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ANSI 18.1-1999 +, ANSI Z-88.2 +, ANSI/ANS 2.8-1992 +, ANSI N13.2-1969 +, ANSI N13.27-1981 +, ANSI N13.5-1972 +, ANSI 42.3-1969 +, ANSI 13.2-1969 +, ANSI/ANS-3.1-1993 +  and ANSI/ANS-3.5-1998 +

ASME Section III +  and ASME Section XI +

Federal Energy Regulatory Commission +, Federal Emergency Management Agency +, Occupational Safety and Health Administration +, Federal Aviation Administration +, National Institute for Occupational Safety and Health +  and National Oceanographic and Atmospheric Administration +

Boron +, Iodine +, Uranium +, Germanium +, Carbon +, Hydrogen +, Chloride +  and Tungsten +

10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.59 +, 10 CFR 52 +, 10 CFR 50.2 +, 10 CFR 2.390 +, 10 CFR 50 Appendix I +, 10 CFR 50 Appendix O +, 10 CFR 52 Appendix D, Appendix D to Part 52-Design Certification Rule for the Ap1000 Design +, 10 CFR 55.25 +, 10 CFR 73.54 +, 10 CFR 20.401 +, 10 CFR 20.202#a +, 10 CFR 50.55a +, 10 CFR 50.71#e +  and 10 CFR 52.79#a31 +

05200014  +  and 05200015  +

ML091490684 +, ML083230868 +, ML093220164 +, ML090910554 +, ML080910149 +, ML100151002 +  and ML090290406 +

Drawing 1.7-1 +  and Drawing 1.8-201 +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

73 FR 7766 +, 74 FR 39349 +  and 73 FR 32750 +

Tennessee Valley Authority +  and Arent G +

ML110040468 +, ML110040468 +, ML110040468 +, ML110040468 +, ML110040468 +, ML110040468 +, ML110040468 +, ML110040468 +, ML110040468 +  and ML110040468 +

IEEE 279 +, IEEE 603 +  and IEEE-450 +

NEI 03-12 +, NEI 97-06, Steam Generator Conditioning Monitoring Report +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

NUREG-1736 +, NUREG-0711 +, NUREG-01512 +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +, NUREG-0041, Request Addl Info Re Requested Clarifications/Exceptions to NUREG-0041,respiratory Protection Program.Nrc Comments Encl +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

RAP +, RT +, CP +, ESP +, Emergency Operating Procedure +, Emergency Plan +  and EP-ITAAC +

Regulatory Guide 1.177 +, Regulatory Guide 1.97 +, Regulatory Guide 1.189 +, Regulatory Guide 1.196 +, Regulatory Guide 1.180 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.163 +, Regulatory Guide 1.75 +, Regulatory Guide 1.78 +, Regulatory Guide 1.205 +, Regulatory Guide 1.147 +, Regulatory Guide 1.194 +, Regulatory Guide 1.45 +, Regulatory Guide 1.47 +, Regulatory Guide 1.76 +, Regulatory Guide 1.195 +, Regulatory Guide 1.201 +, Regulatory Guide 1.33 +, Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.187 +, Regulatory Guide 1.160 +, Regulatory Guide 1.182 +, Regulatory Guide 1.84 +, Regulatory Guide 1.7 +, Regulatory Guide 1.82 +, Regulatory Guide 1.186 +, Regulatory Guide 1.181 +, Regulatory Guide 1.16 +...

1B-1 +, 1A-1 +, N323A-1997 +, 1AA-3 +, 07-80-108 +, 1AA-2 +, 1AA-1 +, 1AA-4 +, 1AA-6 +, 1AA-10 +, 1AA-11 +, 1AA-13 +, 1AA-14 +, 1AA-5 +, 1AA-15 +, 1AA-8 +, 1AA-12 +, 1AA-16 +, 15A-201 +, 15A-202 +, 12AA-201 +, 07-80-094 +, 1AA-7 +, 1AA-9 +, 1AA-17 +, 1AA-18 +, 1AA-19 +, 1AA-20 +, 1AA-21 +...

Tennessee +, Alabama +, Virginia +  and South Carolina +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Emergency Response Data System +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Shield Building +, Fuel Pool Cooling and Cleanup +, Standby Liquid Control +, Circulating Water System +, Emergency Core Cooling System +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Turbine Gland Sealing System +

TS-3.5.1 +, TS-3.8.1 +, TS-3.3.3 +, TS-3.8.5 +, TS-3.4.9 +, TS-3.7.10 +, TS-3.7.5 +, TS-3.4.3 +, TS-3.7.11 +, TS-3.7.6 +, TS-3.9.7 +, TS-3.4.7 +, TS-3.7.12 +, TS-5.5.8 +, TS-3.2.2 +, TS-3.9.4 +, TS-3.2.5 +, TS-3.6.2 +, TS-3.2.4 +, TS-3.2.1 +, TS-3.1.8 +, TS-5.4.1 +, TS-3.9.6 +, TS-5.3.1 +, TS-3.4.18 +  and TS-5.4.2.5 +

Document Control Desk +  and Office of New Reactors +

Safe Shutdown +, Boric Acid +, Fitness for Duty +, Health Physics Network +, High winds +, High Radiation Area +, Ultimate heat sink +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Fire Barrier +, Tornado Missile +, Safe Shutdown Earthquake +, Hydrostatic +, Enforcement Discretion +, Probabilistic Risk Assessment +, Coatings +, Operating Basis Earthquake +, Cyber Security +, Incorporated by reference +, Flow Accelerated Corrosion +, Shift Technical Advisor +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Hemyc +, Earthquake +, Maintenance Rule Program +, Deep Dose Equivalent +, Chernobyl +, Turbine Missile +...

WCAP-15800 +  and WCAP-15799 +

WCAP-15800 +  and WCAP-15799 +