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Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation  and Technical Specifications

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 20 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 51 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 100 Appendix A +, 10 CFR 50.46a#b +, 10 CFR 50.55a +, 10 CFR 50.69#d2ii +, 10 CFR 50.69#e1 +, 10 CFR 50.69#b2ii +, 10 CFR 50.69#b2iv +, 10 CFR 50.69#c1iv +, 10 CFR 50.69#c +, 10 CFR 50.69#c1ii +, 10 CFR 50.54#f +, 10 CFR 50.69#e3 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.55#e +

05000400  +  and 00400  +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, ML071700658 +, ML061090627 +, ML052910035 +, HNP-14-035, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 +, ML17062A466 +, ML19192A012 +, ML19330D909 +, RA-20-0311, License Amendment Request to Revise the 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process. +, ML21047A314 +, ML21099A274 +, ML21067A092 +, ML21082A170 +, RA-21-0162, Supplement to License Amendment Request to Revise the 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative +, ML21316A248 +, RA-19-0153, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear +  and RA-18-0175, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors +

Michael Mahoney +  and Plant Licensing Branch II +

ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +, ML21316A248 +...

ML19192A012 +, RA-20-0311, License Amendment Request to Revise the 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process. +, RA-21-0162, Supplement to License Amendment Request to Revise the 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative +, RA-19-0153, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear +  and RA-18-0175, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors +

NUREG-2180, Enclosure, NRC Response to NEI Concerns Dated July 28, 2016, Regarding Tabletop Pilot Results Using NUREG-2180 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

EPID:L-2018-LLA-0034 +, EPID:L-2018-LLA-0482 +  and EPID:L-2021-LLA-0003 +

Regulatory Guide 1.200 +, Regulatory Guide 1.174 +  and Regulatory Guide 1.201 +

Arkansas +  and North Carolina +

Steam Generator +, Reactor Coolant System +  and Safety Relief Valve +

Duke Energy +  and Maza K +

Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +  and Large early release frequency +