Experience of RCM analysis and evaluation method of establishing critical components in Korean NPPS
Creators
- 1. Nuclear Power Research Laboratory, Korea Electric Power Research Institute, Korea Electric Power Corporation, Yusung-Gu, Daejon (Korea, Republic of)
Description
The analysis of Reliability Centered Maintenance (RCM) for three pilot system of Yonggwang nuclear power unit 1, 2 had been performed from 1997 to 1999. The objective of this analysis was to optimize the preventive maintenance program. For evaluation of critical component, FMEA (Failure Mode and Effect Analysis) and Instrument matrix method had been used in the analysis. As results of the analysis, about 25% of total component was identified as critical component, and the number of preventive maintenance (PM) tasks has been reduced by about 18% compared with current PM tasks. Also as for the types of PM tasks, time-directed tasks were reduced from 75% to 55%, while condition-directed tasks and failure finding tasks were increased from 2% and 23% to 9% and 36%, respectively. Based on this analysis of pilot system, the RCM analysis on extended 25 systems of the same unit has started from 2000 to 2002. In this study, the evaluation method for establishing critical component that can be used for selection of the SSC(system, structure, component) in maintenance rule has been developed. This method is simpler and cost-benefit than FMEA method. In this paper, the results of RCM analysis on pilot systems of Yonggwang nuclear power unit 1 and 2 and evaluation method for determining critical component used in our nuclear power plant are described. Also the future plan for maintenance strategies on the all NPPs in Korea are described. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-112703-0
- Imprint Title
- Guidance for optimizing nuclear power plant maintenance programmes. Report prepared within the framework of the Technical Working Group on Life Management of Nuclear Power Plants
- Imprint Pagination
- 140 p.
- Journal Page Range
- p. 87-96
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1383
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35013631
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S29: ENERGY PLANNING, POLICY AND ECONOMY;
- Descriptors DEI
- FAILURE MODE ANALYSIS; MECHANICAL STRUCTURES; PROGRAM MANAGEMENT; REACTOR COMPONENTS; REACTOR MAINTENANCE; RELIABILITY; YONGGWANG-1 REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; MAINTENANCE; MANAGEMENT; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 figs, 5 tabs