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

Boron +, Iodine +, Cesium +, Uranium +, Rubidium +, Krypton +, Hydrogen +, Xenon +, Lead +  and Bromine +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 100.11 +, 10 CFR 50.67#b2 +, 10 CFR 50.67#b2iii +, 10 CFR 50.36#c3 +, 10 CFR 50.36#c +, 10 CFR 50.36#b +, 10 CFR 50.55a#f +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +

05000424  +, 05000425  +, 00424  +  and 00425  +

Regulatory Guide 1.183 +, Regulatory Guide 1.196 +, Regulatory Guide 1.194 +, Regulatory Guide 1.23 +, ML053460347 +, ML112070118 +, ML003734190 +, ML003740205 +, ML070730398 +, ML070550069 +, ML070190178 +, ML011210348 +, ML012190402 +, ML15092A284 +, ML100130305 +, ML063480542 +, ML081850607 +, ML17346A587 +, ML17213A187 +, ML092290630 +, ML19101A215 +, ML19100A122 +, ML19028A384 +, ML20106F133 +, NUREG-1431 Volume 1, Rev. 5, Standard Technical Specifications Westinghouse Plants: Specifications +, ML19269F014 +, ML21259A159 +, NL-22-0208, License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 +, ML23065A061 +, NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 +...

Turbine Trip +  and Reactor Trip +

Markley M +  and Plant Licensing Branch II +

GDC 20 +, GDC 16 +, GDC 21 +, GDC 24 +, GDC 13 +, GDC 64 +, GDC 23 +, GDC 22 +  and GDC 19, Control room +

ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +, ML23158A018 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 8.101852e-4 d (0.0194 hours, 1.157407e-4 weeks, 2.6635e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +

Tritium +, Cs-137 +, Kr-85 +  and I-131 +

ML18247A400 +, NL-22-0208, License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 +, ML23037A003 +  and ML23083B370 +

NUREG-1431 +, NUREG/CR-6604 +, NUREG/CR-6189 +, NUREG/CR-5966 +, NUREG/CR-0200 +, NUREG-6331 +, NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0409, Discusses NUREG-0409 Iodine Behavior in PWR Cooling Sys Following Postulated Steam Generator Tube Rupture Accident +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

John Parillo +  and Ravi Grover +

Regulatory Guide 1.183 +, Regulatory Guide 1.196 +, Regulatory Guide 1.194 +, Regulatory Guide 1.23 +  and Regulatory Guide 1.145 +

SR-3.9.1.1 +, SR-3.3.6.2 +, SR-3.4.16.2 +, SR-3.3.6.1 +, SR-3.4.16.1 +, SR-3.3.6.5 +, SR-3.3.6.6 +, SR-3.4.16.3 +  and SR-3.3.6.7 +

Vogtle +  and NPF-68 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, HVAC +, Residual Heat Removal +, Control Room Emergency Filtration System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.4.13 +, TS-3.9.2 +, TS-3.8.5 +, TS-3.3.3.6 +, TS-3.8.2 +, TS-3.4.16 +, TS-3.7.10 +, TS-3.7.11 +, TS-1.1 +, TS-3.3.2 +, TS-3.9.3 +, TS-3.9.7 +, TS-3.8.8 +, TS-3.3.7 +, TS-3.7.15 +, TS-3.0 +, TS-3.3.6 +, TS-3.4.15 +, TS-3.8.10 +, TS-3.9.4 +, TS-3.9.1 +, TS-5.5.15 +, TS-3.7.16 +, TS-1.0 +, TS-3.5.6 +, TS-3.9 +, TS-3.0.4.c +  and TS-1.11 +

TSTF-286 +, TSTF-471 +, TSTF-490 +, TSTF-051 +  and TSTF-571 +

Southern Nuclear +  and Brown R +

Unanalyzed Condition +, Boric Acid +, Shutdown Margin +, Surveillance Frequency Control Program +, Loss of Offsite Power +, Fuel cladding +, Pressure Boundary Leakage +, Recently irradiated fuel +, Power change +, Unidentified leakage +, Manual Operator Action +, Operational leakage +  and Control Room Habitability +