The reliability-centered maintenance study at the Fast Flux Test Facility
A reliability-centered maintenance (RCM) program was applied to two Fast Flux Test Facility (FFTF) systems to evaluate this method for improving the equipment reliability and reducing maintenance costs. This technique is a systematic approach to failure analysis and maintenance task development. The RCM method was originally developed by the airline industry to reduce maintenance costs and improve reliability and it has since been adopted by the military. The Electric Power Research Institute (EPRI) has completed two pilot studies with a third in progress to determine the RCM applicability to the commercial nuclear power industry. These studies showed that the RCM methodology could be beneficial to the nuclear power industry. The EPRI study performed at the McGuire nuclear power station (EPRI 1986) was used as the model for the FFTF study.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 6883318
- Report Number(s):
- WHC-EP-0123; ON: DE88014649
- Country of Publication:
- United States
- Language:
- English
Similar Records
Demonstration of reliability centered maintenance
Application of reliability-centered maintenance to the auxiliary feedwater system at San Onofre Nuclear Generating Station
Demonstration of reliability-centered maintenance: Volume 1, Project description
Technical Report
·
Sun Mar 31 23:00:00 EST 1991
·
OSTI ID:5875952
Application of reliability-centered maintenance to the auxiliary feedwater system at San Onofre Nuclear Generating Station
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5529968
Demonstration of reliability-centered maintenance: Volume 1, Project description
Technical Report
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:6371972
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
EPITHERMAL REACTORS
EVALUATION
FAST REACTORS
FFTF REACTOR
LIQUID METAL COOLED REACTORS
MAINTENANCE
REACTOR COMPONENTS
REACTOR MAINTENANCE
REACTORS
RELIABILITY
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
EPITHERMAL REACTORS
EVALUATION
FAST REACTORS
FFTF REACTOR
LIQUID METAL COOLED REACTORS
MAINTENANCE
REACTOR COMPONENTS
REACTOR MAINTENANCE
REACTORS
RELIABILITY
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS