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ACI-349 +  and ACI-201 +

ANSI B31.1 +, ANSI/ANS 56.8 +  and ANSI N45.2.6-1978 +

AR 01813863 +  and AR 01232104 +

IWB-3600 +  and IWB-2500 +

ASME Section XI +  and ASME Section III +

Iron +, Nickel +, Copper +, Carbon +, Sodium +, Hydrogen +, Molybdenum +, Chloride +, Lead +  and Zinc +

BWRVIP-75-A +, BWRVIP-116 +, BWRVIP-190 +, BWRVIP-05 +, BWRVIP-1 +, BWRVIP-27-A +, BWRVIP-47-A +, BWRVIP-48-A +, BWRVIP-49-A +, BWRVIP-74-A +  and BWRVIP-86-A +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.65 +, 10 CFR 50.90 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.3 +, 10 CFR 54.3#a +, 10 CFR 50.49#a +, 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 +, 10 CFR 54.21#c2 +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#b2 +  and 10 CFR 50.55#a +

05000352  +  and 05000353  +

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 +

ML18285A594 +, ML18285A594 +, ML18285A594 +, ML18285A594 +, ML18285A594 +, ML18285A594 +, ML18285A594 +, ML18285A594 +, ML18285A594 +  and ML18285A594 +

LR-ISG-2012-02 +  and LR-ISG-2013-01 +

NUREG/CR-6260 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, 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 +, 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 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.190 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +  and Regulatory Guide 1.89 +

Feedwater +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Circulating Water System +, Spray Pond +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +  and Main Steam +

Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Hydrostatic +, Coatings +, Nondestructive Examination +, VT-2 +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Eddy Current Testing +, License Renewal +, Control of Heavy Loads +, Thermography +, Thermal fatigue +  and Spent fuel rack +