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ML17334A156 +
January 2, 2004 +
NRC Generic Letter 97-02, Revised Contents of the Monthly Operating Report +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 81-07, Control of Heavy Loads + and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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November 2, 2017 +
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18:45:54, 7 January 2025 +
NEI 90-13 +, NEI 07-07, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 2009 + and NEI 03-08, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, Materials Reliability Program: Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants . +
NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG-1672 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 + and 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 +
138 +
Request +
1B-B +, 2B-B +, 1A-A +, 2A-A +, 2A1-A +, 1A-1 +, 1B1-B +, 1A1-A +, 1A2-A +, 2B2-B +, 2B1-B +, 2A2-A +, 45N700-3 +, 45N706-2 +, 1B2-B +, 45N706-4 +, 45W760-82-2 +, 45W760-82-4 +, 47W611-67-1 +, 07-99-007 +, 45W760-12-1 +, 47W610-30-8 +, 47W610-31-8A +, 45W760-31-10 +, 47W611-82-2D +, 45W760-82-12 +, 45W760-82-8A +, 45N706-1 +, 47W605-2 +, 47W605-1 +...
November 2, 2017 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Transformer +, HVAC +, Reactor Pressure Vessel +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Shield Building +, Circulating Water System +, Intermediate Range Monitor +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Safety Relief Valve +, Moisture Separator Reheater +, Main Condenser +, Control Rod +, Main Steam + and Containment Spray +
Amendment 1 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (Redacted) +
Safe Shutdown +, Boric Acid +, Offsite Dose Calculation Manual +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Hydrostatic +, Zebra Mussel +, Incorporated by reference +, Notice of Violation +, Feedwater Heater +, Eddy Current Testing +, Severe Accident Management Guideline +, Containment high range radiation monitor +, Tritium Producing Burnable Absorber Rods +, Earthquake +, Commercial Grade +, Control of Heavy Loads +, Fuel cladding +, Biofouling +, Core Exit Thermocouple +, Dedication package +, Negative rate trip + and Pressure Temperature Limits Report +
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WCAP-14036-P-A +, WCAP-8110 +, WCAP-8687 +, WCAP-12374 +, WCAP-7817 +, WCAP-8673 +, WCAP-8373 +, WCAP-17044-P +, WCAP-7571 +, WCAP-8354-P-A +, WCAP-8355-A +, WCAP-7558 +, WCAP-8624 +, WCAP-8695 +, WCAP-10444-P-A +, WCAP-6065 +, WCAP-8183 +, WCAP-8768 +, WCAP-8377 +, WCAP-8381 +, WCAP-8236 +, WCAP-8288 +, WCAP-8278 +, WCAP-8279 +, WCAP-7800 +, WCAP-13632-P-A +, WCAP-8446 +, WCAP-8449 +, WCAP-7941-P-A +, WCAP-7959-A +...
WCAP-14036-P-A +, WCAP-8110 +, WCAP-8687 +, WCAP-12374 +, WCAP-7817 +, WCAP-8673 +, WCAP-8373 +, WCAP-17044-P +, WCAP-7571 +, WCAP-8354-P-A +, WCAP-8355-A +, WCAP-7558 +, WCAP-8624 +, WCAP-8695 +, WCAP-10444-P-A +, WCAP-6065 +, WCAP-8183 +, WCAP-8768 +, WCAP-8377 +, WCAP-8381 +, WCAP-8236 +, WCAP-8288 +, WCAP-8278 +, WCAP-8279 +, WCAP-7800 +, WCAP-13632-P-A +, WCAP-8446 +, WCAP-8449 +, WCAP-7941-P-A +, WCAP-7959-A +...