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

Pennsylvania Department of Environmental Protection +  and Department of Natural Resources +

Iodine +, Cesium +, Uranium +  and Sodium +

10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 30 +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 54 +, 10 CFR 50.44 +, 10 CFR 50.90 +, 10 CFR 73.21 +, 10 CFR 100.11 +, 10 CFR 50.55a +, 10 CFR 50.67#b2 +, 10 CFR 50.67#b +, 10 CFR 50.54#p +, 10 CFR 73.55#51 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.71#e +

05000277  +, 05000278  +, 00277  +  and 00278  +

ML011210348 +, ML012190402 +, ML040400343 +, ML082340796 +, ML011230531 +, ML040640364 +, ML082490835 +, ML082140237 +, ML081500373 +, ML081090447 +, ML080910502 +, ML040890545 +, ML072570151 +, ML080670277 +  and ML082260396 +

John Hughey +  and NRC/NRR/ADRO/DORL/LPLI-2 +

NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +  and NRC Generic Letter 2003-01, Control Room Habitability +

ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +, ML082320406 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 0.00104 d (0.025 hours, 1.488095e-4 weeks, 3.4245e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.837963e-4 d (0.0236 hours, 1.405423e-4 weeks, 3.23425e-5 months)  +, 4.398148e-4 d (0.0106 hours, 6.283069e-5 weeks, 1.4459e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +  and 9.722222e-4 d (0.0233 hours, 1.388889e-4 weeks, 3.1962e-5 months)  +

I-131 +  and Kr-85 +

05000278/LER-2004-002, Loss of High Pressure Coolant Injection System Automatic High Level Trip as a Result as a Result of Lifted Lead +, ML081430695 +, ML050330124 +, ML062750099 +, LR-N06-0249, Units 2 and 3, Nuclear Facilities, NRC Decommissioning Funding Status Report +  and ML043020352 +

NUREG/CR-5950 +, NUREG-1433 +, NUREG/CR-6604 +, NUREG/CR-2858 +, NUREG/CR-6189 +, NUREG-0917 +, 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 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  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 +

James Shea +  and Alexander Tsirigotis +

TAC:MD6806 +  and TAC:MD6807 +

TAC:MD6806 +  and TAC:MD6807 +

Regulatory Guide 1.183 +, Regulatory Guide 1.196 +, Regulatory Guide 1.194 +, Regulatory Guide 1.52 +, Regulatory Guide 1.23 +, Regulatory Guide 1.145 +  and Regulatory Guide 1.5 +

SR-3.6.1.3 +, SR-3.6.4.1.3 +  and SR-3.1.7.7 +

Reactor Coolant System +, Secondary containment +, Reactor Protection System +, Main Steam Isolation Valve +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Control Room Emergency Ventilation +, Standby Liquid Control +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.6.4.1 +, TS-3.3.6.1 +, TS-3.6.1.3 +, TS-5.5.12 +, TS-1.1 +, TS-3.1.7 +, TS-3.6.4.2 +, TS-3.3.6.2 +, TS-3.6.4.3 +  and TS-3.4.6 +

Pardee C +  and Exelon +

High winds +, Reactor Vessel Water Level +, Design basis earthquake +, Safeguards Contingency Plan +, Earthquake +, Fuel cladding +, Recently irradiated fuel +, Fire Protection Program +  and Control Room Habitability +