Document: NUREG-0800
Document ID: b8d2b8f5-432a-4c0a-81ab-20231f7d0f28
Document Type: srp
Title: PROBABILISTIC RISK ASSESSMENT AND SEVERE ACCIDENT EVALUATION FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1508/ML15089A068.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.0
CFR Part: 
CFR Title: 

Content:
rting or associated analyses (e.g., T-H analyses, human reliability analyses). 2. The staff reviews the applicant’s process for maintaining and upgrading the PRA, as necessary, to ensure that (1) it reasonably reflects the plant design, operation, and experience and (2) its scope, level of detail, and technical adequacy are appropriate for its use in complying with the relevant regulations for new reactors. 3. The staff reviews the applicant’s uses and risk-informed applications (or proposed uses and applications)5 of the PRA for each phase (i.e., design, licensing, construction operations). Specifically, the PRA staff should interface with the primary review branch in the evaluation of licensee programs that use the PRA results and insights (e.g., human factors program, maintenance rule implementation, RAP). Likewise, the PRA staff should interface with the primary review branch in the evaluation of specific risk- informed applications (e.g., 10 CFR 50.69 implementation, risk-informed performance- based fire protection implementation, risk-informed inservice inspection, risk-informed inservice testing). When the applicant enters a new phase, the staff may review any changes to the uses and applications. 4. The staff reviews the description of the applicant’s PRA in Chapter 19 of the FSAR and its associated results and insights, addressing the full scope of information outlined in RG 1.206, Section C.I.19. In particular, the staff should review the applicant’s identification of significant plant features (including nonsafety-related systems) and operator actions that are important to reduce risk and confirm that the plant will meet the expectation identified above that reactors will reflect an extremely low probability for accidents that could result in the release of significant quantities of radioactive fission 5 If the applicant is merely identifying expected uses and applications of the PRA in subsequent phases, the staff will typically not perform