Evaluation of risk impact of changes to surveillance requirements addressing model and parameter uncertainties

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• 作者：S. Martorell^a ; ^{smartore@iqn.upv.es" class="auth_mail} ; M. Villamizar^a ; I. Martó ; n^a ; J.F. Villanueva^a ; S. Carlos^a ; A.I. Sá ; nchez^b
• 关键词：AS ; Automatic scram ; B ; Birnbaum importance measure ; CCF ; Common cause failure ; CDF ; Core damage frequency ; CM ; Corrective maintenance ; CRMS ; Control room manual scram ; CT ; Completion time ; FCDE ; Final core damage equation ; FFNCT ; Fraction of failures no covered by testing ; FV ; Fussel&ndash ; Vesely importance measure ; GAM ; Generalized additive model ; HEP ; Human error probability ; ICCDP ; Incremental conditional core damage probability ; ILERP ; Incremental conditional large early release probability
• 刊名：Reliability Engineering and System Safety
• 出版年：June, 2014
• 年：2014
• 卷：126
• 期：Complete
• 页码：153-165
• 全文大小：606 K

文摘

This paper presents a three steps based approach for the evaluation of risk impact of changes to Surveillance Requirements based on the use of the Probabilistic Risk Assessment and addressing identification, treatment and analysis of model and parameter uncertainties in an integrated manner. The paper includes also an example of application that focuses on the evaluation of the risk impact of a Surveillance Frequency change for the Reactor Protection System of a Nuclear Power Plant using a level 1 Probabilistic Risk Assessment. Surveillance Requirements are part of Technical Specifications that are included into the Licensing Basis for operation of Nuclear Power Plants. Surveillance Requirements aim at limiting risk of undetected downtimes of safety related equipment by imposing equipment operability checks, which consist of testing of equipment operational parameters with established Surveillance Frequency and Test Strategy.