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Aging Management of Reactor Coolant System Mechanical Components in Pressurized Water Reactors for License Renewal

[+] Author Affiliations
M. Subudhi, R. Morante

Brookhaven National Laboratory, Upton, NY

A. D. Lee

U.S. Nuclear Regulatory Commission, Washington, D.C.

Paper No. PVP2002-1372, pp. 41-49; 9 pages
doi:10.1115/PVP2002-1372
From:
  • ASME 2002 Pressure Vessels and Piping Conference
  • Selected Topics on Aging Management, Reliability, Safety and License Renewal
  • Vancouver, BC, Canada, August 5–9, 2002
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4655-5
  • Copyright © 2002 by ASME

abstract

The reactor coolant system (RCS) mechanical components in pressurized water reactors (PWRs) that require an aging management review for license renewal include the primary loop piping and associated connections to other support systems, reactor vessel, reactor vessel internals, pressurizer, steam generators, reactor coolant pumps, and all other inter-connected piping, pipe fittings, valves, and bolting. All major RCS components are located inside the reactor building. Based on the evaluation findings of recently submitted license renewal applications for pressurized water reactors, this paper presents the plant programs and/or activities proposed by the applicants to manage the effects of aging. These programs and/or activities provide reasonable assurance that the intended function(s) of these mechanical components will be maintained for the period of extended operation. The license renewal application includes identification of RCS subcomponents that are within the scope of license renewal and are vulnerable to age-related degradation when exposed to environmental and operational conditions, determination of the effects of aging on their intended safety functions, and implementation of the aging management programs and/or activities including both current and new programs. Industry-wide operating experience, including generic communication by the NRC, is part of the aging management review for the RCS components. This paper presents a number of generic issues, including the time-limited aging analyses, associated with RCS components that require further review by the staff.

Copyright © 2002 by ASME

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