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CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.54#f +, 10 CFR 50.54#q +, 10 CFR 50.59#10 +  and 10 CFR 50.71#e +

05000298  +  and 00298  +

Nebraska Public Power District +  and Horn G +

NRC Generic Letter 90-03, Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2, "Vendor Interface for Safety-Related Components" +, NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +, ML20138L031 +  and ML20138L031 +

Westinghouse +, Limitorque +  and General Electric +

NRC Bulletin 93-02 +, NRC Bulletin 95-02 +  and NRC Bulletin 85-03 +

NUMARC 87-00 +  and NUMARC 90-12 +

NUREG-1433 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

Emergency Operating Procedure +  and DVP +

Regulatory Guide 1.97 +, Regulatory Guide 1.155 +  and Regulatory Guide 1.26 +

Nebraska +  and Washington +

Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, HVAC +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Standby Liquid Control +, Core Standby Cooling System +, Safety Relief Valve +, Control Rod +  and Low Pressure Coolant Injection +

Safe Shutdown +, Reactor Vessel Water Level +, Fire Barrier +, Stroke time +, Commercial Grade Dedication +, Safe Shutdown Earthquake +, Internal Flooding +, Hydrostatic +, Probabilistic Risk Assessment +, Temporary Modification +, Emergency Lighting +, Condition Adverse to Quality +, High Energy Line Break +, Local Leak Rate Testing +, Foreign Material Exclusion +, Operability Determination +, Earthquake +, Commercial Grade +, Fire Protection Program +, Operability Assessment +  and Basic Component +