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

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.59 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50.90 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 51.22 +, 10 CFR 50.36#c2ii +, 10 CFR 50.36#c +, 10 CFR 50.65#a4 +  and 10 CFR 50.92#c +

05000317  +, 05000318  +, 00317  +  and 00318  +

NUREG-1432 Volume 1, Rev. 5, Standard Technical Specifications Combustion Engineering Plants: Specifications +, ML21258A424 +, ML22165A105 +, ML24016A070 +, NUREG-0212, Forwards Revision 3 to Draft NUREG-0212, C-E Sts +  and ML010430247 +

Reactor Trip +  and Turbine Trip +

Para W +  and Constellation +

GDC 15 +, GDC 10 +, GDC 14 +  and GDC 21 +

ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +, ML25352A315 +  and ML25352A315 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

NUREG-1432 +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG/CR-5382 +, 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-0212, Safety Evaluation Supporting Amend 99 to License DPR-20 +  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 +

EPID:L-2021-LLA-0200 +, TAC:M92479 +, TAC:M92480 +  and EPID:L-2023-LLA-0032 +

SR-3.3.1.1 +, SR-3.3.1.5 +, SR-3.3.1.4 +, SR-3.3.1.6 +, SR-3.3.1.7 +  and SR-3.3.1.9 +

Automatic Scram +  and Manual Scram +

Tennessee +, Maryland +, Washington +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Main Steam Safety Valve +  and Decay Heat Removal +

TS-3.3.3 +, TS-3.4.16 +, TS-3.3.2 +, TS-3.1.7 +  and TS-3.3.1 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Shutdown Margin +, Probabilistic Risk Assessment +, Surveillance Frequency Control Program +, License Renewal +, Overspeed +  and High Negative Rate Trip +