Document: NUREG-0800
Document ID: 817bb0ad-6fd7-433e-aa2b-b4b3e1166f9c
Document Type: srp
Title: PROBABILISTIC RISK ASSESSMENT AND SEVERE ACCIDENT EVALUATION FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0717/ML071700652.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.0
CFR Part: 
CFR Title: 

Content:
atory Guide 1.200 presents an acceptable approach for determining that the quality of the applicant’s PRA is sufficient to provide confidence in the results. In particular, Section C.1 of Regulatory Guide 1.200 describes the functional requirements of a technically acceptable PRA, which may be useful to the staff in 19.0-16 Revision 2 - June 2007 determining the technical acceptability of the applicant’s design-specific/plant- specific PRA. In addition, although it relates to the staff review of license applications requesting risk-informed changes to an applicant’s licensing bases, SRP Section 19.2 provides specific review guidance in Subsection IV and Appendix A for specific aspects of a PRA (e.g., scope, initiating event analysis, accident sequence analysis) that would be useful to the staff in performing the reviews of new reactor designs for DC and licensing. In particular, Section A.11 of SRP Section 19.2 lists documents that the staff could use as reference or background material during the review process. The bibliography lists documents by category, covering desirable PRA attributes, review of the PRA, uncertainty and sensitivity analyses, and use of the PRA in risk ranking. It also provides a bibliography for aspects of PRA modeling (e.g., initiating events, common-cause failure modeling, human performance modeling). 2. Severe Accident Evaluations The staff should review the applicant’s description and analysis of the design features to prevent and mitigate severe accidents, in accordance with the requirements in 10 CFR 52.47(23) or 10 CFR 52.79(a)(38), for a DC or a COL application, respectively. This review should specifically address the issues identified in SECY-90-016 and SECY- 93-087, which the Commission approved in related SRMs dated June 26, 1990, and July 21, 1993, respectively, for prevention (e.g., anticipated transients without scram, mid- loop operation, station blackout, fire protection, and intersystem loss-of-coolant accident) and