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:
applicants the staff may expect to see when the applicant incorporates by reference a generic risk assessment of external events in the DCD. 4. Added statements identifying the information that should be provided by applicants for staff review and the format requirements for the information. 19.0-44 Draft Revision 3 –November 2014 5. Added a statement describing the scope of the staff’s review of applicant’s analysis of containment capability. 6. Added a statement clarifying the scope of the PRA staff’s review of Tier 1 information in the DCD. 7. Added statements that identify additional organizations with which staff with primary review responsibility may need to interface with. 8. A statement was added to clarify the interface between the review of combustible gas control and the review of severe accidents 9. Several statements were added to clarify the division or responsibility of the PRA reviewer and the I&C reviewer regarding treatment of the DI&C systems in the PRA. 10. Some considerations for design certification rules were deleted. II. ACCEPTANCE CRITERIA 1. Added a description of 10 CFR 52.47(a)(1) to the list of requirements applicable to DC applicants. 2. In regards to the requirements in 10 CFR 52.47(a)(27), a statement was added to clarify that a PRA-based SMA is an acceptable surrogate for seismic PRA in a design certification application since a seismic PRA cannot be performed unless the site has been adequately characterized 3. Added a statement describing requirements in 10 CFR 52.79(a)(1) for COL applicants. 4. Added statements describing Commission expectations regarding containment performance and SMA. 5. Added several statements describing Commission expectations for use of the PRA in advanced reactor design and licensing. 6. Added (1) a statement to indicate that the PRA is not part of the design bases and therefore not subject to quality assurance requirements in 10 CFR Part 50, Appendix B, and (2) guidelines that establish, at a high