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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

Boron +, Cobalt +, Copper +, Oxygen +, Sodium +, Hydrogen +, Lead +, Fluorine +, Sulfur +  and Manganese +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.66 +, 10 CFR 50.71 +, 10 CFR 50.90 +, 10 CFR 72.48 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 59.59 +, 10 CFR 50.54#p +, 10 CFR 50.34#b +, 10 CFR 5#0 +  and 10 CFR 50.59#a +

Emergency Preparedness +, Initiating Events +  and Mitigating Systems +

SECY-96-024 +, SECY-95-300 +, SECY-86-10 +, SECY-92-314 +, NRC 50 +, NRC 263 +  and NRC 635 +

05000255  +, 05000266  +, 05000301  +, 07200005  +, 07200007  +, 07201007  +  and 00354  +

52 FR 3788 +  and 60 FR 65456 +

Taylor J +  and NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 80-51, On-Site Storage of Low-Level Waste +, NRC Generic Letter 80-29, Modifications to Boiling Water Reactor Control Rod Drive Systems +, NRC Generic Letter 80-09, Low Level Radioactive Waste Disposal +, NRC Generic Letter 84-07, Procedural Guidance for Pipe Replacement at BWRs +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 86-02, Technical Resolution of Generic Issue B-19 - Thermal Hydraulic Stability +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-07, Modified Enforcement Policy Relating to 10 CFR 50.49, "Environmental Qualification of Electrical Equipment Important to Safety" +, NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +, NRC Generic Letter 90-02, Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications +, NRC Generic Letter 91-08, Removal of Component Lists from Technical Specifications +, NRC Generic Letter 93-08, Relocation of Technical Specification Tables of Instrument Response Time Limits +, NRC Generic Letter 95-08, 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval +, NRC Generic Letter 95-02, Use of Numarc/epri Report TR-102348, "Guideline on Licensing Digital Upgrades," in Determining the Acceptability of Performing Analog-to-Digital Replacements under 10 CFR 50.59 +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 1981-38, Storage of Low-Level Radioactive Wastes at Power Reactor Sites +

ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +, ML20128Q143 +  and ML20128Q143 +

General Electric +  and Westinghouse +

NRC 50 +, NRC 263 +  and NRC 635 +

Information Notice 83-64 +, Information Notice 83-23 +, Information Notice 96-17 +, Information Notice 91-63 +, Information Notice 89-81 +, Information Notice 87-04 +, Information Notice 95-54 +  and Information Notice 95-46 +

NUREG-0798, Advises That NRC Review of Sys Leakage Reduction Test Results Cannot Be Completed Until Final Test Procedures & Acceptance Criteria Upon Which Sys Test Results Based Submitted & Reviewed +, NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +, 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 +  and NUREG/BR-195 +

SECY-96-024 +, SECY-95-300 +, SECY-86-10 +  and SECY-92-314 +

Palisades +, Point Beach +  and 07201007 +

Washington +, Arkansas +, Vermont +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Rod Worth Minimizer +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.0.3 +  and TS-3.5.B +

The Chairman +  and NRC COMMISSION (OCM) +

Safe Shutdown +, Boric Acid +, Reactor Vessel Water Level +, Ultimate heat sink +, Anticipated operational occurrence +, Hydrostatic +, Probabilistic Risk Assessment +, Temporary Modification +, High Energy Line Break +, Feedwater Heater +, Loss of Offsite Power +, Operability Determination +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Backfit +, Operability Assessment +, Manual Operator Action +  and Water hammer +