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Regulatory and Industry Guidance on Use of Risk Technology in Nuclear Power Plant Applications

[+] Author Affiliations
Mansoor H. Sanwarwalla

Sargent & Lundy, LLC, Chicago, IL

Paper No. PVP2007-26271, pp. 313-317; 5 pages
  • ASME 2007 Pressure Vessels and Piping Conference
  • Volume 7: Operations, Applications and Components
  • San Antonio, Texas, USA, July 22–26, 2007
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4285-1 | eISBN: 0-7918-3804-8
  • Copyright © 2007 by ASME


Since the United States Nuclear Regulatory Commission (USNRC) published its landmark “Reactor Safety Study — An Assessment of Accident Risks in U. S. Commercial Nuclear Power Plants” in late 1975, commercial nuclear power industry, encouraged by the USNRC, have since then been applying Probabilistic Risk Assessment (PRAs) in their nuclear power units in areas of in-service testing, in-service inspection, quality assurance, technical specifications, maintenance, etc. To guide and regulate the industry in use of PRAs, Regulatory Guides and Standards have been written and are being revised continuously by the USNRC, American Society of Mechanical Engineers (ASME) and American Nuclear Society (ANS). The current use of PRA takes credit for single failure criterion based on applicability of codes and standards. The proposed new USNRC regulation 10 CFR Part 53 applicable for all reactor technologies is silent on the applicability of current standards endorsed by the regulatory body. The impact of the proposed new rule to both new and the current application needs to be studied. This paper will review the application of the various guidance documents for their use in commercial nuclear power plants with emphasis on the new generation nuclear power plants.

Copyright © 2007 by ASME



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