AbstractAbstract
[en] The Nuclear Regulatory Commission's (NRC) guidance, NUREG-1407, on performing Individual Plant Examinations for External Events (IPEEE) allows a Seismic Margins Assessment (SMA) to address the IPEEE seismic issue regarding the survivability of plant equipment during a seismic event and the capability of the plant to safely shutdown following the seismic event. The NRC guidance further allows the use of the NRC SMA approach or the Electric Power Research (EPRI) approach to evaluate these issues. In addition, the NRC's Unresolved Safety Issue A-46 (USI A-46) can also be efficiently addressed with the EPRI SMA evaluation. These methodologies are useful in determining a minimum list of equipment required for safe shutdown (i.e., Safe Shutdown Equipment Lists). The resultant Safe Shutdown Equipment List, SSEL, is used to identify the electrically powered equipment required for safe shutdown for which a relay evaluation is required. The evaluation of relays associated with safe shutdown equipment is necessary since equipment can fail to operate properly due to mechanical failure or improper operation/actuation due to relay failure. SAIC has performed relay evaluations on five nuclear power plants. This paper is intended to summarize the practical insights and lessons learned from use of the EPRI SMA approach
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Saleem, M.A. (ed.) (AECL, Mississauga, Ontario (Canada)); Aggarwal, M.C. (ed.); 372 p; ISBN 0-7918-1787-3; ; 1996; p. 293-297; American Society of Mechanical Engineers; New York, NY (United States); American Society of Mechanical Engineers (ASME) pressure vessels and piping conference; Montreal (Canada); 21-26 Jul 1996; American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, NY 10017 (United States) $60.00
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American Nuclear Society 1975 winter meeting; San Francisco, CA, USA; 16 Nov 1975; Published in Summary Form Only.
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Journal Article
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Transactions of the American Nuclear Society; v. 22 p. 531
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AbstractAbstract
[en] The existing instrument air system at Turkey Point station uses mobile diesel-driven air compressors. Although these diesel compressors have performed their function well, they represent a maintenance and financial burden requiring engineering review. An engineering evaluation is ongoing to develop several feasible conceptual design options to upgrade the instrument air systems. This phase-1 study was performed to assess the reliability of the various proposed design options. A phase-2 study will be conducted later to determine the core damage frequency for a selected option
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Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future; Chicago, IL (United States); 15-20 Nov 1992; CONF-921102--
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[en] The events at Fukushima Daiichi taught us that meeting a deterministic design basis requirement for external hazards does not assure that the risk is low. As observed at the plant, the two primary reasons for this are failure cliffs above the design basis event and that combined hazard effects are not considered in design. Because the possible combinations of design basis exceedences and external hazard combinations are very large and complex, an approach focusing only on the most important ones is needed. For this reason, a risk informed approach is the most effective approach, which is discussed in this paper. (author)
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Canadian Nuclear Society, Toronto, Ontario (Canada); Canadian Nuclear Association, Ottawa, Ontario (Canada); Natural Resources Canada (Canada); International Atomic Energy Agency, Vienna (Austria); 270 Megabytes; ISBN 978-1-926773-16-2; ; 2014; [14 p.]; 19. Pacific Basin Nuclear Conference; Vancouver, British Columbia (Canada); 24-28 Aug 2014; 38. Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association; Vancouver, British Columbia (Canada); 24-28 Aug 2014; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); Paper PBNC2014-097. 8 refs., 1 fig.
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