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

Iron +, Nickel +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Molybdenum +, Chloride +  and Lead +

BWRVIP-75-A +, BWRVIP-116 +, BWRVIP-139 +, BWRVIP-130 +, BWRVIP-74 +, BWRVIP-05 +, BWRVIP-27-A +, BWRVIP-48-A +  and BWRVIP-49-A +

10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix H +, 10 CFR 54.4 +, 10 CFR 54.29 +, 10 CFR 54.24#c1iii +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a1 +, 10 CFR 50.49#f +, 10 CFR 50.49#a +, 10 CFR 50.21#cii +, 10 CFR 54.21#d +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +  and 10 CFR 54.21#c +

05000298  +  and 00298  +

NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +, ML083030241 +  and ML083030241 +

NUREG/CR-6260 +, NUREG-6260 +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

4.16kV +  and 345kV +

Regulatory Guide 1.163 +, Regulatory Guide 1.160 +, Regulatory Guide 1.190 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.89 +

Reactor Coolant System +, Feedwater +, Service water +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Circulating Water System +, Intermediate Range Monitor +, Main Steam Line +, Control Rod +  and Main Steam +

Loop seal +, Non-Destructive Examination +, Fire Barrier +, Anticipated operational occurrence +, Coatings +, Nondestructive Examination +, Aging Management +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Main Steam Line Radiation Monitor +, Moisture barrier +, License Renewal +, Fire Protection Program +, Power Uprate +, Measurement Uncertainty Recapture +, Thermography +  and Spent fuel rack +