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Safety Evaluation Report  and NUREG

Iodine +  and Silicon +

10 CFR 50 +, 10 CFR 50.54 +, 10 CFR 50.55a +  and 10 CFR 50.54#f +

ASME Code Case N-520 +  and ASME Code Case N-520-2 +

SECY-07-0096, Safety Evaluation Regarding Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations +  and L 2007-01 +

05000391  +, 00391  +  and 00390  +

ML090210107 +, ML080320443 +, ML080850253 +, ML072190047 +, ML072570676 +, ML080510469 +, ML083460177 +, ML082750019 +, ML073440022 +, ML081210270 +, ML081500030 +, ML072910331 +, ML080770237 +, ML080860026 +, ML081700293 +, ML082840361 +, ML072570319 +, ML072840337 +, ML081490110 +, ML081500115 +, ML082330421 +, ML082560373 +, ML072570678 +, ML080370185 +, ML080710489 +, ML081340309 +, ML081560183 +, ML083090046 +  and ML090210473 +

Turbine Trip +  and Reactor Trip +

Milano P +, Raghavan L +  and Watts Bar Special Projects Branch +

GDC 18 +, GDC 17, Electric power systems +, GDC 3, Fire protection +  and GDC 5, Sharing of structures, systems, and components +

NRC Generic Letter 04-02 +, NRC Generic Letter 04-01 +, NRC Generic Letter 06-01 +, NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, NRC Generic Letter 2006-03 +, NRC Generic Letter 80-77, Refueling Water Level +, NRC Generic Letter 80-14, LWR Primary Coolant System Pressure Isolation Valves +, NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +, NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 97-05, Steam Generator Tube Inspection Techniques +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +, NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +, NRC Generic Letter 98-02, Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition +, NRC Generic Letter 06-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 2003-01, Control Room Habitability +  and NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +

ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +, ML090570741 +  and ML090570741 +

NRC Bulletin 79-27 +, NRC Bulletin 80-06 +, NRC Bulletin 77-04 +  and NRC Bulletin 75-08 +

NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, 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 +, NUREG-1232, Forwards Safety Evaluation Accepting Improvement Plan for Emergency Diesel Generators Transient Voltage Response.Mods Remain Scheduled by TVA for Completions Prior to Restart of Unit 1,Cycle 4 Refueling Outage +  and NUREG-0750, Index 9, Indexes to Nuclear Regulatory Commission Issuances Vols. 83 - 92 (January 1, 2016 - December 31, 2020) +

ML090570741 +  and ML090570741 +

Manual Scram +  and Automatic Scram +

Tennessee +, Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Turbine Gland Sealing System +

Safe Shutdown +, Ultimate heat sink +, Fire Barrier +, Hydrostatic +, Condition Adverse to Quality +, Hemyc +, Control Room Habitability +, Gas accumulation +  and Leak-Before-Break +