Published February 2012 | Version v1
Journal article

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.2011.10.003

Additional 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)

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.