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ACI-349 +  and ACI-201 +

IWB-2500 +, IWB-3000 +  and IWB-2430 +

ASME Section XI +, ASME Section III +  and ASME Section V +

Iron +, Nickel +, Copper +, Carbon +, Oxygen +, Chloride +, Lead +, Aluminum +  and Zinc +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 50.49#f +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 50.55a#b2 +, 10 CFR 50.55a#g4ii +, 10 CFR 50.55a#b2ix +  and 10 CFR 50.55a#g6ii +

ASME Code Case N-729-1 +  and ASME Code Case N-722 +

NOC-AE-14003135, Response to Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Addiction - Set 26 (TAC ME4936 and ME4937) +, NOC-AE-43003135 +, ND-3649 +  and NOC-AE-24004038 +

05000498  +  and 05000499  +

MRP-139 +, MRP-227 +  and MRP-228 +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, 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 +

ML24130A078 +, ML24130A078 +, ML24130A078 +, ML24130A078 +, ML24130A078 +, ML24130A078 +, ML24130A078 +, ML24130A078 +, ML24130A078 +  and ML24130A078 +

NEI 97-06, Steam Generator Conditioning Monitoring Report +, NEI 03-08, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, Materials Reliability Program: Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants . +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NRC Bulletin 80-11 +, NRC Bulletin 88-09 +, NRC Bulletin 87-01 +, NRC Bulletin 88-11 +  and NRC Bulletin 88-08 +

Information Notice 87-67 +  and Information Notice 99-10 +

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-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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, 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 1.121 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.190 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +, Regulatory Guide 1.54 +, Regulatory Guide 1.43 +, Regulatory Guide 1.14 +, Regulatory Guide 1.89 +  and Regulatory Guide 1.35.1 +

19A-20 +, 19A-3 +, 19A-2 +, 19A-44 +, 19A-50 +, 19A-5 +, 19A-86 +, 19A-87 +, 19A-42 +, 19A-43 +, 19A-46 +, 19A-47 +, 19A-49 +, 19A-52 +, 19A-53 +, 19A-64 +, 19A-65 +, 19A-66 +, 19A-67 +, 19A-70 +, 19A-71 +, 19A-72 +, 19A-78 +, 19A-1 +, 19A-4 +, 19A-25 +, 19A-7 +, 19A-17 +, 19A-14 +, 19A-27 +...

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Primary containment +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +  and Main Steam +

Boric Acid +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Weld Overlay +, Hydrostatic +, Past operability +, Coatings +, Nondestructive Examination +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Integrated leak rate test +, Eddy Current Testing +, License Renewal +, Control of Heavy Loads +, Biofouling +, EVT-1 +, Through-Wall Leakage +, Fire Protection Program +, Core Exit Thermocouple +, Power Uprate +, Thermography +, Operational leakage +, Thermal fatigue +, Leak-Before-Break +...

WCAP-15988-NP +  and WCAP-15338-A +

WCAP-15988-NP +  and WCAP-15338-A +