Document: NRC Regulatory Guide
Document ID: 22ccfd5e-c5d8-4615-a02c-32369aa9f533
Document Type: regulatory_guide
Title: Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1930/ML19308B636.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.200
CFR Part: 
CFR Title: 

Content:
e analysis and model development process. SPR-A3 The verb “encompasses” is overly severe and cannot reasonably be achieved in practice. The wording of this SR should be similar to IE-A3 and IE-A4. Clarification REVIEW plant-specific response to past seismic events, as well as other available seismic risk evaluations for nuclear plants, to ensure that the list of initiating events included in the evaluation encompasses accounts for industry experience. SPR-A4 The plant-response analysis should include all identified events. Clarification INCLUDE in the plant-response analysis the events identified in SPR-A1, and SPR- A2, and SPR-A3 above. Notes -------------------- No objection -------------------- Table 5-2.3-3 Introductory text -------------------- No objection -------------------- SPR-B1 -------------------- No objection -------------------- SPR-B2 Due to the input from the fire and internal flooding PRAs, and possibly other hazard PRAs, in addition to internal events the findings from all relevant PRAs should be appropriately dispositioned. Additionally, it is not clear what is intended by the latter part of this SR (“…does not adversely affect…”). Qualification ENSURE that the peer review findings for the internal-events and other hazard PRAs that are relevant to the seismic PRA are resolved and that the disposition does not adversely affect into the development of the seismic PRA plant-response model. SPR-B3 Incorrect reference to SPR-C4 instead of SPR- C6. Clarification INCLUDE seismically induced failures representing the failure modes of interest in the seismic PRA plant-response model (e.g., tank rupture, pump failure to start/run, etc.). (See SPR-C4SPR-C6.) SPR-B4 -------------------- No objection -------------------- DG-1362, Appendix B, Page B-22 Table B-1. Staff Position on ASME/ANS RA-S Case 1, “Case for ASME/ANS RA-Sb-2013 Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment of Nuclear Power Plant