Aging study of boiling water reactor residual heat removal system
A study of the aging effects on Residual Heat Removal (RHR) systems in Boiling Water Reactors (BWRs) was performed as part of the Nuclear Plant Aging Research (NPAR) program. The objectives of the NPAR program are to provide a technical basis for the identification and evaluation of degradation caused by age in nuclear power plant applications. The information from this and other NPAR studies will be used to assess the impact of aging on plant safety and to develop effective mitigation actions. The effects of aging in the RHR system were characterized using the Aging and Life Extension Assessment Program (ALEAP) Systems Level Plan developed by Brookhaven National Laboratory. Failure data from various national data bases were reviewed and analyzed to identify predominant failure modes, causes and mechanisms. Time-dependent failure frequencies for major components were calculated to identify aging trends. Plant specific information was also reviewed to supplement data base results. A computer program (PRAAGE-1988) was developed and implemented to model a typical RHR design and perform time-dependent Probabilistic Risk Assessment (PRA) calculations. Time-dependent failure probabilities were input to the PRAAGE program to evaluate the effects of aging on component importance and system unavailability. 21 refs., 63 figs., 26 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5960372
- Report Number(s):
- NUREG/CR-5268; BNL-NUREG-52177; ON: TI89014203
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AFTER-HEAT REMOVAL
AGING
AVAILABILITY
BWR TYPE REACTORS
COMPUTER CODES
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
FAILURE MODE ANALYSIS
FAILURES
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
P CODES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
REMOVAL
RHR SYSTEMS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS