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Report, Updated Final Safety Analysis Report (UFSAR)  and Technical

ANSI/ANS 3.5 +, ANSI/ANS 5.1-1979 +, ANSI/ANS 3.5-1985 +  and ANSI/ANS-5.1-1979 +

ASME Section XI +, ASME Section III +  and ASME Section I +

Boron +, Iodine +, Iron +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chlorine +, Lead +, Mercury +  and Zinc +

10 CFR 50 Appendix R +, 10 CFR 55 +, 10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 50.7 +, 10 CFR 50.92 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +  and 10 CFR 50 Appendix B Criterion XI +

Tennessee Valley Authority +  and Schaefer K +

NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +, ML041840116 +  and ML041840116 +

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.861111e-4 d (0.0117 hours, 6.944444e-5 weeks, 1.5981e-5 months)  +, 3.703704e-4 d (0.00889 hours, 5.291005e-5 weeks, 1.2176e-5 months)  +, 5.787037e-4 d (0.0139 hours, 8.267196e-5 weeks, 1.9025e-5 months)  +, 0.0011 d (0.0264 hours, 1.570767e-4 weeks, 3.61475e-5 months)  +, 5.208333e-4 d (0.0125 hours, 7.440476e-5 weeks, 1.71225e-5 months)  +, 0.00191 d (0.0458 hours, 2.728175e-4 weeks, 6.27825e-5 months)  +  and 0.00133 d (0.0319 hours, 1.901455e-4 weeks, 4.37575e-5 months)  +

Tritium +  and N-16 +

NRC Bulletin 79-14 +  and NRC Bulletin 96-03 +

NUREG/CR-5750 +, NUREG-1048, Forwards Safety Evaluation Supporting Proposed Turbine Sys Maint Program Submitted w/870513 Ltr +, NUREG/CR-5500, Discusses Issuance of Final Rept, Reliability Study Auxiliary Emergency Feedwater System 1987-1995, (NUREG/CR-5500,Vol 1).Summary of Comment Resolutions Encl +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, 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-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 +

AOP +, SAP +, SP +, ISP +  and Emergency Operating Procedure +

TAC:MA6481 +, TAC:MA3492 +, TAC:MB2774 +, TAC:M99711 +, TAC:M96135 +  and TAC:M08436 +

Regulatory Guide 1.97 +, Regulatory Guide 1.174 +, Regulatory Guide 1.49 +, Regulatory Guide 1.105 +, Regulatory Guide 1.149 +, Regulatory Guide 1.190 +  and Regulatory Guide 1.20 +

NEDO-32047 +, NEDO-20566A +, NEDE-2401 +, NEDO-32686 +, NEDC-31336 +, NEDC-32424P +, NEDO-10320 +, NEDO-21052 +, NEDE-20566P +, NEDO-20533 +, NEDO-21888 +, NEDE-23785P +, NEDE-24222 +, NEDC-32523P +, NEDO-30832 +, NEDC-32983P +, NEDE-24011P +, NEDE-23504 +, NEDO-24154 +, NEDC-32084P +, NEDE-24154P +, NEDE-23785 +, NEDE-30996P +, NEDC-32950P +, NEDO-32164 +, NEDC-23785P +, NEDO-32983 +, NEDO-32424 +, NEDO-33101 +, NEDC-33101 +...

1E-6 +, 1E-9 +, 6t139-21 +, C28U-2 +, C28S8-2 +  and 32s-e +

Tennessee +, North Carolina +  and California +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Control Room Emergency Ventilation +, Steam Bypass Control System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Remote shutdown +, Stator Cooling Water +...

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Safety Limit Minimum Critical Power Ratio +, Ultimate heat sink +, Non-Destructive Examination +, Stroke time +, Anticipated operational occurrence +, Time to boil +, Internal Flooding +, Hydrostatic +, Probabilistic Risk Assessment +, Coatings +, Nondestructive Examination +, Temporary Modification +, Finite Element Analysis +, High Energy Line Break +, Significance Determination Process +, Flow Accelerated Corrosion +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Feedwater Controller Failure +, Large early release frequency +, MELLLA +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Turbine Missile +, Fuel cladding +, Fire Protection Program +...