Document: NUREG-0800
Document ID: dd4f84a9-8976-44c4-b631-d7c0254f4efc
Document Type: srp
Title: PROBABILISTIC RISK ASSESSMENT AND SEVERE ACCIDENT EVALUATION FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1416/ML14161A594.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.0
CFR Part: 
CFR Title: 

Content:
ing as the generic DCD. This applies to the description of the PRA and its results included in Chapter 19 of the FSAR, but does not apply to the PRA that supports a COL application (including, but not limited to, the event tree analyses, the fault tree analyses, the data analyses, the human reliability analyses, the PRA computer model). Furthermore, Section IV.A.2.a in each existing DCR applies to the overall content and organization of information among the FSAR chapters, but does not apply to the content or organization of information within each FSAR chapter. Specifically, Chapter 19 of each plant-specific FSAR must describe the PRA and severe accident evaluations; however, the format of information within Chapter 19 is left to the 19.0-4 Draft Revision 3 –November 2014 discretion of each COL applicant. The staff should ensure that applicants’ FSAR Chapter 19 contains the information needed to review the COL application, regardless of how the information is formatted or organized within FSAR Chapter 19. In the future revision of RG 1.206, Section C.III.1 will be revised in accordance with Section IV.A.2.a in each existing DCR. The structural performance of the containment under severe accident loads reviewed by the staff encompasses: (1) the applicant’s assessment of the Level C (or factored load) pressure capability of the containment in accordance with 10 CFR 50.44(c)(5)(2) the applicant’s demonstration of the containment capability to withstand the pressure and temperature loads induced by the more likely severe accident scenarios as stipulated in SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor Designs,” Section I.J, (3) the applicant’s containment structural fragility assessment for overpressurization, and (4) the applicant’s assessment of the seismic capacity of the containment structure in meeting the expectation documented in SECY-93-087, Section II.N. The staff also reviews