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ML20339A013 +
NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +, NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 95-06, Changes in the Operator Licensing Program +, NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 97-05, Steam Generator Tube Inspection Techniques +, 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 +
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ML20339A013 +, ML20339A013 +, ML20339A013 +, ML20339A013 +, ML20339A013 +, ML20339A013 +, ML20339A013 +, ML20339A013 +, ML20339A013 +, ML20339A013 +, ML20339A013 + and ML20339A013 +
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months) +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months) +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months) +, 8.101852e-4 d (0.0194 hours, 1.157407e-4 weeks, 2.6635e-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 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months) +
November 20, 2020 +
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11:09:48, 16 March 2025 +
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 + and NUREG/CR-1821, Forwards List of Open Issues from Draft NUREG/CR-1821, Seismic Review of Robert E. Ginna Power Plant as Part of Sep. Addl Info Re Seismic Design Consideration & Component Integrity Should Be Submitted within 30 Days +
141 +
2 +
Request +
November 20, 2020 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam + and Containment Spray +
9 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems, Section 5.1 Thru 5.8 +
Safe Shutdown +, Boric Acid +, Shutdown Margin +, Loop seal +, Ultimate heat sink +, Non-Destructive Examination +, Stroke time +, Safe Shutdown Earthquake +, Hydrostatic +, Anchor Darling +, Nondestructive Examination +, Design basis earthquake +, Loss of Offsite Power +, Earthquake +, Power-Operated Valves +, Fuel cladding +, Liquid penetrant +, Pressure Boundary Leakage +, Flow Induced Vibration +, Core Exit Thermocouple +, GOTHIC +, Unidentified leakage +, Power Uprate +, Overspeed +, Eddy-Current Testing +, Leak-Before-Break + and Pressure Temperature Limits Report +
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