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Letter, Technical Specification, Amendment  and License-Application for Facility Operating License (Amend/Renewal) DKT 50

ASME Section XI +  and ASME Section III +

Boron +, Iodine +, Cesium +, Rubidium +, Krypton +, Carbon +, Sodium +, Hydrogen +, Xenon +, Lead +, Tin +, Tellurium +  and Cerium +

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 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50.90 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 51.22 +, 10 CFR 100.11 +, 10 CFR 100 Appendix A +, 10 CFR 0 +, 10 CFR 50.55a +, 10 CFR 50.34#b +, 10 CFR 50.36#c2ii +  and 10 CFR 50.44#c1 +

RS-08-132, Calculation L-003068, Re-analysis of Loss of Coolant Accident (LOCA) Using Alternative Source Terms, Revision 1, Attachment 7 +, L 60555 +, L-003067 +, L-003064 +, L-003063 +  and L-003068 +

05000373  +, 05000374  +, 00373  +  and 00374  +

Simpson P +  and Exelon +

GDC 41 +, GDC 15 +, GDC 10 +, GDC 14 +, GDC 19, Control room +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 2003-01, Control Room Habitability +  and NRC Generic Letter 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal +

ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +, ML083100149 +  and ML083100149 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-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)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 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)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

Co-60 +, Kr-85 +  and Iodine-131 +

L 60555 +, L-003067 +, L-003064 +, L-003063 +  and L-003068 +

NUMARC 93-01 +  and NUMARC 91-06 +

NUREG/CR-5950 +, NUREG/CR-6189 +, NUREG/CR-5966 +, NUREG/CR-61189 +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, 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 1.97 +, Regulatory Guide 1.25 +, Regulatory Guide 1.196 +, Regulatory Guide 1.194 +, Regulatory Guide 1.52 +, Regulatory Guide 1.23 +, Regulatory Guide 1.29 +, Regulatory Guide 1.197 +  and Regulatory Guide 1.145 +

RIS 2006-04, Draft RAI on Meteorology for Full-Scope AST Application +  and RIS 2001-19, Deficiencies in the Documentation of Design Basis Radiological Analyses Submitted in Conjunction with License Amendment Requests +

NEDO-32977 +, NEDC-31858P +, NEDE-2401 +  and NEDC-32988 +

SR-3.6.4.1.2 +, SR-3.7.4.4 +, SR-3.6.1.3 +, SR-3.7.5.2 +, SR-3.6.4.1.1 +, SR-3.6.4.1.3 +, SR-3.6.4.1.5 +, SR-3.0.3 +, SR-3.6.4.1.4 +, SR-3.6.4.3.2 +, SR-3.6.1.3.9 +, SR-3.7.5.1 +, SR-3.6.4 +, SR-3.3.6.1.1 +, SR-3.6.4.3.1 +, SR-3.6.1.3.8 +, SR-3.6.1.3.1 +, SR-3.7.4.1 +, SR-3.6.1.1.1 +, SR-3.1.7.2 +, SR-3.6.1.3.6 +, SR-3.6.1.3.7 +, SR-3.1.7.3 +, SR-3.3.7.1.4 +, SR-3.3.6.1.2 +, SR-3.6.4.2.2 +, SR-3.3.6.2.4 +, SR-3.3 +, SR-3.1.7.1 +, SR-3.9.6.1 +...

Trojan +  and LaSalle +

Washington +  and Illinois +

Steam Generator +, Reactor Coolant System +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.6.4.1 +, TS-3.0.3 +, TS-3.7.4 +, TS-3.3.1.1 +, TS-3.3.5.1 +, TS-3.3.6.1 +, TS-3.6.1.3 +, TS-3.7.5 +, TS-1.1 +, TS-3.1.7 +, TS-3.1.3 +, TS-3.7.8 +, TS-3.6.4.2 +, TS-3.3.6.2 +, TS-3.6.4.3 +, TS-3.9.7 +, TS-3.3.3.1 +, TS-3.0 +, TS-5.5.8 +, TS-3.1.1 +, TS-3.6.3.2 +, TS-5.5.2 +, TS-5.6.5 +, TS-5.5.15 +, TS-3.3.7.1 +, TS-5.5.13 +, TS-3.9.6 +, TS-5.5.8.a +, TS-5.5.8.b +...

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Mission time +, Stroke time +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Squib +, Seismically rugged +, Scram Discharge Volume +, Loss of Offsite Power +, Integrated leak rate test +, Earthquake +, Maintenance Rule Program +, Deep Dose Equivalent +, Fuel cladding +, Recently irradiated fuel +, Failure to Scram +, Potassium iodide +, Control Room Habitability +  and Leak-Before-Break +