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

IWB-2500 +, IWC-2500 +  and IWC-2000 +

ASME Section III +  and ASME Section XI +

Boron +, Iodine +, Carbon +, Hydrogen +, Chloride +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 100.11 +, 10 CFR 2.790 +, 10 CFR 50.54#f +, 10 CFR 50.55a#g +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g3 +  and 10 CFR 50.55#a +

00423  +  and 05000423  +

GDC 18 +, GDC 51 +, GDC 17, Electric power systems +, GDC 4, Environmental and dynamic effects design bases +  and GDC 5, Sharing of structures, systems, and components +

ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +, ML20154C299 +  and ML20154C299 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

A05331, Responds to 851025 Request for Addl Info Re Use & Training of Shift Advisors.Training Program for Shift Advisors Encl +, B11931, Advises That Mods to Valve Operator & Limit Switch Logic of Return Line Valve MOV 1-IC-3 to Address Dominant Predicted Causes of Isolation Condenser Failure,Described in Probablistic Safety Study,Completed +, A04817, Forwards Executed Certificate M-103 to Maelu Policy 1 & Certificate N-103 to Nelia Policy 1 +, B11231, Forwards Addl Info on Draft SER Open Items CPB-3 & ICSB-14 Re Itemized Documentation & Design for Inadequate Core Cooling,Respectively,Requested in Generic Ltr 82-28 +, A05390, Forwards Addl Info Re Use of RCS Loop Isolation Valve, Degraded Core Cooling Guidelines & Rev to Emergency Operating Procedures,Per 851206 Request Re Procedures Generation Package & Sser 4 (NUREG-1031) +, 05000336/LER-1985-013-01, :on 850822,charging Pump C Removed from Svc Due to Packing Leaks.Caused by High Internal Stresses Causing Cracks to Initiate at Subsurface Inclusions.Pump Replaced +  and 05000245/LER-1985-017, :on 850927,reactor Scrammed on APRM hi-hi When Reactor Mode Switch Changed from Run to Startup/Hot Standby. Off-normal Procedures Followed.Reactor Brought to Hot Shutdown +

NUREG/CR-2627 +, NUREG/CR-2136 +, 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-1031, Forwards Safety Evaluation Re Emergency Operating Procedures Upgrade Program Per TMI Action Item 1.C.1.Eight Procedures Validated on Simulator & Actions Acceptable +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

ES-0.1 +  and RT +

Connecticut +, Maryland +, Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Turbine +, Safety Parameter Display System +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Control Rod +  and Main Steam +

Loop seal +, Hydrostatic +, Operating Basis Earthquake +, Nondestructive Examination +, Emergency Lighting +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Core Exit Thermocouple +, Thermal fatigue +, Water hammer +  and Spent fuel rack +

WCAP-10698 +, WCAP-8691 +  and WCAP-10961-P +

WCAP-10698 +, WCAP-8691 +  and WCAP-10961-P +