Elicitation of items to be considered in seismic design of advanced reactors based on seismic PSA

This paper summarizes the preliminary results of a seismic PSA performed by the Japan Atomic Energy Research Institute for a generic BWR plant of conventional design and discusses the insights from this PSA applicable to the seismic design of advanced reactors. The contributors to seismically induced core damage frequency were identified through a step-by-step examination of important contributors starting from initiating events through safety functions, systems, components, and component capacity data. The importances of systems and components were examined using the Fussell-Vesely measure and the risk achievement worth. The insights from this PSA indicate that there is no single component or system that dominates the core damage frequency of the plant and that the reliability of decay heat removal friction is an important area for consideration in advanced reactor design. 13 refs., 7 figs