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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

ASME Section XI +, ASME Section III +  and ASME Section II +

Boron +, Nitrogen +, Hydrogen +, Zirconium +  and Lead +

10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50 Appendix G +, 10 CFR 50.55a#g4 +  and 10 CFR 50.44#c3iii +

05000000  +, 05000424  +  and 05000425  +

Reactor Trip +  and Turbine Trip +

Houston R +  and Office of Nuclear Reactor Regulation +

GDC 20 +, GDC 44 +, GDC 34 +, GDC 15 +, GDC 10 +, GDC 56 +, GDC 35 +, GDC 31 +, GDC 37 +, GDC 27 +, GDC 36 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +, GDC 3, Fire protection +, GDC 26, Reactivity control system redundancy and capability +  and GDC 5, Sharing of structures, systems, and components +

ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +, ML20136F255 +  and ML20136F255 +

2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +, 1.736111e-4 d (0.00417 hours, 2.480159e-5 weeks, 5.7075e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +  and 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +

Target Rock +  and Westinghouse +

NUREG-0390, Forwards Evaluation of Suppl 1 to Topical Rept TR Ur 85-225, ASEA-ATOM BWR Control Rod Blades for Us Bwrs. Rept Acceptable for Referencing in License Application +, NUREG-1024, Forwards Update of 861121 CRGR Package Re Proposed Generic Ltr on short-term Tech Spec Improvements.Comments from AEOD, IE & Ofc of General Counsel Incorporated in Update or Resolved.Res Concurred W/O Specific Comment +, 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-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.1 +, Regulatory Guide 1.47 +, Regulatory Guide 1.26 +, Regulatory Guide 1.29 +, Regulatory Guide 1.68 +, Regulatory Guide 1.79 +, Regulatory Guide 1.11 +  and Regulatory Guide 1.46 +

05000000 +  and Vogtle +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, Safety Parameter Display System +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +

Novak T +  and Office of Nuclear Reactor Regulation +

Boric Acid +, Shutdown Margin +, Anticipated operational occurrence +, Feedwater Heater +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Earthquake +, Fuel cladding +, Loss of condenser vacuum +  and Water hammer +

WCAP-8963-P-A +, WCAP-7769 +, WCAP-9226 +, WCAP-9230 +  and WCAP-9220 +

WCAP-8963-P-A +, WCAP-7769 +, WCAP-9226 +, WCAP-9230 +  and WCAP-9220 +