Risk evaluation for motor operated valves in an Inservice Testing Program at a PWR nuclear power plant in Taiwan
- 1. National Chung Hsing University, Department of Applied Mathematics, Taiwan (China)
- 2. Graduate School of Engineering Technology, Lunghwa University of Sci. and Tech., Taiwan (China)
- 3. Department of Nuclear Safety, Taiwan Power Company, Taipei, Taiwan (China)
Description
Safety related valves such as Motor Operated Valves (MOV), Air Operated Valves (AOV) or Check Valves (CV) play an important role in nuclear power plant. Functioning of these valves mainly aim at emergency reactivity control, post-accident residue heat removal, post-accident radioactivity removal and containment isolation when a design basis accident occurred. In order to maintain these valves under operable conditions, an Inservice Testing Program (IST) is defined for routine testing tasks based on the ASME Boiler and Pressure Vessel Code section XI code requirements. Risk based Inservice Testing Programs have been studied and developed extensively in the nuclear energy industry since the 1990s. Risk Based evaluations of IST can bring positive advantages to the licensee such as identifying the vulnerability of the system, reducing unnecessary testing burden, concentrating testing resources on the critical pass oriented valves and saving plant's personnel dose exposure. This risk evaluation is incorporated with quantitative and qualitative analyses to the Motor Operated Valves under current Inservice Testing Program for PWR nuclear power plant in Taiwan. With the outcome of the risk classifications for the safety related MOVs through numerical or deterministic analyses, a risk based testing frequency relief is suggested to demonstrate the benefits received from the risk based Inservice Testing Program. The goal made of this study, it could be as a reference and cornerstone for the licensee to perform overall scope Risk-Informed Inservice Testing Program (RI-IST) evaluation by referring relevant methodologies established in this study.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.ijpvp.2011.10.003Additional details
Identifiers
- DOI
- 10.1016/j.ijpvp.2011.10.003;
- PII
- S0308-0161(11)00139-6;
Publishing Information
- Journal Title
- International Journal of Pressure Vessels and Piping
- Journal Volume
- 90-91
- Journal Page Range
- p. 17-21
- ISSN
- 0308-0161
- CODEN
- PRVPAS
Conference
- Title
- Asian Society for Integrity of Nuclear Components (ASINCO) 8. international workshop on the integrity of nuclear components
- Dates
- Apr 2010
- Place
- Awaji (Japan)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43071962
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BOILERS; CONTAINMENT; CONTROL SYSTEMS; COOLING; DESIGN BASIS ACCIDENTS; IN-SERVICE INSPECTION; MOTORS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTIVITY; SAFETY; TESTING; VALVES; VULNERABILITY
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTROL EQUIPMENT; ENGINES; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; INSPECTION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; REMOVAL; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.