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

Iodine +, Nickel +, Krypton +, Carbon +, Oxygen +, Xenon +  and Lead +

10 CFR 50 +  and 10 CFR 50 Appendix J +

00354  +, 05000354  +  and 00361  +

GDC 21 +, GDC 51 +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +  and NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift +

ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +, ML20205E469 +...

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +

ML20137S103 +, ML20137L732 +, IR 05000354/1985055 +, IR 05000354/1985025 +, IR 05000354/1985042 +, ML20133G551 +, IR 05000354/1985039 +, IR 05000354/1986022 +, ML20195D226 +, IR 05000354/1986014 +, ML20199J493 +, ML20199B386 +, ML20197D908 +, IR 05000354/1986019 +, 05000354/LER-1986-016, :on 860508,control Room Emergency Filtration Automatically Initiated & on 860504,Train a of Control Room Ventilation Isolated.Caused by Drifting High Voltage Supply for Detector 1SP-RE-4858C1.Supply Recalibr +, 05000354/LER-1986-028, :on 860607,Channel a of Standby Liquid Control Sys (SLCS) Inadvertently Actuated.Cause Unknown.Bailey Solid State Logic Modules Replaced in Both SLCS Channels +, 05000354/LER-1986-024, :on 860525,surge Occurred in Ref Leg of Channel D Reactor Level Instrumentation Resulting in Actuation of LOCA Logic.Caused by Procedural Inadequacy for Return to Svc Following Calibr.Procedures Revised +, 05000354/LER-1986-009-01, :on 860425,technician Moved Adjacent intermediate-range Monitor Cable While Checking Wire Identification Numbers in Preamplifier Cabinet,Causing Spike of Scram Signal.Addl Training Scheduled +, 05000354/LER-1986-005-01, :on 860416,during Fuel Load,Discovered Filtration,Recirculation,Ventilation Sys Inoperable.Caused by Personnel Error.Review of Addl Training Requirements Initiated +  and 05000354/LER-1986-029, :on 860611,control Area Chiller a Tripped on Low Refrigerant Pressure.Caused by Malfunction of Ball Float Valve.Valve Replaced +

Westinghouse +, General Electric +  and Target Rock +

NUREG-0869, Forwards CRGR Review of Proposed Resolution of Unresolved Safety Issue A-43, Containment Emergency Sump Performance. Draft NUREG-0869 & NUREG-0897 Re Unresolved Safety Issue A-43 Also Encl +, NUREG/CR-1884 +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, NUREG-1048, Forwards Safety Evaluation Supporting Proposed Turbine Sys Maint Program Submitted w/870513 Ltr +, 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 +

George Thomas +  and John Tsao +

FPP +, RT +, CH-TI.ZZ-012 +  and CH-TI-ZZO12 +

Regulatory Guide 1.75 +, Regulatory Guide 1.22 +, Regulatory Guide 1.68 +  and Regulatory Guide 1.115 +

SR-4.6.5.3.b +  and SR-4.6.5.3.e +

07-82-132 +, 2VV-2200E +, 0D-11 +, 23A-MSIV +  and 3yr-and +

Pennsylvania +, Illinois +, Colorado +, Maryland +, Washington +, California +, Massachusetts +, New Jersey +, New York +, Missouri +  and Delaware +

Reactor Coolant System +, Feedwater +, High Pressure Coolant Injection +, Reactor Protection System +, Primary containment +, Main Turbine +, Safety Parameter Display System +, Reactor Pressure Vessel +, Reactor Water Cleanup +, Control Room Emergency Filtration System +, Automatic Depressurization System +, Emergency Core Cooling System +, Safety Relief Valve +, Electrohydraulic Control +, Main Condenser +, Control Rod +  and Main Steam +

TS-3.4.4 +, TS-3.2.3 +, TS-4.6.5.3 +, TS-3.11.2.7 +, TS-4.5.1.d +  and TS-4.4.6.1 +

Safe Shutdown +, Shutdown Margin +, Safety Limit Minimum Critical Power Ratio +, Grab sample +, Abnormal operational transient +, Notice of Violation +, Feedwater Heater +, Shift Technical Advisor +, Stress corrosion cracking +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Excess Flow Check Valve +, Control of Heavy Loads +, Turbine Missile +, Fire Protection Program +, Backfit +, Affidavit +  and Overspeed +