Document: NUREG-0800
Document ID: 8dd882f4-a34f-4415-acd1-ebb441c72786
Document Type: srp
Title: PROBABILISTIC RISK ASSESSMENT AND SEVERE ACCIDENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1213/ML12132A481.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.0
CFR Part: 
CFR Title: 

Content:
of SSCs in accordance with 10 CFR 50.69. 7. 10 CFR 52.79(a)(38) states that a COL application for a LWR design must contain an FSAR that includes a description and analysis of design features for the prevention and mitigation of severe accidents, for example, challenges to containment integrity caused by core-concrete interaction, steam explosion, high-pressure core melt ejection, hydrogen combustion, and containment bypass. 8. 10 CFR 52.79(a)(46) states that a COL application must contain an FSAR that includes a description of the plant-specific PRA and its results. With respect to this regulation, the following items are noted: A. The Statement of Consideration (72 FR 49387) for the revised Part 52 states the understanding that the complete PRA (e.g., codes) would be available for NRC inspection at the applicant’s offices, if needed. The NRC expects that, generally, the information that it needs to perform its review of the COL application from a PRA perspective is that information that will be contained in applicants’ FSAR Chapter 19. B. RG 1.206 provides guidance on reporting PRA-related information. As discussed in the Statement of Consideration (72 FR 49387) for the revised Part 52 the guidance focuses on qualitative description of insights and uses, but also acknowledges that some quantitative PRA results should be submitted. C. In accordance with the requirements in 10 CFR 52.79(d)(1), COL applicants must provide the basis for determining that the SMA of the DCD is applicable to the proposed plant or perform a plant-specific SMA. In any case, a plant-specific supplement must identify any SSCs outside the scope of the DCD that are relied upon for safe shutdown after an earthquake. 9. 10 CFR 52.79(c)(1), (d)(1), and (e)(1) state that if a COL application references a standard design approval, standard DC, or the use of one or more manufactured nuclear power reactors licensed under Subpart F of 10 CFR Part 52, then the plant-specific PRA information must