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Carbon +  and Hydrogen +

ML100080768 +, ML101200155 +, ML072570676 +, SECY-07-0096, Safety Evaluation Regarding Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations +, ML090700378 +, ML093631061 +, ML100130227 +, ML100190443 +, ML100539515 +, ML100200375 +, ML100260594 +, ML100270076 +, ML100120052 +, ML101200035 +, ML100480062 +, ML102080017 +  and ML100770549 +

NRC Generic Letter 04-02 +, NRC Generic Letter 07-01 +, 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 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System +, NRC Generic Letter 82-16, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 93-04, Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +, 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 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits +, 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 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +, NRC Generic Letter 2003-01, Control Room Habitability +, NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +, ML11213A133 +...

ML110980637 +, IR 05000390/2010502 +, IR 05000390/2010003 +, ML090480566 +, IR 05000391/2011601 +, ML101200035 +, ML100480062 +, ML100770549 +, ML101960502 +, ML072570678 +, ML100120026 +, ML021400648 +, ML023540355 +, ML100331603 +, ML082730087 +, ML062910093 +, ML050930031 +  and ML042150438 +

Cutler-Hammer +  and Westinghouse +

NRC Bulletin 04-01 +, NRC Bulletin 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 02-02 +, NRC Bulletin 03-02 +, NRC Bulletin 79-21 +, NRC Bulletin 96-01 +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +

NUREG-1431 +, NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, 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-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +

SR-3.0.1 +, SR-3.0.2 +, SR-3.5.2.3 +  and SR-3.7.10.4 +

2A-A +  and 47W450-53 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Pressure Vessel +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Room Envelope +, Control Rod +  and Containment Spray +

TS-5.7.2 +, TS-3.4.13 +, TS-3.4.17 +  and TS-5.7.2.1 +

TSTF-448 +  and TSTF-449 +

Safe Shutdown +, Boric Acid +, Fire Barrier +, Probabilistic Risk Assessment +, Coatings +, Anchor Darling +, Stress corrosion cracking +, Eddy Current Testing +, Hemyc +, Pressure Boundary Leakage +, Operational leakage +, Control Room Habitability +, Gas accumulation +  and Pressure Temperature Limits Report +