Inspection guidance for the Rancho Seco plant derived from generic PRA information

This paper reports the first application of generic probabilistic risk assessment (PRA) information to the development of guidance for use in planning US Nuclear Regulatory Commission inspection activities at nuclear power plants lacking plant-specific PRA's. A methodology is presented for using the results of PRAs for similar (surrogate) plants, along with plant-specific information about the target and surrogate plants to infer important failure modes for systems and components of the target plant. This methodology, and the rationale on which it is based, is presented in the context of its application to Babcock and Wilcox (B and W) plants. The Rancho Seco plant has been analyzed using PRA information from two surrogate plants: Arkansas Nuclear One Unit 1 (ANO-1) and Oconee. Analysis results have been used to develop plant-specific Rancho Seco information for potential use by inspectors at NRC Region 5