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:
ata in NUREG/CR-4461, Revision 1, and based on data for the central region of the United States will normally be acceptable because the central region of the country has the highest occurrence rate of tornadoes and the highest tornado intensities. 22. In the analysis of high winds, tornados may not always be bounding with respect to the damaging effects of missiles. In coastal regions prone to severe hurricanes a missile generated by hurricane force winds may be more damaging than one created by a tornado (See Interim Staff Guidance DC/COL-ISG-024 pertaining to RG 1.221 for treatment of hurricane missiles). 23. Section 5 of RG 1.7 provides criteria acceptable to the NRC staff for demonstrating the requirements in 10 CFR 50.44(c)(5) regarding containment structural integrity have been met. 19.0-18 Draft Revision 3 –November 2014 24. The RG 1.216 describes methods that the NRC staff considers acceptable for (1) predicting the internal pressure capacity for containment structures above the design- basis accident pressure, (2) demonstrating containment structural integrity related to combustible gas control, and (3) demonstrating containment structural integrity through an analysis that specifically addresses the Commission’s performance goals related to the prevention and mitigation of severe accidents. Acceptance Criteria for a PRA-based SMA 25. The staff will determine that the applicant has performed a PRA-based SMA to determine the seismic capacity of the plant and for each sequence that may lead to core damage or large release. 26. The design-specific plant system and accident sequence analysis for a PRA-based SMA is performed in accordance with, at a minimum, the Capability Category I requirements of Section 5-2.3 of Part 5 of the ASME/ANS PRA Standard (Ref. 9), with the exceptions that the analysis should not be based on site-specific and plant-specific information and should not rely on an as-built and as-operated plant. 27. Screening of rugged SSCs may be