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Letter, License-Operating (New/Renewal/Amendments) DKT 50  and Safety Evaluation

ASME Section III +, ASME Section I +, ASME Section IV +  and ASME Section VII +

Boron +, Carbon +, Oxygen +, Hydrogen +, Molybdenum +  and Chromium +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 50.36 +, 10 CFR 50.63 +, 10 CFR 30 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 51 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +

05000338  +, 05000339  +, 00338  +  and 00339  +

ML081540280 +, ML081410652 +, ML092250616 +, ML050740524 +, ML090900055 +, ML080350347 +, ML073600419 +, ML051590510 +, ML082250013 +, ML091910204 +, ML091970595 +, ML092050714 +, ML0918203660 +, ML041950277 +, ML051860255 +, ML0534701720 +, ML0604603931 +, ML023090559 +, ML0534803582 +, ML050840156 +, ML072681096 +  and ML091910205 +

V Sreenivas +  and Plant Licensing Branch II +

GDC 15 +, GDC 14 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +, ML092250616 +...

6.365741e-4 d (0.0153 hours, 9.093915e-5 weeks, 2.09275e-5 months)  +, 5.787037e-4 d (0.0139 hours, 8.267196e-5 weeks, 1.9025e-5 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

ML050740524 +, ML090900055 +, ML091910204 +, ML092050714 +, ML051860255 +, ML091600347 +, ML041950195 +  and ML053480051 +

NUREG-1766, Issuance of NUREG-1766, Safety Evaluation Report Related to the License Renewal of North Anna Power Station, Units 1 and 2, and Surry Power Station, Units 1 and 2 +, NUREG-1802 +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-1344, Advises That Util 890710 Response to Generic Ltr 89-08 Re Pipe Wall Thinning Induced by Erosion &/Or Corrosion Acceptable,Based on Confirmation That Erosion/Corrosion Program Meets or Exceeds App a to NUREG-1344 Requirements +

AOP +, TOP +  and Emergency Operating Procedure +

Regulatory Guide 1.183 +, Regulatory Guide 1.155 +, Regulatory Guide 1.105 +  and Regulatory Guide 1.99 +

RIS 2006-17, NRC Staff Position on the Requirements of 10 CFR 50.36, Technical Specification, with Respect to Limiting Safety System Settings (LSSS) During Periodic Testing and Calibration of Instrument Channels +  and RIS 2002-03, Guidance for Submitting Measurement Uncertainty Recapture Power Uprate Applications +

Pennsylvania +, Maryland +, Washington +, Virginia +  and New Jersey +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Transformer +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Extraction steam +

TS-1.1 +, TS-1.3 +  and TS-3.11.1 +

Dominion +  and Heacock D +

Safe Shutdown +, Shutdown Margin +, Ultimate heat sink +, Anticipated operational occurrence +, Hydrostatic +, Coatings +, Reserve Station Service Transformer +, Operator Manual Action +, High Energy Line Break +, Aging Management +, Abnormal operational transient +, Feedwater Heater +, Stress corrosion cracking +, Loss of Offsite Power +, B.5.b Mitigating Strategies +, License Renewal +, Earthquake +, Fuel cladding +, Fire Protection Program +, Power change +, Flow Induced Vibration +, Power Uprate +, Measurement Uncertainty Recapture +, Control Room Habitability +  and Leak Before Break +