ABSTRACT

Probabilistic Safety Analysis (PSA) is an essential tool for assessing, maintaining, assuring and improving the nuclear power plant safety. It is an essential and efficient tool for evaluation of risk impact in the framework of the Risk Informed Decision Making according to R.G. 1.174 (USNRC, 2011), which is adopted by many regulatory bodies. Often, neither the effect of equipment ageing nor maintenance and testing programs are explicitly considered in PSA models and data, e.g. adoption of constant failure rate instead of age dependent failure rates.