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ANSI B31.1 +, ANSI B30.2 +, ANSI B30.11 +  and ANSI B30.16 +

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

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

BWRVIP-75 +, BWRVIP-116 +, BWRVIP-25 +, BWRVIP-03 +, BWRVIP-74 +, BWRVIP-05 +, BWRVIP-48-A +, BWRVIP-74-A +  and BWRVIP-86-A +

10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50.55a +, 10 CFR 50.49#e +, 10 CFR 50.49#a +, 10 CFR 54.21#d +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +  and 10 CFR 50.55a#b +

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 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +

ML14010A314 +, ML14010A314 +, ML14010A314 +, ML14010A314 +, ML14010A314 +, ML14010A314 +, ML14010A314 +, ML14010A314 +  and ML14010A314 +

NUREG/CR-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-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-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 +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

Nozzle:N6 +  and Nozzle:N12 +

Regulatory Guide 1.190 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.89 +

Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Spray Pond +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Loop seal +, Fire Barrier +, Safe Shutdown Earthquake +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Incorporated by reference +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, License Renewal +, Fire Protection Program +, Flow Induced Vibration +, Power Uprate +, Thermography +  and Spent fuel rack +