Probabilistic Safety Study Applications Program for inspection of the Indian Point Unit 3 Nuclear Power Plant

By prioritizing the various areas of interest for inspection and by better defining inspection needs, the NRC expects to make more effective use of finite inspection resources by concentrating on those potential areas most significant to safety. Through review and application of the Indian Point Unit 3 Probabilistic Safety Study's numerical data and event tree modeling, and by utilizing related documents, a technical basis for prioritizing areas for NRC inspection has been developed. This was then tested at the plant site for the NRC Operating Reactor Inspection Program, I and E Manual Chapter 2515. Inspection activities addressed include normal operations, system and component testing, maintenance and surveillance. A computer program entitled NSPKTR, which was developed specifically for this program, modeled the internal plant states to the system level and performed the risk and importance calculations. 17 refs., 21 tabs.