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AbstractAbstract
[en] The projected increase in electricity demand, increased concern over emissions along with more stringent emission requirements, volatility of the gas and oil supplies and prices, and the convergence of favourable conditions and legislation make nuclear power a practical option for meeting future electricity base-load demands. (author)
Primary Subject
Source
Jencic, I.; Lenosek, M. (Nuclear Society of Slovenia, Ljubljana (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: Agency for Radwaste Management, Ljubljana (Slovenia); AREVA, Framatome ANP, Paris (France); Atel AG, Olten (Switzerland); Atel Energija, Ljubljana (Slovenia); GEN energija, Krsko (Slovenia); Inst. of Metal Constructions, Ljubljana (Slovenia); INETEC-Inst. for Nuclear Technology, Zagreb (Croatia); Inst. Jozef Stefan, Ljubljana (Slovenia); Financial Fund for Decommissioning of Nuclear Power Plant Krsko, Krsko (Slovenia); Westinghouse Electric Europe, Brussels (Belgium); ANSYS, Canonsburg, PA (United States); Slovenian Research Agency, Ljubljana (Slovenia); Elmont, Krsko (Slovenia); IBE, Consulting Engineers Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); Pool for Insurance and Reinsurance of Nuclear Risk, Ljubljana (Slovenia); NUMIP Engineering, Construction, Maintenance and Production, Ljubljana (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); [831 p.]; ISBN 978-961-6207-28-7;
; 2007; [8 p.]; International Conference Nuclear Energy for New Europe 2007; Portoroz (Slovenia); 10-13 Sep 2007; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 10 refs.

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AbstractAbstract
[en] Operating experience is not new, in the most of the activities that we perform in our daily lives, we can find examples of how, using the knowledge that we acquired to develop a work and to solve problems, we can get an improvement or sounded benefit. (Author)
Original Title
Aprendiendo de la experiencia operativa
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Journal Article
Journal
Nuclear Espana (1996); ISSN 1137-2885;
; v. 283; p. 25-28

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Magnarelli, D.; Levin, A.E.
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France)2007
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France)2007
AbstractAbstract
[en] The 10 CFR 52 process provides for a single combined license (COL) to be granted prior to the beginning of construction. Incorporated into the COL is a set of inspections, tests, analyses and acceptance criteria (ITAAC) which, when satisfied, provide the Nuclear Regulatory Commission (NRC) with reasonable assurance that the completed plant has been constructed properly and will operate safely in accordance with the terms of the license. The licensee performs the inspections, tests and analyses, and determines that the acceptance criteria have been fulfilled; the NRC must make a finding that the ITAAC requirements have been satisfied before fuel loading at the nuclear power plant is permitted. The challenge is that the concept of ITAAC is new and not well defined. This paper addresses some of the ITAAC issues for the U.S. EPR approach for coordination of ITAAC with design, procurement, construction and startup activities to ensure timely approval of fuel loading and commissioning for plant operation. (authors)
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Source
2007; 5 p; ICAPP 2007 - International congress on advances in nuclear power plants. The nuclear renaissance at work; Nice Acropolis (France); 13-18 May 2007; Available from: SFEN, 5 rue des Morillons, 75015 Paris (France); 3 refs.
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Jordan, Pete
Idaho National Laboratory (United States). Funding organisation: DOE - NE (United States)2010
Idaho National Laboratory (United States). Funding organisation: DOE - NE (United States)2010
AbstractAbstract
[en] This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.
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Source
1 Sep 2010; vp; AC07-05ID14517; Available from http://www.inl.gov/technicalpublications/Documents/4655323.pdf; PURL: https://www.osti.gov/servlets/purl/991911-2o1L9B/; doi 10.2172/991911
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Chung, D.-H.; Kim, J.-H.; Cho, C.-H.; Kim, S.-M., E-mail: dhchung@actbest.com
New nuclear frontiers. 30th annual Canadian Nuclear Society conference and 33rd CNS/CNA student conference2009
New nuclear frontiers. 30th annual Canadian Nuclear Society conference and 33rd CNS/CNA student conference2009
AbstractAbstract
[en] The trip delay time that is determined by using RFSP-IST is applied to the Loss of Regulation (LOR) simulations of Wolsong-1, which is scheduled to undergo a major refurbishment project. The safety analyses required for licensing after refurbishment are currently being carried out using the update-to-date Canadian Industry Standard Toolset code suite. Since the POINTSIM program used in the past to calculate trip delay time is not included in IST, the RFSP-IST code is being mandatorily used in place of the POINTSIM functions. The CATHENA LOR simulation results obtained based upon the RFSP-IST determined trip delay times clearly justify the use of procedures that are developed to run *CERBERUS, *INTREP and *TRIP-TIME modules in the context of determining trip delay time. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); 275 Megabytes; ISBN 0-919784-95-X;
; 2009; [9 p.]; 30. annual canadian nuclear society conference; Calgary, Alberta (Canada); 31 May - 3 Jun 2009; 33. CNS/CNA student conference; Calgary, Alberta (Canada); 31 May - 3 Jun 2009; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 14 refs., 3 tabs., 3 figs.

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AbstractAbstract
No abstract available
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2009; 19 p; BULATOM International Nuclear Forum on Nuclear Energy - Challenges and Prospects; Varna (Bulgaria); 27-29 May 2009; Power Point Presentation
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Lafreniere, K.
Atoms for Power, Health and the Environment. 31st annual conference of the Canadian Nuclear Society and 34th annual conference of the Canadian Nuclear Society and Canadian Nuclear Association2010
Atoms for Power, Health and the Environment. 31st annual conference of the Canadian Nuclear Society and 34th annual conference of the Canadian Nuclear Society and Canadian Nuclear Association2010
AbstractAbstract
[en] CNSC staff introduced a new Power Reactor Operating Licence (PROL) in order to strengthen the regulatory oversight of power reactor operation, while increasing regulatory effectiveness and efficiency by focusing on risk-significant issues and reducing purely administrative efforts. The PROLs have been simplified by incorporating a more risk-informed approach and by eliminating cascading references to working level licensee documentation and regulatory expectations. To ensure that there is a common understanding for each requirement specified in the PROL, CNSC staff prepared a Licence Conditions Handbook (LCH), which provides technical details and compliance verification criteria on how licence conditions are to be met. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); 111 Megabytes; ISBN 978-1-926773-01-8;
; 2010; [5 p.]; 31. Annual Conference of the CNS; Montreal, Quebec (Canada); 24-27 May 2010; 34. Annual Student Conference of the CNS and CNA; Montreal, Quebec (Canada); 24-27 May 2010; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 1 fig.

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O'Hara, J.; Persensky, J. J.; Szabo, A.
Proceedings of the 5. International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology2006
Proceedings of the 5. International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology2006
AbstractAbstract
[en] Advanced reactors are expected to be based on a concept of operations that is different from what is currently used in today's reactors. Therefore, regulatory staff may need new tools, developed from the best available technical bases, to support licensing evaluations. The areas in which new review guidance may be needed and the efforts underway to address the needs will be discussed. Our preliminary results focus on some of the technical issues to be addressed in three areas for which new guidance may be developed: automation and control, operations under degraded conditions, and new human factors engineering methods and tools. (authors)
Primary Subject
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American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States); 1430 p; ISBN 0-89448-051-0;
; 2006; p. 938-943; NPIC and HMIT 2006: 5. International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology; Albuquerque, NM (United States); 12-16 Nov 2006; Country of input: France; 4 refs.

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Book
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O'HARA, J.; PERSENSKY, J.; SZABO, A.
BROOKHAVEN NATIONAL LABORATORY (United States). Funding organisation: DOE/NRC/ANS (United States)2006
BROOKHAVEN NATIONAL LABORATORY (United States). Funding organisation: DOE/NRC/ANS (United States)2006
AbstractAbstract
[en] Advanced reactors are expected to be based on a concept of operations that is different from what is currently used in today's reactors. Therefore, regulatory staff may need new tools, developed from the best available technical bases, to support licensing evaluations. The areas in which new review guidance may be needed and the efforts underway to address the needs will be discussed. Our preliminary results focus on some of the technical issues to be addressed in three areas for which new guidance may be developed: automation and control, operations under degraded conditions, and new human factors engineering methods and tools
Primary Subject
Source
1 Oct 2006; 6 p; ANS 2006 WINTER MEETING AND NUCLEAR TECHNOLOGY EXPO; ALBUQUERQUE, NM (United States); 12-16 Nov 2006; 66015113277; AC02-98CH10886; Available from http://www.pubs.bnl.gov/documents/32656.pdf; PURL: https://www.osti.gov/servlets/purl/893861-rTg6db/
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AbstractAbstract
[en] The first experience on how a part of the ARAMIS methodology has contributed to demonstration of safety in the licensing process in Slovenia for a new Seveso II plant is described. There are two foci of this description: first, trustworthy of the methodology for evaluating safety, and second, the role of a land-use plan in issuing a construction permit for the new plant. In the context of the first focus, we present why has been safety report first rejected by the regulator, and later-on accepted after applying components of the ARAMIS methodology in its revised version. In the context of the second focus, we discuss a relationship between the land-use plan and the licensing process for the new plant. The outcomes of this Seveso II plant licensing case are that the ARAMIS approach, in spite it was still under development when applied, is more transparent and credible comparing to the others, which have also been applied. This is related to the demonstration of how safety management system and general safety behaviour is integrated into the overall management policy. The conclusions take into account regulator's response in the licensing process
Primary Subject
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S0304-3894(05)00385-7; Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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