Screening System, which can be installed into a tollboothfor automated recognition of vehicle license plate information using a photograph of a vehicle. An automatedsystem could then be implemented to control the payment of fees, parking areas, highways, bridges ortunnels, etc. This paper contains new algorithm for recognition number plate using Morphological operation,Thresholding operation, Edge detection, Bounding box analysis for number plate extract...

  10. Licensing Experience for EPR Flamanville 3

    International Nuclear Information System (INIS)

    This presentation discusses the three stages of the EPR Flamanville 3 Licensing process: the political decision to build a new nuclear power plant, the authorization decree for nuclear power plant creation/construction license, and the commission and operation license. The operating license process requires the operator to submit the safety analysis report, the general operating rules, a study on waste management, the onsite emergency plan, and an update, as necessary of the decommissioning plan and the environmental impact assessment. The presentation follows with a discussion on the licensing of the Flamanville 3 EPR reactor. Flamanville 3 licensing was a longstanding and continuous process taking 18 years for the 3 main steps (1989 to 2007) and resulting in the authorization decree. The presentation describes the safety objectives utilized in the process, the integration of recent operating experience, innovations, and design and manufacturing. It also highlights several examples of modifications that resulted from the technical assessment supporting the authorization decree, including diversification of emergency electrical supply, practical elimination of fuel melt in the fuel pool, and diversification of heat sink and essential service water system. It reviews the contents of the authorization decree. Next, it discusses current on-going activities and milestones related to commissioning and operating license application and notes that current ASN/IRSN review activities are focused on a number of topics, including accident studies, I and C, protection system, internal and external events, detailed design of systems playing a safety role as supporting systems, equipment qualification to accident conditions, radiological consequences, several accident management, probabilistic studies, and several other topics. It explains that a 'focusing' review principle is used to inform the level of review for each topic. This principle is used to choose the SSCs that will

  11. CANDU safety and licensing framework and process

    International Nuclear Information System (INIS)

    Nuclear Safety is a shared responsibility of the Industry, public and the Government. The International Atomic Energy Agency's (IAEA) safety fundamentals, basic objectives and safety guides lay down the principles from which requirements, recommendations and methodologies for safety design of Nuclear Power Plants (NPP) are derived. Within the framework of the international regulations and those of the Canadian Nuclear Safety Commission (CNSC), this paper will discuss the overall safety objectives, the defence in depth philosophy guiding CANDU safety, as well as the licensing process defined to meet all applicable CNSC regulations. The application of such philosophy to the ACR design and safety approach will also be discussed along with aspects of its implementation. The role of deterministic analysis, and Probabilistic Safety Analysis (PSA) in the design and licensing process of the Advanced CANDU Reactor will be discussed. Postulated initiating events and their combinations, acceptance criteria, CANDU margins and limits, supporting methodologies and computer codes used in safety analysis will be reviewed. The paper will also note intrinsic safety characteristics of CANDU, some of the ACR passive safety features built-in by design, CANDU distinctive features with respect to severe core damage, mechanisms of heat rejection in those extreme conditions, emergency coolant injection system features and other post accident mitigating systems. Update on the ACR Canadian and US licensing progress will also be provided. (authors)

  12. Licensing of ANSTO's Replacement Research Reactor

    International Nuclear Information System (INIS)

    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)

  13. Image simulation for automatic license plate recognition

    Science.gov (United States)

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

    2012-01-01

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

  14. Exporting the Canadian licensing program

    International Nuclear Information System (INIS)

    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. Patent license negotiation :best practices

    OpenAIRE

    Giordano-Coltart, J. (Jennifer); Calkins, C.W. (Charles)

    2009-01-01

    In all areas of the biotechnology and pharmaceutical industries, the licensing of intellectual property is in most cases an essential step in the translation of basic research into a commercial product. Negotiating IP licensing agreements and developing the terms of the business transaction involve evaluating numerous factors pertaining to the specific circumstances of the parties and the technology at issue. As the quality of the business relationship after licensing of the intellectual prop...

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

    International Nuclear Information System (INIS)

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

  17. Licensed operating reactors

    International Nuclear Information System (INIS)

    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

  18. Licensed operating reactors

    International Nuclear Information System (INIS)

    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

  19. FCC Universal Licensing System (ULS)

    Data.gov (United States)

    Federal Communications Commission — The Universal Licensing System allows electronic filing of applications processed by the Commission. The ULS allows you to indicate the application purpose and...

  20. VEHICLE LICENSE PLATE CHARACTER SEGMENTATION – A VEHICLE LICENSE PLATE CHARACTER SEGMENTATION – A STUDY

    Directory of Open Access Journals (Sweden)

    V. Karthi Keyan

    2013-02-01

    Full Text Available License plate recognition (LPR plays a major role in this busy world, as the number of vehicles increases day by day, theft of vehicles, breaking traffic rules, entering restricted area are also increases linearly, so to block this act license plate recognition system is designed. License Plate Recognition (LPR systems basically consist of 3 main processing steps such as: Detection of number plate, Segmentation of plate characters and Recognition of each character. Among this, character segmentation is a most challenging task, as the accuracy of the character recognition relies on the accuracy of the character segmentation. Problems of different lighting condition, adhesion, fracture, rivet, rotation degrades the accuracy of the character segmentation. So in order to overcome these problems and uplift the accuracy of character segmentation various algorithms are developed for this work. Purpose of this paper is to categorize the vehicle plate character and recognize the segmented characters.

  1. Safety and licensing issues for Indian PHWRs

    International Nuclear Information System (INIS)

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

  2. Investment issues in nuclear plant license renewal

    International Nuclear Information System (INIS)

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

  3. Development of licensing process for SMART-P

    International Nuclear Information System (INIS)

    The basic design of System-integrated Modular Advanced Reactor (SMART), a small-to-medium sized integral type pressurized water reactor (PWR) with the capacity of 330MWth, has been developed in Korea. Presently, for the purpose of demonstrating the safety and performance of the SMART design, 'Development Project of SMART-P (SMART-Pilot Plant)' is being performed as one of the 'National Mid and Long-term Atomic Energy R and D Programs', which includes design, construction, and start-up operation of the SMART-P with the capacity of 65MWth, a 1/5 scaled-down design of the SMART. At the same time, a study on the establishment of a licensing process for the SMART-P has been carried out by KINS in order to prepare for the forthcoming SMART-P licensing. The results of this study performed from Aug. of 2002 to June of 2004 can be summarized as follows: (1) The construction purpose and design characteristics of the SMRAT-P were reviewed. (2) The licensing processes for reactors in Korea, U.S.A., Japan, France, U.K., Canada, and IAEA were analyzed. (3) Reactor classification criteria were established based on the analysis results for the foreign licensing processes. And a development direction for the licensing process applicable to the development reactor was established. (4) 4 candidate models of licensing process for the development reactor were proposed based on the domestic licensing processes considering the general trends and practices of the foreign licensing processes. Evaluation of the candidate models were performed. (5) Through the expert review of the candidate models, an optimized model was finally selected and an implementation plan for the optimized model including legalization was established. The licensing process for the development reactor proposed in this study can be applied directly to the licensing of the SMART-P. Furthermore, it will be also applied to the licensing of the development reactors for the advanced reactors such as the GEN-IV

  4. Development of radioactive waste management licensing review assistant

    International Nuclear Information System (INIS)

    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

  5. License Plate Recognition System based on Image Processing Using Labview

    Directory of Open Access Journals (Sweden)

    Kuldeepak

    2012-07-01

    Full Text Available A License plate recognition (LPR system is one kind of an intelligent transport system and is of considerable interest because of its potential applications in highway electronic toll collection and traffic monitoring systems. A lot of work has been done regarding LPR systems for Korean, Chinese, European and US license plates that generated many commercial products. However, little work has been done for Indian license plate recognition systems. The purpose of this paper is to develop a real time application which recognizes license plates from cars at a gate, for example at the entrance of a parking area or a border crossing. The system, based on regular PC with video camera, catches video frames which include a visible car license plate and processes them. Once a license plate is detected, its digits are recognized, displayed on the user interface or checked against a database. The focus is on the design of algorithms used for extracting the license plate from a single image, isolating the characters of the plate and identifying the individual characters. The proposed system has been implemented using Vision Assistant 8.2.1 & Labview 11.0 the recognition of about 98% vehicles shows that the system is quite efficient.

  6. Responsibilities of NARM Licensing States

    International Nuclear Information System (INIS)

    There are 30 Licensing States of Naturally Occurring and Accelerator-Produced Radioactive Materials (NARM) in the U.S. In these States NARM is licensed in a similar manner as is by-product material in the Agreement States. Each Licensing State has the responsibility to identify and evaluate NARM products including informing other State and Federal radiation control agencies of potential problems encountered during the lifetime of the product. Licensing States have authority to perform on-site inspections of manufacturers, enforce radiation regulations, require compliance with all conditions of the license, and amend or terminate the license for possession and use of NARM. A Licensing State also has the responsibility to accept the recommendation on NARM products evaluated by other Licensing States. To assist States in the evaluation of NARM products the Conference of Radiation Control Program Directors developed a report entitled 'Guides for Naturally Occurring and Accelerator-Produced Radioactive Materials (NARM).' The NARM Guides report (HEW Publication (FDA) 77-8025) was published by the Bureau of Radiological Health/FDA in July 1977. The NARM Guides establish uniform criteria for evaluating the manufacture, assembly and distribution of NARM products in the U.S. The Radioactive Materials Reference Manual which is coordinated by BRH/FDA is the medium for communicating NARM information with the radiation control agencies of the 50 States, certain Federal and local agencies. (author)

  7. Total System Performance Assessment-License Application Design Selection (LADS) Phase 1 Analysis of Surface Modification Consisting of Addition of Alluvium (Feature 23a)

    International Nuclear Information System (INIS)

    The objective of this report is to document the analysis that was conducted to evaluate the effect of a potential change to the TSPA-VA base case design that could improve long-term repository performance. The design feature evaluated in this report is a modification of the topographic surface of Yucca Mountain. The modification consists of covering the land surface immediately above the repository foot-print with a thick layer of unconsolidated material utilizing rip-rap and plants to mitigate erosion. This surface modification is designated as Feature 23a or simply abbreviated as F23a. The fundamental aim of F23a is to reduce the net infiltration into the unsaturated zone by enhancing the potential for evapotranspiratiration at the surface; such a change would, in turn, reduce the seepage flux and the rate of radionuclide releases from the repository. Field and modeling studies of water movement in the unsaturated zone have indicated that shallow infiltration at the surface is almost negligible in locations where the bedrock is covered by a sufficiently thick soil layer. In addition to providing storage for meteoric water, a thick soil layer would slow the downward movement of soil moisture to such an extent that evaporation and transpiration could easily transfer most of the soil-water back to the atmosphere. Generic requirements for the effectiveness of this design feature are two-fold. First, the soil layer above the repository foot-print must be thick enough to provide sufficient storage of meteoric water (from episodic precipitation events) and accommodate plant roots. Second, the added soil layer must be engineered so as to mitigate thinning by erosional processes and have sufficient thickness to accommodate the roots of common desert plants. Under these two conditions, it is reasonable to expect that modification would be effective for a significant time period and the net infiltration and deep percolation flux would be reduced by orders of magnitude lower

  8. The Monticello license renewal project

    International Nuclear Information System (INIS)

    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

  9. Licensed operating reactors

    International Nuclear Information System (INIS)

    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. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  10. Licensed operating reactors

    International Nuclear Information System (INIS)

    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 of 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

  11. Licensed operating reactors

    International Nuclear Information System (INIS)

    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. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  12. Licensed operating reactors

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission's annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar 1990) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  13. Licensed operating reactors

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commissions annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December, the year to date (in this case calendar year 1993) and cumulative data, usually for the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  14. Licensed operating reactors

    International Nuclear Information System (INIS)

    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. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  15. Decommissioning licensing procedure

    International Nuclear Information System (INIS)

    Decommissioning or closure of a nuclear power plant, defined as the fact that takes place from the moment that the plant stops producing for the purpose it was built, is causing preocupation. So this specialist meeting on Regulatory Review seems to be the right place for presenting and discusing the need of considering the decommissioning in the safety analysis report. The main goal of this paper related to the licensing procedure is to suggest the need of a new chapter in the Preliminary Safety Analysis Report (P.S.A.R.) dealing with the decommissioning of the nuclear power plant. Therefore, after a brief introduction the problem is exposed from the point of view of nuclear safety and finally a format of the new chapter is proposed. (author)

  16. Waste management and licensing

    International Nuclear Information System (INIS)

    It is the Court's consideration of the repercussions the regulation on waste management of Sect. 9a of the Atomic Energy Law will have, relating to the licensing of a plant according to Sect. 7 (2) of the Atomic Energy Law which is noteworthy. Overruling its former legal conception, the Administrative Court Schleswig now assumes, together with the public opinion, that the problem of waste management being brought to a point only with the initial operation of a nuclear power station is accordingly to be taken into account in line with the discretion of licensing according to Sect. 7 (2) of the Atomic Energy Law. In addition, the Administrative Court expressed its opinion on the extent to the right of a neighbour to a nuclear power station to file suit. According to the Sections 114 and 42 (2) of the rules of Administrative Courts it is true that a plaintiff cannot take action to set aside the licence because public interests have not been taken into account sufficiently, but he may do so because his own interests have not been included in the discretionary decision. The Administrative Court is reserved when qualifying the regulation on waste management with regard to the intensity of legal control. The Court is not supposed to replace controversial issues of technology and natural sciences on the part of the executive and its experts by its own assessment. According to the proceedings, the judicial review refers to the finding as to whether decisions made by authorities are suited - according to the way in which they were made - to guarantee the safety standard prescribed in Subdivision 3 of Sect. 7 (2) of the Atomic Energy Law. (HSCH)

  17. Licensing system for primary category radioactive installations

    International Nuclear Information System (INIS)

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

  18. Spatio-temporal evolution of aseismic ground deformation in the Mexicali Valley (Baja California, Mexico) from 1993 to 2010, using differential SAR interferometry

    Science.gov (United States)

    Sarychikhina, O.; Glowacka, E.

    2015-11-01

    Ground deformation in Mexicali Valley, Baja California, Mexico, the southern part of the Mexicali-Imperial valley, is influenced by active tectonics and human activity, mainly that of geothermal fluid extraction in the Cerro Prieto Geothermal Field. Significant ground deformation, mainly subsidence (~ 18 cm yr-1), and related ground fissures cause severe damage to local infrastructure. The technique of Differential Synthetic Aperture Radar Interferometry (DInSAR) has been demonstrated to be a very effective remote sensing tool for accurately measuring the spatial and temporal evolution of ground displacements over broad areas. In present study ERS-1/2 SAR and ENVISAT ASAR images acquired between 1993 and 2010 were used to perform a historical analysis of aseismic ground deformation in Mexicali Valley, in an attempt to evaluate its spatio-temporal evolution and improve the understanding of its dynamic. For this purpose, the conventional 2-pass DInSAR was used to generate interferograms which were used in stacking procedure to produce maps of annual aseismic ground deformation rates for different periods. Differential interferograms that included strong co-seismic deformation signals were not included in the stacking and analysis. The changes in the ground deformation pattern and rate were identified. The main changes occur between 2000 and 2005 and include increasing deformation rate in the recharge zone and decreasing deformation rate in the western part of the CPGF production zone. We suggested that these changes are mainly caused by production development in the Cerro Prieto Geothermal Field.

  19. 75 FR 74640 - International Fisheries; South Pacific Tuna Fisheries; Procedures To Request Licenses and a...

    Science.gov (United States)

    2010-12-01

    ... partner or partners and indicating the Party's or Parties' approval of the joint venture arrangement and... engaged in ``joint venture'' arrangements designed to maximize the benefits generated for the PIPs. The... between joint venture licenses (licenses for fishing activities designed to maximize the...

  20. CANDU 9-meeting evolving safety and licensing requirements

    International Nuclear Information System (INIS)

    To date the safety and licensing experience with CANDU has been good, with plants successfully licensed and operating safely both domestically and in other countries. Nevertheless it is now clearly recognized that the utilities need more formal evidence that the licensing risk is low, if they are to proceed with new nuclear power projects. The CANDU 9 is an evolutionary design generating over 900 MWe. It is based on already-operating CANDUs, with improvements in the areas of construct ability, economics, plant layout, operations and maintenance, and safety. Even so, both domestic and foreign potential users require evidence of safety and licensability in Canada as of 'today'. For CANDU 9, this involves two main activities : · incorporation by designers not just of new Canadian safety regulations, but also of world trends in areas such as severe accidents and human factors, and · a two-year formal intensive review by the Canadian regulatory agency, the AECB (Atomic Energy Control Board) which will end in January 1997, with a first report mid-1996. In the severe accident area, CANDU 9 has improved the ability of the water-filled shield tank to act as a 'core catcher' for accidents such as a combined failure of the reactor cooling system piping, plus loss of emergency core cooling, plus loss of the moderator as a backup heat sink. A reserve water tank supplies sufficient water to the shield tank to remove decay heat and prevent melt-through. The licensing review documents encompass all of the Safety Design Guides, Design Requirements and flowsheets of the major systems, a preliminary Safety Analysis Report, a preliminary Probabilistic Safety Assessment, a Human Factors Engineering Programme Plan, the procedures for producing safety-critical software, and others. The licensing review scope includes comparison of the design and safety assessment results with current Canadian licensing requirements. The review will be complete once there is a finding that there are 'no

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-09-15

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

  2. Decision of decommissioning and license renewal

    International Nuclear Information System (INIS)

    This paper describes the concept in judging the decommissioning or license renewal of a nuclear power plant. As for the criteria for decision, it is important to have the recognition that the problem is that the type and design concept of whole facilities including reactor itself, design standards, and material specifications are out of date, not because that equipment is decrepit. This paper takes up Tsuruga Unit 1 reactor, which adopted Japan's sole BWR/2 reactor type, as an example, and analyzed the factors for that when a loss-of-coolant accident (LOCA) has happened, the reactor core is stripped of everything in a very short time, assuming from the material specifications and multiplex design at the time of construction. This paper points out the following problems: (1) existence of superiority and inferiority among generations depending on the evolution of basic design, (2) loose standards/criteria at the time of construction, and (3) non-establishment of standard design at the initial stage of construction. It also introduces the failed example of license renewal that was attempted through remodeling, by referring to the example of a power plant in the United States, and advices that we should be prudent for the renewal. (A.O.)

  3. A Developers Bill of Rights: What Open Source Developers Want in a Software License

    OpenAIRE

    MacCormack, Alan

    2007-01-01

    In this paper, we study open source developers' perspectives on the nature and structure of software licenses as well as the processes through which these licenses are designed. Recent history has shown that software licensing approaches are critical to the dynamics of the software industry and the open source ecosystem, and thus of interest to the many policy makers and practitioners that follow this part of the global economy. The study is timely, since it informs the debate on the revision...

  4. Validation and licensing of intelligent software

    International Nuclear Information System (INIS)

    The potential benefits of using artificial intelligence (AI) technology will only be realized if AI systems can be validated and successfully licensed. The issues associated with these systems are part of the wider problems of validation and licensing of computer systems in nuclear power plants. The plant considers the role of AI systems in plant safety and recommends the development of appropriate standards or guidelines. It considers the issues which need to be addressed in developing such documents. These include the need for design guidelines which restrict architectures and extend conventional safety engineering to AI and to limit the role of certain types of AI system. The issues addressed by the corresponding development guidelines include the validation of the reference engine, the problem of justifying the calculus used for reasoning under uncertainty, the role of logics versus heuristics, and the need to have formally defined semantics for the development process. The particular problems of real time systems are briefly mentioned together with the problems of distributed decision making. The paper concludes that there are many issues to be resolved if AI systems are to be successfully licensed. Some of these can be addressed by adapting existing guidelines, some require the definition of current good practice in the AI field and others must await the results of research. The paper recommends that research and standardization initiatives should be undertaken to ensure that nuclear power plants will benefit fully from AI technology. (author). 17 refs

  5. Licensed operating reactors

    International Nuclear Information System (INIS)

    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. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  6. License restrictions at Barnwell

    Energy Technology Data Exchange (ETDEWEB)

    Autry, V.R. [S.C. Dept. of Health and Environmental Control, Columbia, SC (United States). Bureau of Radiological Health

    1991-12-31

    The State of South Carolina was delegated the authority by the US Nuclear Regulatory Commission to regulate the receipt, possession, use and disposal of radioactive material as an Agreement State. Since 1970, the state has been the principal regulatory authority for the Barnwell Low-Level Waste Disposal Facility operated by Chem-Nuclear Systems, Inc. The radioactive material license issued authorizing the receipt and disposal of low-level waste contains numerous restrictions to ensure environmental protection and compliance with shallow land disposal performance criteria. Low-level waste has evolved from minimally contaminated items to complex waste streams containing high concentrations of radionuclides and processing chemicals which necessitated these restrictions. Additionally, some waste with their specific radionuclides and concentration levels, many classified as low-level radioactive waste, are not appropriate for shallow land disposal unless additional precautions are taken. This paper will represent a number of these restrictions, the rationale for them, and how they are being dealt with at the Barnwell disposal facility.

  7. Licensed operating reactors

    International Nuclear Information System (INIS)

    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 are 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. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  8. VEHICLES LICENSED IN SWITZERLAND

    CERN Multimedia

    Service des Relations avec les Pays-Hôtes

    2000-01-01

    1.\tVehicle licensinga)\tTime limitsVehicles must have a Swiss registration document and Swiss number plates: -\tif the owner has been residing in Switzerland for more than one year without a break of more than three consecutive months and has been using it for more than one month on Swiss territory, or -\tif the vehicle itself has been on Swiss territory for more than one year without a break of more than three consecutive months. b)\tTechnical details Vehicles belonging to non-Swiss members of the personnel who hold a carte de légitimation issued by the Swiss Federal Department of Foreign Affairs (hereinafter referred to as 'DFAE') and who were not permanently resident in Switzerland before taking up their appointment may be licensed in Switzerland with virtually no restrictions provided that their owner produces: -\tthe vehicle registration document and number plates of the country in which the car was previously registered, or -\ta manufacturer's certi...

  9. 10 CFR 50.52 - Combining licenses.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Combining licenses. 50.52 Section 50.52 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance, Limitations, and Conditions of Licenses and Construction Permits § 50.52 Combining licenses. The Commission may combine in...

  10. Unionization Structure, Licensing and Innovation

    OpenAIRE

    Mukherjee, Arijit; Pennings, Enrico

    2005-01-01

    This discussion paper led to a publication in the 'International Journal of Industrial Organization', 29(2), 232-41.Taking technological differences between firms as given, we show that the technologically advanced firm has a stronger incentive for technology licensing under a decentralized unionization structure than with centralized wage setting. Furthermore, We show that, in presence of licensing, the incentive for innovation may also be stronger under decentralized unions. Unions have a c...

  11. 7 CFR 51.34 - Suspension or revocation of license of a licensed inspector.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 2 2010-01-01 2010-01-01 false Suspension or revocation of license of a licensed... revocation of license of a licensed inspector. Pending final action by the Secretary, the Administrator may..., supported by any argument or evidence that he may wish to offer as to why his license should not...

  12. Evaluation of Terminated Nuclear Material Licenses

    International Nuclear Information System (INIS)

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

  13. AUTOMATIC LICENSE PLATE LOCALISATION AND IDENTIFICATION VIA SIGNATURE ANALYSIS

    Directory of Open Access Journals (Sweden)

    Lorita Angeline

    2014-02-01

    Full Text Available A new algorithm for license plate localisation and identification is proposed on the basis of Signature analysis. Signature analysis has been used to locate license plate candidate and its properties can be further utilised in supporting and affirming the license plate character recognition. This paper presents Signature Analysis and the improved conventional Connected Component Analysis (CCA to design an automatic license plate localisation and identification. A procedure called Euclidean Distance Transform is added to the conventional CCA in order to tackle the multiple bounding boxes that occurred. The developed algorithm, SAICCA achieved 92% successful rate, with 8% failed localisation rate due to the restrictions such as insufficient light level, clarity and license plate perceptual information. The processing time for a license plate localisation and recognition is a crucial criterion that needs to be concerned. Therefore, this paper has utilised several approaches to decrease the processing time to an optimal value. The results obtained show that the proposed system is capable to be implemented in both ideal and non-ideal environments.

  14. Using the RM-ODP to express the nuclear licensing process

    International Nuclear Information System (INIS)

    Although some specific requirements in any licensing procedures of nuclear installations are not discussed by Brazilian Government, it is clear the basic requirements and recommendations that must be met to ensure design and acquisition control activities, to provide a good understanding of licensing procedures of those installations. Qualified Supplies, System Responsible, Licensing Requirers and others Members States might establish one federation in ODP (Open Distributed Process) for supporting licensing procedures. This work outlines concepts of RM-ODP (Reference Model of Open Distributed Process) to characterization of nature of interactions in this context to improve the confidence and the flexibility to support the regulatory decisions. (author)

  15. Extent and distribution of aseismic slip on the Ismetpaşa segment of the North Anatolian Fault (Turkey) from Persistent Scatterer InSAR

    KAUST Repository

    Cetin, Esra

    2014-07-01

    We use the Persistent Scatterer InSAR (PSI) technique with elastic dislocation models and geology along the creeping section of the North Anatolian Fault (NAF) at Ismetpaşa, to map and deduce the velocity field and the aseismic slip distribution. Revealing the spatiotemporal nature of the creep helped us associate the creep with potential lithological controls, hence providing a new perspective to better understand the underlying causes and mechanisms. The PSI analysis of Envisat ASAR images between 2003 and 2010 reveals a clear picture of surface creep along the fault and a new interseismic velocity field transitioning gradually between the creeping and the locked fault sections. The creep rate is found to fluctuate along a 100 km long section of the fault in a manner similar to that along the Hayward fault, reaching a maximum of ∼20±2 mm/yr, close to the far field plate velocity (∼25±1.5 mm/yr). At Ismetpaşa, it is in the range of 8±2 mm/yr, consistent with the previous geodetic observations. The creeping section appears to extend 30 km further east than those previously reported. Modeling of the PSI data reveals a heterogeneous creep distribution at depth with two main patches confined mostly to the uppermost 5 km portion of the seismogenic crust, releasing annually 6.2 × 1016 Nm (Mw=5.1) geodetic moment. Our analysis combined with previous studies suggests that creep might have commenced as postseismic deformation following the 1944 earthquake and has evolved to stable fault creep with time. There is a correlation between aseismic surface creep and the geology along the fault as it is in major part associated to rocks with low frictional strength such as the andesitic-basaltic, limestone, and serpentine bodies within the fault zone. © 2014. American Geophysical Union. All Rights Reserved.

  16. The Prevalence and Effects of Occupational Licensing. NBER Working Paper No. 14308

    Science.gov (United States)

    Kleiner, Morris M.; Krueger, Alan B.

    2008-01-01

    This study provides the first nation-wide analysis of the labor market implications of occupational licensing for the U.S. labor market, using data from a specially designed Gallup survey. We find that in 2006, 29 percent of the workforce was required to hold an occupational license from a government agency, which is a higher percentage than that…

  17. Systems approach to developing and implementing an HLW licensing process

    International Nuclear Information System (INIS)

    Developing and licensing a repository for the disposal of high-level nuclear waste (HLW) is an important national goal. Congress reaffirmed this goal by the passage of the Nuclear Waste Policy Amendments Act (NWPAA) in December 1987. In addition to designating Yucca Mountain in Nevada as the sole site to undergo characterization, it authorized a monitored retrievable storage facility (MRS) and created a negotiator, a technical review board, and other entities whose efforts are directed to provide greater certainty in the nation's ability to manage its HLW. Responsibility for the formal licensing process for the life of the repository is assigned by law to the US Nuclear Regulatory Commission (NRC). In October of 1987, the NRC established the Center for Nuclear Waste Regulatory Analysis as a federally funded research and development center to assist in fulfilling its licensing mission with regard to HLW. The broad objective of the center is to assist the NRC in identifying and recommending solutions for technical, regulatory, and institutional uncertainties to ensure timely and credible completion of the licensing process. To meet this objective, the center is currently developing a systems approach to implement and streamline the HLW licensing process. This paper describes the basic systems approach and the design process and provides a status on the initial efforts of the center to develop this system

  18. 76 FR 31616 - Government-Owned Inventions; Availability for Licensing

    Science.gov (United States)

    2011-06-01

    ... model. Radiology 2006 Apr;239(1);86-93. Licensing Status: Available for licensing. Licensing Contacts...@mail.nih.gov . Collaborative Research Opportunity: The NIH Clinical Center, Interventional...

  19. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    The guide applies to the nuclear power plant operator licensing procedure referred to the section 128 of the Finnish Nuclear Energy Degree. The licensing procedure applies to shift supervisors and those operators of the shift teams of nuclear power plant units who manipulate the controls of nuclear power plants systems in the main control room. The qualification requirements presented in the guide also apply to nuclear safety engineers who work in the main control room and provide support to the shift supervisors, operation engineers who are the immediate superiors of shift supervisors, heads of the operational planning units and simulator instructors. The operator licensing procedure for other nuclear facilities are decided case by case. The requirements for the basic education, work experience and the initial, refresher and complementary training of nuclear power plant operating personnel are presented in the YVL guide 1.7. (2 refs.)

  20. NRC licensing requirements: DOD options

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-09-01

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

  1. NRC licensing requirements: DOD options

    International Nuclear Information System (INIS)

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

  2. Technology Licensing and Firm Innovation

    DEFF Research Database (Denmark)

    Moreira, Solon

    Although licensing has repeatedly been acknowledged to be a major vehicle for firms to acquire external knowledge, surprisingly little is known about how firms use it as part of their overall inventive efforts. Furthermore, with the exception of absorptive capacity, the organizational determinants...... relationship. The findings also suggest that high levels of Organizational Slack (available financial resources) strengthen the positive effect of licensing on innovation. However, higher levels of Organizational Myopia (the extent to which a firm draws on its own knowledge) can decrease the main effect of...

  3. Mock Site Licensing Demonstration Project. Final report

    International Nuclear Information System (INIS)

    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

  4. Licensing of future LWRs

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission (NRC) expects that advanced reactors will provide enhanced margins of safety and that new nuclear power plants will achieve a higher standard of severe accident safety performance than previous reactor designs. Also, the NRC requires that the performance of new safety features be demonstrated by tests, analyses, or a combination thereof. Accordingly, the NRC developed new review standards for future nuclear plant designs based on operating experience, including the accident at Three Mile Island; the results of probabilistic risk assessments; early efforts on severe accident rulemaking; and research conducted to address previously identified generic safety issues. These new standards were used during the design certification reviews performed by the NRC in the 1990's and the resolutions are documented in the NRC's final safety evaluation reports. (authors)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  7. Modeling reasons for Russian bank license withdrawal: Unaccounted factors

    OpenAIRE

    Peresetsky , Anatoly

    2013-01-01

    In the paper we analyze the reasons of Russian bank license withdrawal, formulated in orders of CB RF at the period 2005.2–2008.4. During this period, after establishing deposit insurance system in Russia, two main reasons were «money laundering» and «financial insolvency». We design binary choice logit models and multinomial logit models to model probability of license withdrawal one year ahead of the event. We use in model macro indicators to control for the varying economic environment and...

  8. Practical issues in structuring seismic licensing and acquisition contracts

    International Nuclear Information System (INIS)

    Some of the key subjects addressed in the International Association of Geophysical Contractors' (IAGCs') Contract Manual concerning the structuring of seismic licences are explained. The IAGC is the international trade association of the seismic industry headquartered in Houston, Texas. The manuals (i.e. U.S. and International) were designed to provide users with some basic, useful guidelines regarding contracts and licenses. This paper described the structure of the manuals and reviewed some key contract clauses such as liability/indemnity, permitting, contractor's rights, conflict resolution and applicable laws (important in the case of international licenses)

  9. Review of licensing criteria for soil-structure interaction analysis

    International Nuclear Information System (INIS)

    In June 1986 the US Nuclear Regulatory Commission (NRC) sponsored a workshop to discuss the licensing criteria in one area of soil-structure interaction (SSI) analysis. This paper discusses some of the key findings, issues, and recommendations emerging from the workshop. Emphasis is on how the workshop was used as an input to the on-going activities related to the resolution of Unresolved Safety Issue (USI) A-40, Seismic Design Criteria. Under these activities, the NRC staff is proposing a revision to its SSI licensing criteria. The proposed changes and their basis are highlighted. (author)

  10. Managing Licensing in a Market for Technology

    DEFF Research Database (Denmark)

    Arora, Ashish; Fosfuri, Andrea; Rønde, Thomas

    2013-01-01

    valuable licensing opportunities because the rewards for licensing are (optimally) weaker than those for product market profits. This distortion is stronger when production-based incentives, especially private benefits, of business unit managers are more powerful, making centralization more attractive......Technology licensing is an important means for companies to extract more value from their intellectual assets. We build a model that helps understand how licensing activity should be organized within large corporations. More specifically, we compare decentralization—where the business unit using...... the technology makes licensing decisions—to centralized licensing. The business unit has superior information about licensing opportunities but may not have the appropriate incentives because its rewards depend on product market performance. If licensing is decentralized, the business unit forgoes...

  11. Guide to request license for teletherapy practice

    International Nuclear Information System (INIS)

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

  12. List of Nuclear Materials Licensing Actions Received

    Data.gov (United States)

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

  13. Scallop License Limitation Program (SLLP) Permit Program

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — A federal Scallop License Limitation Program (SLLP) license is required onboard any vessel deployed in scallop fisheries in Federal waters off Alaska (except for...

  14. Reports of the Technical Assessment Task Force on selection, training, qualification, and licensing of Three Mile Island reactor operating personnel; technical assessment of operating, abnormal, and emergency procedures; control room design and performance

    International Nuclear Information System (INIS)

    As a part of the effort to identify and evaluate the possible causes of the Three Mile Island accident, an analysis of operator training, qualification, licensing, selection, and manning was conducted by the staff. The study included review of documents, interviews, and depositions at Three Mile Island, Babcock and Wilcox, and the Nuclear Regulatory Commission (NRC) during June, July, and August 1979. Analysis of the information obtained was conducted almost exclusively by the writer. This paper examines the roles of the actors involved in training and it reviews the various programs which were intended to staff Three Mile Island with sufficient numbers of competent, trained operators and supervisors. The analysis includes a review of the regulations concerning operator training and licensing; describes how the requirements were implemented by the NRC, Metropolitan Edison Company (Met Ed), and Babcock and Wilcox Company (B and W), and then evaluates the programs conducted by these three organizations

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

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

    International Nuclear Information System (INIS)

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

  17. Environmental licensing issues for cogeneration plants

    International Nuclear Information System (INIS)

    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

  18. Legal Challenges to Licensing Examinations.

    Science.gov (United States)

    Pyburn, Keith M., Jr.

    1990-01-01

    Discrepancies between court and professional association views of licensing examinations are discussed. Litigation associated with Title VII of the Civil Rights Act of 1964 and constitutional law is considered. Courts should examine professional standards and apply those that are consistent with the court's determination of the proper…

  19. Natural analog studies: Licensing perspective

    Energy Technology Data Exchange (ETDEWEB)

    Bradbury, J.W. [Nuclear Regulatory Commission, Washington, DC (United States)

    1995-09-01

    This report describes the licensing perspective of the term {open_quotes}natural analog studies{close_quotes} as used in CFR Part 60. It describes the misunderstandings related to its definition which has become evident during discussions at the U.S Nuclear Regulatory Commission meetings and tries to clarify the appropriate applications of natural analog studies to aspects of repository site characterization.

  20. 25 CFR 11.601 - Marriage licenses.

    Science.gov (United States)

    2010-04-01

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

  1. Operation of Trades Licensing Office after the amendment of Trades Licensing Act

    OpenAIRE

    Neužilová, Barbora

    2011-01-01

    My work "Operation of Trades Licensing Office after amendement of the Trades Licensing Act" deals with valid legal regulation of the Trade Licensing Act, which the officers follow. My work is divided into two parts. The first part contains the valid legal regulation. Here I analyse not only the Trades Licensing Act, but also the law about Trades Licensing Offices. Further, the practical part follows. At the beginnning of the practical part of my work I describe the operations of the rele...

  2. ACR-1000 Project - Licensing Opportunities and Challenges

    International Nuclear Information System (INIS)

    Full text: 1000 (ACR-1000) as an evolutionary advancement of the current CANDU 6 reactor. The ACR-1000 design has evolved from AECL's in-depth knowledge of CANDU systems, components, and materials, as well as the experience and feedback received from owners and operators of CANDU plants. The ACR design retains the proven strengths and features of CANDU reactors, while incorporating innovations and state-of-the-art technology. It also features major improvements in economics, inherent safety characteristics, and performance, while retaining the proven benefits of the CANDU family of nuclear power plants. The Canadian nuclear reactor design evolution that has reached today's stage represented by the ACR-1000 as described above, has a long history dating back to the early 1950s. In this regard, Canada is in a unique situation, shared only by a very few other countries, where original nuclear power technology has been invented and further developed. With the Canadian nuclear technology development, in parallel, the development of Canadian regulations and licensing processes took place. This latter development was carried out by the Atomic Energy Control Board (AECB), established in 1946. The AECB mandate, originally focused on security, and later extended to include nuclear safety, was focused on regulating the nuclear sector, establishing health and safety regulations, and also played an instrumental role in forming the International Atomic Energy Agency (IAEA). The AECB, which preceded the Canadian Nuclear Safety Commission (CNSC), established in 2000, licensed all CANDU power reactors in Canada and provided assistance to the overseas regulatory authorities in licensing of CANDU reactors in Korea, Argentina, China and Romania. The regulatory framework in Canada is currently in a period of change. The CNSC is further developing its requirements for new reactor designs in Canada whilst at the same time AECL development of the ACR design. This situation has created

  3. Managing Licensing in a Market for Technology

    DEFF Research Database (Denmark)

    Arora, Ashish; Rønde, Thomas; Fosfuri, Andrea

    Over the last decade, companies have paid greater attention to the management of their intellectual assets. We build a model that helps understand how licensing activity should be organized within large corporations. More specifically, we compare decentralization—where the business unit using the...... technology makes licensing decisions—to centralized licensing. The business unit has superior information about licensing opportunities but may not have the appropriate incentives because its rewards depend upon product market performance. If licensing is decentralized, the business unit forgoes valuable...... licensing opportunities since the rewards for licensing are (optimally) weaker than those for product market profits. This distortion is stronger when production-based incentives are more powerful, making centralization more attractive. Growth of technology markets favors centralization and drives higher...

  4. Licensing plan for UMTRA project disposal sites

    International Nuclear Information System (INIS)

    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

  5. IRIS. Progress in licensing and toward deployment

    International Nuclear Information System (INIS)

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

  6. Expert judgment in NRC licensing proceedings and its impact on the regulatory decision-making process

    International Nuclear Information System (INIS)

    Expert judgment will be widely used in the site characterization, repository performance assessment and the licensing of a high-level radioactive waste repository. Technical expert judgment relates to the consideration of parameters for which little or no experimental data exists. The use of technical expert judgment in repository performance assessment is intended to complement and interpret available data rather than to substitute for technical data and scientific information. Decision-maker expert judgment will be used on the other hand by the NRC or by the Hearing Licensing Board to choose among conflicting technical expert judgments during licensing hearings or review, and gauge the limitations in scientific understanding of repository performance. This paper examines the use of expert judgment by the Atomic Safety and Licensing Board on the proper seismic and geologic design bases in the show cause licensing proceeding for the restart of the Vallecitor - General Electric Test Reactor

  7. European ITER site studies: Lessons learnt in safety and licensing

    International Nuclear Information System (INIS)

    On June 28th 2005, an agreement was reached among the ITER parties on the selection of EU Site of Cadarache in France. In consequence, the ITER generic site safety assessments had to be adapted to the French requirements in order to get the required license. It is precisely in this point that Europe has been working through the European ITER Site Studies contract framework. The main objective: to contribute to the ITER Organization to fulfill in time the deliverable of licensing files to the French authorities. This paper details the gained lessons by the organizations involved in the writing of supporting studies for these licensing files. The lessons learnt tackle a very wide range of technical and strategic aspects, some of them never considered before for a fusion facility. It could be mentioned, for instance, the application of international codes and standards to typical fusion components, the integration of the approach for accident evaluation, the compilation of safety feed-back from fusion experiments, the definition of waste treatment strategies or the incorporation of the human factor in design and operation among others. The effort has involved EFDA, the current F4E organization, EURATOM associations and European industries. Two facts have made specially challenging the task of support the licensing process: ITER being the first fusion reactor to be licensed as Installation Nucleaire de Base and the entry in force of a new nuclear regulation in France. So original and challenging scenario has lead to adaptation strategies and innovative for fusion approaches in safety and licensing studies. (author)

  8. 10 CFR 32.51 - Byproduct material contained in devices for use under § 31.5; requirements for license to...

    Science.gov (United States)

    2010-01-01

    ...) Operating experience with identical devices or similarly designed and constructed devices. (c) In the event... NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES TO MANUFACTURE OR TRANSFER CERTAIN...

  9. Licensing of the Australian replacement research reactor

    International Nuclear Information System (INIS)

    The Australian Nuclear Science and Technology Organisation (ANSTO)'s Replacement Research Reactor has been submitted to a comprehensive licensing process of which peer review has been a fundamental part. Following Australian Regulation, an application for a site licence was the first step supported by an Environmental Impact Statement approved by The Minister for the Environment and Heritage, and a Reference Accident Analysis. After the site licence had been granted and the contract awarded to the Designer and Constructor, INVAP S.E:, a 2500 page Preliminary Safety Analysis Report was submitted by ANSTO to the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA), which conducted its review. ARPANSA requested that the PSAR be also reviewed by an experts mission from the International Atomic Energy Agency. The PSAR was also reviewed by the Argentine Regulatory Body, it was submitted to public examination in Australia and it was reviewed by international experts hired as consultants by several Australian organisations. A public forum was also held in Sydney. The Regulator, the applicant and the Designer-Constructor maintained constant interaction during the whole process, so that questions, comments and observations that arose from the review of the PSAR were fed back to the designers. This process allowed for a robust, safe design enriched by the results of the safety analysis and review process. (author)

  10. Evaluation of aseismic integrity in HTTR core-bottom structure. Pt. 3. Structural integrity of core support post component

    International Nuclear Information System (INIS)

    Component testing of the core support post for the high temperature engineering test reactor (HTTR) was carried out to verify its structural integrity using full-scale and (1)/(2)-scale models. The compressive fracture load was measured at room temperature under the conditions of post inclination up to about 1 degree, cyclic load up to 200 times and oxidation up to about 30% of oxidation weight-loss. In this paper, the effects of post inclination angle, cyclic load and oxidation weight-loss of this component on the compressive fracture load were discussed and the fracture load was compared with the design load of the HTTR. ((orig.))

  11. Set of criteria for licensing procedures

    International Nuclear Information System (INIS)

    A general model of licensing procedures thought to be the most appropriate for small countries is discussed. Because of the similarities in the administration and economy of small countries, the licensing process proceeds on a step-by-step basis and the licensing procedures, as one of the steps in the is process, consists of two parts: a pre-licensing period and the main part, i.e. issuing of the license. A detailed discussion of the directives of the nuclear authority for the selection of the site for a nuclear facility is provided, together with some remarks on the directives for the other licensing procedures. The licensee has to provide a special answer in a specific case which need not agree strictly with the general directives. However, the licensee is required to give a detailed explanation of the other case. (author). 4 figs

  12. 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.

  13. Technology Spillover and Licensing Strategy of Patentee

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    The optimal license proportions with and without technology spillover are analyzed with a game-theoretical approach when a patent-holding firm licensed non-drastic process innovation to his incumbent rivals by means of a first price sealed bid auction. The optimal strategy is obtained through solving the game by backward induction. It is found that the range of optimal license proportion is narrower when there is spillover compared to the no spillover case.

  14. Licensing documentation and licensing process for dismantling and decontamination projects in Lithuania

    Energy Technology Data Exchange (ETDEWEB)

    Uspuras, Eugenijus; Rimkevicius, Sigitas; Babilas, Egidijus [Lithuanian Energy Institute (LEI), Kaunas (Lithuania)

    2013-07-01

    One of the main tasks of any decommissioning project is the licensing process which allows implementation of developed strategies in real NPP. The Lithuanian laws on nuclear energy and on radioactive waste management require that the dismantling and decontamination (D and D) projects shall be licensed by the Lithuanian State Nuclear Power Safety Inspectorate (VATESI) and other Authorities. Licensing is an inseparable part of the Lithuania regulatory and supervisory system for safety of nuclear facilities. The licensing process starts when NPP submits the first licensing document(s) to the Authorities. It is completed when all the licensing documents are approved by the Authorities and authorization to start D and D works is received by NPP. Current paper will discuss one of the main steps in D and D projects implementation process - Licensing and will provide information about D and D licensing approach used in Lithuania. (orig.)

  15. Licensing documentation and licensing process for dismantling and decontamination projects in Lithuania

    International Nuclear Information System (INIS)

    One of the main tasks of any decommissioning project is the licensing process which allows implementation of developed strategies in real NPP. The Lithuanian laws on nuclear energy and on radioactive waste management require that the dismantling and decontamination (D and D) projects shall be licensed by the Lithuanian State Nuclear Power Safety Inspectorate (VATESI) and other Authorities. Licensing is an inseparable part of the Lithuania regulatory and supervisory system for safety of nuclear facilities. The licensing process starts when NPP submits the first licensing document(s) to the Authorities. It is completed when all the licensing documents are approved by the Authorities and authorization to start D and D works is received by NPP. Current paper will discuss one of the main steps in D and D projects implementation process - Licensing and will provide information about D and D licensing approach used in Lithuania. (orig.)

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

    International Nuclear Information System (INIS)

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

  17. Analysis of the morphology and deformation of the collision zone between the Muertos thrust belt and the aseismic Beata Ridge in the NE Caribbean plate

    Science.gov (United States)

    Granja Bruña, J.; Carbo-Gorosabel, A.; Llanes Estrada, M.; Munoz Martin, A.; Druet, M.; Gómez, M.; ten Brink, U. S.; Vitolla, M.

    2010-12-01

    The Beata Ridge is an aseismic bathymetric high located in the center of the Caribbean plate whose evolution is not yet well understood. The present collision between the Beata Ridge and the island arc at the Hispaniola island region may be driven by a small N-S component of compression. The basin-and-range physiography of southern Hispaniola, the turn and termination of the Muertos thrust belt and the surprisingly sharp termination of the Enriquillo-Plantain Garden Fault Zone seem to be related with this collision process. Swath bathymetry data and reflection seismic profiles acquired during the 2009 CARIBENORTE cruise aboard the Spanish R/V Hesperides, together with reprocessed multichannel seismic profiles provide the basis of the analysis of the morphology and deformation of the western end of the Muertos thrust belt and the northern aseismic Beata Ridge. The 650 km-long Muertos thrust belt turns progressively from E-W to N and then becomes narrower and disappears in the collision zone with the NNE-SSW trending Beata Ridge. The collision is evidenced because the active Muertos thrust belt has a southward transport direction and the NNE-SSW trending Beata Ridge acts as a basement high in the foreland area. The deep and elongated Muertos Trough located at the toe of the thrust belt, becomes narrower and progressively shallower and then sharply disappears at 70.9W and 18.1N. Both the thrust belt and the trough are replaced westward by a steep insular slope characterized by a dense network of submarine canyons draining to the south and east from the Bahoruco peninsula and the Ocoa and Azua Bays. The northern Beata Ridge shows a strongly asymmetrical cross-shape, with a main steep fault-scarp showing a maximum bathymetrical step of 4300 m-high in the western side and a gentler eastern slope formed by an alternation of terraces, interior basins and subsidiary ridges. Generally subsidiary ridges are N-S trending and then sub-parallel to the NNE-SSW trending main

  18. Initiatives in transport cask licensing

    International Nuclear Information System (INIS)

    The variations in research reactor fuel form, configuration, irradiation characteristics, and transport cask have required a substantial number of transport cask licensing actions associated with foreign research reactor spent fuel transportation. When compounded by limited time for shipment preparations, due to contract timing or delayed receipt of technical data, the number and timing of certifications has adversely impacted the ability of regulatory agencies to support intended shipping schedules. This issue was brought into focus at a april, 1998 meeting among DOE, the US Nuclear Regulatory Commission, and DOE's spent fuel transportation contractors. (author)

  19. Vehicle License Plate Recognition Syst

    Directory of Open Access Journals (Sweden)

    Meenakshi,R. B. Dubey

    2012-12-01

    Full Text Available The vehicle license plate recognition system has greater efficiency for vehicle monitoring in automatic zone access control. This Plate recognition system will avoid special tags, since all vehicles possess a unique registration number plate. A number of techniques have been used for car plate characters recognition. This system uses neural network character recognition and pattern matching of characters as two character recognition techniques. In this approach multilayer feed-forward back-propagation algorithm is used. The performance of the proposed algorithm has been tested on several car plates and provides very satisfactory results.

  20. Vehicle License Plate Recognition System

    Directory of Open Access Journals (Sweden)

    Meenakshi

    2012-12-01

    Full Text Available The vehicle license plate recognition system has greater efficiency for vehicle monitoring in automatic zone access control. This Plate recognition system will avoid special tags, since all vehicles possess a unique registration number plate. A number of techniques have been used for car plate characters recognition. This system uses neural network character recognition and pattern matching of characters as two character recognition techniques. In this approach multilayer feed-forward back-propagation algorithm is used. The performance of the proposed algorithm has been tested on several car plates and provides very satisfactory results.

  1. Initiatives in transport cask license

    Energy Technology Data Exchange (ETDEWEB)

    Patterson, John [NAC International, Aiken, SC (United States). Foreign Research Reactor Liaison]. E-mail: nacaiken@aol.com

    1998-07-01

    The variations in research reactor fuel form, configuration, irradiation characteristics, and transport cask have required a substantial number of transport cask licensing actions associated with foreign research reactor spent fuel transportation. When compounded by limited time for shipment preparations, due to contract timing or delayed receipt of technical data, the number and timing of certifications has adversely impacted the ability of regulatory agencies to support intended shipping schedules. This issue was brought into focus at a april, 1998 meeting among DOE, the US Nuclear Regulatory Commission, and DOE's spent fuel transportation contractors. (author)

  2. Status of activities on the unresolved licensing issues for HANARO

    International Nuclear Information System (INIS)

    HANARO is a light-water-cooled and heavy-water-reflected research reactor designed to be operated at full power of 30 MWth. When the reactor operating license was issued for HANARO in 1995, there were imposed two licensing conditions related to its rated operating power; the fuel power rating and the CHF prediction. The HANARO fuel design was based on AECL's tests in NRU. The Korean Institute of Nuclear Safety (KINS) requires KAERI to get more experimental data at higher linear heat rates which would prove the fuel integrity. For the analysis of CHF during steady state and transient events, COBRA-IV-I/KMRR was used. KINS requires KAERI to perform the further validation of the CHF analysis method. In this paper, the status of activities to resolve these issues and the future plans are described. (author)

  3. Texas site selection and licensing status

    Energy Technology Data Exchange (ETDEWEB)

    Avant, R.V. Jr.

    1989-11-01

    Texas has identified a potential site in Hudspeth County in far West Texas near the town of Fort Hancock. Over the past year the Texas Low-Level Radioactive Waste Disposal Authority has been conducting detailed geology, hydrology, meteorology, soils, and flora and fauna evaluations. An authorization by the Board of Directors of the Authority to proceed with a license application, assuming that the detailed evaluation indicates that the site is suitable, is expected by September. A prototype license has been prepared in anticipation of the order to proceed with licensing, and the formal license application is expected to be submitted to the Texas Department of Health-Bureau of Radiation Control in December, meeting the license application milestone. Although site selection processes in all siting areas across the country have experienced organized opposition, El Paso County has funded a particularly well-organized, well-financed program to legally and technically stop consideration of the Fort Hancock site prior to the licensing process. Many procedural, regulatory, and technical issues have been raised which have required responses from the Authority in order to proceed with licensing. This has provided a unique perspective of what to expect from well-organized opposition at the licensing stage. This paper presents an update on the Texas siting activity with detailed information on the site evaluation and license application. Experience of dealing with issues raised by opposition relating to NRC guidelines and rules is also discussed.

  4. Licensing to Market with Logit Demand Functions

    Institute of Scientific and Technical Information of China (English)

    YAN Qing-you; ZHU Li-li

    2009-01-01

    This paper studies the licensing of a brand innovation to a monopoly in an uncovered market characterized by a logit demand framework. The innovator is an outsider to the market and sells the license via fixed-fee, royalty or their combinations. It is shown that the license occurs irrespective of whether the utility of the new brand is improved or not, and that the optimal licensing policy for the innovator is fixed-fee only. Ultimately, the monopoly produces both the old and the new brand products, even in the case of utility-improving brand innovation. In addition, the incentive for the innovator was examined.

  5. Licensing Electronic Content in Today's Information Marketplace

    Science.gov (United States)

    Okerson, Ann

    This session will develop topics such as: what is a license, what is a shrinkwrap license and is it binding, how do licenses or contracts relate to national copyright laws, what is a good negotiating stance, what to look for in a license (key issues), and where to look for more information. The session will be outlined by a series of overheads that can help to guide the library professional who needs to work through these matters during the course of negotiating for electronic information content. The article contains the text of the transparencies shown during the presentation.

  6. Overview of the Yucca Mountain Licensing Process

    International Nuclear Information System (INIS)

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

  7. Licensing framework of storage for spent fuel installation in Indonesia

    International Nuclear Information System (INIS)

    Management, - CD No. 01/1999 on radiation safety, - CD No. 06 year 1999 on the Licensing Construction and Operation of Nuclear Reactor, - GR 63 year 2000 on Safety and Health against the utilization of Ionizing Radiation, - GR No. 27/2002 on radioactive waste management. CDRRT-BATAN has applied for a licence by submitting licensing documents to BAPETEN (at that time the Atomic Energy Control Bureau - BATAN). BAPETEN carried out the safety evaluations based on the regulation above. The licensing documents submitted include: safety analysis report; the quality assurance programme, related procedures (i.e. environmental monitoring, radioactive monitoring procedures, etc.), the emergency preparedness programme, Design Information Questionnaire (DIQ) and physical protection programme. Bapeten has carried out the safety evaluation based on the available guides and regulations. BAPETEN has gained considerable experience from previous related activities. BAPETEN has evaluated the Safety Analysis Report proposed by CDRRT and carried out inspections to check the safety of the TC-ISFSFI activities. This paper addresses present regulations related to spent fuel storage, including licensing system regulations. (author)

  8. Brand Licensing : Once you pop you can’t stop: When brand licensing goes too far

    OpenAIRE

    Dementev, Kirill; Lukyanchenko, Yuliya; Emilsson, Cecilia

    2011-01-01

    Purpose: The purpose of this study is to investigate consumer’s attitude towards licensed products in relation to the parent brand, with respect to perceived quality, likelihood to buy and associations’ transferability. Background: Brand licensing has become one of an increasingly popular ways of stretching a brand into new product categories to reach more consumers in new markets. Despite the fact that brand licensing is less risky than building a brand from scratch, the odds that licensed p...

  9. Upper Plate Deformation in Response to Aseismic Ridge Subduction along a Convergent Margin - the Piano Player Model: Osa Peninsula, Costa Rica

    Science.gov (United States)

    Gardner, T. W.; Fisher, D. M.; Morell, K. D.; Cupper, M. L.

    2008-12-01

    The Osa Peninsula, an outer forearc high ~20 km inboard of the Middle America Trench, is deforming in response to short wavelength variations in the bathymetry on the subducting aseismic Cocos Ridge, an elongate region of thickened crust ( up to 40% thicker) created by motion of the Cocos plate across the Galapagos Hotspot. Plate convergence is nearly orthogonal to the trench at ~90 mm/yr and the plate interface occurs at a depth ~5 km under the peninsula. Relief on the Cocos Ridge locally exceeds 1 km with the dominant topography expressed as two nearly parallel, but locally offset ridges separated by an axial graben. The strike of these features is sub-parallel to the convergence vector. Modern topography of the Osa Peninsula, elevation of the basement rocks (Early to Middle Tertiary Osa Mélange), elevations of late Quaternary marine deposits, and distribution of late Quaternary deformation rates directly mirror the bathymetry on the Cocos Ridge just outboard of the MAT. New geologic mapping, radiometric dating and fission track analysis constrain distribution and rates of deformation on the Osa Peninsula. The Osa Peninsula is fragmented into a complex set of blocks that vary in size from several kms on a side to 15 mm/yr directly inboard of subducting ridges to < -6 mm/yr directly inboard of axial grabens. These new results imply a model in which the thin, mechanically weak, outer margin, characterized by pervasive, penetrative, brittle deformation of the Osa Melange basement rocks, deforms directly in response to short wavelength, high-relief bathymetric features on the down going plate. In this case bathymetry dominates over basal traction in controlling deformation of the upper plate. Surface uplift or subsidence of the Osa Peninsula, is not significantly driven by shortening within the outer margin nor underplating or subduction erosion at the plate interface, but by the variations in bathymetry, relief, of the subducting Cocos Ridge.

  10. Time-dependent model of aseismic slip on the central San Andreas Fault from InSAR time series and repeating earthquakes

    Science.gov (United States)

    Khoshmanesh, M.; Shirzaei, M.; Nadeau, R. M.

    2015-09-01

    The Central segment of San Andreas Fault (CSAF) is characterized by a nearly continuous right-lateral aseismic slip. However, observations of the creep rate obtained using small characteristically repeating earthquakes (CREs) show pulses of creep along the CSAF, which may indicate spatially and temporally variable seismic hazard along the CSAF. Therefore, the goal of this study is to obtain a high-resolution time-dependent model of creep along the CSAF to examine this hypothesis. To this end, we apply a time-dependent creep modeling approach, which combines interferometric synthetic aperture radar (InSAR) surface deformation time series and observations of fault creep obtained from CREs. The SAR data set includes C band scenes acquired by the ERS-2 and Envisat satellites between 2003 and 2011. The resulting creep rate distribution implies a peak rate up to 32 mm/yr along the central part of the CSAF. Afterslip due to the 2004 Parkfield earthquake on the southeastern segment of the CSAF is also manifest in the model, and there is clear evidence of creep pulsing along strike and depth of the CSAF. Estimated annual rate of slip deficit accumulation is equivalent to a magnitude 5.6-5.7 earthquake. Taking advantage of the time-dependence of our model, we also refine the scaling relationship, which associates the released seismic moment due to a CRE event with the amount of creep on the fault, surrounding the CRE patches. This study provides the first kinematic model of creep pulsing, constrained using geodetic and seismic data, which can enhance time-dependent seismic hazard maps and improve earthquake operational forecast models.

  11. Aseismic magma supply inferred from geodetic Finite Element inversions: the case of the 2001-2002 non-eruptive unrest at Cotopaxi volcano

    Science.gov (United States)

    Hickey, James; Gottsmann, Jo; Mothes, Patricia

    2015-04-01

    The complex interplay between magma supply, storage and transportation, and how these processes interact with the host rock dictate the unrest signals we observe at the surface. Mechanical modelling allows us to link our recorded geophysical signals to subsurface processes and constrain a causative mechanism. We carry out this analysis for the 2001-2002 non-eruptive unrest episode at Cotopaxi volcano, Ecuador. During this period the volcano underwent a general inflation of its iconic edifice, recorded by an Electronic Distance Meter (EDM) network, and was accompanied by increased seismicity beneath the north-east flank. To solve for the optimum deformation source parameters we use an inverse Finite Element method accounting for subsurface material heterogeneity and surface topography. The model solutions favour a shallow source beneath the south-west flank, in contradiction to the seismicity locations in the north-east. The best-fit deformation model is a small, oblate shaped source approximately 1 km above sea level with a 20 x 106 m3 volume increase. To reconcile the deformation and seismicity simultaneously further Finite Element models were employed, incorporating an additional temperature-dependent rheology. These were used to assess the viscosity of the host rock surrounding the source. By comparing the elastic and viscous timescales associated with a small magma intrusion (implied by the best-fit deformation source in the south-west), we can infer this process occurred aseismically. To explain the recorded seismicity in the north-east we propose a mechanism of fluid migration from the south-west to the north-east along fault systems. Our analysis further shows that if future unrest crises are accompanied by measurable seismicity around the deformation source, this could indicate a higher magma supply rate and a critical level of unrest with increased likelihood of a forthcoming eruption. This research received funding through the EC FP7 "VUELCO" (#282759

  12. 10 CFR 52.173 - Duration of manufacturing license.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Duration of manufacturing license. 52.173 Section 52.173... POWER PLANTS Manufacturing Licenses § 52.173 Duration of manufacturing license. A manufacturing license... issuance. A holder of a manufacturing license may not initiate the manufacture of a reactor less than...

  13. 10 CFR 52.105 - Transfer of combined license.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Transfer of combined license. 52.105 Section 52.105 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined Licenses § 52.105 Transfer of combined license. A combined license may be transferred...

  14. An overview of Class I Structures license renewal Industry Report

    International Nuclear Information System (INIS)

    The results of this evaluation indicate that license renewal of Class I Structures is technically achievable and that most age-related degradation can be managed by existing effective programs such that the continued safe operation of the plant is assured. Existing effective programs are satisfactory as long as plant-unique verification of design and operating features is performed. Thus, the conclusions of this IR can be applied to individual plants. (author)

  15. 76 FR 38463 - SAFE Mortgage Licensing Act: Minimum Licensing Standards and Oversight Responsibilities

    Science.gov (United States)

    2011-06-30

    ... On December 15, 2009, at 74 FR 66548, HUD published a proposed rule to clarify HUD's responsibilities... Mortgage Licensing Act: Minimum Licensing Standards and Oversight Responsibilities; Final Rule #0;#0...: Minimum Licensing Standards and Oversight Responsibilities AGENCY: Office of the Assistant Secretary...

  16. Reproductive 'surrogacy' and parental licensing.

    Science.gov (United States)

    Overall, Christine

    2015-06-01

    A serious moral weakness of reproductive 'surrogacy' is that it can be harmful to the children who are created. This article presents a proposal for mitigating this weakness. Currently, the practice of commercial 'surrogacy' operates only in the interests of the adults involved (the gestator and the commissioning individuals who employ her), not in the interests of the child who is created. Whether 'surrogacy' is seen as the purchase of a baby, the purchase of parental rights, or the purchase of reproductive labor, all three views share the same significant flaws. They endorse the transfer, for a fee, of the infant from the woman who gestated it to those who commissioned it, but without justifying such a transfer; they fail to demonstrate that the commissioners have any entitlement to the infant, or, for that matter, suitability to be the infant's parents; and they fail to take any notice of the infant's needs, interests, and wellbeing. A mere genetic connection is not enough to establish that the commissioners are entitled to receive the baby or that they are competent to raise it. Their good intentions, however caring, are not enough. Therefore, just as in the practice of adoption, there should be a formal institutionalized system for screening and licensing the prospective social parents, which would make the infant's needs, interests, and wellbeing paramount. I reply to several potential objections to this proposal, including the objection that genetic parents who raise their own child are not screened and licensed. PMID:25082172

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

    Science.gov (United States)

    DeVita-Cochrane, Cynthia

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Jamieson, T. [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada)

    2009-07-01

    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

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

    International Nuclear Information System (INIS)

    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

  1. Article Details Copyright Statement: This is an open access article licensed under a Creative Commons Attribution 4.0 International License, which permits unrestricted use, distribution, and reproduction in any medium, even commercially as long as the original work is properly cited. Developing a Feasible and Maintainable Ontology for Automatic Landscape Design

    Directory of Open Access Journals (Sweden)

    Pintescu Alina

    2016-03-01

    Full Text Available In general, landscape architecture includes analysis, planning, design, administration and management of natural and artificial. An important aspect is the formation of so-called sustainable landscapes that allow maximum use of the environment, natural resources and promote sustainable restoration of ecosystems. For such purposes, a designer needs a complete database with existing and suitable plants, but no designing tool has one. Therefore it is presented the structure and the development of on ontology suitable for storing and managing all information and knowledge about plants. The advantage is that the format of the ontology allows the storage of any plant species (e.g. live or fossil and automated reasoning. Ontology is a formal conceptualization of a particular knowledge about the world, through the explicit representation of basic concepts, relations, and inference rules about themselves. Therefore the ontology may be used by a design tool for helping the designer and choosing the best options for a sustainable landscape.

  2. 75 FR 70674 - Ocean Transportation Intermediary License; Revocation

    Science.gov (United States)

    2010-11-18

    ... valid bonds. License Number: 020760F. Name: AAA Cuban Transportation Cargo & Logistics, Inc. Address... Ocean Transportation Intermediary License; Revocation The Federal Maritime Commission hereby gives notice that the following Ocean Transportation Intermediary licenses have been revoked pursuant...

  3. Licensing aspects regarding the RBMN project

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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

  5. 22 CFR 96.30 - State licensing.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false State licensing. 96.30 Section 96.30 Foreign Relations DEPARTMENT OF STATE LEGAL AND RELATED SERVICES ACCREDITATION OF AGENCIES AND APPROVAL OF PERSONS UNDER THE INTERCOUNTRY ADOPTION ACT OF 2000 (IAA) Standards for Convention Accreditation and Approval Licensing and Corporate Governance §...

  6. NEG-shift, Licensing, and Repair Strategies

    DEFF Research Database (Denmark)

    Christensen, Ken Ramshøj

    2008-01-01

    I entertain the idea that the cross-linguistic variation in the licensing of NEG-shift, the movement of negative objects to spec-NegP, can be accounted for by a few representational constraints that are not directly related to case licensing or feature checking, and which potentially conflict wit...

  7. Licensing-In Fosters Rapid Invention!

    DEFF Research Database (Denmark)

    Leone, Maria Isabella; Reichstein, Toke

    2012-01-01

    -back clause, shifting incentives from licensee to licensor. Also, the effect is significantly reduced if the licensee is unfamiliar with the licensed technology. The effect of the grant-back clause is offset if the licensee is unfamiliar with the licensed technology, suggesting that the licensee retains the...... incentives to invent under these circumstances...

  8. 9 CFR 166.10 - Licensing.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Licensing. 166.10 Section 166.10 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE SWINE HEALTH PROTECTION SWINE HEALTH PROTECTION General Provisions § 166.10 Licensing. (a) Application....

  9. 75 FR 62692 - Dairy Import Licensing Program

    Science.gov (United States)

    2010-10-13

    ... the historical license reduction provisions of the Dairy Import Licensing Program, 7 CFR part 6, for a... this proposed rule to Ron Lord, Branch Chief, Sugar and Dairy Branch, Import and Trade Support Programs... CONTACT: Ron Lord, Branch Chief, Sugar and Dairy Branch, Import and Trade Support Programs...

  10. Licensing of radioactive material (CPR Part 2)

    International Nuclear Information System (INIS)

    This Code of PAEC Regulations (CPR) part 2 sets forth the rules and regulations applicable to all persons in the Philippines governing the licensing of radioactive materials by the Philippine Nuclear Research Institute (PNRI). The following are the parts of the CPR, 1) General provisions, 2) Exceptions, 3) Licenses, 4) Records, reports, inspections and tests, and 5) Enforcement. (ELC)

  11. The legalizative effect of nuclear permits valid in law in the context of substantial design modifications and licensing under atomic energy law. Also a review of the BVerwG court judgment of 21.8.1996, 11 C 9.95

    International Nuclear Information System (INIS)

    Although the Kruemmel judgment of the BVerwG (German Federal Administrative Court) is based in essence on the atomic energy law, it nevertheless contains a novel approach to solving the problem of the licensing requirement of substantial design modifications in compliance with section 7, sub-sec. 1 Atomic Energy Act in a way that is highly pragmatic and raises problems with respect to the legal status of existing operating licences. The key issue revealed by this judgment is of dogmatic nature for administrative law, questioning the legalizative effects of administrative acts. The author explains the subject matter in court and very specifically reviews the possible impact of the court decision on future practice. (orig./CB)

  12. Estimation of Seismic and Aseismic Deformation in Mexicali Valley, Baja California, Mexico, in the 2006-2009 Period, Using Precise Leveling, DInSAR, Geotechnical Instruments Data, and Modeling

    Science.gov (United States)

    Sarychikhina, Olga; Glowacka, Ewa; Robles, Braulio; Nava, F. Alejandro; Guzmán, Miguel

    2015-11-01

    Ground deformation and seismicity in Mexicali Valley, Baja California, Mexico, the southern part of the Mexicali-Imperial valley, are influenced by active tectonics and human activity. In this study, data from two successive leveling surveys in 2006 and 2009/2010 are used to estimate the total deformation occurred in Mexicali Valley during 2006-2009. The leveling data span more than 3.5 years and include deformation from several natural and anthropogenic sources that acted at different temporal and spatial scales during the analyzed period. Because of its large magnitude, the aseismic anthropogenic deformation caused by fluid extraction in the Cerro Prieto geothermal field obscures the deformation caused by other mechanisms and sources. The method of differential interferograms stacking was used to estimate the aseismic (interseismic tectonic and anthropogenic) components of the observed displacement, using SAR images, taken in 2007 during a period when no significant seismicity occurred in the study area. After removing the estimated aseismic signal from the leveling data, residual vertical displacement remained, and to identify possible sources and mechanisms of this displacement, a detailed analysis of records from tiltmeters and creepmeters was performed. The results of this analysis suggest that the residual displacement is mainly caused by moderate-sized seismicity in the area of study. Modeling of the vertical ground deformation caused by the coseismic slip on source fault (primary mechanism) of the two most important earthquakes, May 24, 2006 (Mw = 5.4) and December 30, 2009 (Mw = 5.8), was performed. The modeling results, together with the analysis of geotechnical instruments data, suggests that this moderate-sized seismicity influences the deformation in the study area by coseismic slip on the source fault, triggered slip on secondary faults, and soft sediments deformation.

  13. 7 CFR 735.103 - Amendments to license.

    Science.gov (United States)

    2010-01-01

    ... AGRICULTURE REGULATIONS FOR WAREHOUSES REGULATIONS FOR THE UNITED STATES WAREHOUSE ACT Warehouse Licensing... licensing and examination fees; (c) Receipt of bonding or other financial assurance if required in...

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

    International Nuclear Information System (INIS)

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

  15. Licensing requirements for backfit incinerators at commercial nuclear power plants

    International Nuclear Information System (INIS)

    This paper, and the project it reports on, examines the licensing requirements for backfit incinerators at operating power plants. Analysis was made of incinerating low-level dry radioactive waste in a backfit incinerator at an existing power plant. The operation of the incinerator has been studied from viewpoints of operator safety, consequence of system failures including worst case scenarios, and radiological impact for normal and upset conditions. Analysis showed that releases under all normal operating or upset conditions are an extremely small fraction of the applicable limits. Nuclear Regulatory Commission review concluded that the document produced as a result of this project was useful as a design guide and of value in licensing backfit incinerators. 1 table

  16. NRC, DOE, and industry begin fight for nuclear-licensing reforms

    International Nuclear Information System (INIS)

    New proposals for nuclear licensing must first convince Congress that the reforms can revive the nuclear industry and that over-regulation has been its problem. Congress will give careful scrutiny to the Nuclear Regulatory Commission (NRC) and DOE efforts to streamline licensing to make sure that public health and safety and public access to regulatory decision making are protected. Congress will also challenge whether the industry needs regulatory reform. The NRC and DOE bills pursue the same goals of combining and standardizing construction permits and operating-license procedures to resolve issues in the early stages of a project. The industry sees more incentives in the DOE version, however, because DOE codifies the changes rather than making them discretionary, eliminates a pre-operational hearing and review, and eases backfit requirements. A side-by-side summary of the two proposals compares their provisions for construction permits and operating licenses hearing process, early site approval, and pre-approved designs

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

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

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

    International Nuclear Information System (INIS)

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

  19. Radioisotope thermoelectric generator licensed hardware package and certification tests

    International Nuclear Information System (INIS)

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

  20. AVC/H.264 patent portfolio license

    Science.gov (United States)

    Skandalis, Dean A.

    2006-08-01

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

  1. Regulation and license for NPP in Indonesia

    International Nuclear Information System (INIS)

    Any activity relating to nuclear energy shall maintain safety, security, safeguards, health worker and public as well as environmental protection, according to article 16(1) act No. 10 year 1997 on Nuclear Energy. The act No. 10 year 1997 on Nuclear Energy stipulated independent government agency as nuclear energy regulatory called BAPETEN (Nuclear Energy Regulatory Agency). BAPETEN has task to make regulation, licensing process and inspection. Bapeten shall have a licensing and inspection system in fulfilling his function to issued licensing according to Nuclear Energy Act. In Article 17 stipulated that any nuclear energy utilization or construction and operation of nuclear reactor and other nuclear installation as well as decommissioning of nuclear reactor shall have license. Requirements and process to issue license for nuclear reactor stipulated further in Government Regulation no. 43 year 2006. The purpose of the Government Regulation No. 43 is to stipulate licensing of nuclear reactor in order to assure the health of worker and public, environment protection and security of nuclear material and nuclear facility. Requirement and guidance in licensing NPP mandated by Government Regulation or Presidential Decree stipulated in Bapeten Chairman Regulation

  2. Seismic design of equipment and piping systems for nuclear power plants in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Minematsu, Akiyoshi [Tokyo Electric Power Co., Inc. (Japan)

    1997-03-01

    The philosophy of seismic design for nuclear power plant facilities in Japan is based on `Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981` (referred to as `Examination Guide` hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in `Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association`. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

  3. Seismic design of equipment and piping systems for nuclear power plants in Japan

    International Nuclear Information System (INIS)

    The philosophy of seismic design for nuclear power plant facilities in Japan is based on 'Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981' (referred to as 'Examination Guide' hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in 'Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association'. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

  4. Hanau licenses voided by German state court

    International Nuclear Information System (INIS)

    On July 21, the Higher Administrative Court in the German state of Hesse declared illegal three of the first four partial construction licenses for the plutonium section of the Siemens fuel fabrication complex at Hanau. The licenses were issued in the late 1980s by the former Christian Democrat administration of Hesse, but final licensing of the plant - now 90 percent complete - has been held up by the Social Democrat/Green Party coalition government that is now in power. The court ruling came as a result of four cases, and a so-called urgent application, initiated by antinuclear groups in the area

  5. Yucca Mountain licensing support network archive assistant.

    Energy Technology Data Exchange (ETDEWEB)

    Dunlavy, Daniel M.; Bauer, Travis L.; Verzi, Stephen J.; Basilico, Justin Derrick; Shaneyfelt, Wendy

    2008-03-01

    This report describes the Licensing Support Network (LSN) Assistant--a set of tools for categorizing e-mail messages and documents, and investigating and correcting existing archives of categorized e-mail messages and documents. The two main tools in the LSN Assistant are the LSN Archive Assistant (LSNAA) tool for recategorizing manually labeled e-mail messages and documents and the LSN Realtime Assistant (LSNRA) tool for categorizing new e-mail messages and documents. This report focuses on the LSNAA tool. There are two main components of the LSNAA tool. The first is the Sandia Categorization Framework, which is responsible for providing categorizations for documents in an archive and storing them in an appropriate Categorization Database. The second is the actual user interface, which primarily interacts with the Categorization Database, providing a way for finding and correcting categorizations errors in the database. A procedure for applying the LSNAA tool and an example use case of the LSNAA tool applied to a set of e-mail messages are provided. Performance results of the categorization model designed for this example use case are presented.

  6. INTERNAL HAZARDS ANALYSIS FOR LICENSE APPLICATION

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Garrett

    2005-02-17

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

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

    International Nuclear Information System (INIS)

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

  8. The licensing dilemma: understanding the determinants of the rate of technology licensing

    OpenAIRE

    2006-01-01

    The licensing of technology entails a trade-off: licensing payments net of transaction costs (revenue effect) must be balanced against the lower price-cost margin and/or reduced market share implied by increased competition (profit dissipation effect) from the licensee. We argue that the presence of multiple technology holders, which compete in the market for technology, changes such a trade-off and triggers more aggressive licensing behavior. To test our theory, we analyze technology licensi...

  9. Aseismic Behavior Analysis of a Multi-Deck Intersected Tunnel Structure System at an Urban Transport Node%城市交通节点多层交叉隧道结构体系抗震性能分析

    Institute of Scientific and Technical Information of China (English)

    赵光; 张涛; 徐翔; 戴惠兰

    2015-01-01

    concrete cracking; however, 3) the interstory drift ratios under frequent earthquakes and rare earthquakes are within the limits, represented by the fact that the steel bars do not yield, and the tunnel structure is still in the elastic deformation state. Based on this, the design scheme of the intersection node structure composed of a double-deck tunnel and a double-deck ramp can satisfy the specified requirements for aseismic performance.

  10. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

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

  11. Application of probabilistic safety analysis to licensing in Japan

    International Nuclear Information System (INIS)

    The safety criteria and standards in Japan are basically deterministic in nature though there are a few probabilistic criteria, even which are given only qualitatively. This does not mean however that quantitative probabilistic argument has not been used in the licensing review process. Three cases can be distinguished where quantitative probabilistic argument plays a major role in the licensing process. They are as follows: (1) exclusion of certain events as residual risk contributors, (2) classification of certain event category among normal operation, anticipated transient and accident, and (3) evaluation of core damage frequency which supports evidences of the adequacy of safe design and safety evaluation. The example of the adoption of these cases in the regulatory process is presented. As is shown in these examples, probabilistic evaluations are more and more used to supplement the deterministic evaluations. However it is cautioned not to rely on the absolute values predicted by the probabilistic safety assessment in the licensing discussion, especially in the case where an extremely small frequency plays a decisive role in the process

  12. Compulsory licenses for pharmaceuticals: an inconvenient truth?

    OpenAIRE

    Thambisetty, Sivaramjani

    2013-01-01

    LSE’s Sivaramjani Thambisetty discusses the legal and strategic implications for the pharmaceutical industry of the Indian decision to uphold the grant of the first compulsory license on a patented drug.

  13. Whom to Choose as License Partner?

    DEFF Research Database (Denmark)

    Laursen, Keld; Reichstein, Toke; Trombini, Giulia

    2013-01-01

    benefits and obviate issues related to technology transfer and knowledge recombination. At the same time, firms wish to select a partner operating in a different product market to minimize competitive downside issues and to access other product markets, skills and resources. We contend interdependence......This paper investigates the matching of firms on the market for technology. The paper forwards two dimensions along which license formation occurs: technology and product-market. Both sides of the market search for a partner representing potential for high technology synergies to maximize licensing...... between technology and market forces: if partners are market distant, the likelihood of technology license contractual partnership decreases with partners’ technological distance. Using data on the formation of license partnerships in the global biopharmaceutical industry over the period 1994-2004 the...

  14. Licensing and Certification District Offices, California

    Data.gov (United States)

    U.S. Department of Health & Human Services — This data contains a list of California Licensing and Certification District Offices. The California Department of Public Health, Center for Health Care Quality,...

  15. Visualization of License Plate Recognition System

    Directory of Open Access Journals (Sweden)

    Zhiyi Ruan

    2013-11-01

    Full Text Available The image of the license plate is located and segmented by some digital-image processing technologies such as gray-scale processing, gray-scale stretching and filtering, edge detection, morphological processing, Hough transformation etc. According to the characteristics of the license plate, binary matrix of character image sets the fuzzy matrix, and based on the principle of proximity computing space of closeness to get the fuzzy pattern recognition of characters. On the basis of the data of image pixels, the samples which are randomly selected under noisy condition and which are treated by morphological processing are randomly selected, and then the samples are used to test the simulation and identification of Back Propagation (BP Neural Networks. With the mathematical software-Matlab programming, the license plates are recognized. The aim is to develop the Visualization of user interface in License Plate Recognition System.  

  16. Licensing Opportunities for NIH, CDC & FDA Technologies

    Data.gov (United States)

    U.S. Department of Health & Human Services — This dataset represents all technologies available for licensing from the National Institutes of Health (NIH), the Food and Drug Administration (FDA), and the...

  17. 10 CFR 55.57 - Renewal of licenses.

    Science.gov (United States)

    2010-01-01

    ... Administrator specified in § 55.5(b). (3) Provide written evidence of the applicant's experience under the... 10 Energy 2 2010-01-01 2010-01-01 false Renewal of licenses. 55.57 Section 55.57 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) OPERATORS' LICENSES Licenses § 55.57 Renewal of licenses. (a) The...

  18. 7 CFR 6.32 - Globalization of licenses.

    Science.gov (United States)

    2010-01-01

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

  19. 78 FR 21366 - Ocean Transportation Intermediary License Revocations

    Science.gov (United States)

    2013-04-10

    ... Ocean Transportation Intermediary License Revocations The Commission gives notice that the following Ocean Transportation Intermediary licenses have been revoked pursuant to section 19 of the Shipping Act... 26, 2013. Reason: Voluntary Surrender of License. License No.: 022076NF. Name: KT Logistics,...

  20. 10 CFR 52.175 - Transfer of manufacturing license.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Transfer of manufacturing license. 52.175 Section 52.175 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Manufacturing Licenses § 52.175 Transfer of manufacturing license. A manufacturing...

  1. 10 CFR 52.167 - Issuance of manufacturing license.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Issuance of manufacturing license. 52.167 Section 52.167... POWER PLANTS Manufacturing Licenses § 52.167 Issuance of manufacturing license. (a) After completing any... manufacturing license if the Commission finds that: (1) Applicable standards and requirements of the Act and...

  2. 10 CFR 51.54 - Environmental report-manufacturing license.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Environmental report-manufacturing license. 51.54 Section... report—manufacturing license. (a) Each applicant for a manufacturing license under subpart F of part 52... Environmental Report—Manufacturing License.” The environmental report must address the costs and benefits...

  3. 21 CFR 601.5 - Revocation of license.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 7 2010-04-01 2010-04-01 false Revocation of license. 601.5 Section 601.5 Food... LICENSING General Provisions § 601.5 Revocation of license. (a) A biologics license shall be revoked upon... for, and offering an opportunity for a hearing on the proposed revocation if the Commissioner...

  4. 7 CFR 58.34 - Suspension or revocation of license.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Suspension or revocation of license. 58.34 Section 58... Dairy Products Licensing of Inspectors Or Graders § 58.34 Suspension or revocation of license. For good... by any argument or evidence that he may wish to offer as to why his license should not be...

  5. 10 CFR 52.104 - Duration of combined license.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Duration of combined license. 52.104 Section 52.104 Energy... Combined Licenses § 52.104 Duration of combined license. A combined license is issued for a specified... criteria are met under § 52.103(g) or allowing operation during an interim period under the...

  6. 10 CFR 52.103 - Operation under a combined license.

    Science.gov (United States)

    2010-01-01

    ... the combined license will be processed as a request for action in accordance with 10 CFR 2.206. The... 10 Energy 2 2010-01-01 2010-01-01 false Operation under a combined license. 52.103 Section 52.103... POWER PLANTS Combined Licenses § 52.103 Operation under a combined license. (a) The licensee...

  7. 10 CFR 52.109 - Continuation of combined license.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Continuation of combined license. 52.109 Section 52.109... POWER PLANTS Combined Licenses § 52.109 Continuation of combined license. Each combined license for a... applicable to the facility in accordance with the NRC's regulations and the provisions of the...

  8. Patent licensing, bargaining, and product positioning

    OpenAIRE

    Matsumura, Toshihiro; Matsushima, Noriaki

    2010-01-01

    Innovators who have developed advanced technologies, along with launching new products by themselves, often license these technologies to their rivals. When a firm launches a new product, product positioning is also an important matter. Using a standard linear city model with two firms, we investigate how the bargaining power of the licenser affects the product positions of the firms. We find that the inventor more likely chooses the central position when its bargaining power is weak. We also...

  9. Current safety issues of CANDU licensing

    International Nuclear Information System (INIS)

    As requested by Korea Institute of Nuclear Safety(KINS), the status of five generic licensing issues has been examined and their potential impact on a new plant that would be constructed in Canada has been evaluated. The results and conclusions of this evaluation are summarized as follows: steam explosion in calandria, hydrogen explosion in containment, use of PSA in reactor licensing, human factors, safety critical software

  10. Spectrum licensing, policy instruments and market entry

    OpenAIRE

    Madden, Gary; Bohlin, Erik; Tran, Thien; Morey, Aaron

    2013-01-01

    Competition policy attempts to address the potential for market failure by encouraging competition in service markets. Often, in wireless communication service markets, national regulatory authorities seek to encourage entry via the spectrum assignment process. Instruments used include the assignment mode (auction or beauty contest), setting aside licenses and providing bidding (price and quantity) credits for potential entrants, and making more licenses (spectrum blocks) available than incum...

  11. Smart Card Driving License System in Gujarat

    OpenAIRE

    Deepak Kumar

    2005-01-01

    Gujarat was the first state in India which introduced the smart card license system in 1999. It was the first place in the world which introduced this innovative system and, thus, its implementation was a real challenge. As of now, Gujarat Government has issued 5 million smart card driving licenses to its people. This card is basically a plastic card having ISO 7810 certification and integrated circuit,capable of storing and verifying information according to its programming. To avoid corrupt...

  12. 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.

  13. System 80+ licensing gears up

    International Nuclear Information System (INIS)

    ABB Combustion Engineering Nuclear Power's 1300MWe System 80+TM Standard Plant Design has now entered the intensive stage of the US Nuclear Regulatory Commission (NRC)'s review process for design certification. The design is docketed under the NRC's new rule for certifying the designs of advanced reactors. It is one of two evolutionary Advanced Light Water Reactors (ALWRs) whose certification process is sponsored by the US DoE. (Author)

  14. 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)

    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

  15. Licensing of nuclear and radioactive installations in Peru

    International Nuclear Information System (INIS)

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

  16. License renewal industry reports: An overview

    International Nuclear Information System (INIS)

    The 40 year limit for nuclear power plant operating licenses in the United States was established in the Atomic Energy Act of 1954. This was established primarily on the basis of a reasonable investment recovery period, rather than the result of technical life evaluations. Technical and economic evaluations have confirmed the feasibility of operation beyond the original license term. As the first of these operating licenses nears expiration, considerable efforts are being made by both the industry (under the direction of EPRI and DOE) and the US Nuclear Regulatory Commission (NRC) to demonstrate the technical and institutional basis for a predictable, rational and stable license extension option. These efforts include the publication of a proposed license renewal rule, and issuance of a series of Industry Reports (IRs). The IRs were developed with the common objective of identifying and resolving key technical issues associated with age-related degradation of selected Light Water Reactor (LWR) Systems, Structures and Components (SSCs). This paper addresses the ten IRs developed by the industry, and how they contribute to streamlining the license renewal process

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

  18. A Comparison of international regulatory organizations and licensing procedures for new nuclear power plants

    International Nuclear Information System (INIS)

    This paper considers measures needed to license new nuclear power plants efficiently. We base our analysis on the international standards and the comparison of the national regulatory and licensing framework of seven countries (Canada, France, Germany, Japan, Switzerland, the United-Kingdom and the United States of America). We split the review into the organization of regulatory responsibilities and the licensing process. We propose a set of aspects that should be incorporated into national solutions. We advise the creation of an independent specialized regulator. It should consult extensively other expert bodies as a way to ensure the soundness of its decisions. Based on the regulator's recommendations the government should issue the licenses, possibly after parliamentary approval. The licensing process should be split into different fixed steps like: design, site, construction, pre-commissioning tests and operation. Public should be first consulted on a large-scale during the siting process and then consulted over the lifetime of the project at each license renewal. Legislators should ensure that a reduced, up-to-date and coherent set of laws covers each aspect of nuclear safety. We suggest that no more than 10 laws should be in force

  19. Licensing challenges and lessons learned in new reactors in the U.S

    International Nuclear Information System (INIS)

    The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing the construction and operation of new commercial power reactors proposed in the United States. This paper will provide a brief overview of the NRC's Code of Federal Regulations (10 CFR) Part 52, 'Licenses, Certifications, and Approvals for Nuclear Power Plants', licensing process for nuclear reactors. The paper will provide a snapshot of the status of large light water reactor new reactor licensing reviews and projections for future applications. The paper will then provide a discussion of the regulatory, technical and environmental issues that have created challenges for the NRC in completing its required licensing activities. The paper will then close by discussing future regulatory challenges as licensees are constructing plants. The NRC's goals in establishing Part 52 included standardization, enhanced safety, and a more predictable licensing process, as well as resolving safety and environmental issues before authorizing construction. In addition, Part 52 goals included providing for timely and meaningful public participation, encouraging standardization of nuclear plant designs and reducing financial risks to licensees. All of these goals are being realized, although it has been much harder to achieve than initially expected

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

    International Nuclear Information System (INIS)

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

  1. 77 FR 13376 - Notice of License Termination for the University of Arizona Research Reactor, License No. R-52

    Science.gov (United States)

    2012-03-06

    ... COMMISSION Notice of License Termination for the University of Arizona Research Reactor, License No. R-52 The... No. R-52, for the University of Arizona Research Reactor (UARR). The NRC has terminated the license... released for unrestricted use. Therefore, Facility Operating License No. R-52 is terminated. For...

  2. Licensing Strategies of the Entreprising - But Vulnerable - `Intellectual property' Vendors

    DEFF Research Database (Denmark)

    Davis, Lee N.

    This paper investigates in an exploratory manner the licensing strategies pursued by firms whose business model is based on developing and licensing out their intellectual property rights (IPRs). These are not traditional suppliers, since they do not engage in production or commercialization, but...... this basis, four main licensing strategies are identified. We investigate the relative benefits and costs of these four strategies, and the factors affecting licensing choices.Key words: Intellectual property, licensing, strategyJEL Codes: O31, OO34...

  3. 土石坝坡极限抗震能力的下限有限元法%Lower bound FEM for limit aseismic capability of earth-rockfill dams

    Institute of Scientific and Technical Information of China (English)

    杨昕光; 迟世春

    2013-01-01

    基于极限分析下限定理,假设材料严格服从Mohr-Coulomb屈服准则,同时考虑了堆石料内摩擦角较大以及抗剪强度具有非线性的特性,提出了一个用于求解土石坝坝坡极限抗震能力的有限元计算方法.该方法通过静力平衡条件、应力间断面连续条件、边界条件、屈服条件以及所求极限荷载,形成标准的二次锥规划数学模型,并用内点法进行优化迭代求解,得到土石坝坡极限抗震能力的下限值.对一条形基础地基承载力进行下限极限分析,通过与已有计算结果比较表明所提方法的具有很高的计算精度.运用所提方法对一典型心墙土石坝进行抗震极限分析,其计算结果符合土石坝坡在地震作用下的一般破坏规律,证明此方法具有很高的实用价值.%An FEM basea on the lower bound theorem of limit analysis is proposed to study the limit aseismic capability of earth-rock-fill dams.Considering the large internal friction angel and non-linear shear strength parameters of rockfill materials,the proposed method formulates the limit analysis as a second-order cone programming (SOCP) problem with constraints based on the conditions of equilibrium,stress discontinuity,stress boundary and native Mohr-Coulomb yield criterion.The lower bound of the limit aseismic capability is then obtained by means of the interior-point algorithm and the iterative approach.Comparison with the published solutions illustrates the correctness and effectiveness of the proposed method for a smooth strip footing problem.The proposed approach is also applied to the seismic stability analysis of a typical rockfill dam with core wall so that the limit aseismic capability of the dam is obtained.The results proclaim the seismic failure mechanisms of earth-rockfill dams and demonstrate the practical value of the proposed method.

  4. RM - ODP to express nuclear licensing

    International Nuclear Information System (INIS)

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

  5. FHR Generic Design Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Flanagan, G.F.; Holcomb, D.E.; Cetiner, S.M.

    2012-06-15

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

  6. FHR Generic Design Criteria

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-06-01

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

  7. Seismic Isolation of Curved Continuous Bridge with Double Spherical Aseismic Bearing%双曲面球型减隔震支座曲线连续梁桥的减隔震

    Institute of Scientific and Technical Information of China (English)

    顾正伟; 钟铁毅; 张贞阁

    2011-01-01

    针对某3跨门式桥墩轨道交通曲线连续梁桥,采用其桥址提供的3条地震动时程曲线,应用SAP2000有限元软件,分析未隔震和双曲面球型减隔震支座隔震条件下的罕遇地震响应,进行双曲面球型减隔震支座曲线连续梁桥的减隔震研究.研究结果表明,曲线连续梁桥各桥墩的内力响应受响应内力方向与地震动输入方向火角的影响;仅固定墩切向隔震时,固定墩的切向内力大幅减少,弯矩和剪力分别减小约70%和50%,但各墩的径向内力均有增加,最大增幅约达10%,不能满足桥梁的抗震要求;固定墩切向和径向双向、滑动墩径向隔震时,固定墩的切向和径向内力均大幅减少,弯矩和剪力分别降低约73%和49%,同时各滑动墩的径向内力也大幅降低40%~60%,减震效果明显.%The FEA model of a 3-span rail transit curved continuous bridge with twin-legged portal pier is established by SAP2000. By using three earthquake time history waves provided by Seismic Safety Evaluation Report, the calculation of isolation and non-isolation seismic responses of curved continuous bridge with and without double spherical aseismic bearing under rarely-occurred earthquake is carried out. By comparison, the results show that the internal force responses of each pier of the curved continuous bridge are influenced by the angle between the response internal force direction and the earthquake input direction. When using double spherical aseismic bearing on braking pier in tangential direction, the seismic responses of the bending moment and the shearing force of braking pier in tangential direction decrease about 70% and 50% respectively while the seismic response of each pier in radial direction increases to a maximum of 10%, which can't meet the seismic requirements of the bridge. When putting double spherical aseismic bearing on braking pier both in tangential and radial direction and on sliding pier in radial direction, the

  8. Use of modeling in repository licensing

    International Nuclear Information System (INIS)

    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

  9. The Atomic Safety and Licensing Board Panel

    International Nuclear Information System (INIS)

    Through the Atomic Energy Act, Congress made is possible for the public to get a full and fair hearing on civilian nuclear matters. Individuals who are directly affected by any licensing action involving a facility producing or utilizing nuclear materials may participate in a formal hearing, on the record, before independent judges on the Atomic Safety and Licensing Board Panel (ASLBP or Panel). Frequently, in deciding whether a license, permit, amendment, or extension should be granted to a particular applicant, the Panel members must be more than mere umpires. If appropriate, they are authorized to go beyond the issues the parties place before them in order to identify, explore, and resolve significant questions involving threats to the public health and safety that come to a board's attention during the proceedings. This brochure explains the purpose of the panel. Also addressed are: type of hearing handled; method of public participation; formality of hearings; high-level waste; other panel responsibilities and litigation technology

  10. Challenges of licensing the first research reactor in Nigeria

    International Nuclear Information System (INIS)

    Full text: The Nigerian Nuclear Regulatory Authority (NNRA) was established in May 2001 in accordance with the provisions of the Nuclear Safety and Radiation Protection Act 19 of 1995. The NNRA has the responsibility for nuclear safety and radiological protection regulation in the country. Its responsibilities include amongst others, regulating the possession and application of radioactive substances and devices emitting ionizing radiation and; regulating the safe promotion of nuclear research and development, and the application of nuclear energy for peaceful purposes. The NNRA is empowered to, amongst others, license operators of nuclear reactors and other critical facilities listed under Category III in section 29 of the Act. Furthermore the Act imposes strong regulatory control on nuclear materials and radiation sources and the premises where they can be used or stored and ensures the 'from cradle to grave' principle of the Agency. The NNRA thus at inception took steps to put in place the proper regulatory framework, within the context of its enabling Act, to effectively license, and inspect nuclear reactor operation and to enforce nuclear safety and nuclear safeguards nationwide. It has also taken necessary measures to have in place the basic administrative and technical capability to support its activities. These have been achieved through a very rigorous regulatory control programme, which incorporates Regulations and Guidance; Authorization; Oversight Functions; Emergency Planning and Response and Ancillary Functions. The NNRA issues licences for Siting, Design and Construction of research reactors. These regulatory functions constitute the first major challenge for the NNRA. The challenge arose from an IAEA Technical Cooperation Project, which involved the supply of a Miniature Neutron Source Reactor (MNSR). For the MNSR, these were issued retroactively after an authorization process initiated by the formal application by the operating organization, the

  11. Shallow Moho with aseismic upper crust and deep Moho with seismic lower crust beneath the Japanese Islands obtained by seismic tomography using data from dense seismic network

    Science.gov (United States)

    Matsubara, Makoto; Obara, Kazushige

    2015-04-01

    P-wave seismic velocity is well known to be up to 7.0 km/s and over 7.5 km/s in the lower crust and in the mantle, respectively. A large velocity gradient is the definition of the Moho discontinuity between the crust and mantle. In this paper, we investigates the configuration of Moho discontinuity defined as an isovelocity plane with large velocity gradient derived from our fine-scale three-dimensional seismic velocity structure beneath Japanese Islands using data obtained by dense seismic network with the tomographic method (Matsubara and Obara, 2011). Japanese Islands are mainly on the Eurasian and North American plates. The Philippine Sea and Pacific plates are subducting beneath these continental plates. We focus on the Moho discontinuity at the continental side. We calculate the P-wave velocity gradients between the vertical grid nodes since the grid inversion as our tomographic method does not produce velocity discontinuity. The largest velocity gradient is 0.078 (km/s)/km at velocities of 7.2 and 7.3 km/s. We define the iso-velocity plane of 7.2 km/s as the Moho discontinuity. We discuss the Moho discontinuity above the upper boundary of the subducting oceanic plates with consideration of configuration of plate boundaries of prior studies (Shiomi et al., 2008; Kita et al., 2010; Hirata et al, 2012) since the Moho depth derived from the iso-velocity plane denotes the oceanic Moho at the contact zones of the overriding continental plates and the subducting oceanic plates. The Moho discontinuity shallower than 30 km depth is distributed within the tension region like northern Kyushu and coastal line of the Pacific Ocean in the northeastern Japan and the tension region at the Cretaceous as the northeastern Kanto district. These regions have low seismicity within the upper crust. Positive Bouguer anomaly beneath the northeastern Kanto district indicates the ductile material with large density in lower crust at the shallower portion and the aseismic upper crust

  12. 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.

  13. 78 FR 22576 - Application and Amendment to Facility Operating License Involving Proposed No Significant Hazards...

    Science.gov (United States)

    2013-04-16

    ... steady state full power operation'' shall be based upon the steam generators being operated under... operation of the steam generators nor introduce any changes to existing design functions of systems... temporary change to the steam generator management program and the license condition for maximum power....

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

    International Nuclear Information System (INIS)

    To develop and license a breakthrough nuclear fuel technology for commercial use is becoming challenging. All the former safety analysis design limits (SAFDLs) defined in the 1970's for the standard UO2-Zr fuels, might no longer be applicable. Identification of the appropriate safety analysis design limits For each type of innovative fuel, the developers will have to identify and investigate all the possible failure/ruins scenarios (not only those related to severe accidents but also those related to normal operation). In order to save time and to focus on the best options, those failure scenarios (which could be 'killers' for the ATF concept) have to be determined early enough in the development process. Based on the above failure scenarios, the developers will have to propose the licensing limits (and the experimental protocol to determine and to justify them). As mentioned earlier, the licensing limits should not be defined against the accidental conditions only. For the operators, the (good) in-reactor fuel behaviour is crucial. As an example, in the case of the new fuel concepts coming with an outer coating, it is important to include the analysis of the consequences of the loss of this protective outer layer in the licensing process due to a manufacturing defect or an inevitable in-reactor fretting wear. Obviously, the new/specific SAFDLs will have to be endorsed by the regulators (which could be a long process by itself). Identification of a commercial reactor to irradiate the first ATF A commercial NPP is not a material test reactor (MTR); irradiating lead test fuel rods (LTFRs) or lead test assemblies (LTAs) implies strict requirements regarding the manufacturing processes [which should not include chemicals (additives or solvents) potentially incompatible with the nuclear technical specifications], the compatibility with the hosting fuel core (in terms of geometry, enrichment, thermal hydraulic performances, etc.) and the robustness and the

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

    Energy Technology Data Exchange (ETDEWEB)

    McCoy, Gilbert A.

    1992-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    McCoy, Gilbert A.

    1992-12-01

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

  17. AREVA solutions to licensing challenges in PWR and BWR reload and safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Curca-Tivig, Florin [AREVA GmbH, Erlangen (Germany)

    2016-05-15

    Regulatory requirements for reload and safety analyses are evolving: new safety criteria, request for enlarged qualification databases, statistical applications, uncertainty propagation.. In order to address these challenges and access more predictable licensing processes, AVERA is implementing consistent code and methodology suites for PWR and BWR core design and safety analysis, based on first principles modeling and extremely broad verification and validation data base. Thanks to the high computational power increase in the last decades methods' development and application now include new capabilities. An overview of the main AREVA codes and methods developments is given covering PWR and BWR applications in different licensing environments.

  18. Licensing concerns in SSI methodology

    International Nuclear Information System (INIS)

    This paper addresses some of the more immediate Nuclear Regulatory concerns in the controversial subject of soil-structure interactions in US nuclear power plant design practice. Topics covered include: choice of solution method, the need for sophisticated analyses, frequency variation, ground motion reduction with depth, and buried structures. Recommendations under consideration by NRC staff are presented

  19. 9 CFR 354.22 - Surrender of license.

    Science.gov (United States)

    2010-01-01

    ... promptly be surrendered by the licensee to his immediate superior. Upon termination of the services of a licensed inspector, the licensee shall promptly surrender his license to his immediate superior....

  20. 77 FR 42312 - Ocean Transportation Intermediary License; Revocations

    Science.gov (United States)

    2012-07-18

    ... From the Federal Register Online via the Government Publishing Office FEDERAL MARITIME COMMISSION Ocean Transportation Intermediary License; Revocations The Federal Maritime Commission hereby gives notice that the following Ocean Transportation Intermediary licenses have been revoked pursuant...

  1. 77 FR 37044 - Ocean Transportation Intermediary License; Revocations

    Science.gov (United States)

    2012-06-20

    ... From the Federal Register Online via the Government Publishing Office FEDERAL MARITIME COMMISSION Ocean Transportation Intermediary License; Revocations The Federal Maritime Commission hereby gives notice that the following Ocean Transportation Intermediary licenses have been revoked pursuant...

  2. 78 FR 3425 - Ocean Transportation Intermediary License Revocations

    Science.gov (United States)

    2013-01-16

    ... From the Federal Register Online via the Government Publishing Office ] FEDERAL MARITIME COMMISSION Ocean Transportation Intermediary License Revocations The Commission gives notice that the following Ocean Transportation Intermediary licenses have been revoked pursuant to section 19 of...

  3. Groundfish/Crab License Limitation Program (LLP) Permit Program

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — As of January 1, 2000 a Federal License Limitation Program (LLP) license is required for vessels participating in directed fishing for LLP groundfish species in the...

  4. 42 CFR 1001.501 - License revocation or suspension.

    Science.gov (United States)

    2010-10-01

    ... license), for reasons bearing on the individual's or entity's professional competence, professional performance or financial integrity; or (2) Has surrendered such a license while a formal disciplinary proceeding concerning the individual's or entity's professional competence, professional performance...

  5. 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. PMID:19041620

  6. Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

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

    International Nuclear Information System (INIS)

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

  8. House passes energy bill with one-step plant licensing

    International Nuclear Information System (INIS)

    The US House of Representatives which has traditionally been wary of measures that would allow nuclear power to expand, came down strongly on the side of nuclear when it approved a much-amended omnibus energy bill on May 27 by a vote of 381 to 37. The key for the nuclear industry is the presence in the bill (H.R. 776) of language on one-step power plant licensing that was taken directly from the Senate energy bill (S. 2166) that passed in February. This means that when the House and Senate work out a compromise version of the legislation, one-step licensing is almost certain to be carried through--and become law once the final bill is signed by President George Bush, which is expected later this year. The House's endorsement of nuclear power--both as it exists now, and as it could be with the introduction of new plant designs and an end to the long hiatus in plant orders by utilities--went beyond one-step licensing. Debate on the House floor prior to Memorial Day totally transformed the nuclear-related part of the energy bill. H.R. 776 was reported to the floor by the Rules Committee with language by the Interior and Insular Affairs Committee that would have created a nominal one-step system, with a full evidentiary hearing prior to plant construction but also allowing an intervenor who later presents new information on the plant to get another full evidentiary hearing after construction but before operation. This would effectively duplicate the two-step process that existed for all plants now in service, and which utilities no longer want to endure

  9. 10 CFR 72.44 - License conditions.

    Science.gov (United States)

    2010-01-01

    ..., construction and operation. The Commission may also include additional license conditions as it finds... materials of construction and geometric arrangements. (5) Administrative controls. Administrative controls... conditions: (1) Construction of the MRS may not begin until the Commission has authorized the construction...

  10. Partner Selection in Technological Licensing Agreements

    DEFF Research Database (Denmark)

    Laursen, Keld; Trombini, Giulia

    as attractors, and market competition and potential involuntary spillovers act as repellants. Firms seek potential licensing partners by trying to maximize technological synergies while attempting to minimize the competitive downsides. We hypothesize that when licensees engage in matches involving a partner...

  11. 14 CFR 1274.942 - Export licenses.

    Science.gov (United States)

    2010-01-01

    ... appropriate licenses or other approvals, if required, for exports of hardware, technical data, and software... International Traffic in Arms Regulations (ITAR), 22 CFR Parts 120 through 130, and the Export Administration Regulations (EAR), 15 CFR parts 730 through 799, in the performance of this Cooperative Agreement. In...

  12. Information management and NRC licensing: Intervenor's perspective

    International Nuclear Information System (INIS)

    The NRC licensing of a high-level waste repository will place extraordinary information management demands on its participants. The large volumes of information and logn timeframes in the program strongly support the efficacy of automated solutions. DOE is currently considering establishment of a computerized licensing support system (LSS), and NRC is considering institution of a negotiated rulemaking to amend its procedural rules for licensing to accommodate such a system. However, because the actual ability of affected parties to influence key programmatic decisions diminishes with time, the need for affected parties to gain ready access to repository data arises long before the formal licensing proceeding. The best and more efficient way to achieve a workable information management system in time to be useful is to develop the pilot system already set up by the NRC staff as an interim system, to subsequently develop that system into the full-blown LSS, and to retain its management within NRC. Appropriate means should be found to reimburse NRC for the costs of such a system from the Nuclear Waste Trust Fund

  13. The licensing procedure under Atomic Energy Law

    International Nuclear Information System (INIS)

    This post-doctoral thesis of 1981 has been updated to include developments in this field up to the year 1983. The author discusses in detail all questions relating to the peaceful uses of nuclear energy in the Federal Republic of Germany, predominantly from the point of view of administrative law. He investigates nuclear energy and its contribution to electricity supplies with a view to other energy sources, renewable energy sources, alternative energy policies, nuclear fuel and the fuel cycle, development of the nuclear industry, nuclear power stations in operation, under construction, or in development. Following a survey of the nuclear controversy, both on the national and the international level, the author reviews the legal system and arising controversies in the Federal Republic of Germany, defining the purpose of this thesis to be the systematic analysis of the available legal instruments, in order to show structural deficiencies in the planning law relating to nuclear power stations, and thus reasons of ambiguities within the licensing procedure. The author studies the following terms and requirements: licensing requirements and licensability, the licensing method and scenario, the legal character of licences, their contents and effects within the stepwise procedure, and due publication. (HSCH)

  14. Permission Granted: Open Licensing for Educational Resources

    Science.gov (United States)

    Bissell, Ahrash N.

    2009-01-01

    Open licences are critical for defining Open Educational Resources. The goal of this article is to explain the logic of open licensing to teachers, funders, and educational policy-makers--to explain the relatively simple but vital considerations that are necessary to build this global educational commons of free learning material. In particular,…

  15. 15 CFR 336.5 - Licenses.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Licenses. 336.5 Section 336.5 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) INTERNATIONAL TRADE... authorization in writing or by electronic notice to the importer and providing a copy of such authorization...

  16. 15 CFR 335.5 - Licenses.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Licenses. 335.5 Section 335.5 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade (Continued) INTERNATIONAL TRADE... its behalf by making such an authorization in writing or by electronic notice to the importer...

  17. Licensing Revisited: Open Access Clauses in Practice

    Directory of Open Access Journals (Sweden)

    Birgit Schmidt

    2012-11-01

    Full Text Available Open access increases the visibility and use of research outputs and promises to maximize the return on our public investment in research. However, only a minority of researchers will "spontaneously" deposit their articles into an open access repository. Even with the growing number of institutional and funding agency mandates requiring the deposit of papers into the university repository, deposit rates have remained stubbornly low. As a result, the responsibility for populating repositories often falls onto the shoulders of library staff and/or repository managers. Populating repositories in this way – which involves obtaining the articles, checking the rights, and depositing articles into the repository – is time consuming and resource intensive work.The Confederation of Open Access Repositories (COAR, a global association of repository initiatives and networks, is promoting a new strategy for addressing some of the barriers to populating repositories, involving the use of open access archiving clauses in publisher licenses. These types of clauses are being considered by consortia and licensing agencies around the world as a way of ensuring that all the papers published by a given publisher are cleared for deposit into the institutional repository. This paper presents some use cases of open access archiving clauses, discusses the major barriers to implementing archiving language into licenses, and describes some strategies that organizations can adopt in order to include such clauses into publisher licenses.

  18. Information Technology Trends, Creative Commons Licenses

    Directory of Open Access Journals (Sweden)

    Felician ALECU

    2012-11-01

    Full Text Available The Creative Commons licenses, also known as CC, allow the authors to retain the copyright over the works while granting some right to the others, like the permission to modify or to use the work for commercial purposes.

  19. Screening vs. signaling in technology licensing

    OpenAIRE

    Manel Antelo

    2010-01-01

    A patent holder owning a two-period lasting innovation is unable to push it into the market, so it is licensed to a downstream user with production capabilities to market it. The production cost of this firm can be low or high, but the patent holder has only a prior on this fact

  20. You've Licensed It. Now What?

    OpenAIRE

    McCleskey, Sarah E.; Fischer, Christine M.; Milewski, Steven D.; Davis, Jim

    2015-01-01

    While libraries face challenges in building usage of a new medium like streaming video, strategic, active marketing by libraries, with support from vendors, can overcome these challenges. Time‐tested marketing strategies, as well as leveraging new promotional tools can help the library attain the usage that justifies the investment in new media. If you license, with a little help, they will come.

  1. Licensing failure in the European decentralised procedure.

    Science.gov (United States)

    Langedijk, Joris; Ebbers, Hans C; Mantel-Teeuwisse, Aukje K; Kruger-Peters, Alexandra G; Leufkens, Hubert G M

    2016-05-25

    The majority of the licensing applications in the European Union are submitted via the decentralised procedure. Little is known about licensing failure (i.e. refusal or withdrawal of a marketing authorisation application) in the EU decentralised procedure compared to the EU centralised procedure and the approval procedure in the United States. The study aim was to determine the frequency of and determinants for licensing failure of marketing authorisation applications submitted via this procedure. We assessed procedures that failed between 2008 and 2012 with The Netherlands as leading authority and assessed the remaining major objections. In total 492 procedures were completed, of which 48 (9.8%) failed: 8 refused, 40 withdrawn. A wide variety of major objections was identified and included both quality (48 major objections) and clinical (45 major objections) issues. The low failure rate may be related to the regular interaction between competent authorities and applicants during the procedure. Some degree of licensing failure may be inevitable, as it may also be affected by the financial feasibility or willingness to resolve major objections, as well as other reasons to withdraw an application besides the raised major objections. PMID:26493584

  2. 7 CFR 1530.103 - License eligibility.

    Science.gov (United States)

    2010-01-01

    ... OF AGRICULTURE THE REFINED SUGAR RE-EXPORT PROGRAM, THE SUGAR CONTAINING PRODUCTS RE-EXPORT PROGRAM, AND THE POLYHYDRIC ALCOHOL PROGRAM § 1530.103 License eligibility. (a) A raw cane sugar refiner, a manufacturer of sugar containing products, or a producer of certain polyhydric alcohols, that owns and...

  3. Compulsory licensing and access to drugs.

    Science.gov (United States)

    Stavropoulou, Charitini; Valletti, Tommaso

    2015-01-01

    Compulsory licensing allows the use of a patented invention without the owner's consent, with the aim of improving access to essential drugs. The pharmaceutical sector argues that, if broadly used, it can be detrimental to innovation. We model the interaction between a company in the North that holds the patent for a certain drug and a government in the South that needs to purchase it. We show that both access to drugs and pharmaceutical innovation depend largely on the Southern country's ability to manufacture a generic version. If the manufacturing cost is too high, compulsory licensing is not exercised. As the cost decreases, it becomes a credible threat forcing prices down, but reducing both access and innovation. When the cost is low enough, the South produces its own generic version and access reaches its highest value, despite a reduction in innovation. The global welfare analysis shows that the overall impact of compulsory licensing can be positive, even when accounting for its impact on innovation. We also consider the interaction between compulsory licensing and the strength of intellectual property rights, which can have global repercussions in other markets beyond the South. PMID:24408475

  4. AIDS, essential medicines, and compulsory licensing.

    Science.gov (United States)

    Berman, D

    1999-04-01

    Delegates to the AIDS and Essential Medicines and Compulsory Licensing conference examined issues related to compulsory licensing of pharmaceuticals worldwide. Compulsory licenses allow members of the World Trade Organization (WTO) to use patented material when justified in the public interest. This agreement is part of the Trade Related Aspects of Intellectual Property Rights, or TRIPS. Current estimates of the HIV/AIDS pandemic show that 33 million persons worldwide are infected, with 26 million of those in Sub-Saharan Africa. Most of these people have no access to antiretroviral treatment due to its cost, and medicines for other life-threatening illnesses like tuberculosis, malaria, and meningitis are also too expensive. The U.S. government opposes the use of compulsory licenses, and has attempted to block their implementation in countries trying to obtain AIDS drugs at a lower price. The U.S. has also pressured countries to adopt stricter trade laws than those included in the TRIPS agreement. Meeting delegates were encouraged to pursue existing and legal means to increase the supply of affordable drugs. PMID:11367046

  5. Experiments in Image Segmentation for Automatic US License Plate Recognition

    OpenAIRE

    Diaz Acosta, Beatriz

    2004-01-01

    License plate recognition/identification (LPR/I) applies image processing and character recognition technology to identify vehicles by automatically reading their license plates. In the United States, however, each state has its own standard-issue plates, plus several optional styles, which are referred to as special license plates or varieties. There is a clear absence of standardization and multi-colored, complex backgrounds are becoming more frequent in license plates. Commercially availab...

  6. Sensor network based vehicle classification and license plate identification system

    Energy Technology Data Exchange (ETDEWEB)

    Frigo, Janette Rose [Los Alamos National Laboratory; Brennan, Sean M [Los Alamos National Laboratory; Rosten, Edward J [Los Alamos National Laboratory; Raby, Eric Y [Los Alamos National Laboratory; Kulathumani, Vinod K [WEST VIRGINIA UNIV.

    2009-01-01

    Typically, for energy efficiency and scalability purposes, sensor networks have been used in the context of environmental and traffic monitoring applications in which operations at the sensor level are not computationally intensive. But increasingly, sensor network applications require data and compute intensive sensors such video cameras and microphones. In this paper, we describe the design and implementation of two such systems: a vehicle classifier based on acoustic signals and a license plate identification system using a camera. The systems are implemented in an energy-efficient manner to the extent possible using commercially available hardware, the Mica motes and the Stargate platform. Our experience in designing these systems leads us to consider an alternate more flexible, modular, low-power mote architecture that uses a combination of FPGAs, specialized embedded processing units and sensor data acquisition systems.

  7. Manual for conducting radiological surveys in support of license termination

    International Nuclear Information System (INIS)

    This document describes a process for conducting radiological surveys during decommissioning, to demonstrate that residual radioactive material satisfies criteria established by the U.S. Nuclear Regulatory Commission (NRC) for termination of a license. The Manual describes procedures for design and conduct of surveys in a manner which will provide a high degree of assurance that NRC guidelines and conditions have been satisfied. The Manual also describes methods for documenting the survey findings in a final report to the NRC. This Manual updates information contained in NUREG/CR-2082, Monitoring for Compliance with Decommissioning Termination Survey Criteria, (ORNL 1981). It incorporates statistical approaches to survey design and data interpretation used by the Environmental Protection Agency for evaluation of hazardous materials sites under Superfund (CERCLA). Quality assurance is emphasized throughout. (author)

  8. 47 CFR 90.904 - Aggregation of EA licenses.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Aggregation of EA licenses. 90.904 Section 90.904 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES... Service § 90.904 Aggregation of EA licenses. The Commission will license each Spectrum Block A through...

  9. 9 CFR 114.7 - Personnel at licensed establishments.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Personnel at licensed establishments... REQUIREMENTS FOR BIOLOGICAL PRODUCTS § 114.7 Personnel at licensed establishments. (a) Each licensee shall...) All personnel employed in the preparation of biological products at a licensed establishment shall...

  10. 76 FR 55909 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-09-09

    ..., Application Type: New NVO License. International Movers Network Inc. (NVO), 70-20 73rd Street, Glendale, NY..., President, Application Type: New NVO License. Unity Holdings, Inc. (NVO), 2860 W. State Road 84, Suite 118.../Treasurer (Qualifying Individual), Application Type: New NVO License. Echo Trans World Inc. (NVO), 462...

  11. 10 CFR 72.210 - General license issued.

    Science.gov (United States)

    2010-01-01

    ... for Storage of Spent Fuel at Power Reactor Sites § 72.210 General license issued. A general license is hereby issued for the storage of spent fuel in an independent spent fuel storage installation at power... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF...

  12. 78 FR 21366 - Ocean Transportation Intermediary License Reissuances

    Science.gov (United States)

    2013-04-10

    ... Ocean Transportation Intermediary License Reissuances The Commission gives notice that the following Ocean Transportation Intermediary license has been reissued pursuant to section 19 of the Shipping Act of 1984 (46 U.S.C. 40101). License No.: 016816N. Name: Green Integrated Logistics, Inc....

  13. 78 FR 23252 - Ocean Transportation Intermediary License Revocations

    Science.gov (United States)

    2013-04-18

    ... Ocean Transportation Intermediary License Revocations The Commission gives notice that the following Ocean Transportation Intermediary licenses have been revoked pursuant to section 19 of the Shipping Act... maintain a valid bond. License No.: 003445F. Name: Nedlloyd Logistics, Inc. Address: Giralda Farms,...

  14. Experience acquired by Furnas for licensing nuclear power plants

    International Nuclear Information System (INIS)

    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.)

  15. 7 CFR 70.21 - Suspension of license; revocation.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Suspension of license; revocation. 70.21 Section 70.21... Graders § 70.21 Suspension of license; revocation. Pending final action by the Secretary, any person... any argument or evidence that the licensee may wish to offer as to why the license should not...

  16. 9 CFR 354.21 - Suspension of license; revocation.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Suspension of license; revocation. 354... Services § 354.21 Suspension of license; revocation. Pending final action by the Secretary, any person..., supported by any argument or evidence that he may wish to offer as to why his license should not be...

  17. License - Taxonomy Icon | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available g this database. The license for this database is specified in the Creative Commons Attribution 2.1 Japan . ...ase Center for Life Science licensed under CC Attribution 2.1 Japan . The summary... of the Creative Commons Attribution 2.1 Japan is found here . With regard to this database, you are license

  18. Black Residential Segregation: Impact of State Licensing Laws.

    Science.gov (United States)

    Darden, Joe T.

    1982-01-01

    Compared the level of Black residential segregation among two groups of States: those whose real estate licensing laws contain explicit fair housing or anti-discrimination provisions, and those whose licensing laws contain no such provisions. Found that State licensing laws have no significant impact on Black residential discrimination. (GC)

  19. 25 CFR 558.4 - Granting a gaming license.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 2 2010-04-01 2010-04-01 false Granting a gaming license. 558.4 Section 558.4 Indians NATIONAL INDIAN GAMING COMMISSION, DEPARTMENT OF THE INTERIOR GAMING LICENSES AND BACKGROUND INVESTIGATIONS FOR KEY EMPLOYEES AND PRIMARY MANAGEMENT OFFICIALS GAMING LICENSES FOR KEY EMPLOYEES AND...

  20. 10 CFR 52.8 - Combining licenses; elimination of repetition.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Combining licenses; elimination of repetition. 52.8... NUCLEAR POWER PLANTS General Provisions § 52.8 Combining licenses; elimination of repetition. (a) An applicant for a license under this part may combine in its application several applications for...

  1. 10 CFR 52.97 - Issuance of combined licenses.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Issuance of combined licenses. 52.97 Section 52.97 Energy... Combined Licenses § 52.97 Issuance of combined licenses. (a)(1) After conducting a hearing in accordance with § 52.85 and receiving the report submitted by the ACRS, the Commission may issue a...

  2. 10 CFR 110.42 - Export licensing criteria.

    Science.gov (United States)

    2010-01-01

    ... NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Review of License Applications § 110.42 Export licensing criteria. (a) The review of license applications for export... nonproliferation objectives or otherwise jeopardize the common defense and security, in which case the...

  3. 19 CFR 360.108 - Loss of electronic licensing privileges.

    Science.gov (United States)

    2010-04-01

    ... MONITORING AND ANALYSIS SYSTEM § 360.108 Loss of electronic licensing privileges. Should Commerce determine... system, Commerce may revoke its electronic licensing privileges without prior notice. The filer will then... 19 Customs Duties 3 2010-04-01 2010-04-01 false Loss of electronic licensing privileges....

  4. 24 CFR 3286. 211 - Expiration and renewal of installation licenses.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 5 2010-04-01 2010-04-01 false Expiration and renewal of... Licensing in HUD-Administered States § 3286. 211 Expiration and renewal of installation licenses. (a) Expiration. Each installation license issued or renewed under this subpart C will expire 3 years after...

  5. 7 CFR 51.36 - Expiration and renewal of license.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 2 2010-01-01 2010-01-01 false Expiration and renewal of license. 51.36 Section 51.36 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards... STANDARDS) Regulations 1 Licensing of Inspectors § 51.36 Expiration and renewal of license. An...

  6. 76 FR 20249 - Update Station License Expiration Dates

    Science.gov (United States)

    2011-04-12

    ... COMMISSION 47 CFR Part 73 Update Station License Expiration Dates AGENCY: Federal Communications Commission... reflect the current license expiration dates for radio and television broadcast stations. The current version of the rule specifies license expiration dates from 2011 through 2014 for radio stations and...

  7. 77 FR 29340 - Intent To Grant Patent License

    Science.gov (United States)

    2012-05-17

    ... AGENCY Intent To Grant Patent License AGENCY: Environmental Protection Agency (EPA). ACTION: Notice of Intent to Grant Co-Exclusive Patent License. SUMMARY: Pursuant to 35 U.S.C. 207 (Patents) and 37 CFR part 404 (U.S. Government patent licensing regulations), EPA hereby gives notice of its intent to grant...

  8. 76 FR 3128 - Intent to Grant Patent License

    Science.gov (United States)

    2011-01-19

    ... AGENCY Intent to Grant Patent License AGENCY: Environmental Protection Agency (EPA). ACTION: Notice of Intent to Grant Co-Exclusive Patent License. SUMMARY: Pursuant to 35 U.S.C. 207 (Patents) and 37 CFR part 404 (U.S. Government patent licensing regulations), EPA hereby gives notice of its intent to grant...

  9. 78 FR 48460 - Notice of Revocation of Customs Broker License

    Science.gov (United States)

    2013-08-08

    ... SECURITY U.S. Customs and Border Protection Notice of Revocation of Customs Broker License AGENCY: U.S. Customs and Border Protection, Department of Homeland Security. ACTION: Notice of revocation of a customs broker license. SUMMARY: Notice is hereby given that a customs broker license is being revoked...

  10. 78 FR 48456 - Notice of Cancellation of Customs Broker Licenses

    Science.gov (United States)

    2013-08-08

    ... SECURITY U.S. Customs and Border Protection Notice of Cancellation of Customs Broker Licenses AGENCY: U.S. Customs and Border Protection, Department of Homeland Security. ACTION: Customs broker license cancellations. SUMMARY: Notice is hereby given that the customs broker licenses and any and all...

  11. 76 FR 71584 - Notice of Revocation of Customs Broker Licenses

    Science.gov (United States)

    2011-11-18

    ... SECURITY U.S. Customs and Border Protection Notice of Revocation of Customs Broker Licenses AGENCY: U.S. Customs and Border Protection, U.S. Department of Homeland Security. ACTION: Customs broker license... of the Code of Federal Regulations at Sec. 111.30(d), the following Customs broker licenses...

  12. 76 FR 71591 - Notice of Revocation of Customs Broker Licenses

    Science.gov (United States)

    2011-11-18

    ... License, dated July 25, 2006 (71 FR 42105). The current Notice of Revocation of Customs Broker Licenses... SECURITY Bureau of Customs and Border Protection Notice of Revocation of Customs Broker Licenses AGENCY: Bureau of Customs and Border Protection, U.S. Department of Homeland Security. ACTION: Customs...

  13. NRC Licensing Status Summary Report for NGNP

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-11-01

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

  14. Present day design challenges exemplified by the Clinch River Breeder Reactor Plant

    International Nuclear Information System (INIS)

    The present day design challenges faced by the Clinch River Breeder Reactor Plant engineer result from two causes. The first cause is aspiration to achieve a design that will operate at conditions which are desirable for future LMFBRs in order for them to achieve low power costs and good breeding. The second cause is the licensing impact. Although licensing the CRBRP won't eliminate future licensing effort, many licensing questions will have been resolved and precedents set for the future LMFBR industry

  15. Design

    DEFF Research Database (Denmark)

    Volf, Mette

    2009-01-01

    Design - proces og metode går bag om designerens arbejde og giver et indblik i den skabelsesproces, som designeren er involveret i. Bogen er enestående, fordi den fokuserer på processens flygtige og komplekse karakter, afmystificerer den og gør den operationel - uden at fjerne dens magi. Ud over at...

  16. Design

    Science.gov (United States)

    Buchanan, Richard; Cross, Nigel; Durling, David; Nelson, Harold; Owen, Charles; Valtonen, Anna; Boling, Elizabeth; Gibbons, Andrew; Visscher-Voerman, Irene

    2013-01-01

    Scholars representing the field of design were asked to identify what they considered to be the most exciting and imaginative work currently being done in their field, as well as how that work might change our understanding. The scholars included Richard Buchanan, Nigel Cross, David Durling, Harold Nelson, Charles Owen, and Anna Valtonen. Scholars…

  17. 78 FR 5840 - Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115

    Science.gov (United States)

    2013-01-28

    ... COMMISSION Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115... No. R-115, for the University of Illinois Advanced TRIGA Reactor (ATR). The NRC has terminated the..., Facility Operating License No. R-115 is terminated. The above referenced documents may be examined,...

  18. 76 FR 2918 - Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder

    Science.gov (United States)

    2011-01-18

    ... SECURITY U.S. Customs and Border Protection Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder AGENCY: U.S. Customs and Border Protection, U.S. Department of Homeland... Federal Regulations at section 111.51(a), the following individual Customs broker license and any and...

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

    NARCIS (Netherlands)

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

    2013-01-01

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

  20. 76 FR 22912 - Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder

    Science.gov (United States)

    2011-04-25

    ... SECURITY U.S. Customs and Border Protection Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder AGENCY: U.S. Customs and Border Protection, DHS. ACTION: General notice... 111.51(a), the following individual Customs broker licenses and any and all permits have...

  1. 76 FR 44033 - Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder

    Science.gov (United States)

    2011-07-22

    ... SECURITY U.S. Customs and Border Protection Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder AGENCY: U.S. Customs and Border Protection, U.S. Department of Homeland... Federal Regulations at section 111.51(a), the following individual Customs broker licenses and any and...

  2. 77 FR 45648 - Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder

    Science.gov (United States)

    2012-08-01

    ... SECURITY U.S. Customs and Border Protection Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder AGENCY: U.S. Customs and Border Protection, U.S. Department of Homeland... Federal Regulations at section 111.51(a), the following individual Customs broker licenses and any and...

  3. 75 FR 11899 - Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder

    Science.gov (United States)

    2010-03-12

    ... SECURITY Customs and Border Protection Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder AGENCY: U.S. Customs and Border Protection, U.S. Department of Homeland Security... Regulations at section 111.51(a), the following individual Customs broker licenses and any and all...

  4. 78 FR 48456 - Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder

    Science.gov (United States)

    2013-08-08

    ... SECURITY U.S. Customs and Border Protection Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder AGENCY: U.S. Customs and Border Protection, Department of Homeland Security. ACTION: Customs broker license cancellation due to death of the broker. SUMMARY: Notice is hereby...

  5. 77 FR 16249 - Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder

    Science.gov (United States)

    2012-03-20

    ... SECURITY U.S. Customs and Border Protection Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder AGENCY: U.S. Customs and Border Protection, U.S. Department of Homeland... Federal Regulations at section 111.51(a), the following individual Customs broker licenses and any and...

  6. Simulator training and licensing examination for nuclear power station operator

    International Nuclear Information System (INIS)

    For the recruitment, training and position qualification of the simulator instructors and feedback of training effect, the management approaches are formulated in 'The System for Simulator Training and Licensing Examination of Daya Bay Nuclear Power Station Operators'. The concrete requirements on the professional knowledge, work experience and foreign language ability of a simulator instructor are put forward. The process of instructor training is designed. The training items include the trainer training, pedagogy training, time management training, operation activities training during outage of unit, 'shadow' training and on-the-jot training on simulator courses. Job rotation is realized between simulator instructor and licensing personnel on site. New simulator instructor must pass the qualification identification. After a duration of 2 years, re-qualification has to be carried out. On the basis of the operator training method introduced from EDF (electricite De France), some new courses are developed and the improvement on the initial training, retaining courses, the technical support and the experience feedback by using the simulator is done also. (authors)

  7. Status of safety issues at licensed power plants

    International Nuclear Information System (INIS)

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the second volume of a three-volume series, addresses the status of unresolved safety issues (USIs) at licensed plants. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 27 safety issues designated as USIs and to make this information available to other interested parties, including the public. A corollary purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants. 3 figs., 4 tabs

  8. Sodium fast reactor safety and licensing research plan. Volume I.

    Energy Technology Data Exchange (ETDEWEB)

    Sofu, Tanju (Argonne National Laboratory, Argonne, IL); LaChance, Jeffrey L.; Bari, R. (Brokhaven National Laboratory Upton, NY); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.; Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN)

    2012-05-01

    This report proposes potential research priorities for the Department of Energy (DOE) with the intent of improving the licensability of the Sodium Fast Reactor (SFR). In support of this project, five panels were tasked with identifying potential safety-related gaps in available information, data, and models needed to support the licensing of a SFR. The areas examined were sodium technology, accident sequences and initiators, source term characterization, codes and methods, and fuels and materials. It is the intent of this report to utilize a structured and transparent process that incorporates feedback from all interested stakeholders to suggest future funding priorities for the SFR research and development. While numerous gaps were identified, two cross-cutting gaps related to knowledge preservation were agreed upon by all panels and should be addressed in the near future. The first gap is a need to re-evaluate the current procedures for removing the Applied Technology designation from old documents. The second cross-cutting gap is the need for a robust Knowledge Management and Preservation system in all SFR research areas. Closure of these and the other identified gaps will require both a reprioritization of funding within DOE as well as a re-evaluation of existing bureaucratic procedures within the DOE associated with Applied Technology and Knowledge Management.

  9. Sodium Fast Reactor Safety and Licensing Research Plan

    International Nuclear Information System (INIS)

    This paper summarizes potential research priorities for the US Department of Energy (DOE) with the intent of improving the licensability of the sodium cooled fast reactor (SFR). In support of this project, five panels were tasked with identifying potential safety related gaps in the available information, data and models needed to support the licensing of an SFR. The areas examined were sodium technology; accident sequences and initiators; source term characterization, codes and methods; and fuels and materials. It is the intent of this paper to utilize a structured and transparent process that incorporates feedback from all interested stakeholders to suggest future funding priorities for SFR research and development. While numerous gaps were identified, two cross-cutting gaps related to knowledge preservation were agreed upon by all panels and should be addressed in the near future. The first gap is a need to re-evaluate the current procedures for removing the applied technology access control designation from old documents. The second cross-cutting gap is the need for a robust knowledge management and preservation system in all SFR research areas. Closure of these and the other identified gaps will require both a reprioritization of funding within DOE as well as a re-evaluation of existing bureaucratic procedures within the DOE associated with applied technology and knowledge management. (author)

  10. Planning and licensing two replacement nuclear power plants in Switzerland

    International Nuclear Information System (INIS)

    Switzerland is facing the challenges of steadily rising electricity consumption and an aging pool of power plants. Its electricity mix of roughly 60% hydroelectric power and 40% nuclear power is the reason for its excellent carbon balance in electricity production. Consequently, replacement must be found for the oldest nuclear power plants and for future electricity import contracts. Security of supply, environmental protection, and economic performance must be taken into account in equal proportions. For the overarching strategic project of a ''replacement nuclear power plant'', 2 of the big Swiss electricity utilities, Axpo and BKW, in 2008 jointly founded a project development company, Resun AG. Performing the project design work in a joint effort allows synergies to be exploited and expenses to be focused. The 2003 Nuclear Power Act (KEG) of Switzerland provides a 3-stage plant licensing procedure. In addition, the political system in Switzerland offers a number of possibilities for involvement and participation at various stages in the licensing procedure of new nuclear power plants. The political debate about the future energy policy of Switzerland was triggered for good when the framework applications for approval of the replacement nuclear power plants were submitted. Construction of the replacement nuclear power plants corresponds to the political strategy, communicated by the Federal Council, to ensure future energy supply also by building new large power plants. (orig.)

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

    International Nuclear Information System (INIS)

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

  12. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    International Nuclear Information System (INIS)

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement

  13. Regulators experiences in licensing and inspection of dry cask storage facilities

    International Nuclear Information System (INIS)

    Full text: All operating nuclear power reactors in the United States (US) are storing spent fuel in NRC licensed on-site spent fuel pools (SFPs). Most reactors were not designed to store, in these pools, the full amount of spent fuel generated during the life of plant operation. Utilities originally planned for spent fuel to remain in the SFPs for a few years after discharge from the reactor core and then to be sent to a reprocessing facility. However, the US Government declared a moratorium on reprocessing in 1977. Although the ban was later lifted, reprocessing has not been pursued as a feasible option. Consequently, utilities expanded the storage capacity of SFPs by the use of high-density storage racks. Eventually, utilities needed additional storage capacity. In response to these needs, NRC provided a regulatory alternative for interim spent fuel storage in dry cask storage systems. For spent fuel management, both pool storage and dry storage are safe methods, but there are significant differences. Pool storage requires a greater operational vigilance on the part of the nuclear power plant to maintain the performance of electrical and mechanical systems using pumps, piping and instrumentation. Dry storage technology uses passive cooling systems with robust cask designs requiring minimal operational vigilance. The United States Nuclear Regulatory Commission (NRC), through the combination of a rigorous licensing and inspection program, ensures the safety and security of dry cask storage. NRC authorizes the storage of spent fuel at an independent spent fuel storage installation (ISFSI) under two licensing options: site-specific licensing and general licensing. In July 1986, the NRC issued the first site-specific license to the Surry Nuclear Power Plant in Virginia, authorizing the interim storage of spent fuel in a dry storage cask configuration. Today, there are over 30 ISFSIs currently licensed by the NRC with over 700 loaded dry casks. Current projections

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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

  16. Design and operational experience of dry cask storage systems

    International Nuclear Information System (INIS)

    This paper (Power Point presentation) describes cask storage design features and available dry cask storage technology, cask types used for dry storage, design characteristics of CASTOR casks, the German licensing basis for cask storage systems, shielding requirements, thermal layout, mechanical design, criticality safety and containment, licensing procedure, operational experience of dry cask storage in Germany and worldwide

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

    International Nuclear Information System (INIS)

    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

  18. ITER - Safety and licensing - One year after site decision

    International Nuclear Information System (INIS)

    The safe design of ITER has been paramount since the beginning of the ITER studies and the safety analysis was included in the Generic Site Safety Report produced in July 2001. On June, 28th 2005 it was decided to implement the experimental fusion facility in Europe, close to Marseilles, south of France. The design now needs to be checked according to the local legal requirements and the licensing will have to comply with the French regulations. The safety analysis will be presented to the regulator and public hearings should lead to the 'license'. Construction will then start. From March to May 2006 a public debate was launched to present the facility during a set of 20 meetings mostly in the locality. This process is the French implementation of the Aarhus convention, signed on June, 25th 1998. The future ITER operator was represented by the French Atomic Energy Authority (CEA), the ITER team being present for all meetings. The French regulations are mostly non-prescriptive and request that design provisions be taken according to the level of risk. Any codes and standards can be used as long as their safety margins are in good agreement with the level of reliability requested by the analysis. Nevertheless a few areas must follow prescriptive design rules. Fire prevention thus requires putting in place fire and confinement sectors; any chemical and radioactive vessels must be protected against accidental spilling. Pressure vessels and equipment must comply with a European directive and a French order in case of nuclear inventory. Building design and construction have to comply with European rules. The ITER designers, in close contact with the Participant Teams, are proceeding with the upgrading of the design to comply with these requirements. Priority has been given to those inputs which could have high impact on the design, for instance the building layout. The codes and standards for all equipment are also under revision in order to fit with the expected

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  1. NRC antitrust licensing actions, 1978--1996

    International Nuclear Information System (INIS)

    NUREG-0447, Antitrust Review of Nuclear Power Plants, was published in May 1978 and includes a compilation and discussion of U.S. Nuclear Regulatory Commission (NRC) proceedings and activity involving the NRC's competitive review program through February 1978, NUREG-0447 is an update of an earlier discussion of the NRC's antitrust review of nuclear power plants, NR-AIG-001, The US Nuclear Regulatory Commission's Antitrust Review of Nuclear Power Plants: The Conditioning of Licenses, which reviewed the Commission's antitrust review function from its inception in December 1970 through April 1976. This report summarizes the support provided to NRC staff in updating the compilation of the NRC's antitrust licensing review activities for commercial nuclear power plants that have occurred since February 1978. 4 refs., 4 tabs

  2. Adjuvants: Classification, Modus Operandi, and Licensing

    Science.gov (United States)

    Apostólico, Juliana de Souza

    2016-01-01

    Vaccination is one of the most efficient strategies for the prevention of infectious diseases. Although safer, subunit vaccines are poorly immunogenic and for this reason the use of adjuvants is strongly recommended. Since their discovery in the beginning of the 20th century, adjuvants have been used to improve immune responses that ultimately lead to protection against disease. The choice of the adjuvant is of utmost importance as it can stimulate protective immunity. Their mechanisms of action have now been revealed. Our increasing understanding of the immune system, and of correlates of protection, is helping in the development of new vaccine formulations for global infections. Nevertheless, few adjuvants are licensed for human vaccines and several formulations are now being evaluated in clinical trials. In this review, we briefly describe the most well known adjuvants used in experimental and clinical settings based on their main mechanisms of action and also highlight the requirements for licensing new vaccine formulations.

  3. AN EVALUATIONOF LICENSE PLATE RECOGNITION ALGORITHMS

    Directory of Open Access Journals (Sweden)

    Hadi Sharifi Kolour

    2011-01-01

    Full Text Available In the last decades vehicle license plate recognition systems are as central part in many traffic management and security systems such as automatic speed control, tracking stolen cars, automatic toll management, and access control to limited areas. There are many techniques for license plate detection. The goal of this paper is study and evaluate some most important LPD algorithms and compared them in terms of accuracy, performance, complexity, and their usefulness in different environmental condition. This evaluation gives views to the developers or end-users to choose the most appropriate technique for their applications. Our study and investigation show that the dynamic programming algorithm is the fastest and the Gabor transform is the most accuracy algorithm compared to other algorithms.

  4. NRC antitrust licensing actions, 1978--1996

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, S.J.; Simpson, J.J.

    1997-09-01

    NUREG-0447, Antitrust Review of Nuclear Power Plants, was published in May 1978 and includes a compilation and discussion of U.S. Nuclear Regulatory Commission (NRC) proceedings and activity involving the NRC`s competitive review program through February 1978, NUREG-0447 is an update of an earlier discussion of the NRC`s antitrust review of nuclear power plants, NR-AIG-001, The US Nuclear Regulatory Commission`s Antitrust Review of Nuclear Power Plants: The Conditioning of Licenses, which reviewed the Commission`s antitrust review function from its inception in December 1970 through April 1976. This report summarizes the support provided to NRC staff in updating the compilation of the NRC`s antitrust licensing review activities for commercial nuclear power plants that have occurred since February 1978. 4 refs., 4 tabs.

  5. Radiation control through licensing and intensive training

    International Nuclear Information System (INIS)

    Various types of intensive training courses to suit radiation workers in different fields were sponsored by both the Atomic Energy Council of Executive Yuan and the National Health Administration of Executive Yuan, Republic of China during the past seven years. During the years 1974-79, the number of radiation workers attending each training course, their age, sex and educational background are presented in detail. The typical course contents for both medical and non-medical radiation workers are given. A summary of the percentage of passes and failures of the final examination given at the end of each training course is also given. The present status of licensing for radiation facilities and workers is described, and its results are indicated. The successful control of ionizing radiation through this kind of intensive training and licensing is evidenced in the film badge records given by a centralized service laboratory located at the National Tsing Hua University. (author)

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

    International Nuclear Information System (INIS)

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

  7. Handling of design and licensing changes in France

    International Nuclear Information System (INIS)

    In France, the approach to obtaining an LTO operating licence is primarily based on the PSR system, which offers the opportunity to both examine, in depth, the installation conditions and to check that it actually complies with all the applicable regulatory requirements and provisions (conformity check). Another objective of a PSR in an LTO context is to improve the safety level of the operating unit, aligning it as much as possible with the most recent requirements applicable to newer installations with higher safety objectives, taking into account the latest developments in national and international expertise and OE (safety reassessment). Periodic safety reviews cover all the risks or drawbacks the installation may present in terms of safety, public health and environmental protection, including radioactive waste and releases. Within this PSR framework, the decision to authorize LTO is likely to require addressing issues covering a timeframe longer than ten years, although, when the period of extended operation is entered, PSRs continue to be conducted every ten years

  8. NRC licensing of uranium enrichment plants

    International Nuclear Information System (INIS)

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

  9. Licensing procedure for interim stores in Germany

    International Nuclear Information System (INIS)

    The coalition agreement of October 1998 signed by the parties in government contains a provision about the treatment of spent fuel elements from nuclear power plants which, in principle, seeks to avoid transports and terminate, which would also end transports to France and the UK, by July 1, 2005. After that date, all fuel elements arising are to be managed by direct disposal. Pending the start of operation of a suitable repository, this concept requires safekeeping of spent fuel elements in appropriate storage facilities. The consensus agreement between the federal government and the power utilities contains this approach with the goal of building on-site storage facilities. The Federal Office for Radiation Protection (BfS), as the competent supervisory authority under Sec. 6 of the Atomic Energy Act, has received licensing applications for temporary and on-site stores, respectively, as decentralized interim stores for all nuclear power plant sites in Germany (with the exception of Muelheim-Kaerlich, for which special regulations exist). Three technical concepts, namely two variants of a hall structure, a tunnel concept for Neckarwestheim, and a temporary store, must be examined by BfS in a licensing procedure including as its main steps public participation, examination of the preconditions for a permit, and drafting of the licensing decision. In addition, on-site stores require that an environmental impact assessment be carried out. Proceedings are conducted at BfS largely in parallel and speedily by a project group set up. BfS intends to finish all steps involving public participation still this year. When all preconditions have been met for licensing decisions to be granted, and with an assumed construction period of two years, on-site interim stores ought to be available from 2005 on. (orig.)

  10. Technology evaluation and licensing in Portuguese Universities

    OpenAIRE

    Rocha, António Miguel Sousa; Romero, Fernando

    2010-01-01

    Universities have adopted knowledge valorisation strategies to foster the practical application of research results. Technology transfer offices have been implemented in almost all European universities to evaluate, protect and support the transfer of university’s research outcomes. To this end, technology evaluation and licensing activities have been widely adopted and implemented by technology transfer units, allowing universities and inventors to obtain revenues through the establishment o...

  11. Compulsory licensing and access to drugs

    OpenAIRE

    Stavropoulou, C; Valletti, T.

    2015-01-01

    Compulsory licensing allows the use of a patented invention without the owner's consent, with the aim of improving access to essential drugs. The pharmaceutical sector argues that, if broadly used, it can be detrimental to innovation. We model the interaction between a company in the North that holds the patent for a certain drug and a government in the South that needs to purchase it. We show that both access to drugs and pharmaceutical innovation depend largely on the Southern country's abi...

  12. International Harmonization of Reactor Licensing Regulations

    International Nuclear Information System (INIS)

    The purpose of a harmonization policy for reactor licensing regulations on the basis of already considerable experience is to attain greater rationalisation in this field, in the interest of economic policy and healthy competition, and most important, radiation protection and safety of installations. This paper considers the legal instruments for such harmonization and the conditions for their implementation, in particular within the Communities framework. (NEA)

  13. Advances in PHWR design

    International Nuclear Information System (INIS)

    Recent advances by AECL in improved performance, cost reduction and safety improvement of CANDU reactors are described. Topics include: computer-aided design tools, up-front licensing, site utilization, plant life management, construction techniques, plant control, safety-critical software, advanced fuels, human-machine interface, heat sinks, radiation protection, feedback to design, emergency core cooling and probabilistic safety assessment

  14. 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.

  15. Safety and licensing program for the proposed irradiation research facility

    International Nuclear Information System (INIS)

    Atomic Energy of Canada Limited (AECL) proposes to replace NRU with a dual-purpose irradiation-research facility (IRF) to test Canada deuterium uranium (CANDU) fuels and materials and to perform materials research using neutrons. The reference IRF concept was estimated to cost $500 million and would require 87 months to complete. Approval of the IRF project is not expected to occur before 1997, and a favorable decision will be influenced by the estimated cost and confidence in the estimate. Accordingly, AECL has initiated a preproject program that includes code validation, analysis, development and testing, safety and licensing, and concept design activities to reduce uncertainties in the reference IRF project cost and schedule, and to develop cost and schedule reductions

  16. Licensing Support Experience of the BN-600 Operation

    International Nuclear Information System (INIS)

    License procedure - Main principle: • All works, including fatigue tests of new types of fuel, are carried out at the unit 3 Beloyarsk nuclear power plants with the BN-600 reactor with the justification of the regulatory body. • Justification procedure is standard for all power units and independent from the reactor types. • The regulatory body and independent experts or technical support organizations, which can be involved in this work by the regulatory body, review SAR, operational manuals and other operator documents. • Safety requirements (i.e. Federal rules and codes). The project and design documents shall meet safety requirements. • The technical and organizational measures for safety guarantee shall meet well-known results of the research investigations or shall be experimental validate

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

    International Nuclear Information System (INIS)

    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

  18. Licensing and continuous professional development of geodetic experts

    Directory of Open Access Journals (Sweden)

    Slobodan Pandžić

    2014-06-01

    Full Text Available The same as other engineering and technical fields, performing geodetic activities in the Republic of Serbia is regulated by relevant standards and system of licensing. Geodetic professionals licensing is conducted in accordance with the Law on Planning and Construction and the Regulations on Granting Licenses prescribed by Serbian Chamber of Engineers. Simultaneously, geodetic activity relating to the affairs of state survey and cadaster is regulated by the Law on State Survey and Cadaster and the Law on Amendments to the Law on State Survey and Cadaster, in which a special licensing system is implemented by the Republic Geodetic Authority. In both cases, the requirements to obtain licenses are: a diploma of higher education, prescribed work experience and the appropriate professional examination passed. The procedure for periodic renewing or extending the license validity is not stipulated. In most countries, like in other professions where a licensing system is applied, extending license validity with the proof of completed professional development is anticipated. Unfortunately, this is not the case for any type of license for geodetic experts in Serbia. This paper presents the proposal for establishing license renewal procedure and its linkage to the continuous professional development.

  19. Aseismic Test of Stationary Lead-acid Batteries and Brackets Based on Nuclear Safety Level%核安全级固定型铅酸蓄电池组及支架抗震试验研究

    Institute of Scientific and Technical Information of China (English)

    杨勇; 宫必宁; 张莹莹

    2011-01-01

    According to the aseismic test of stationary lead acid batteries and the brackets with nuclear safety level,the mathematical model is established to calculate the seismic response of the brackets by using finite element response spectrum method and equivalent static method. Compared with the experimental data, the results show that the response spectrum finite element method has better precision and reasonableness than the equivalent static method, which also has a conservative margin.%基于核安全级固定型铅酸蓄电池组及支架抗震试验,构建了相应数学分析模型,采用反应谱有限元法和等效静力法计算了支架地震响应,并与试验数据进行了对比.结果表明,反应谱有限元计算结果相对于等效静力计算结果相对精确、合理,且有一定保守裕度.

  20. Burnup credit considerations in dry spent-fuel storage licensing

    International Nuclear Information System (INIS)

    Burnup credit has been allowed in reactor basin spent-fuel storage at pressurized water reactors for a number of years. However, such storage occurs under strict administrative, procedural, and design controls. In recent years, dry spent-fuel storage cask vendors have expressed interest in designing cask fuel baskets with allowance for burnup credit. At last year's American Nuclear Society Winter Meeting, an ad hoc session was organized and authorized on burnup credit for dry storage and transportation casks. It has become clear that some utilities are interested in burnup credit for dry storage designs. Given this, the US Nuclear Regulatory Commission (NRC) staff is examining the technical issues involved in allowing burnup credit. Analytical work focused on the development of branch technical positions for determination of burnup credit for dry spent-fuel storage technology designs has begun. Procedural and administrative issues will be examined, based on licensing experience, and will also be the subject of branch technical positions. At an appropriate time, preparation of regulatory guides will be considered

  1. Four Essays on Technology Licensing and Firm Innovation

    DEFF Research Database (Denmark)

    Moreira, Solon

    &D strategies. On the supply side, the existing literature has been focused on understanding how technology licensing can be used by firms as a mechanism to recover investments in innovative activities and to foster learning opportunities. On the demand side, it has been shown that licensing is an important...... source that firms can tap into to feed their internal needs for innovative knowledge. While several studies have examined technology licensing through the lens of the licensor, research on how firms rely on licensing contracts to acquire knowledge and improve their innovation performance still leaves...... much to be investigated. Furthermore, with few exceptions, neither organizational nor contractual characteristics related to the licensing deals have received enough attention as determinants of the capacity of the acquiring firm to benefit from licensing in a new technology. The purpose of this...

  2. Licensing Procedures for Interim Storage of Spent Fuel in Germany

    International Nuclear Information System (INIS)

    In accordance with the waste management concept in Germany spent fuel is stored in interim storage facilities for 40 years until disposal in a geological repository. The storage concept bases on dry storage of the spent fuel in metallic transport and storage casks, standing upright in halls of reinforced concrete. Storage of spent fuel as well as significant modifications of the storage require a license according to art. 6 of the Atomic Energy Act. The Federal Office for Radiation Protection (Bundesamt für Strahlenschutz - BfS) is the competent licensing authority. The mode of the licensing procedure — whether formalized or non-formalized — depends on the necessity to carry out an environmental impact assessment. Formalized licensing procedures include a public participation procedure. In the following, the licensing prodecures are illustrated and a short overview over the current licensing procedures conducted by BfS is given. (author)

  3. Survey and Evaluation of Digital I and C Licensing Experiences

    International Nuclear Information System (INIS)

    Digital I and C licensing experiences showed significant performance variance among different cases, i.e., some were smooth and efficient while others were lengthy and problematic. In order to explain the causes of such variance and to develop more efficient licensing techniques, we conducted an in-depth survey and analysis of these licensing experiences. By viewing the licensing process as an evidence- confidence conversion process, a Licensing Performance Model has been developed and used as a framework to analyze the behavior characteristics of licensing activities. The model identified major factors and functions that dominate the performance of licensing process, among which the proficiency maturity and evidence profiles are the most critical factors that affect the licensing performance. During the evaluation step we were able to apply this model to explain why some previous licensing cases were successful and some were troublesome. This successful application shows the validity of the proposed model. Finally, we presented insights into the nature of licensing process gained form this study and recommended approaches for improving licensing performance. In this paper we reported the preliminary result of our survey and evaluation of major digital I and C licensing experiences accumulated in the recent years. The motivation is that we noticed the performance variance among different digital I and C licensing cases, i.e., some were smooth and efficient while others were lengthy and problematic. In order to explain the causes of such variance and to develop techniques for improving the effectiveness of licensing process, we conducted an in-depth survey and analysis of these experiences. By viewing the licensing process as a confidence conversion process, a Licensing Performance Model is developed and used as a framework to analyze the behavior characteristics of licensing activities. The model identified major factors and functions that dominate the performance

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  6. Four Essays on Technology Licensing and Firm Innovation

    OpenAIRE

    Moreira, Solon

    2014-01-01

    Licensing contracts represent one of the most widely used mechanisms to exchange technologies and transfer know-how between firms. Due to the opportunities that licensing creates for firms operating on both sides of the markets for technology, it has increasingly become an integral part of firms’ R&D strategies. On the supply side, the existing literature has been focused on understanding how technology licensing can be used by firms as a mechanism to recover investments in inn...

  7. Licensing One of the World's Oldest Professions: Massage

    OpenAIRE

    Robert J. Thornton; Edward J. Timmons

    2013-01-01

    In this paper, we analyze the development of occupational regulation of massage therapists in the United States as well as the effects of state licensing and certification on their earnings and numbers. Our results suggest that massage therapists working in states with licensing receive an earnings premium of as much as 16.2 percent. We also find some evidence that licensing seems to reduce the number of massage therapists. We find less convincing evidence that certification has had similar e...

  8. Creative Commons International The International License Porting Project

    OpenAIRE

    Maracke, Catharina

    2010-01-01

    When Creative Commons (CC) was founded in 2001, the core Creative Commons licenses were drafted according to United States Copyright Law. Since their first introduction in December 2002, Creative Commons licenses have been enthusiastically adopted by many creators, authors, and other content producers – not only in the United States, but in many other jurisdictions as well. Global interest in the CC licenses prompted a discussion about the need for national versions of the CC l...

  9. Licensing and continuous professional development of geodetic experts

    OpenAIRE

    Slobodan Pandžić; Slavoljub Tomić

    2014-01-01

    The same as other engineering and technical fields, performing geodetic activities in the Republic of Serbia is regulated by relevant standards and system of licensing. Geodetic professionals licensing is conducted in accordance with the Law on Planning and Construction and the Regulations on Granting Licenses prescribed by Serbian Chamber of Engineers. Simultaneously, geodetic activity relating to the affairs of state survey and cadaster is regulated by the Law on State Survey and Cadaster a...

  10. Methodology and findings of the NRC's materials licensing process redesign

    International Nuclear Information System (INIS)

    This report describes the work and vision of the team chartered to redesign the process for licensing users of nuclear materials. The Business Process Redesign team was chartered to improve the speed of the existing licensing process while maintaining or improving public safety and to achieve required resource levels. The report describes the team's methods for acquiring and analyzing information about the existing materials licensing process and the steps necessary to radically change this process to the envisioned future process

  11. Atomic Safety and Licensing Board Panel annual report

    International Nuclear Information System (INIS)

    In Fiscal Year 1990, The Atomic Safety and Licensing Board Panel (Panel) handled 40 proceedings involving the construction, operation, and maintenance of commercial nuclear power reactors or other activities requiring a license from the Nuclear Regulatory Commission. This report summarizes, highlights, and analyzes how the judges and licensing boards of the Panel addressed the wide-ranging issues raised in these proceedings during the year

  12. Social license to operate: case from brazilian mining industry

    Science.gov (United States)

    Santiago, Ana Lúcia F.; Demajorovic, Jacques; Aledo, Antonio

    2015-04-01

    influence of the company's approach. The results show that the strategy adopted by the company contributed to the process of SLO, furthermore it is necessary adopt strong methodologies that facilitate the engagement processes of the other company's stakeholders, as well as the challenge to keep on local legitimacy earned. Key words: Mining, social license to operate (SLO), social impact, corporate social responsibility, stakeholders. References: * FRANKS, DANIEL M.; COHEN, TAMAR. Social Licence in Design: Constructive technology assessment within a mineral research and development institution. Centre for Social Responsibility in Mining, Sustainable Minerals Institute, University of Queensland, Australia. 79 122 Technological Forecasting & Social Change. 2012.

  13. Licensing process for the power increase

    International Nuclear Information System (INIS)

    The licensing process for the power increase of a nuclear power station is presented, this includes the description of the effective normative framework, the attributions of the one Mexican regulator organism in nuclear matter, the definition and importance of the power level of a nuclear reactor for the safety studies. Also, the types of power increase according to its magnitude, and the regulator process that it includes the scope and the detail of the required information that it should be evaluated by the one regulator organism are discussed. Finally it offers a summary of the experience that one has in Mexico for this type of processes. (Author)

  14. Optimal Licensing Contracts with Three Innovation Types

    Directory of Open Access Journals (Sweden)

    Daniela MARINESCU

    2011-10-01

    Full Text Available In the paper we analyze the features of the optimal licensing contracts in the situation of asymmetric information between the license’s owner and the potential buyer. The approach is based on a classical model of adverse selection first proposed by Macho-Stadler and Perez-Castrillo (1991 and solved in an alternative way, using the informational rents as variables, by Marinescu and Marin (2011. Their model is extended in the present paper by assuming that the adverse selection parameter can have one of three possible values (corresponding to three possible types of innovations.

  15. Interim report of the DOE [Department of Energy] Type B Investigation Group: Appendix D, Licensing correspondence

    International Nuclear Information System (INIS)

    Sometime between April 28, 1988 and June 5, 1988, a 22-inch long by 2.625-in. diameter doubly encapsulated cesium-137 irradiation source began leaking in the RSI-Decatur, Georgia, irradiation facility. By November 1988 when the source was isolated, between 7 and 8 curies (0.4 grams) leaked. This source was one of 1576 produced at Hanford to isolate the highly radioactive elements of wastes stored in single-walled tanks there. The capsule was designed for long term storage in a benign controlled pool environment on the Hanford reservation. An investigation was conducted to evaluate the cause of the incident, the management and administrative matters including leasing and licensing, the capsule design and manufacture, and the capsule qualification process. This appendix presents licensing correspondence

  16. Power uprating and steam generator replacement at Tihange 1 - licensing aspects

    International Nuclear Information System (INIS)

    The licensing of the power uprating and steam generator replacement (PUSGR) of a nuclear power plant is a long multiple-step process. This paper describes the numerous aspects investigated during the PUSGR of Tihange 1, as seen by AVN, the technical support of the Belgian authorities. The main aspects covered are: 1) the regulatory context and the licensing procedure, 2) the safety studies: choice of the operating domain, data base for the accident analysis, methodologies for these analysis, reference core loading pattern and nuclear design, thermohydraulic studies and safety limits, justification for not reanalysing accidents not affected by the PUSGR, accident analysis (design basis accidents), transient analysis, verification of the capacity of safety systems and auxiliary systems, radiological consequences of accidents, regulations and protections, transition cycles, mechanical studies, 3) the follow-up of construction and installation activities, 4) the requalification and commissioning tests on site, 5) the upgrading of documents (procedures, Safety Analysis Report, Technical Specifications...). (author)

  17. 78 FR 23886 - Notice of Intent To Grant Exclusive License

    Science.gov (United States)

    2013-04-23

    ..., Agricultural Research Service, intends to grant to Biosortia Pharmaceuticals of Dublin, Ohio, an exclusive... the public interest to so license this invention as Biosortia Pharmaceuticals of Dublin, Ohio...

  18. 76 FR 78007 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2011-12-15

    ... (OFF), 7823 New London Drive, Springfield, VA 22153, Officers: Feras Hindi, Member, (Qualifying Individual), Ruba Hindi, Member, Application Type: New OFF License. Kemka USA Limited Liability Company...

  19. 77 FR 23719 - Ocean Transportation Intermediary License; Applicants

    Science.gov (United States)

    2012-04-20

    ... Type: New NVO License. Bertschi North America Inc. (NVO), 15811 Heatherdale Drive, Houston, TX 77059. Officers: Eloy Ramos, Director/President/Secretary/ Treasurer (Qualifying Individual), Hans J....

  20. Licensing biotech intellectual property in university-industry partnerships.

    Science.gov (United States)

    Drozdoff, Vladimir; Fairbairn, Daryl

    2015-03-01

    Appropriate negotiation and drafting of license agreements are critical to successfully establishing and managing the expansive and complex relationships that are becoming more common between industry and universities. More often than not, the resulting licensing agreements become quite lengthy and complex, and the key principles become difficult to discern among all the details. This summary provides a short, nonexhaustive introduction to some of the essential components of these licenses with the intent of providing the non-licensing professional a better appreciation of some of the key commercial and legal terms from both an academic and company perspective, keeping in mind some of the considerations that particularly apply to biotechnology deals. PMID:25605752

  1. 77 FR 61752 - Ocean Transportation Intermediary License Applicants

    Science.gov (United States)

    2012-10-11

    ... Embarque Corporation (NVO & OFF), 376 Totowa Avenue, Paterson, NJ 07502, Officers: Robert Guerra, President (QI), Henry Guerra, Vice President, Application Type: New NVO & OFF License. Ocean Line Logistics...

  2. 78 FR 15747 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Science.gov (United States)

    2013-03-12

    ... Nuclear Engineering (GEH) Licensing Topical Report, NEDC-33178P-A, Revision 1, ``General Electric... features (69 FR 33536; June 16, 2004). Engineering analyses, which may include engineering evaluations....315(c), must be filed in accordance with the NRC's E-Filing rule (72 FR 49139; August 28, 2007). The...

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

    DEFF Research Database (Denmark)

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

    2012-01-01

    performance lies in differences of absorptive capacity. In this study, we intend to relax this assumption and use data about 186 Chinese indigenous firms to investigate how differences in in-licensing portfolios lead to different effects on innovation performance. We find that firms benefit from prior in...

  4. 10 CFR 171.15 - Annual fees: Reactor licenses and independent spent fuel storage licenses.

    Science.gov (United States)

    2010-01-01

    ... only status and has spent fuel onsite, and each independent spent fuel storage 10 CFR part 72 licensee... onsite, and to each independent spent fuel storage 10 CFR part 72 licensee who does not hold a 10 CFR... NRC § 171.15 Annual fees: Reactor licenses and independent spent fuel storage......

  5. Nuclear Regulatory Commission activities to prepare for reviewing license applications and issuing licenses

    Energy Technology Data Exchange (ETDEWEB)

    Uleck, R.B.; DeFino, C.V. [Nuclear Regulatory Commission, Washington, DC (United States)

    1991-12-31

    The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) assigned States the responsibility to provide for disposal of commercial low-level radioactive waste (LLRW) by 1993. The LLRWPAA also required the US Nuclear Regulatory Commission (NRC) to establish procedures and develop the technical review capability to process license applications for new LLRW disposal facilities. Under the LLRWPAA, NRC is required, to the extent practicable, to complete its review of an LLRW disposal facility license application within 15 months of its submittal by a State. This provision of the LLRWPAA helps ensure that NRC, in addition to protecting public health and safety and the environment, facilitates States` achievement of LLRWPAA milestones for new facility development. A timely NRC review is needed for States to accomplish their objective of having new disposal facilities in operation on the dates prescribed in the LLRWPAA. To help assure NRC and States` compliance with the provisions of the LLRWPAA, NRC has developed a licensing review strategy that includes: (1) the further development of regulatory guidance, (2) enhancement of licensing review capability, and (3) prelicensing regulatory consultation with potential applicants.

  6. COMPARISON OF CERTAIN ABILITIES NEEDED BY WORKERS IN LICENSED NURSERIES AND LICENSED ORNAMENTAL HORTICULTURE BUSINESSES.

    Science.gov (United States)

    DILLON, ROY D.

    THIS STUDY WAS CONDUCTED TO DETERMINE THE EXTENT TO WHICH WORKERS WITH THE JOB TITLES OF GENERAL DIRECTORS, SALESMEN, SUPERVISORS, AND FIELD WORKERS IN LICENSED NURSERIES NEEDED AGRICULTURALLY ORIENTED KNOWLEDGE OF THE SAME KIND AND LEVEL AS WORKERS IN COMPARABLE JOB TITLES IN ORNAMENTAL HORTICULTURE BUSINESSES. DATA WERE COLLECTED BY PERSONAL…

  7. Main issues of the licensing of the Creys-Malville's LMFBR

    International Nuclear Information System (INIS)

    This report presents the main features of general interest concerning the licensing procedures, procedures which are still in progress. The design studies and the construction of the Creys-Malville power plant were submitted to several assessments which allowed to verify the correct realisation of the plant and to intervene in due time on important issues. All related aspects of the start-up tests are followed by the safety authorities in satisfactory conditions without increasing significantly the applicant own duties

  8. Navigating the Patent Thicket: Cross Licenses, Patent Pools and Standard Setting

    OpenAIRE

    Shapiro, Carl

    2004-01-01

    In several key industries, including semiconductors, biotechnology, computer software, and the Internet, our patent system is creating a patent thicket: an overlapping set of patent rights requiring that those seeking to commercialize new technology obtain licenses from multiple patentees. The patent thicket is especially thorny when combined with the risk of hold-up, namely the danger that new products will inadvertently infringe on patents issued after these products were designed. The need...

  9. STRATEGIC PARTNERSHIP FORMATION IN IT OFFSHORE OUTSOURCING: INSTITUTIONAL ELEMENTS FOR A BANKING ERP SYSTEM LICENSING

    OpenAIRE

    Luís Kalb Roses

    2013-01-01

    The purpose of this paper is to design a conceptual model of institutional elements for the formation of a client-supplier strategic partnership in IT outsourcing, involving an ERP system license contract. The model resulted from a longitudinal case study performed in a Brazilian transnational bank with businesses in four continents. This bank is one of the 10 largest American banks in terms of assets volume. Qualitative content analysis technique evaluated data collected from interviews, doc...

  10. Lessons learnt from ITER safety and licensing for DEMO and future nuclear fusion facilities

    International Nuclear Information System (INIS)

    Highlights: •The ITER safety and licensing process successfully reached the stage of the granting of the authorization to construct the facility. •Despite differences between ITER and DEMO, there are lessons to be learned for DEMO safety and licensing. •A number of issues have been identified where development is required for DEMO, strategies to be decided, technical issues to be resolved. -- Abstract: One of the strong motivations for pursuing the development of fusion energy is its potentially low environmental impact and very good safety performance. But this safety and environmental potential can only be fully realized by careful design choices. For DEMO and other fusion facilities that will require nuclear licensing, S and E objectives and criteria should be set at an early stage and taken into account when choosing basic design options and throughout the design process. Studies in recent decades of the safety of fusion power plant concepts give a useful basis on which to build the S and E approach and to assess the impact of design choices. The experience of licensing ITER is of particular value, even though there are some important differences between ITER and DEMO. The ITER project has developed a safety case, produced a preliminary safety report and had it examined by the French nuclear safety authorities, leading to the licence to construct the facility. The key technical issues that arose during this process are recalled, particularly those that may also have an impact on DEMO safety. These include issues related to postulated accident scenarios, environmental releases during operation, occupational radiation exposure, and radioactive waste

  11. Licensing of spent fuel dry storage and consolidated rod storage

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  13. Licensing systems for reactor operators in Japan

    International Nuclear Information System (INIS)

    Any person proposing to set up a reactor, whether for commercial power generation or for research, is obliged by law to adopt a ''chief tech-ician'' for the reactor from among those who have passed national examinations for such technicians, for appointment to the supervisory position to ensure safety in reactor operation (System for Reactor Chief Technicians). Candidates for chief technicians first take a written test, followed by an oral test. The written test is given to find out whether or not they have the special knowledge necessary to discharge their possible duties as chief technicians. The oral test is given to see if they have the practical knowledge necessary for reactor operation. After the TMI accident, the Ministry of International Trade and Industry carried out a special inspection of nuclear power plants, leading to the conclusion that it was necessary to make constant efforts to upgrade the skills of the operators. Thus the MITI enforced a new system (System for Reactor Responsible Operators) in July 1980, with the aim of fostering and securing highly qualified responsible operators. The Thermal and Nuclear Power Engineering Society was appointed as the licensing organization in January 1981. It was made obligatory for owners of commercial power reactors to assign persons licensed by the Society as responsible operators of nuclear power reactors. (Nogami, K.)

  14. Licensing Support Network: An Electronic Discovery System

    International Nuclear Information System (INIS)

    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

  15. Licensing new uranium production projects in Argentina

    International Nuclear Information System (INIS)

    Due to the decision to complete construction and begin operation of the Atucha II Plant, Argentina's nuclear reactor fuel requirements will increase in the mid-term from 120 tU/year to 220 tU/year. Current market conditions justify reactivation of indigenous production of uranium concentrates that could progressively replace imports. Consequently, CNEA presented to the Mendoza Province and national (Nuclear Regulatory Authority) licensing authorities a proposal for reactivation of the San Rafael Mining-Milling Complex. The main step in the licensing process is the Environmental Impact Assessment (EIA). This includes both assessment of the engineering for remediation of waste generated during previous production activities, and of environmental management of future production activities. The EIA was carried out by the National Technological University. The Cerro Solo Project, Chubut Province, which is currently at the pre-feasibility stage, is being considered for initiation of the feasibility study and development-production stage. Under present market conditions, the estimated project production cost has become competitive, and the resources of the project could be sufficient to supply the long-term needs of Argentina's nuclear power plants. Taking into account the increasing interest in environmental issues, and stricter environmental regulations, the main challenges to re-activation of uranium production in Argentina are: improvement of interaction with local communities; training of skilled personnel in waste management; and developing cost estimates and plans for mine-mill closure. (author)

  16. Uranium mine project licensing: Cameco's current experience

    International Nuclear Information System (INIS)

    Environmental assessment and licensing requirements for new uranium projects have become more complex, and can have a substantial influence on the timelines needed to bring new production on-line. This increased complexity is taking place in an era that is witnessing a resurging interest in uranium exploration. The assessment and licensing process has evolved to include more sophisticated ecological risk assessment, more detailed waste rock and tailings management plans and comprehensive socio-economic impact assessments. While such assessments are fully compatible with sustainable development objectives, they do take time. The current challenges, as encountered by Cameco in its most recent work, are associated with timelines, predictability and effectiveness. All are needed in the process if market demands are to be met efficiently. The good news remains that the assessment process, while frustrating at times in its duration, strongly supports our main collective environmental goal, which is to solidly support the clean environment aspects of nuclear power at our end of the nuclear fuel chain. (author)

  17. Licensing strategies for electric power generating facilities

    International Nuclear Information System (INIS)

    Siting and licensing electric power generating facilities can be a time-consuming, costly, and frustrating process. An aggressive and constantly changing regulatory climate, heightened public awareness of environmental issues, and the proliferation and resilience of opposition groups have created a permitting atmosphere in which the developer must shoulder the burden of proof that the environmental impacts of his project will be acceptable; and today, acceptable is fast becoming negligible. Throughout this complex process, it is important that the developer not lose sight of the objective of environmental permitting, environmental protection in order to ensure successful facility implementation and operation. Done properly, the environmental permitting process can also ensure continued good community relations long after the facility comes on line. As discussed in this paper, important keys to the successful licensing of a power project include assembling the right permitting team at the right stage in the development process, selecting the right site within the right host community, developing and implementing a sound permitting strategy, and executing a careful public interaction program

  18. DESIGNING A PRODUCT CATALOGUE FOR CAT BAGS FALL WINTER 2016

    OpenAIRE

    Vorobyeva, Lidia

    2015-01-01

    The objective of this thesis project was to create a product catalogue for the brand Cat Bags. The project was conducted in co-operation with the bag manufacturer GROWN UP Group and its part called GROWN UP Licenses. The GROWN UP Licenses owns a license to produce and sell bags and related products under the brand Cat. Designing a product catalogue is a complex project including co-operation and collaboration with the GROWN UP Licenses marketing team and a senior graphic designer. The proc...

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

    International Nuclear Information System (INIS)

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

  20. Pedagogy and Culture: An Educational Initiative in Supporting UAE Nursing Graduates Prepare for a High-Stakes Nurse Licensing Examination

    Science.gov (United States)

    Brownie, Sharon M.; Williams, Ged; Barnewall, Kate; Bishaw, Suzanne; Cooper, Jennifer L.; Robb, Walter; Younis, Neima; Kuzemski, Dawn

    2015-01-01

    Graduates of an Abu Dhabi transnational nursing degree struggled with the mandatory national licensing examination. Poor pass rates undermine graduate career futures and impact on the workforce capacity building contributions of the partnering transnational educational providers. This paper describes how the design and delivery of an intensive…