Demonstration of reliability-centered maintenance
Technical Report
·
OSTI ID:5740519
- Erin Engineering and Research, Inc., Walnut Creek, CA (USA)
On March 9, 1988 the Southern California Edison Company was selected by the Electric Power Research Institute as one of two utilities to perform a large scale Reliability-Centered Maintenance demonstration project to be co-funded by EPRI and SCE. The overall objective of this project is to demonstrate that RCM can be effectively performed in a plant environment leading to improved overall unit performance. The objective of SCE is to optimize the existing Preventive Maintenance program at San Onofre Nuclear Generating Station Unit 2. The successful achievement of this goal requires the active involvement and the cooperative efforts of the operations and Maintenance Support, Maintenance, Station Technical, and Operations Divisions. This report describes progress to date in the RCM core elements such as system selection, applications of the RCM methodology to the systems selected, lessons learned, course corrections, implementation of the RCM recommendations, results achieved, and development of a living program. The overall project involves analysis of approximately twelve to sixteen systems. To date, six have been completed and two are underway. The results to date indicate a significant payback in maintenance cost reduction, even with the expansion of some PM activities for identified critical failure modes. 7 refs., 12 figs., 7 tabs.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (USA); Southern California Edison Co., San Clemente, CA (USA); Erin Engineering and Research, Inc., Walnut Creek, CA (USA)
- Sponsoring Organization:
- EPRI
- OSTI ID:
- 5740519
- Report Number(s):
- EPRI-NP-6152-Vol.2
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONDENSATES
DATA ACQUISITION
DATA ANALYSIS
DEMONSTRATION PROGRAMS
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FEEDWATER
HYDROGEN COMPOUNDS
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MANAGEMENT
MONITORING
OXYGEN COMPOUNDS
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POWER REACTORS
PROGRESS REPORT
PWR TYPE REACTORS
QUALITY ASSURANCE
RADIATION MONITORING
REACTOR COMPONENTS
REACTOR MAINTENANCE
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
SAN ONOFRE-2 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CONDENSATES
DATA ACQUISITION
DATA ANALYSIS
DEMONSTRATION PROGRAMS
DOCUMENT TYPES
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FEEDWATER
HYDROGEN COMPOUNDS
MAINTENANCE
MANAGEMENT
MONITORING
OXYGEN COMPOUNDS
PERSONNEL
POWER REACTORS
PROGRESS REPORT
PWR TYPE REACTORS
QUALITY ASSURANCE
RADIATION MONITORING
REACTOR COMPONENTS
REACTOR MAINTENANCE
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
SAN ONOFRE-2 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS