Reliability Assurance Program for New Reactors and Lessons Learned and Insights Gained

摘要

The U.S. Nuclear Regulatory Commission reviews the reliability assurance program (RAP) for new reactor applications using NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," Section 17.4, "Reliability Assurance Program." The RAP applies to those systems, structures, and components (SSCs) that are identified as being risk-significant (or significant contributors to plant safety). These SSCs are identified through probabilistic and deterministic analyses, including information obtained from the probabilistic risk assessment (PRA) and severe accident evaluations. The purposes of the RAP are to provide reasonable assurance that: ? a reactor is designed, constructed, and operated consistent with the risk insights and key assumptions from probabilistic, deterministic, and other methods of analysis ? the SSCs within the scope of RAP do not degrade to an unacceptable level of reliability, availability, or condition during plant operations ? the frequency of transients that challenge these SSCs is minimized ? these SSCs function reliably when challenged The goal of this paper is to describe the RAP process, taking into consideration the lessons learned and insights gained from RAP reviews of new reactor applications. It also identifies the most recent guidance on RAP, which incorporates these lessons and insights.