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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

Boron +, Iodine +, Cesium +, Copper +, Nitrogen +, Xenon +, Lead +  and Tin +

10 CFR 50 Appendix R +, 10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 50.109 +, 10 CFR 6.7 +, 10 CFR 50.54#f +  and 10 CFR 50.47#b10 +

Initiating Events +  and Mitigating Systems +

SECY 91-283 +, L 38 +, SECY 92-067 +  and L-1449 54 +

NRC Generic Letter 80-53, Decay Heat Removal Capability +, NRC Generic Letter 81-21, Natural Circulation Cooldown +, NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +, NRC Generic Letter 85-05, Inadvertent Boron Dilution Events +, NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML20057E700 +, ML20057E700 +, ML20057E700 +, ML20057E700 +, ML20057E700 +  and ML20057E700 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 0.0246 d (0.59 hours, 0.00351 weeks, 8.085625e-4 months)  +  and 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +

L-1449 54 +  and L 38 +

05000387/LER-90-005 +, 05000271/LER-89-013 +, 05000397/LER-88-011 +, 05000302/LER-86-003 +, 05000382/LER-86-015 +, 05000285/LER-90-006 +, 05000323/LER-87-005 +, 05000397/LER-85-030 +  and 05000456/LER-89-016 +

General Electric +  and Westinghouse +

Information Notice 91-54 +, Information Notice 91-36 +  and Information Notice 91-41 +

NUREG/CR-4550 +, NUREG-1269 +, NUREG/BR-0150 +, NUREG/CR-5820 +, NUREG/CR-5015 +, NUREG/CR-5819 +, NUREG-1123, Rev. 3 Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors +, NUREG-1122, Rev. 3 Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors +, NUREG-1032, Draft Reg Guide,Task SI 501-4, Station Blackout. Draft NUREG-1109 & NUREG-1032 Re Regulatory/Backfit Analysis for Resolution of USI A-44 & Evaluation of Station Blackout Accidents at Nuclear Power Plants,Respectively,Encl +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, 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-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-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, NUREG/CR-4674, Forwards NUREG/CR-4674,Vols 9 & 10, 1988 Accident Sequence Precursor Rept. Rept Describes & Evaluates Significant Operational Events Reported by LERs for CY88. W/O Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +, NUREG-1410, Discusses NRC Concerns Re Operator Diligence While in Shutdown Conditions & Requests Quick & Appropriate Mgt Reactions to Generic Ltr 88-17.Supporting Documentation Encl +  and NUREG-12.69 +

ES +, ST +, SP +, Emergency Operating Procedure +  and AOP-32 +

Regulatory Guide 1.149 +  and Regulatory Guide 1.101 +

SECY 91-283 +  and SECY 92-067 +

3E-5 +, 1M-1 +, 16E-4 +, 8S-17 +, 2o-t +, 285h0-006 +  and R3R-27A +

Manual Scram +  and Automatic Scram +

Pennsylvania +, Georgia +, Illinois +, Maryland +, Washington +, Idaho +, New York +, Mississippi +, Arkansas +  and Vermont +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Primary Containment Isolation System +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +...

TS-3.5.2 +, TS-6.12.2 +  and TS-6.5.1 +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Loop seal +, High Radiation Area +, Half scram +, Ultimate heat sink +, Mission time +, Stroke time +, Time to boil +, Hydrostatic +, Probabilistic Risk Assessment +, Temporary Modification +, Job Performance Measure +, Local Leak Rate Testing +, Scram Discharge Volume +, Loss of Offsite Power +, Integrated leak rate test +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Fire Watch +, Scaffolding +, Backfit +, Core Exit Thermocouple +, Reactive Inspection +  and Spill +