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Letter, Technical Specifications  and License-Application for Facility Operating License (Amend/Renewal) DKT 50

Strontium +, Iodine +, Cesium +, Nitrogen +, Carbon +, Hydrogen +, Lead +, Tellurium +, Barium +  and Cerium +

10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 1 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 50 Appendix I +, 10 CFR 52.22#c +, 10 CFR 65.6 +, 10 CFR 50.67#b2 +, 10 CFR 50.54#o +, 10 CFR 50.36#c2ii +, 10 CFR 50.91#b +, 10 CFR 5#o64 +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +

SECY-98-154 +  and SECY-99-240 +

05000423  +  and 00423  +

Turbine Trip +  and Reactor Trip +

Dominion Nuclear Connecticut +  and Grecheck E +

ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +, ML041560464 +  and ML041560464 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 0.0951 d (2.283 hours, 0.0136 weeks, 0.00313 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +, 0.00113 d (0.0272 hours, 1.62037e-4 weeks, 3.7289e-5 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +, 0.00793 d (0.19 hours, 0.00113 weeks, 2.606425e-4 months)  +, 0.0947 d (2.273 hours, 0.0135 weeks, 0.00311 months)  +, 0.00641 d (0.154 hours, 9.160053e-4 weeks, 2.10797e-4 months)  +, 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 0.0104 d (0.25 hours, 0.00149 weeks, 3.4245e-4 months)  +

Am-241 +, Cs-137 +, Y-90 +, Kr-85 +, I-131 +, Mo-99 +, Pu-238 +  and Pu-239 +

NUREG-800 +, NUREG/CR-6604 +, NUREG/CR-6189 +, 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-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  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 +

TAC:MC3333 +  and TAC:MC0498 +

TAC:MB3700 +, TAC:MA1749 +  and TAC:MB8137 +

Regulatory Guide 1.183 +, Regulatory Guide 1.1 +, Regulatory Guide 1.163 +, Regulatory Guide 1.194 +, Regulatory Guide 1.52 +, Regulatory Guide 1.109 +  and Regulatory Guide 1.145 +

SECY-98-154 +  and SECY-99-240 +

SR-4.7.7 +, SR-4.7.7.e +, SR-4.7.1.3.2 +, SR-4.7.7.a +, SR-4.7.5.a +, SR-4.7.5.b +, SR-4.7.8.c +, SR-4.7.7.e.2 +  and SR-4.7.8.C +

55E-06 +, 20E-08 +, 69E-02 +, 17E-05 +, 27E-03 +, 15E-01 +, 07-04-285 +, 1ft-10in +  and 3HVC-PDI +

Connecticut +, Washington +, Virginia +  and New Mexico +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Residual Heat Removal +, Control Room Emergency Ventilation +, Control Room Emergency Filtration System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.4.6.2 +, TS-3.7.1.3 +, TS-6.8 +  and TS-6.8.4.f +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Boric Acid +, Ultimate heat sink +, Probabilistic Risk Assessment +, Loss of Offsite Power +, Deep Dose Equivalent +, Manual Operator Action +  and Control Room Habitability +

WCAP-13132 +  and WCAP-7828 +

WCAP-7828 +  and WCAP-13132 +