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Boron +, Hydrogen +  and Tin +

BVY 03-23 +, BVY 03-80 +, BVY 03-98 +, BVY 03-90 +, BVY 03-981 +  and BVY 03 +

10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 71 +, 10 CFR 20.1302 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.61 +, 10 CFR 50.55a +, 10 CFR 50.62#c4 +, 10 CFR 50.62#c3 +, 10 CFR 50.55a#f +, 10 CFR 50.55a#h +  and 10 CFR 50.55#a1 +

BVY 03-23 +, BVY 03-80 +, BVY 03-98 +, BVY 03-90 +, BVY 03-981 +, RS-00 14 +, RS-001 +  and BVY 03 +

05000271  +  and 00271  +

Turbine Trip +  and Reactor Trip +

Entergy +  and Thayer J +

GDC 20 +, GDC 38 +, GDC 41 +, GDC 44 +, GDC 34 +, GDC 15 +, GDC 50 +, GDC 16 +, GDC 54 +, GDC 10 +, GDC 12 +, GDC 55 +, GDC 61 +, GDC 35 +, GDC 14 +, GDC 60 +, GDC 24 +, GDC 11 +, GDC 13 +, GDC 30 +, GDC 46 +, GDC 31 +, GDC 40 +, GDC 25 +, GDC 64 +, GDC 28 +, GDC 62 +, GDC 22 +, GDC 29 +, GDC 42 +...

NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +, ML033100141 +  and ML033100141 +

ML032580089 +  and ML032810438 +

Information Notice 97-90 +, Information Notice 95-16 +, Information Notice 97-85 +, Information Notice 96-48 +, Information Notice 96-49 +, Information Notice 00-17 +  and Information Notice 02-26 +

NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +

ST +  and CP +

RS-00 14 +  and RS-001 +

Regulatory Guide 1.174 +, Regulatory Guide 1.147 +, Regulatory Guide 1.84 +, Regulatory Guide 1.190 +, Regulatory Guide 1.99 +, Regulatory Guide 1.161 +, Regulatory Guide 1.154 +  and Regulatory Guide 8.14 +

RIS 2000-03, Resolution of Safety Issue 158: Performance of Safety Related Power-Operated Valves Under Design Basis Conditions +  and RIS 2001-02, Guidance on Risk-Informed Decisionmaking in License Amendment Reviews +

NEDC-33004P +, NEDO-33004 +  and NEDC-33090P +

07-01-015 +  and 07-91-005 +

Washington +  and Vermont +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Main Turbine +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Main Condenser +, Control Rod +, Main Steam +  and Turbine Gland Sealing System +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Shutdown Margin +, Ultimate heat sink +, Stroke time +, Anticipated operational occurrence +, Abnormal operational transient +, Feedwater Heater +, Stress corrosion cracking +, Fuel cladding +, Fire Protection Program +, Flow Induced Vibration +, Power Uprate +, Overspeed +, Manual Operator Action +, Loss of condenser vacuum +, Control Room Habitability +  and Leak-Before-Break +