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

ASTM D4057 +, ASTM D2709 +, ASTM D975 +  and ASTM D5452 +

Iron +, Nitrogen +, Carbon +, Chloride +, Aluminum +  and Manganese +

BWRVIP-75-A +, BWRVIP-41 +, BWRVIP-86 +, BWRVIP-25 +, BWRVIP-183 +, BWRVIP-18 +, BWRVIP-38 +, BWRVIP-234 +, BWRVIP-05 +, BWRVIP-26-A +, BWRVIP-27-A +, BWRVIP-47-A +, BWRVIP-48-A +, BWRVIP-139-A +, BWRVIP-74-A +  and BWRVIP-76-A +

10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 54.21 +  and 10 CFR 54.4#b +

05000010  +, 05000237  +  and 05000249  +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 87-05, Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, 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 +

ML25232A229 +, ML25232A229 +, ML25232A229 +, ML25232A229 +, ML25232A229 +, ML25232A229 +, ML25232A229 +, ML25232A229 +, ML25232A229 +  and ML25232A229 +

DPR-002  +, DPR-019  +  and DPR-025  +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, 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-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

Regulatory Guide 1.163 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.54 +

Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Reactor Water Cleanup +, Standby Liquid Control +, Intermediate Range Monitor +, Stator Cooling Water +, Stator Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +, Main Steam +, Low Pressure Coolant Injection +  and Electro-Hydraulic Control +

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

Fire Barrier +, Coatings +, Nondestructive Examination +, Aging Management +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Eddy Current Testing +, Main Steam Line Radiation Monitor +, Moisture barrier +, License Renewal +, Biofouling +  and Spill +