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ANSI B31.1 +, ANSI N45.2 +, ANSI B31.1-1980 +  and ANSI/ANS-5.1-1979 +

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

Nickel +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chloride +, Lead +, Helium +, Silicon +  and Zinc +

BWRVIP-75-A +, BWRVIP-41 +, BWRVIP-86 +, BWRVIP-78 +  and BWRVIP-86-A +

10 CFR 50 +, 10 CFR 50.2 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 50.55a#g +, 10 CFR 50.55a#g6i +, 10 CFR 50.55a#c +  and 10 CFR 50.55a#a1 +

05000010  +, 05000237  +  and 05000249  +

Drawing 5.1-2 +, Drawing 5.2-5 +  and Drawing 5.4-23 +

Turbine Trip +  and Reactor Trip +

GE-NE-523-A71-0594 +  and GE-NE-523-93-0991 +

NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML23180A020 +, ML23180A020 +, ML23180A020 +, ML23180A020 +, ML23180A020 +, ML23180A020 +, ML23180A020 +, ML23180A020 +, ML23180A020 +, ML23180A020 +  and ML23180A020 +

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.513889e-4 d (0.0108 hours, 6.448413e-5 weeks, 1.48395e-5 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

IEEE 323-1974 +  and IEEE 344-1975 +

Westinghouse +, General Electric +  and Target Rock +

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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

ST +, ISP +, TP-304 +  and TP-316 +

Regulatory Guide 1.45 +, Regulatory Guide 1.70 +, Regulatory Guide 1.26 +, Regulatory Guide 1.190 +, Regulatory Guide 1.99 +, Regulatory Guide 1.43 +, Regulatory Guide 1.50 +, Regulatory Guide 1.31 +, Regulatory Guide 1.44 +, Regulatory Guide 1.34 +  and Regulatory Guide 1.71 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Main Steam Safety Valve +, Steam Jet Air Ejector +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Office of Nuclear Reactor Regulation +  and Office of Nuclear Material Safety and Safeguards +

Safe Shutdown +, Shutdown Margin +, Weld Overlay +, Hydrostatic +, Nondestructive Examination +, High Energy Line Break +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Feedwater Controller Failure +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Liquid penetrant +, Pressure Boundary Leakage +, Dissimilar Metal Weld +, Unidentified leakage +, Unidentified leak +, Power Uprate +, Overspeed trip +, Overspeed +, Subsequent actuation +  and Water hammer +