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

Boron +  and Lead +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 50.12 +, 10 CFR 50.65 +, 10 CFR 50.69 +, 10 CFR 50.90 +, 10 CFR 73.21 +, 10 CFR 50.54#f +, 10 CFR 50.54#p +, 10 CFR 50.36#c2 +, 10 CFR 50.36#c5 +, 10 CFR 50.65#a4 +, 10 CFR 54.21#d +, 10 CFR 50.55a#h +, 10 CFR 50.48#c +, 10 CFR 50.48#a +, 10 CFR 73.55#51 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +, 10 CFR 50.46#a1 +  and 10 CFR 50.71#e4 +

H.3(e) +, H.1(e) +, P.7(c) +, P.6(b) +  and P.8(d) +

05000244  +  and 00244  +

Regulatory Guide 1.177 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, ML122860402 +, ML070380228 +, ML17086A431 +, ML15072A009 +, RS-17-026, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal +, 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 +, ML18269A041 +, ML20339A309 +, ML21140A324 +, ML202388871 +, ML21222A114 +, ML21287A006 +, ML22118B143 +, ML22160A411 +, ML22119A094 +, ML21160A411 +  and RS-14-068, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force +

Turbine Trip +  and Reactor Trip +

V Sreenivas +  and Plant Licensing Branch I +

ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +, ML22119A094 +...

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)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 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)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

ML061230392 +, ML22118B143 +  and ML22160A396 +

NEI 05-04 +, NEI 04-10, E-mail from J. Whited to D. Filchner: Susquehanna Steam Electric Station Acceptance of License Amendment Request Implementation of TSTF-425 (TAC Nos. MF5151 and MF5152) +  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 +

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

SR-3.8.1.3 +, SR-3.8.1.1 +, SR-3.7.5.2 +, SR-3.8.1.7 +, SR-3.8.7.1 +, SR-3.7.5.1 +, SR-3.7.5.3 +, SR-3.6.6.3 +, SR-3.5.2.1 +, SR-3.8.1.8 +, SR-3.8.1.2 +, SR-3.6.6.6 +, SR-3.8.1.9 +, SR-3.3.1.1 +, SR-3.0.2 +, SR-3.3.2.6 +, SR-3.7.7.2 +, SR-3.6.6.2 +, SR-3.5.2.3 +, SR-3.3.1.5 +, SR-3.6.6.7 +, SR-3.3.1.8 +, SR-3.8.1.6 +, SR-3.4.11.1 +, SR-3.3.2.5 +, SR-3.8.9.1 +, SR-3.3.1 +, SR-3.4.14.1 +, SR-3.3.2.1 +, SR-3.7.7.1 +...

5E-11 +, 1E-5 +, 1E-4 +, 1E-06 +, 1E-07 +, 5E-6 +, 1E-05 +, 7E-5 +  and 2E-06 +

Manual Scram +  and Automatic Scram +

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

TS-3.0.3 +, TS-3.7.2 +, TS-3.8.1 +, TS-3.3.2.2 +, TS-3.3.1.1 +, TS-3.3.5.1 +, TS-3.4.13 +, TS-3.5.2 +, TS-3.8.7 +, TS-3.3.6.1 +, TS-3.7 +, 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-3.4.12 +, TS-3.3.2 +, TS-3.9.3 +, TS-3.3.5 +, TS-3.6.6 +, TS-3.3.4 +, TS-5.5.18 +, TS-3.7.8 +, TS-3.3.1 +, TS-1.3 +, TS-3.8.9 +, TS-3.3.8.1 +, TS-3.0.4.b +...

Exelon +, Constellation +  and Rhoades D +

Safe Shutdown +, High winds +, High Radiation Area +, Tornado Missile +, Probabilistic Risk Assessment +, Cyber Security +, FLEX +, Surveillance Frequency Control Program +, Large early release frequency +, Loss of Offsite Power +, Safeguards Contingency Plan +, Flooding Focused Evaluation +, Preemption Authority +, Maintenance Rule Program +, Offsite Circuit +, Fire Protection Program +, Overspeed +  and Gas accumulation +