Aging management evaluation of the residual heat removal system for Westinghouse PWRs. Final report
Technical Report
·
OSTI ID:123186
- Westinghouse Electric Corporation, Pittsburgh, PA (United States)
This report presents a generic methodology to justify operating nuclear plant auxiliary systems beyond their design operating life. Referred to as Aging Management Evaluation, it considers safety-related functions as required for license renewal ({open_quotes}intended functions{close_quotes} as defined in 10CFR Part 54) as well as non-safety-related functions. The Residual Heat Removal System (RHRS), which generally provides both safety-related and non-safety-related functions, was selected as the vehicle for demonstrating the methodology. The methodology presented in this report has demonstrated that all RHRS functions are ensured during a period of extended operation. All functions, including safety related ({open_quotes}intended{close_quotes}) and non-safety-related functions, are ensured by design assumptions/margins, existing maintenance programs/practices, and applicable regulatory programs.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (United States); Westinghouse Electric Corp., Pittsburgh, PA (United States)
- Sponsoring Organization:
- Electric Power Research Inst., Palo Alto, CA (United States)
- OSTI ID:
- 123186
- Report Number(s):
- EPRI-TR--105135
- Country of Publication:
- United States
- Language:
- English
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