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

ASME Section III +  and ASME Section XI +

Boron +, Iodine +, Germanium +, Nitrogen +, Carbon +, Hydrogen +, Lead +  and Silver +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 2.101 +, 10 CFR 50.49 +, 10 CFR 73.21 +, 10 CFR 50.55a +, 10 CFR 50.55a#g +, 10 CFR 50.55a#b +, 10 CFR 50.55a#c +  and 10 CFR 50.55a#g3 +

00354  +  and 05000354  +

GDC 31 +, GDC 36 +, GDC 51 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-08, Modification of Vacuum Breakers on Mark I Containments +, NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs +, NRC Generic Letter 85-17, Availability of Supplements 2 and 3 to NUREG-0933, "A Prioritization of Generic Safety Issues" +, NRC Generic Letter 85-16, High Boron Concentrations +, NRC Generic Letter 85-15, Information on Deadlines for 10CFR50.49, "Environmental Qualification of Electric Equipment Important to Safety at Nuclear Power Plants" +, NRC Generic Letter 85-14, Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste Not Generated by The Utility +, NRC Generic Letter 85-13, Transmittal of NUREG-1154 Regarding The Davis-Besse Loss of Main And Auxiliary Feedwater Event +  and NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +

ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +, ML20198C162 +...

IEEE 279 +  and IEEE 384 +

ML20079L983 +, ML20102C170 +, ML20099H061 +, ML20099C308 +, ML20095G849 +, ML20107F230 +, IR 05000354/1985027 +, ML20134H086 +, IR 05000354/1985028 +, ML20133D477 +, ML20133A528 +, IR 05000354/1985015 +, IR 05000354/1985023 +, ML20128E312 +, ML20127J347 +, ML20125E485 +, ML20099C854 +, ML20033C197 +, ML20066K741 +  and ML20066K807 +

General Electric +  and Westinghouse +

NRC Bulletin 79-27 +  and NRC Bulletin 79-15 +

Information Notice 79-22 +  and Information Notice 1983-42, Reactor Mode Switch Malfunctions +

NUREG-1074 +, NUREG/CR-2136 +, NUREG-0408, Discusses Review of Generic Mark I Containment Short Term Program Conducted by Owners Group.Info Avaiable in NUREG-0408 +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, 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-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-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-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +, NUREG-0927, Informs Commissioners of Issuance of NUREG-0927 Re Resolution of USI A-1, Water Hammer. Issue Dealt W/ Consideration of Frequency & Severity of Water Hammer Events +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

Regulatory Guide 1.75 +, Regulatory Guide 1.65 +, Regulatory Guide 1.92 +  and Regulatory Guide 1.148 +

NEDE-24539 +  and NEDE-24840 +

10C-399 +, B0P-3 +, 80P-6 +, 1HD-9603B1 +, 1AP-206 +, 80P-2 +, 1HD-960381 +, 10C-026 +, 80P-7 +, 80P-10(d) +, 80P-11 +, 10C-011 +, 10C-6081 +, 80P-8 +, 80P-5 +, 80P-9 +, B0P-2 +, B0P-10(a) +, 80P-10(b) +, 10P-216 +, 10P-217 +, 1AP-202 +, 1AP-401 +, 1AP-502 +, 1HV-4680 +, 1HV-F015A +  and 1AE-V007 +

Maryland +, Washington +, New Jersey +, Idaho +  and New York +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Hot Short +, Safe Shutdown +, Reactor Vessel Water Level +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, High Energy Line Break +, Feedwater Heater +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Stress corrosion cracking +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Affidavit +, Thermal fatigue +  and Water hammer +