System analysis procedures for conducting PSA of nuclear power plants
Description
This document, the Probabilistic Safety Assessment(PSA) procedures guide for system analysis, is intended to provide the guidelines to analyze the target of system consistently and technically in the performance of PSA for nuclear power plants(NPPs). The guide has been prepared in accordance with the procedures and techniques for fault tree analysis(FTA) used in system analysis. Normally the main objective of system analysis is to assess the reliability of system modeled by Event Tree Analysis(ETA). A variety of analytical techniques can be used for the system analysis, however, FTA method is used in this procedures guide. FTA is the method used for representing the failure logic of plant systems deductively using AND, OR or NOT gates. The fault tree should reflect all possible failure modes that may contribute to the system unavailability. This should include contributions due to the mechanical failures of the components, Common Cause Failures (CCFs), human errors and outages for testing and maintenance. After the construction of fault tree is completed, system unavailability is calculated with the CUT module of KIRAP, and the qualitative and quantitative analysis is performed through the process as above stated. As above mentioned, the procedures for system analysis is based on PSA procedures and methods which has been applied to the safety assessments of constructing NPPs in the country. Accordingly, the method of FTA stated in this procedures guide will be applicable to PSA for the NPPs to be constructed in the future. (author). 6 tabs., 11 figs., 7 refs
Availability note (English)
MF available from INIS under the Report Number.Files
28064780.pdf
Files
(1.1 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:4ba9c7eefa285948fa5c283626716127
|
1.1 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 73 p.
- Report number
- KAERI/TR--846/97
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 28064780
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- FAULT TREE ANALYSIS; HUMAN FACTORS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; RISK ASSESSMENT; SAFETY ANALYSIS; SYSTEMS ANALYSIS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS