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TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

Boron +, Nickel +, Copper +, Hydrogen +, Lead +  and Phosphorus +

10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +  and 10 CFR 50.44 +

Emergency Preparedness +  and Initiating Events +

00361  +, 00362  +, 05000361  +  and 05000362  +

Reactor Trip +  and Turbine Trip +

GDC 2, Design bases for protection against natural phenomena +  and GDC 41 +

ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +, ML20055B280 +  and ML20055B280 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

05000206/LER-1981-024, Submits Followup to LER 81-024 Re Failure of Energy Products Group Ball Valves W/Efcomatic Actuators to Trip Initially Per Commitment Made in Design Change 78-34.Actuators Will Be Replaced W/Different Design +, ML13317B088 +  and ML13310A243 +

Westinghouse +  and General Electric +

NUREG-0623 +, NUREG-712 +, NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, NUREG-0712, Forwards Suppl 6 to SER,NUREG-0712.W/o Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +  and NUREG-0645, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +

Regulatory Guide 1.97 +, Regulatory Guide 1.7 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.68 +

N6t-the +  and 5G-361 +

Maryland +, Washington +, California +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Shutdown Margin +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Process Control Program +, Loss of Offsite Power +, Rod Drop Event +, Earthquake +, Backfit +, Siren +, Loss of condenser vacuum +  and Water hammer +