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Letter, Technical Specification  and Bases Change

Boron +, Lead +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +  and 10 CFR 50.36#c2ii +

05000498  +, 05000499  +, 00498  +  and 00499  +

Turbine Trip +  and Reactor Trip +

South Texas +  and Head S +

GDC 54 +, GDC 60 +, GDC 17, Electric power systems +  and GDC 19, Control room +

ML073450383 +, ML073450383 +, ML073450383 +, ML073450383 +, ML073450383 +, ML073450383 +, ML073450383 +, ML073450383 +, ML073450383 +, ML073450383 +, ML073450383 +, ML073450383 +  and ML073450383 +

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-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)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-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)  +  and 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +

IEEE 485 +, IEEE 308 +, IEEE 485-1983 +  and IEEE-450 +

NUREG-1431 +, 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 1.97 +, Regulatory Guide 1.93 +, Regulatory Guide 1.6 +, Regulatory Guide 1.32 +  and Regulatory Guide 1.129 +

SR-4.8.1.1.2 +, SR-4.7.7.e.3 +, SR-4.6.1.2 +, SR-4.0.5 +, SR-4.8.2.1.b +, SR-4.8.2.3.b +, SR-4.8.2.1.c +, SR-4.8.2 +, SR-4.8.2.1.a +, SR-4.7.4.a +, SR-4.8.2.3.a +, SR-4.8.2.3.e +, SR-4.8.2.3.f +, SR-4.8.2.3.c +, SR-4.8.2.3.d +, SR-4.8.2.2.c +, SR-4.8.2.2.a +  and SR-4.8.2.2.b +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Residual Heat Removal +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Control Rod +  and Containment Spray +

TS-3.0.3 +, TS-3.8.3.1 +, TS-3.7.7 +, TS-3.3.3.6 +, TS-3.6.3 +, TS-3.8.1.1 +, TS-3.8.2.1 +, TS-3.7.8 +, TS-3.7.1.2 +, TS-3.3.1 +, TS-3.8.2.3 +, TS-3.0.2 +, TS-3.7.4.b +, TS-3.3.3.5 +, TS-3.7.14 +, TS-3.7.4.a +, TS-3.8.3.2 +, TS-3.8.2.2 +, TS-8.2 +  and TS-6.8.3.k +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Anticipated operational occurrence +, Large early release frequency +, Loss of Offsite Power +, Operability Determination +, Battery sizing +, Maintenance Rule Program +, Pressure Boundary Leakage +, Offsite Circuit +  and Core Exit Thermocouple +