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Title: Regulatory instrument review: Management of aging of LWR (light water reactor) major safety-related components

Abstract

This report comprises Volume 1 of a review of US nuclear plant regulatory instruments to determine the amount and kind of information they contain on managing the aging of safety-related components in US nuclear power plants. The review was conducted for the US Nuclear Regulatory Commission (NRC) by the Pacific Northwest Laboratory (PNL) under the NRC Nuclear Plant Aging Research (NPAR) Program. Eight selected regulatory instruments, e.g., NRC Regulatory Guides and the Code of Federal Regulations, were reviewed for safety-related information on five selected components: reactor pressure vessels, steam generators, primary piping, pressurizers, and emergency diesel generators. Volume 2 will be concluded in FY 1991 and will also cover selected major safety-related components, e.g., pumps, valves and cables. The focus of the review was on 26 NPAR-defined safety-related aging issues, including examination, inspection, and maintenance and repair; excessive/harsh testing; and irradiation embrittlement. The major conclusion of the review is that safety-related regulatory instruments do provide implicit guidance for aging management, but include little explicit guidance. The major recommendation is that the instruments be revised or augmented to explicitly address the management of aging.

Authors:
 [1]
  1. Pacific Northwest Lab., Richland, WA (USA)
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Pacific Northwest Lab., Richland, WA (USA)
Sponsoring Org.:
USNRC
OSTI Identifier:
6528445
Report Number(s):
NUREG/CR-5490-Vol.1; PNL-7190-Vol.1
ON: TI91002432; TRN: 91-001143
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 29 ENERGY PLANNING, POLICY AND ECONOMY; REACTOR COMPONENTS; AGING; US NRC; RECOMMENDATIONS; PIPES; PRESSURE VESSELS; REACTOR SAFETY; REGULATIONS; STANDARDS; STEAM GENERATORS; WATER COOLED REACTORS; BOILERS; CONTAINERS; NATIONAL ORGANIZATIONS; REACTORS; SAFETY; US ORGANIZATIONS; VAPOR GENERATORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210700 - Nuclear Power Plants- Regulation & Licensing; 293000 - Energy Planning & Policy- Policy, Legislation, & Regulation; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Werry, E V. Regulatory instrument review: Management of aging of LWR (light water reactor) major safety-related components. United States: N. p., 1990. Web.
Werry, E V. Regulatory instrument review: Management of aging of LWR (light water reactor) major safety-related components. United States.
Werry, E V. Mon . "Regulatory instrument review: Management of aging of LWR (light water reactor) major safety-related components". United States.
@article{osti_6528445,
title = {Regulatory instrument review: Management of aging of LWR (light water reactor) major safety-related components},
author = {Werry, E V},
abstractNote = {This report comprises Volume 1 of a review of US nuclear plant regulatory instruments to determine the amount and kind of information they contain on managing the aging of safety-related components in US nuclear power plants. The review was conducted for the US Nuclear Regulatory Commission (NRC) by the Pacific Northwest Laboratory (PNL) under the NRC Nuclear Plant Aging Research (NPAR) Program. Eight selected regulatory instruments, e.g., NRC Regulatory Guides and the Code of Federal Regulations, were reviewed for safety-related information on five selected components: reactor pressure vessels, steam generators, primary piping, pressurizers, and emergency diesel generators. Volume 2 will be concluded in FY 1991 and will also cover selected major safety-related components, e.g., pumps, valves and cables. The focus of the review was on 26 NPAR-defined safety-related aging issues, including examination, inspection, and maintenance and repair; excessive/harsh testing; and irradiation embrittlement. The major conclusion of the review is that safety-related regulatory instruments do provide implicit guidance for aging management, but include little explicit guidance. The major recommendation is that the instruments be revised or augmented to explicitly address the management of aging.},
doi = {},
url = {https://www.osti.gov/biblio/6528445}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1990},
month = {10}
}

Technical Report:
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