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ACI-318 +  and ACI-349 +

ANSI B31.1 +, ANSI N45.2.6 +, ANSI N101.2 +  and ANSI B31.7 +

ASME Section XI +  and ASME Section III +

Boron +, Nickel +, Carbon +, Oxygen +, Lead +  and Sulfur +

10 CFR 54.21#d +, 10 CFR 54.21#a3 +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +  and 10 CFR 54.21#c +

ASME Code Case N-481 +  and ASME Code Case N-415 +

L-11-203, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 9 +, L-11-166, Reply to Request for Additional Information for the Review of the License Renewal Application, Batch 3 (TAC No. ME4640), and License Renewal Application Amendment No. 8 +, L-11-153, Reply to Requests for Additional Information for the Review of License Renewal Application, Batch 2 and Batch 1, and License Renewal Application Amendment No. 7 +  and L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application. +

ML011200090 +, ML033100370 +, ML040620456 +, ML033370836 +, ML040890175 +, L-11-153, Reply to Requests for Additional Information for the Review of License Renewal Application, Batch 2 and Batch 1, and License Renewal Application Amendment No. 7 +  and L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application. +

Turbine Trip +  and Reactor Trip +

NRC Generic Letter 04-02 +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +

ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +, ML11234A356 +  and ML11234A356 +

L-11-203, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 9 +, L-11-166, Reply to Request for Additional Information for the Review of the License Renewal Application, Batch 3 (TAC No. ME4640), and License Renewal Application Amendment No. 8 +, L-11-153, Reply to Requests for Additional Information for the Review of License Renewal Application, Batch 2 and Batch 1, and License Renewal Application Amendment No. 7 +  and L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application. +

LRA B.2.16 +, LRA B.2.39 +  and LRA B.2.42 +

IR 05000346/2011502 +, ML033100370 +, L-11-153, Reply to Requests for Additional Information for the Review of License Renewal Application, Batch 2 and Batch 1, and License Renewal Application Amendment No. 7 +  and ML032680830 +

NRC Bulletin 03-01 +  and NRC Bulletin 79-14 +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, 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-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, 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 1.58 +, Regulatory Guide 1.54 +  and Regulatory Guide 1.46 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +  and Containment Spray +

Weld Overlay +, Hydrostatic +, Coatings +, High Energy Line Break +, Aging Management +, Stress corrosion cracking +, License Renewal +, Earthquake +, Dissimilar Metal Weld +, Power change +, Flow Induced Vibration +  and Leak-Before-Break +