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

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

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 51 +, 10 CFR 50.67#b2 +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +

05000389  +  and 00389  +

ML053460347 +, ML011210348 +, ML012190402 +, ML082060400 +, ML082410327 +, ML082060465 +, L-2008-060, Proposed License Amendment, Request for Additional Information Response, Alternative Source Term Amendment +  and L-2004-203, Request for Additional Information Alternate Source Term License Amendment +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

73 FR 33460 +  and 72 FR 49579 +

Mozafari B +  and NRC/NRR/ADRO/DORL/LPLII-2 +

ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +, ML082060400 +...

3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 7.523148e-4 d (0.0181 hours, 1.074735e-4 weeks, 2.47325e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 0.0122 d (0.293 hours, 0.00174 weeks, 4.006665e-4 months)  +, 3.703704e-4 d (0.00889 hours, 5.291005e-5 weeks, 1.2176e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

Kr-85 +  and I-131 +

L-2008-046, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report +, L-2004-203, Request for Additional Information Alternate Source Term License Amendment +  and L-2003-115, Comment (14) Submitted by Florida Power & Light Co., J. A. Stall, on Proposed Rules PR-170 & 171 Re Revision of Fee Schedules; Fee Recovery for Fy 2003 +

NUREG-1432 +, NUREG/CR-5950 +, NUREG/CR-6604 +, NUREG/CR-2858 +, NUREG-0917 +, NUREG/CR-4102 +, 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-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 +, NUREG-0409, Discusses NUREG-0409 Iodine Behavior in PWR Cooling Sys Following Postulated Steam Generator Tube Rupture Accident +  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 +

Natasha Greene +, John Parillo +, Chakrapani Basavaraju +  and Brian Lee +

Regulatory Guide 1.183 +, Regulatory Guide 1.196 +, Regulatory Guide 1.1 +, Regulatory Guide 1.194 +, Regulatory Guide 1.52 +, Regulatory Guide 1.23 +  and Regulatory Guide 1.145 +

SR-4.7.8 +, SR-4.7.8.1 +, SR-4.6.6.1 +, SR-4.3.3.2 +  and SR-4.6.6.1.b +

2L-7B +  and 2L-7A +

Pennsylvania +, Washington +, Virginia +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, Shield Building +, Main Steam Safety Valve +, Emergency Core Cooling System +, Main Steam Line +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.6.1.1 +, TS-3.4.8 +, TS-6.8.4.h +, TS-6.8.4.k +, TS-6.8.4.1 +  and TS-3.7.1.4 +

NextEra Energy +  and Stall J +

Boric Acid +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, GOTHIC +, Operational leakage +, Loss of condenser vacuum +  and Control Room Habitability +