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
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ameters and the interfaces with undeveloped aspects of the design. This is acceptable at the DC stage and results in the identification of PRA-based insights that include design, site, and operational assumptions. Although the staff has not published a format and content document specific to DC applications, RG 1.206, Section C.I.19, is intended to include all information needed for the staff to review a COL application that does not refer to a DC. Therefore, DC applicants are expected to provide the material in RG 1.206, Section C.I.19, except for those elements that require site-specific or plant-specific information not yet available. 19.0-3 Draft Revision 3 –November 2014 As indicated 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 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 (72 FR 49365), for the revised 10 CFR Part 52, “License, Certifications, and Approvals for Nuclear Power Plants,”