Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Application of reliability-centered maintenance to boiling water reactor emergency core cooling systems fault-tree analysis

Journal Article · · Nuclear Technology
OSTI ID:89656
;  [1]
  1. Pennsylvania State Univ., University Park, PA (United States). Nuclear Engineering Dept.

Reliability-centered maintenance (RCM) methods are applied to boiling water reactor plant-specific emergency core cooling system probabilistic risk assessment (PRA) fault trees. The RCM is a technique that is system function-based, for improving a preventive maintenance (PM) program, which is applied on a component basis. Many PM programs are based on time-directed maintenance tasks, while RCM methods focus on component condition-directed maintenance tasks. Stroke time test data for motor-operated valves (MOVs) are used to address three aspects concerning RCM: (a) to determine if MOV stroke time testing was useful as a condition-directed PM task; (b) to determine and compare the plant-specific MOV failure data from a broad RCM philosophy time period compared with a PM period and, also, compared with generic industry MOV failure data; and (c) to determine the effects and impact of the plant-specific MOV failure data on core damage frequency (CDF) and system unavailabilities for these emergency systems. The MOV stroke time test data from four emergency core cooling systems [i.e., high-pressure coolant injection (HPCI), reactor core isolation cooling (RCIC), low-pressure core spray (LPCS), and residual heat removal/low-pressure coolant injection (RHR/LPCI)] were gathered from Philadelphia Electric Company`s Peach Bottom Atomic Power Station Units 2 and 3 between 1980 and 1992. The analyses showed that MOV stroke time testing was not a predictor for eminent failure and should be considered as a go/no-go test. The failure data from the broad RCM philosophy showed an improvement compared with the PM-period failure rates in the emergency core cooling system MOVs. Also, the plant-specific MOV failure rates for both maintenance philosophies were shown to be lower than the generic industry estimates.

OSTI ID:
89656
Journal Information:
Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 1 Vol. 111; ISSN 0029-5450; ISSN NUTYBB
Country of Publication:
United States
Language:
English

Similar Records

Application of reliability-centered-maintenance to BWR ECCS motor operator valve performance
Conference · Thu Dec 31 23:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States) · OSTI ID:6960056

MOV refurbishment program cuts costs, meets requirements
Journal Article · Thu Jan 31 23:00:00 EST 1991 · Power Engineering; (United States) · OSTI ID:5243809

Effects of a RCIC steamline break on the HPCI room
Conference · Tue Oct 01 00:00:00 EDT 1996 · OSTI ID:376171