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

Iodine +, Cesium +, Uranium +  and Sodium +

10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.81 +, 10 CFR 100.11 +, 10 CFR 50.47#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.71#e +

05000440  +  and 00440  +

ML011210348 +, ML012190402 +, ML15075A139 +, ML14282A218 +, ML021840462 +, ML023580025 +, ML02180462 +, ML003724441 +, L-15-018, Response to Request for Additional Information Regarding Request for Licensing Action on Alternative Accident Source Term Radiological Dose Calculations +, L-14-245, Response to Request for Additional Information Regarding Request for Licensing Action on Alternative Accident Source Term Radiological Dose Calculations +, L-14-090, Acceptance Review Supplemental Information for Alternative Accident Source Term Design Basis Accident Analysis Request for Licensing Action +  and L-13-306, Request for Licensing Action Pursuant to 10 CFR 50.59. 50.67. and 50.90: Full Implementation of Alternative Accident Source Term Design Basis Accident Analyses. and an Associated Technical Specification Change +

Technical Support Center +  and Emergency Operations Facility +

Ellen Brown +  and Plant Licensing Branch III +

GDC 29 +, GDC 17, Electric power systems +, GDC 19, Control room +  and GDC 26, Reactivity control system redundancy and capability +

ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +, ML15075A139 +...

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)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +  and 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +

Kr-85 +, I-131 +  and Iodine-131 +

IR 05000440/2002008 +, L-14-245, Response to Request for Additional Information Regarding Request for Licensing Action on Alternative Accident Source Term Radiological Dose Calculations +  and ML20205B887 +

NUREG/CR-5950 +, NUREG-1228 +, NUREG/CR-6189 +, NUREG/CR-5966 +, NUREG/CR-0009 +, 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-1150, Weekly Info Rept for Wk Ending 890922 +, 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-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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 +

Regulatory Guide 1.183 +, Regulatory Guide 1.189 +, Regulatory Guide 1.196 +, Regulatory Guide 1.194 +, Regulatory Guide 1.52 +  and Regulatory Guide 1.23 +

SR-3.6.1.3 +, SR-3.6.4.1.1 +  and SR-3.6.1.3.9 +

Ohio +  and Washington +

Reactor Coolant System +, Secondary containment +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Shield Building +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.6.1.3 +, TS-3.4.8 +, TS-1.1 +  and TS-3.6.1.9 +

FirstEnergy +  and Harkness E +

Reactor Vessel Water Level +, Anticipated operational occurrence +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Power Uprate +  and Control Room Habitability +