Document: NUREG-0800
Document ID: 2dc4ec7e-926d-4aba-8a72-19deee03b06d
Document Type: srp
Title: DETERMINING THE TECHNICAL ADEQUACY OF PROBABILISTIC RISK
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0717/ML071700657.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.1
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Content:
ASSESSMENT RESULTS FOR RISK-INFORMED ACTIVITIES REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of probabilistic risk assessment. Secondary - None I. AREAS OF REVIEW Introduction While this SRP section was primarily developed to address the technical adequacy of a baseline PRA used by a licensee to support license amendments for an operating reactor, it is also applicable to assessing the technical adequacy of a PRA used to support a design certification or combined license application. However, it needs to be recognized that in these cases there will be aspects of the plant design or operating features, e.g., emergency operating procedures, site specific external factors, that will not be fully developed. Therefore, the PRA used to support such applications will of necessity be incomplete. In using this SRP section the reviewer should focus on the determination that the baseline PRA reflects the status of the design and operational features appropriate to the application. This SRP section relies on the existence of NRC endorsed PRA standards. The following paragraphs describe the historical development and current status of these standards, and their relevance to this SRP section. 19.1-2 Revision 2 - June 2007 In their March 1999 report, "Nuclear Regulation: Strategy Needed To Regulate Safety Using Information on Risk," GAO/RCED-99-95, the General Accounting Office (GAO) identified a number of issues that it believed required resolution for the NRC to successfully implement a risk-informed regulatory approach. Among these, GAO indicated that more was needed to "develop standards on the scope and detail of risk assessments needed for utilities to determine that changes to their plants' designs will not negatively affect safety." Probabilistic risk assessment (PRA) standards have been developed by the American Society of Mechanical Engineers (ASME) and American Nuclear Society (ANS). On April 5, 2002, ASME issued a standard (ASME RA-S-2002)