Evaluation of Risk Importance and Inspection Methods for Piping Segments
Applications of Probabilistic Safety Assessment (PSA) have been tried to give priorities, from the viewpoint of risk, to portions for Systems, Structures and Components (SSC) of Nuclear Power Plants (NPP) for improving inspection methodologies in Japan. Evaluations of risk importance and reviews of inspection methods for piping segments of BWR5 systems were conducted as part of the trials.
KeywordsStress Corrosion Crack Inspection Method Failure Frequency Prior Probability Distribution Piping Segment
Unable to display preview. Download preview PDF.
- 1.J. I. Braverman et. al. Assessment of Age-Related Degradation of Structures and Passive Components for U.S. Nuclear Power Plants. NUREGICR-6679, August 2000Google Scholar
- 2.U. S. NRC. Feedwater Line Break. Information Notice No. 86-106, December 16, 1986Google Scholar
- 3.CATAWBA 2 — Event Date: 01I31I1993 — LER Number: 93-004-. LER Abstracts 1990-1994Google Scholar
- 4.ORNL. Licensee Event Report (LER) Compilation For month of September 1990. NUREGICR-2000 Vol. 9, No. 9, October 1990Google Scholar
- 5.Prediction Technologies, Inc. ReDAT 1.4 Manual. DRAFT — November 2002Google Scholar
- 6.NSRA. Investigation on Failure Rate Data for PSA. March 1997 (In Japanese)Google Scholar
- 7.J. A. Julius. WinNUPRA Version 2.0 USER’S MANUAL. SCIENTECH Inc., April 2000Google Scholar
- 8.JAPEIC. Improvement of Accuracy for Detecting Crack Sizing in Recirculation System Piping by Ultrasonic Testing. June 4, 2003 (In Japanese)Google Scholar
- 9.http://www.iapc.co.ip/news/bn/hl5/pdf/150930.pdf (In Japanese)Google Scholar