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:
he site-specific seismic hazard may need to review these aspects of the seismic risk analyses. The technical branches that perform the systems and T-H analyses may need to interface with the PRA staff reviewers to ensure that the applicant’s PRA properly considers and addresses important issues (e.g., failure mechanisms, system interactions, and T-H modeling and uncertainties) and, to the extent possible, to focus their review resources more heavily on areas of higher risk importance. Some technical branches may need to participate in the review of the applicant’s identified risk- informed applications of the PRA (e.g., risk-informed inservice inspection, risk-informed inservice testing, 10 CFR 50.69 implementation, implementation of risk-informed/performance- based fire protection). In addressing these risk-informed programs, the applicant should provide the program description in the appropriate section of its FSAR, with a cross-reference to that program in Chapter 19 of its FSAR. Likewise, the staff should present its review of the program in the appropriate section of the staff evaluation, with a brief description of the application of the PRA and a cross-reference to the subject program evaluation in Chapter 19 of the staff SER. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: For a DC 1. 10 CFR 52.47(8) - The information necessary to demonstrate compliance with any technically relevant portions of the Three Mile Island requirements set forth in 10 CFR 50.34(f), specfically 10 CFR 50.34(f)(1)(i). 19.0-6 Revision 2 - June 2007 2. 10 CFR 52.47(a)(23) - For light-water reactor designs, a description and analysis of design features for the prevention and mitigation of severe accidents, e.g., challenges to containment integrity caused by core-concrete interaction, steam explosion, high-pressure core melt ejection, hydrogen combustion, and containment bypass. 3. 10 CFR