Document: NRC Regulatory Guide
Document ID: cde52d5a-adf9-49be-9d1f-59449dfca895
Document Type: regulatory_guide
Title: TRIAL - Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2123/ML21235A008.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.247
CFR Part: 
CFR Title: 

Content:
utors to the NLWR PRA; however, it is currently not known whether that is the case. Though there is significant experience with operating light- water reactors (LWRs) to justify the consensus approach of excluding EOCs from the Level 1/LERF LWR PRA standard, there is Qualification A systematic review of relevant available procedures, any past operational events, procedural guidance, and training shall be used to identify the set of post- initiator operator responses required for each of the event sequences, as well as the well-intended post-initiator operator responses that result in adverse safety impacts. RG 1.247, Appendix A, Page A-14 Table A-7. Staff Position on ASME/ANS RA-S-1.4-2021, Technical Requirements for Human Reliability Analysis Index No. Issue Position Resolution little to no operating experience for NLWRs dictating that the same approach can be applied. It is expected that NLWRs will rely less on human actions than operating LWRs, which implies that EOCs would play a more important role in NLWR PRAs. In addition, there is no consensus for LWRs regarding whether EOCs should be addressed in the accident progression analysis (i.e., Level 2 PRA). Likewise, there is currently no basis for excluding EOCs from the mechanistic source term analysis in a NLWR PRA. HLR-HR-F through HLR-HR-I ------------------------ No objection ---------------------------------- Table 4.3.6.1-2 HR-A1 through HR-A10 ------------------------ No objection ---------------------------------- Table 4.3.6.1-3 HR-B1 through HR-B3 ------------------------ No objection ---------------------------------- Table 4.3.6.1-4 HR-C1 through HR-C6 ------------------------ No objection ---------------------------------- Table 4.3.6.1-5 RG 1.247, Appendix A, Page A-15 Table A-7. Staff Position on ASME/ANS RA-S-1.4-2021, Technical Requirements for Human Reliability Analysis Index No. Issue Position Resolution HR-D1 through HR-D3 ------------------------ No objection