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Letter  and Inservice/Preservice Inspection and Test Report

IWB-3410 +, IWC-3000 +, IWB-2500 +, IWB-3000 +, IWB-3132 +, IWC-2500 +, IWC-3410 +, IWB-3142 +, IWC-3122 +, IWB-2412 +, IWB-1220 +, IWB-2400 +, IWB-2200 +, IWB-1200 +, IWB-2430 +, IWC-2400 +, IWB-2600 +, IWC-2520 +, IWC-3132 +, IWC-2412 +, IWB-3144 +, IWC-2411 +, IWB-3134 +, IWC-1200 +, IWC-3125 +, IWC-3134 +, IWB-34 +, IWA-6000 +, IWA-2300 +, IWA-5000 +...

ASME Section XI +, ASME Section III +  and ASME Section V +

10 CFR 50 +, 10 CFR 50.2 +, 10 CFR 50.55a +, 10 CFR 50.55a#b2xiv +, 10 CFR 50.55a#g6iiA +, 10 CFR 50.55a#3i +, 10 CFR 50.55a#g3v +, 10 CFR 50.55a#c1 +, 10 CFR 50.55a#3ii +, 10 CFR 50.55a#b2xD +  and 10 CFR 50.55#g4iv +

ASME Code Case N-498-1 +  and ASME Code Case N-524 +

05000259  +, 00259  +  and 00296  +

Tennessee Valley Authority +  and Abney T +

ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +, ML023250275 +  and ML023250275 +

Target Rock +  and General Electric +

NUREG-03 +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, 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 +  and NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +

AM +, ST +, CP-1 +  and CP-189 +

Regulatory Guide 1.147 +  and Regulatory Guide 1.26 +

66C60-90744 +, 67C60-91750 +, 47W813-1 +, 47W812-1 +, 07-69-500 +, 1B-SE +, 47B435-series +, 07-69-580 +, 2A-SE +, 2B-SE +, 2C-SE +, 2D-SE +, 2E-SE +, 2F-SE +, 2G-SE +, 2H-SE +, 2J-SE +, 2K-SE +, 5A-SE +, 5B-SE +, 435KAA-002 +, 07-85-576 +, 1WA-3000 +, 17C2556-4-ISI +, 17C2556-5-ISI +  and 1WX-3000 +

Tennessee +, Georgia +, Maryland +, Washington +  and Alabama +

Feedwater +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Reactor Water Recirculation +, Control Rod +  and Main Steam +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Hydrostatic +, Anchor Darling +, Nondestructive Examination +, VT-2 +, Flow Accelerated Corrosion +, Scram Discharge Volume +, Liquid penetrant +  and Dissimilar Metal Weld +