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SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT

ANSI B31.1 +  and ANSl/ANS 3.5-1985 +

Boron +, Iodine +, Iron +, Nickel +, Copper +, Oxygen +, Hydrogen +, Zirconium +  and Mercury +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +  and 10 CFR 51.21#51 +

SECY-97-042 +, L 34 +  and L 377 +

05000263  +  and 00263  +

Reactor Trip +  and Turbine Trip +

63 FR 46489 +, 63 FR 9606 +  and 63 FR 3929 +

SIL 380 +, SIL 480 +  and SIL 377 +

NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +, ML20153F867 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 2.893519e-4 d (0.00694 hours, 4.133598e-5 weeks, 9.5125e-6 months)  +, 3.125e-4 d (0.0075 hours, 4.464286e-5 weeks, 1.02735e-5 months)  +, 2.662037e-4 d (0.00639 hours, 3.80291e-5 weeks, 8.7515e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +, 5.439815e-4 d (0.0131 hours, 7.771164e-5 weeks, 1.78835e-5 months)  +, 0.00194 d (0.0467 hours, 2.777778e-4 weeks, 6.3924e-5 months)  +, 0.0847 d (2.033 hours, 0.0121 weeks, 0.00278 months)  +, 0.00961 d (0.231 hours, 0.00137 weeks, 3.15815e-4 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

IEEE 323 +, IEEE 323-1974 +  and IEEE 323-1971 +

L 377 +  and L 34 +

ML20116D816 +, IR 05000263/1998009 +, IR 05000263/1997008 +, ML20202H675 +, ML20236P424 +, ML20217Q440 +, 05000263/LER-1998-001, Forwards LER 98-001-00 Re Containment Isolation Valve Leakage Which Exceeded Ts.Commitment Made by Util,Listed +, ML20216H372 +, ML20216C131 +  and ML20217D846 +

General Electric +  and Target Rock +

NUREG/CR-4772 +, NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +, NUREG/CR-5055, Informs of 970422 Telcon Re Plant,Unit 1 & 2 Applicability of NUREG/CR-5055, Atmospheric Diffusion for Control Room Habitability Assessments. Ltrs from Pnl & 0823 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-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

24V +, 115kV +  and 345kV +

TAC:M96238 +, TAC:M95087 +, TAC:M97781 +  and TAC:M96256 +

Regulatory Guide 1.97 +, Regulatory Guide 1.49 +, Regulatory Guide 1.7 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.145 +

NEDC-31858P +, NEDC-31336 +, NEDC-32514P +, NEDC-32424P +, NEDO-32205 +, NEDC-32523P +, NEDO-30832 +, NEDO-22155 +, NEDE-23785 +, NEDC-32546P +, NEDC-24387 +, NEDO-42205 +  and NEDC-2424P +

44aA-3 +  and 7E-8Near +

Minnesota +, Washington +  and Maine +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Stator Cooling Water +, Residual Heat Removal Service Water +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Main Condenser +, Control Rod +...

TS-2.4 +, TS-3.5.C +, TS-3.1 +, TS-2.2 +, TS-3.5.A +, TS-2.3 +, TS-3.2 +, TS-1.0 +  and TS-2.3.A +

Safe Shutdown +, Shutdown Margin +, Ultimate heat sink +, Tornado Missile +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, High Energy Line Break +, Abnormal operational transient +, Seismically rugged +, Feedwater Heater +, Large early release frequency +, MELLLA +, Loss of Offsite Power +, Earthquake +, Maintenance Rule Program +, Turbine Missile +, Fuel cladding +, Flow Induced Vibration +, Coast down +, Power Uprate +, Overspeed trip +, Overspeed +, Simmer margin +, Subsequent actuation +, Loss of condenser vacuum +  and Control Room Habitability +

Cooling Tower +  and Mississippi River +