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GENERAL EXTERNAL TECHNICAL REPORTS, INDIVIDUAL PLANT EXAM (OF EXTERNAL EVENTS)  and TEXT-SAFETY REPORT

Nitrogen +, Sodium +, Hydrogen +, Lead +  and Mercury +

10 CFR 50 Appendix R +, 10 CFR 50 +  and 10 CFR 50.54#f +

Initiating Events +  and Mitigating Systems +

Northern States Power Company +, Nierode C +, Tilly D +  and Riedel P +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +, ML20094P954 +  and ML20094P954 +

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)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, NUREG-1488, Notice of Draft NUREG 1488, Revised Livermore Seismic Hazard Estimates for 69 Nuclear Power Plant Sites East of Rocky Mountains +, NUREG/CR-0098, Forwards SEP Position Re Consideration of Inelastic Response Using NUREG/CR-0098 Ductility Factor Approach,Providing Addl Guidance Regarding Application of Ductility Methodology +, 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/CR-5088, Discusses Proposed Actions Re SECY-89-170, Fire Risk Scoping Study:Summary of Results & Proposed Staff Actions, (NUREG/CR-5088).Need for Addl Research Will Be Considered Following Final Definition of fire-related Parts +  and NUREG-1070, 07-18-84 ACRS Report on NUREG-1070, NRC Policy on Future Reactor Designs - Decisions on Severe Accident Issues +

4.16KV +  and 4kV +

AM +, TP +  and Emergency Plan +

2E-2 +, 13A-K29 +, 10A-K63A +, 10A-K63B +, 23A-K8 +, 10A-K79A +, 10A-K80A +, 5E-2 +, 5A-C +, 14A-K23A +, 14A-K25A +, 23A-K5 +, 13A-K13 +, 13A-K17 +, 2E-K12A +  and 13A-K24 +

Minnesota +  and California +

Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Main Turbine +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +  and Reactor Water Cleanup +

Hot Short +, Safe Shutdown +, High winds +, Reactor Vessel Water Level +, Fire Barrier +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Squib +, Emergency Lighting +, B.5.b +, Seismically rugged +, Scram Discharge Volume +, Loss of Offsite Power +, Earthquake +  and Fire Protection Program +