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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CFR Title: 

Content:
of results and descriptions of the assessment of high winds in the PRA. 13. Procedures were added for use during audits of the PRA in the applicant’s office. 14. Procedures were added for reviewing design features that have been added to mitigate severe accidents. 15. A statement was added to make clear that the EPRI Fire-Induced Vulnerability Evaluation (FIVE) method is acceptable along with the method in NUREG\CR-6850 for addressing fire in the PRA. 16. An explicitly review procedure was added for the containment performance assessment. 17. Review procedures for the staff’s review of an applicant’s assessment of risk from accidents that could affect multiple modules in facilities with small, modular, integral pressurized water reactors (iPWRs) were added. 18. Additional review procedures for the staff’s review of an applicant’s assessment of risk from accidents that could affect multiple modules in facilities with small modular integral pressurized water reactors (iPWRs) were added 19.0-47 Draft Revision 3 –November 2014 19. Additional review procedures for the staff’s review of the results of the PRA for non- power modes of operation were added. IV. EVALUATION FINDINGS 1. Three additional findings that reviewers should pursue were added. These findings relate to specific objectives of the Commission for use of PRA in the design of new and advanced reactors. V. IMPLEMENTATION No Changes VI. REFERENCES 1. A number of additional documents are referred to in Sections II and III. Complete references for these documents have been added to the reference section (i.e., Section VI).