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ANSI B31.1 +  and ANSI/ANS 56.8 +

IWB-2500 +  and IWA-2300 +

ASME Section XI +  and ASME Section III +

Iron +, Nickel +, Copper +, Carbon +, Sodium +, Hydrogen +, Chloride +, Lead +  and Aluminum +

BWRVIP-75-A +, BWRVIP-86 +, BWRVIP-25 +, BWRVIP-183 +, BWRVIP-38 +, BWRVIP-76 +, BWRVIP-139 +, BWRVIP-130 +, BWRVIP-180 +, BWRVIP-05 +, BWRVIP-26-A +, BWRVIP-27-A +, BWRVIP-47-A +, BWRVIP-48-A +, BWRVIP-18-A +, BWRVIP-42-A +  and BWRVIP-49-A +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 50.55a +, 10 CFR 54.3#a +, 10 CFR 50.49#e +, 10 CFR 54.21#d +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +  and 10 CFR 50.55#a +

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 +  and NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds +

ML18334A150 +, ML18334A150 +, ML18334A150 +, ML18334A150 +, ML18334A150 +, ML18334A150 +, ML18334A150 +, ML18334A150 +, ML18334A150 +  and ML18334A150 +

LRA B.2.1.31 +, LRA B.2.1.33 +, LRA B.2.1.10 +, LRA B.2.1.13 +, LRA B.2.1.7 +, LRA B.2.1.9 +, LRA B.2.1.11 +, LRA B.2.1.21 +, LRA B.2.1.29 +, LRA B.2.1.30 +, LRA B.2.1.32 +, LRA B.2.1.39 +, LRA B.2.2.3 +, LRA B.2.1.22 +, LRA B.2.1.23 +, LRA B.3.1.1 +, LRA B.3.1.2 +, LRA B.2.1.2 +, LRA B.2.1.18 +, LRA B.2.1.19 +, LRA B.2.1.35 +, LRA B.2.1.34 +, LRA B.2.1.16 +, LRA B.2.1.20 +, LRA B.2.1.17 +, LRA B.2.2.1 +, LRA B.2.1.28 +, LRA B.2.1.24 +, LRA B.2.1.12 +, LRA B.2.1.27 +...

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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

Regulatory Guide 1.163 +, Regulatory Guide 1.147 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.190 +, Regulatory Guide 1.65 +  and Regulatory Guide 1.99 +

5E-6 +, 1A-T-403 +, 1B-T-403 +, 1C-T-403 +, 1G-T-403 +, 1D-T-403 +, 1E-T-403 +, 1F-T-403 +  and 1H-T-403 +

Feedwater +, Service water +, High Pressure Coolant Injection +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Control Rod +  and Low Pressure Coolant Injection +

Safe Shutdown +, Non-Destructive Examination +, Fire Barrier +, Anticipated operational occurrence +, Hydrostatic +, Coatings +, Nondestructive Examination +, VT-2 +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, Earthquake +, Biofouling +, EVT-1 +, Fire Protection Program +, Power Uprate +  and Thermography +