DocumentCode
3313316
Title
“Level-1 PSA of RAPS-2: Review of the safety of the first Indian PHWR by probabilistic method”
Author
Jha, K.K. ; Budhiraja, Y.K. ; Vijaya, A.K. ; Guptan, Rajee
Author_Institution
Nucl. Power Corp. of India Ltd., Mumbai, India
fYear
2010
fDate
14-16 Dec. 2010
Firstpage
230
Lastpage
233
Abstract
This paper presents the tasks and insights of Level-1 PSA of Rajasthan Atomic Power Station, RAPS-2 viz. Initiating Events, Event Tree Analysis, Data Analysis and Quality Assurance program. This also brings out the strengths in design and operating experiences of the oldest IPHWR. The PSA has been carried out with plant specific data to gain insights to the overall safety of the plant. In the present analysis, the entire spectrum of fuel damage accidents has been considered with four major classes. These were further sub-divided depending on the severity of core damage. Common Cause Failures and Human reliability have also been considered. The calculated CDF indicate good operational health and adequacy of maintenance program & surveillance requirements.
Keywords
data analysis; fission reactor accidents; fission reactor containment; fission reactor core control; heavy water reactors; nuclear reactor maintenance; CDF; Indian PHWR; RAPS-2; Rajasthan Atomic Power Station; common cause failures; core damage; data analysis; event tree analysis; fission reactor containment; fuel damage accidents; human reliability; level-1 PSA; maintenance program; probabilistic method; Biomedical monitoring; Inductors; Instruments; Monitoring; Reliability; Valves; CDF; PSA; Quality Assurance;
fLanguage
English
Publisher
ieee
Conference_Titel
Reliability, Safety and Hazard (ICRESH), 2010 2nd International Conference on
Conference_Location
Mumbai
Print_ISBN
978-1-4244-8344-0
Type
conf
DOI
10.1109/ICRESH.2010.5779552
Filename
5779552
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