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

Boron +, Nitrogen +  and Hydrogen +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 50.65 +, 10 CFR 50.69 +, 10 CFR 50.55a +, 10 CFR 50.36#c2 +, 10 CFR 50.36#c5 +, 10 CFR 50.36#c2i +, 10 CFR 50.65#a4 +, 10 CFR 54.21#d +, 10 CFR 50.55a#h +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.71#e4 +

Barrier Integrity +  and Initiating Events +

H.3(e) +, H.1(e) +, S.1(e) +  and S.2(e) +

05000369  +, 05000370  +, 00369  +  and 00370  +

Regulatory Guide 1.177 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.160 +, ML070380228 +, ML12073A348 +, ML071200238 +, ML17086A431 +, ML041830612 +, Information Notice 2010-18, Generic Issue 199, Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States on Existing Plants +, ML12286A321 +, ML17062A466 +, TSTF-18-07, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-505, Provide Risk-Informed Extended Completion Times and Submittal of TSTF-505, Revision 2 +, ML18267A259 +, ML19126A030 +, ML19241A615 +, RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b +, RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power +, ML24019A139 +, ML24031A540 +  and ML23257A246 +

Reactor Trip +  and Turbine Trip +

51 FR 30028 +, 51 FR 28044 +  and 88 FR 31285 +

Klos L +  and Plant Licensing Branch II +

ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +, ML24031A540 +...

6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

NEI 17-07 +  and NEI 06-09, Risk-Managed Technical Specifications (RMTS) Guidelines +

NUREG-1431 +, 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-2023-LLA-0021 +  and EPID:L-2023-LLA-0022 +

Regulatory Guide 1.177 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +  and Regulatory Guide 1.160 +

SR-3.8.1.3 +, SR-3.8.1 +, SR-3.8.1.1 +, SR-3.8.1.7 +, SR-3.8.7.1 +, SR-3.8.1.8 +, SR-3.8.1.2 +, SR-3.8.1.9 +, SR-3.3.1.1 +, SR-3.3.2.8 +, SR-3.0.2 +, SR-3.7.7.2 +, SR-3.3.1.5 +, SR-3.3.1.8 +, SR-3.8.1.6 +, SR-3.4.11.1 +, SR-3.4.11.3 +, SR-3.6.9.1 +, SR-3.8.9.1 +, SR-3.3.5.2 +, SR-3.3.1 +, SR-3.4.14.1 +, SR-3.3.2.1 +, SR-3.7.7.1 +, SR-3.8.1.5 +, SR-3.1.1.1 +, SR-3.3.1.2 +, SR-3.8.1.4 +, SR-3.3.5.1 +, SR-3.3.1.3 +...

Manual Scram +  and Automatic Scram +

McGuire +  and Mcguire +

North Carolina +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Residual Heat Removal +, Emergency Core Cooling System +  and Containment Spray +

TS-3.0.3 +, TS-3.7.2 +, TS-3.8.1 +, TS-3.5.2 +, TS-3.8.7 +, TS-3.7.7 +, TS-3.8.4 +, TS-3.6.3 +, TS-3.8.2 +, TS-3.6.1 +, TS-3.7.5 +, TS-3.7.6 +, TS-3.3.2 +, TS-3.3.5 +, TS-3.6.6 +, TS-5.5.18 +, TS-3.3.1 +, TS-1.3 +, TS-3.4.6 +, TS-3.8.9 +, TS-3.8 +, TS-3.8.1.a +, TS-3.6.9 +, TS-3.0.4.b +, TS-3.4.11 +, TS-3.8.1.d +, TS-3.6.2 +, TS-3.6.11 +, TS-3.8.1.b +, TS-3.6.14 +...

Pigott E +  and Duke Energy +

Safe Shutdown +, High winds +, High Radiation Area +, Anticipated operational occurrence +, Internal Flooding +, Probabilistic Risk Assessment +, FLEX +, Fukushima Dai-Ichi +, Surveillance Frequency Control Program +, Large early release frequency +, Loss of Offsite Power +, Maintenance Rule Program +  and Offsite Circuit +