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Letter, License-Operating (New/Renewal/Amendments) DKT 50  and Safety Evaluation

Boron +, Iodine +, Cesium +, Uranium +, Sodium +  and Lead +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 30 +, 10 CFR 51 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 100.11 +, 10 CFR 30#40 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 51.22#c10 +

05000368  +  and 00368  +

Regulatory Guide 1.183 +, ML053460347 +, ML003740205 +, ML082520574 +, ML032450205 +, ML081850607 +, ML003769825 +, ML0314305050 +, ML031390664 +, ML021130826 +, 2CAN091002, Request for Additional Information Technical Specification Changes and Analyses Relating to Use of Alternative Source Term +, 2CAN081001, Request for Additional Information, Technical Specification Changes and Analyses Relating to Use of Alternative Source Term +, 2CAN061004, License Amendment Request Technical Specification Changes and Analyses Relating to Use of Alternative Source Term - Supplemental Information +, 2CAN061002, Request for Additional Information Technical Specification Changes and Analyses Relating to Use of Alternative Source Term +, 2CAN031001, License Amendment Request, Technical Specification Changes and Analyses Relating to Use of Alternative Source Term +  and 2CAN020802, License Amendment Request Replacement of Containment Sump Buffer Request for Additional Information, Arkansas Nuclear One, Unit 2 +

EC-180 +  and EC-1560 +

75 FR 37475 +  and 75 FR 44024 +

Kalyanam N +  and Plant Licensing Branch IV +

GDC 17, Electric power systems +  and GDC 19, Control room +

ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +, ML110980197 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +  and 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +

U-235 +  and Kr-85 +

ML071980041 +, 2CAN081001, Request for Additional Information, Technical Specification Changes and Analyses Relating to Use of Alternative Source Term +, 2CAN061002, Request for Additional Information Technical Specification Changes and Analyses Relating to Use of Alternative Source Term +, 2CAN031001, License Amendment Request, Technical Specification Changes and Analyses Relating to Use of Alternative Source Term +, ML032450054 +  and 2CAN061001, License Amendment Request Changes to Reflect Revision to 10 CFR 50.55a Technical Change Travelers – TSTF-479-A and TSTF-497-A +

NUREG/CR-5950 +, NUREG/CR-6604 +, NUREG/CR-2858 +, NUREG/CR-0200 +, NUREG-0917 +, NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

Regulatory Guide 1.183 +, Regulatory Guide 1.194 +, Regulatory Guide 1.23 +, Regulatory Guide 1.197 +, Regulatory Guide 1.145 +  and Regulatory Guide 1.1.8 +

Washington +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Shutdown Cooling +, Reactor Pressure Vessel +, Control Room Emergency Ventilation +, Main Steam Safety Valve +, Main Steam Line +, Control Room Envelope +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.4.6.2 +, TS-3.4.8 +, TS-1.19 +, TS-1.0 +, TS-1.18 +  and TS-6.5.12 +

Boric Acid +, Loss of Offsite Power +, Fuel cladding +, Pressure Boundary Leakage +, Power change +, Unidentified leakage +, Power Uprate +, Operational leakage +  and Control Room Habitability +