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SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT

Iodine +, Nitrogen +, Carbon +, Oxygen +  and Hydrogen +

10 CFR 50 Appendix R +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix I +, 10 CFR 51.21 +  and 10 CFR 50#3 +

05000321  +, 05000366  +, 00321  +  and 00366  +

Turbine Trip +  and Reactor Trip +

SIL 377 +  and SIL 480 +

GDC 12 +  and GDC 19, Control room +

NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +

ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +, ML20091S082 +  and ML20091S082 +

2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

HL-4812, Forwards Response to NRC 950310 RAI Re Util 950113 Power Uprate Submittal.Info Relative to Plant Setpoint Methodology & Calculations Also Encl +, HL-4781, Submits Addl Info Requested by NRC Re Recent Core Shroud Mod on Plant Unit 1 +, 05000321/LER-1991-016-01, :on 910905,RWCU Sys Isolated Due to Blown Fuse. Cause for Fuse Blowing Not Determined.Blown Fuse Replaced & RWCU Sys Returned to Svc +, 05000366/LER-1994-009-02, :on 941220,failed Component Results in Unplanned Engineered Safety Feature Sys Actuation.Relay Coil Was Replaced +  and ML20064M929 +

NUREG/CR-5055, Informs of 970422 Telcon Re Plant,Unit 1 & 2 Applicability of NUREG/CR-5055, Atmospheric Diffusion for Control Room Habitability Assessments. Ltrs from Pnl & 0823 Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

Regulatory Guide 1.3 +, Regulatory Guide 1.49 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.139 +

NEDC-32405P +, NEDC-31336 +, NEDC-31897P +, NEDC-31984P +  and NEDC-31897 +

Washington +  and Georgia +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Circulating Water System +, Residual Heat Removal Service Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +...

Safe Shutdown +, Safety Limit Minimum Critical Power Ratio +, Ultimate heat sink +, Anticipated operational occurrence +, Hydrostatic +, High Energy Line Break +, Flow Accelerated Corrosion +, Feedwater Heater +, Feedwater Controller Failure +, Turbine Missile +, Power Uprate +, Overspeed +, Simmer margin +  and Subsequent actuation +