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Technical Specification, Bases Change  and Letter type:NLS

ASME Section XI +, ASME Section VI +  and ASME Section XIV +

Boron +, Iodine +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Zirconium +  and Lead +

10 CFR 50.67 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.49 +, 10 CFR 50.36#c2ii +, 10 CFR 50.36#c2 +, 10 CFR 50.36#c +, 10 CFR 36#c2ii +  and 10 CFR 50.71#e +

05000298  +  and 00298  +

Turbine Trip +  and Reactor Trip +

Nebraska Public Power District +  and Shaw J +

NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +, NLS2017033, Technical Specification Bases Changes +  and NLS2017033, Technical Specification Bases Changes +

6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-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)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +

NUREG-0562, Advises That NUREG-0562 Fuel Failure Criteria Not Approved as Basis for Licensing.Use of Criteria Should Be Discontinued to Eliminate Licensing Delays.List of Plants Applying Criteria Requested +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

NEDC-32914P +, NEDC-31892P +, NEDC-32687P +  and NEDE-24258 +

SR-3.6.4.1.2 +, SR-3.5.1.1 +, SR-3.5.1.9 +, SR-3.5.1.6 +, SR-3.6.4.1.1 +, SR-3.6.4.1.3 +, SR-3.6.4.1.4 +, SR-3.6.4 +, SR-3.2.3.1 +, SR-3.6.4.3.1 +, SR-3.5.2.1 +, SR-3.6.2.2.1 +, SR-3.2.2.1 +, SR-3.7.7.2 +, SR-3.5.2.3 +, SR-3.1.4.2 +, SR-3.1.4.1 +, SR-3.4.1.1 +, SR-3.4.9.4 +, SR-3.3.5.1.5 +, SR-3.7.7.1 +, SR-3.4.9.1 +, SR-3.6.2.3.1 +, SR-3.6.4.2.2 +, SR-3.5.2.2 +, SR-3.4.9.3 +, SR-3.6.1.9.2 +, SR-3.6.4.2.1 +, SR-3.6.2.1.1 +, SR-3.6.3.1.1 +...

Nebraska +  and Washington +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Containment Spray +, Low Pressure Coolant Injection +  and Main Turbine Bypass System +

TS-3.0.3 +, TS-3.5.1 +, TS-3.8.1 +, TS-3.3.1.1 +, TS-3.3.5.1 +, TS-3.5.2 +, TS-3.8.2 +, TS-3.2.3 +, TS-3.4.1 +, TS-3.6.4.2 +, TS-3.3.6.2 +, TS-3.6.4.3 +, TS-3.6.1.9 +, TS-3.6.2.2 +, TS-3.1.4 +, TS-3.2.2 +, TS-3.3.8.1 +, TS-3.2.1 +  and TS-5.5.10.d +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Unanalyzed Condition +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Ultimate heat sink +, Stroke time +, Anticipated operational occurrence +, Post Accident Monitoring +, Hydrostatic +, High Energy Line Break +, Abnormal operational transient +, Scram Discharge Volume +, Feedwater Controller Failure +, Loss of Offsite Power +, Fuel cladding +, Recently irradiated fuel +, Operational leakage +  and Pressure Temperature Limits Report +