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:
above, format and content guidance for COL applications is provided in RG 1.206. COL applicants not referring to a DC should follow the guidance in RG 1.206, Section C.I.19. The staff will review the full scope of information requested by this guidance. Where the DC included generic analysis of external events, the COL applicant may demonstrate that the relevant parameters of the generic analysis bound the corresponding site-specific parameters. Alternatively, the COL applicant may show that a particular initiating event is too infrequent or inconsequential to affect core damage frequency (CDF) or large release frequency (LRF). Otherwise, the event must be included in the description of risk results and insights. For a COL application that references a DC, the staff review of the PRA for the COL should focus on the plant-specific aspects of the PRA and site-specific design features that deviate 19.0-3 Draft Revision 3 – September 2012 from the referenced DC and the associated differences in risk results and insights. Similar limitation in the scope of the review applies to severe accident evaluations. This review corresponds to RG 1.206, Section C.III.19. In accordance with the Statement of Consideration for the revised Part 52 [72 FR 49365], the design-specific PRA is excluded from the Tier 1 or Tier 2 information that comprises the DC information. As a result, the description of the PRA and its results included in Chapter 19 of the DC FSAR is subject to the restrictions of 10 CFR 52.63(a)(1) concerning the finality of DCs. An applicant’s COL or DC FSAR is expected to contain a qualitative description of PRA insights and uses, as well as some quantitative PRA results, such that the staff can perform the review, ensure risk insights were factored into the design, and make the evaluation findings described in this SRP section. In accordance with the Statement of Consideration for the revised Part 52 (72 FR 49387), the U.S. Nuclear Regulatory Commission (NRC)