Browse wiki

INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

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

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

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

05000412  +  and 00412  +

Turbine Trip +  and Reactor Trip +

Office of Nuclear Reactor Regulation +  and Houston R +

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 +

ML20132C310 +, ML20132C310 +, ML20132C310 +, ML20132C310 +, ML20132C310 +, ML20132C310 +, ML20132C310 +, ML20132C310 +, ML20132C310 +, ML20132C310 +, ML20132C310 +  and ML20132C310 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 3.587963e-4 d (0.00861 hours, 5.125661e-5 weeks, 1.17955e-5 months)  +

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-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-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +

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 +

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

Novak T +  and Office of Nuclear Reactor Regulation +

Boric Acid +, Shutdown Margin +, Anticipated operational occurrence +, Post Accident Monitoring +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Loss of condenser vacuum +  and Water hammer +