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

ASME Section XI +  and ASME Section III +

Boron +, Iodine +, Uranium +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Lead +  and Lithium +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 51 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 51.21 +, 10 CFR 50.46#b +, 10 CFR 50.46#b5 +  and 10 CFR 50.46#b4 +

SECY 97-168 +  and SECY-97-042 +

H.2(n) +  and H.2(t) +

05000368  +  and 00368  +

ML021130826 +, ML021140674 +  and ML021150408 +

Turbine Trip +  and Reactor Trip +

67 FR 12587 +  and 67 FR 20176 +

Alexion T +  and Office of Nuclear Reactor Regulation +

GDC 64 +, GDC 63 +, GDC 17, Electric power systems +, GDC 19, Control room +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, 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 +

ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +, ML021130826 +...

4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +, 6.134259e-4 d (0.0147 hours, 8.763227e-5 weeks, 2.01665e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 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)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 0 d (0 hours, 0 weeks, 0 months)  +

Iodine-131 +  and I-131 +

0CAN060104, Letter Re Arkanasas Nuclear One-Units 1 and 2 Registration of Cask Use +, 1CAN010201, License Amendment Request Re One-Time Extension of the Integrated Leak Rate Test Interval +, 2CAN020203, Response to Request for Additional Information on Vessel Head Penetration Nozzles Re the ANO-2 Power Uprate License Application +  and 0CAN010201, December 2001 Monthly Operating Report for Arkansas Nuclear One, Units 1 and 2 +

Westinghouse +  and General Electric +

NUMARC 91-06 +  and NUMARC 91-04 +

NUREG-1269 +, NUREG-0917 +, 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 +  and 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 +

AOP +  and Emergency Operating Procedure +

ML021130826 +  and ML021130826 +

Regulatory Guide 1.4 +, Regulatory Guide 1.174 +, Regulatory Guide 1.121 +, Regulatory Guide 1.105 +, Regulatory Guide 1.190 +, Regulatory Guide 1.23 +, Regulatory Guide 1.68 +, Regulatory Guide 1.145 +  and Regulatory Guide 1.77 +

SECY 97-168 +  and SECY-97-042 +

1E-6 +, 2E-6 +, 2T-41A +, 8E-5 +, 2AAC-17 +  and 2VEF-56 +

Maryland +, Washington +, Missouri +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Stator Water Cooling +, Main Steam Safety Valve +, Remote shutdown +, Stator Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Room Envelope +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +, Emergency Feedwater System +  and Emergency Feedwater Actuation System +

TS-3.5.4 +, TS-3.1.3.1 +, TS-3.1.3.6 +, TS-6.9.1.1 +, TS-9.1 +  and TS-6.9.5.1 +

Entergy +  and Anderson C +

Safe Shutdown +, Boric Acid +, High winds +, Shutdown Margin +, Ultimate heat sink +, Fire Barrier +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Hydrostatic +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Finite Element Analysis +, High Energy Line Break +, Main transformer failure +, Feedwater Heater +, Large early release frequency +, Stress corrosion cracking +, Severe Accident Management Guideline +, Atmospheric Relative Concentration Values +, Earthquake +, Turbine Missile +, Fuel cladding +, Fire Protection Program +, Flow Induced Vibration +, Core Exit Thermocouple +, Weak link +, Power Uprate +, Overspeed trip +, Overspeed +, Thermography +...

WCAP-10263 +  and WCAP-15406 +

WCAP-10263 +  and WCAP-15406 +