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IWB-2400 +, IWB-3512 +, IWA-2300 +  and IWA-3000 +

ASME Section III +  and ASME Section XI +

Boron +, Iodine +, Iron +, Nickel +, Potassium +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Molybdenum +, Chloride +, Lead +, Aluminum +, Silicon +, Calcium +, Zinc +, Chromium +  and Arsenic +

10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 54.3 +, 10 CFR 54.4 +, 10 CFR 54.4#a +, 10 CFR 54.4#a2 +, 10 CFR 54.21#c1 +, 10 CFR 54.21#a1 +, 10 CFR 54.21#c +, 10 CFR 54#a1 +, 10 CFR 54#a3 +  and 10 CFR 54#1 +

05000244  +  and 00244  +

Turbine Trip +  and Reactor Trip +

Rochester Gas & Electric Corp +  and Mecredy R +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +

ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +, ML031410763 +  and ML031410763 +

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +  and 0.0116 d (0.278 hours, 0.00165 weeks, 3.805e-4 months)  +

Information Notice 2001-09, Main Feedwater System Degradation in Safety-Related ASME Code Class 2 Piping Inside the Containment of a Pressurized Water Reactor +  and Information Notice 80-36 +

NUREG-6260 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0821, Forwards Safety Evaluations of SEP Topics,Vols I-III,per App E of NUREG-0821, Integrated Plant Safety Assessment Rept for Re Ginna Nuclear Power Plant +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

RT +  and CP-189 +

Regulatory Guide 1.155 +, Regulatory Guide 1.190 +, Regulatory Guide 1.99 +, Regulatory Guide 1.13 +  and Regulatory Guide 1.35 +

N2B-2 +  and N2B-1 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Auxiliary Feed Water +, Main Steam +  and Containment Spray +

Arrighi R +, Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Boric Acid +, Fire Barrier +, Weld Overlay +, Internal Flooding +, Hydrostatic +, Coatings +, VT-2 +, High Energy Line Break +, Aging Management +, Foreign Material Exclusion +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Biofouling +, Fire Protection Program +, Flow Induced Vibration +, Eddy Current Test +, Operational leakage +, Thermal fatigue +  and Control Room Habitability +

WCAP-14574-A +, WCAP-15837 +, WCAP-15873 +  and WCAP-14577 +

WCAP-14574-A +, WCAP-15837 +, WCAP-15873 +  and WCAP-14577 +