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Letter  and Audit Report

ANSI B31.1 +, ANSI 56.8-1981 +  and ANSI N45.1-1972 +

AR 02062987 +, AR 01822156 +, AR 02354397 +, AR 01823513 +, AR 01868962 +, AR 01809387 +, AR 02300737 +, AR 01910016 +, AR 01817471 +, AR 01806638 +, AR 02243692 +, AR 02300094 +, AR 02307069 +, AR 01818330 +, AR 01856672 +, AR 01874317 +, AR 01909374 +, AR 02024538 +, AR 02248993 +, AR 01566581 +, AR 01909411 +, AR 02275269 +, AR 01850417 +, AR 01847393 +, AR 01869129 +, AR 01830379 +, AR 01870699 +, AR 02336986 +, AR 01847131 +, AR 02352039 +...

ASME Section XI +  and ASME Section III +

Boron +, Iron +, Nickel +, Copper +, Carbon +, Sodium +, Hydrogen +, Molybdenum +, Lead +, Lithium +, Aluminum +, Sulfur +  and Tin +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 54 +, 10 CFR 50.12 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.61 +, 10 CFR 50.90 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 54.4#a +, 10 CFR 54.4#a1 +, 10 CFR 54.4#b +, 10 CFR 54.3#a +, 10 CFR 50.54#wi +, 10 CFR 54.21#d +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#a1 +, 10 CFR 54.21#c2 +...

ASME Code Case N-770-1 +, ASME Code Case N-716-1 +, ASME Code Case N-588 +, ASME Code Case N-514 +, ASME Code Case N-845 +  and ASME Code Case N-853 +

L-20 +  and RA-19-0253, Proposed License Amendment Request to Revise the Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of the Containment Building +

S.5(a) +  and S.7(n) +

05000269  +, 05000270  +, 05000287  +, 00269  +, 00270  +  and 00287  +

IR 05000269/2016002 +, ML14135A383 +, ML14135A384 +, ML14135A385 +, ML16144A789 +, ML003708443 +, RIS 2015-01, Qualification Requirements for Bolt and Stud Non-Destructive Examinations +, ML17331A086 +, ML16068A245 +, ML16068A246 +, ML14041A093 +, ML120580196 +, ML003670061 +, ML130580060 +, ML011710267 +, ML11164A257 +, ML012000058 +, RA-18-0138, Refuel 29 (03R29) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval +, ML15090A665 +, ML16274A402 +, ML19081A001 +, RA-19-0253, Proposed License Amendment Request to Revise the Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of the Containment Building +, ML16274A389 +, ML20006D152 +, RA-19-0394, Refuel 29 (O2R29) Inservice Inspection (ISI) and Steam Generator Inservice Inspection (SG-ISI) Reports, Fifth 10-Year ISI Interval +, ML091310038 +, ML20203J930 +, ML20315A536 +, ML20335A001 +, ML20217L203 +...

MRP-146 +, MRP-227 +, MRP-175 +, MRP-192 +, MRP-058 +, MRP-189 +, MRP-277 +, MRP-149 +, MRP-148 +  and MRP-384 +

Angela Wu +  and NRC/NRR/DNRL/NLRP +

ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +, ML22045A053 +...

IR 05000269/2016002 +, IR 05000625/200720 +  and IR 05000269/2026002 +

ML17331A086 +, ML21158A195 +, ML15224A084 +  and ML15238A097 +

Westinghouse +  and Limitorque +

NCR 02242165 +, NCR 02305906 +, NCR 02328243 +, NCR 02228068 +, NCR 02226162 +  and NCR 01981365 +

NEI 17-01 +, NEI 14-12 +  and 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 . +

Information Notice 07-21 +, Information Notice 2019-08, Flow-Accelerated Corrosion Events +, Information Notice 2007-21, Pipe Wear Due to Interaction of Flow-Induced Vibration and Reflective Metal Insulation +  and Information Notice 11-20 +

NUREG/CR-6260 +, NUREG/CR-4513 +, NUREG-1723 +, NUREG/CR-6177 +, NUREG-1743, Review of Revisions to Regulatory Commitments Documented in NUREG-1743, Safety Evaluation Report Related to License Renewal of Arkansas Nuclear One, Unit 1 +, NUREG-1509 +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-2191, Draft NUREG-2191 Vol 2 GALL-SLR Rev1 -12-14-24 +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

Bryce Lehman +, George Thomas +, Brian Allik +, Roger Kalikian +, Andrew Prinaris +, Steve Jones +, Nageswara Karipineni +, Gordon Curran +, Andrew Johnson +, Ali Rezai +, Jay Collins +, Juan Lopez +, Jennifer Whitman +, David Dijamco +, Thinh Dinh +, Naeem Iqbal +, James Gavula +, On Yee +, Seung Min +, Carolyn Fairbanks +, Bart Fu +, Ata Istar +, George Wang +, Zuhan Xi +, Paul Klein +, Bill Rogers +, Duc Nguyen +, Brian Lee +, Matthew Yoder +, Matthew Mcconnell +...

115KV +, 4.16kV +  and 345kV +

ML22045A053 +  and ML22045A053 +

EPID:L-2021-SLR-0000 +  and TAC:MF0763 +

Regulatory Guide 1.147 +, Regulatory Guide 1.190 +, Regulatory Guide 1.65 +  and Regulatory Guide 1.99 +

RIS 2008-30, Fatigue Analysis of Nuclear Power Plant Components +, RIS 2015-01, Qualification Requirements for Bolt and Stud Non-Destructive Examinations +, RIS 2011-14, Metal Fatigue Analysis Performed by Computer Software +, RIS 2015-10, Applicability of ASME Code Case N-770-1 as Conditioned in 10 CFR 50.55a, Codes and Standards, to Branch Connection Butt Welds +, RIS 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components +  and RIS 2018-06, Clarification of the Requirements for Reactor Vessel Upper Head Bare Metal Visual Examinations +

3NI-5 +, 3SF-97 +, 3B-9 +, 1P-A +, 1CS-46 +, 1BS-4 +, 3LWD-1 +, 1CS-IV-0097 +, 1RC-261-Elbo +, 3FDW-355 +, 1BS-17 +, 3HPSW-37 +, 3HPS-112 +, 0HPS-450 +, 1HPSW-688 +, 3RBC-AH0022D +, 318A-SR-02 +  and K0ELK-TF-CX +

Ohio +, Maryland +  and South Carolina +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Decay Heat Removal +, Main Condenser +, Control Rod +  and Main Steam +

Duke Energy +  and Snider S +

Boric Acid +, High winds +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Fire Barrier +, Weld Overlay +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, VT-2 +, Incorporated by reference +, Finite Element Analysis +, High Energy Line Break +, Aging Management +, Open Phase Condition +, Flow Accelerated Corrosion +, Feedwater Heater +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, Exemption Request +, Subsequent License Renewal +, Subsequent License Renewal Application +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, EVT-1 +, Pressure boundary leak +, Through Wall Leak +...

WO 02043113 +, WO 20248932 +, WO 02135161#48 +, WO 20353930 +, WO 98035368 +, WO 01930591 +, WO 20091459 +, WO 20226325 +, WO 20226325#01 +, WO 01875343#01 +  and WO 02078219 +