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

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

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 51 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 100.11 +, 10 CFR 50.49#b +, 10 CFR 50.67#b2 +, 10 CFR 50.36#a +, 10 CFR 50.36#c3 +, 10 CFR 50.36#c2ii +, 10 CFR 50.36#c2 +, 10 CFR 50.36#c5 +, 10 CFR 50.36#c2i +, 10 CFR 50.36#c +, 10 CFR 50.36#60 +, 10 CFR 50.36#a1 +, 10 CFR 50.36#b +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +, 10 CFR 50.46#b4 +  and 10 CFR 50.71#e +

05000333  +  and 00333  +

Regulatory Guide 1.183 +, Regulatory Guide 1.196 +, Regulatory Guide 1.174 +, ML041040063 +, ML053460347 +, ML100351425 +, ML101750625 +, ML021720780 +, ML073230597 +, ML12045A149 +, ML011210348 +, ML012190402 +, ML063480542 +, ML052570461 +, ML081230439 +, ML062210214 +, ML18031A041 +, ML011230531 +, ML003683718 +, ML071580314 +, ML9903110303 +, ML17213A187 +, ML17055A387 +, ML022350228 +, ML18078A061 +, ML18058A602 +, JAFP-20-0008, Response to Request for Additional Information Associated with the License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences +, ML050940234 +, ML070110240 +, ML070110231 +...

58 FR 39132 +  and 84 FR 63899 +

Samson Lee +  and Plant Licensing Branch I +

GDC 35 +  and GDC 19, Control room +

NRC Generic Letter 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal +  and NRC Generic Letter 99-01 +

ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +, ML20140A070 +...

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0 d (0 hours, 0 weeks, 0 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 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)  +

ML073650019 +, JAFP-20-0008, Response to Request for Additional Information Associated with the License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences +, JAFP-19-0084, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI +, JAFP-19-0077, License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences +  and ML20090E279 +

NUREG/CR-5950 +, NUREG/CR-6604 +, NUREG/CR-2858 +, NUREG/CR-5966 +, NUREG/CR-0009 +, 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 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  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 +

Regulatory Guide 1.183 +, Regulatory Guide 1.196 +, Regulatory Guide 1.174 +, Regulatory Guide 1.194 +, Regulatory Guide 1.52 +  and Regulatory Guide 1.23 +

NEDC-31858P +  and NEDE-33005P +

SR-3.6.4.1.2 +, SR-3.6.1.3 +, SR-3.6.4.1.1 +, SR-3.6.4.1.3 +, SR-3.0.3 +, SR-3.6.4.1.4 +, SR-3.6.1.3.9 +, SR-3.3.6.1.1 +, SR-3.6.1.3.8 +, SR-3.0.2 +, SR-3.6.1.3.7 +, SR-3.3.6.1.3 +, SR-3.1.7.1 +, SR-3.3.6.1.7 +  and SR-3.3.6.1.4 +

H21C-106 +, 10th-percent +  and 70DMPR-105 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Emergency Core Cooling System +, Main Steam Line +, Control Room Emergency Ventilation Air Supply +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.6.4.1 +, TS-3.3.6.1 +, TS-3.1.7 +, TS-3.6.4.3 +, TS-5.5.8 +, TS-5.5.11 +, TS-5.5.2 +, TS-5.5.6 +, TS-3.6.1.8 +, TS-5.5.8.a +, TS-5.5.8.c +  and TS-5.5.6.b +

Exelon +  and Bryan Hanson +

Safe Shutdown +, Boric Acid +, Reactor Vessel Water Level +, Mission time +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Squib +, Fukushima Dai-Ichi +, Surveillance Frequency Control Program +, Large early release frequency +, Loss of Offsite Power +, Exemption Request +, Earthquake +, GOTHIC +, Control Room Habitability +  and Pre-application +