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

Iodine +, Hydrogen +  and Lead +

10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.206 +, 10 CFR 50.90 +, 10 CFR 73.21 +, 10 CFR 140.21 +, 10 CFR 50.5S#b +, 10 CFR 50.49#i +, 10 CFR 50.54#p +, 10 CFR 50.54#s2 +, 10 CFR 50 Appendix R#j +, 10 CFR 50.55#a +  and 10 CFR 50.71#b +

S.0(x) +  and S.8(c) +

00440  +, 00441  +, 05000440  +  and 05000441  +

Reactor Trip +  and Turbine Trip +

GDC 51 +, GDC 17, Electric power systems +  and GDC 19, Control room +

NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs +, NRC Generic Letter 86-08, Availability of Supplement 4 to NUREG-0933, "A Prioritization of Generic Safety Issues" +, NRC Generic Letter 86-07, Transmittal of NUREG-1190 Regarding the San Onofre Unit 1 Loss of Power and Water Hammer Event +  and NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift +

ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +, ML20214N808 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 1.041667e-4 d (0.0025 hours, 1.488095e-5 weeks, 3.4245e-6 months)  +

ML031150264 +, NRC Generic Letter 1986-12 +, ML20082M927 +, ML20100A022 +, IR 05000318/2009016 +, ML20141P000 +, ML20141N204 +, ML20138S032 +, IR 05000440/1985074 +, ML20199K691 +, ML20199E019 +, ML20198K952 +, ML20202F905 +, ML20207L183 +, ML20206J264 +, ML20244D711 +, IA-86-254, Final Response to FOIA Request for Encl 1 of NRC Re Metalweld,Inc Work Allegations & Addl Info Since 851118 Request.Forwards App D Documents.App D Documents Partially & Completely Withheld (Ref FOIA Exemption 7).Info in PDR +, IR 05000440/1985034 +, ML20210P251 +, PY-CEI-NRR-0504, Forwards Description of Emergency Procedures Developed for Hydrogen Igniter Sys,Per Paragraph 2.C.10(b) of License NPF-45.Specific Instruction Under Review & Will Be Approved Upon Receipt of Sser 10 +, PY-CEI-NRR-0480, Forwards plant-unique Analysis for Emergency Containment Venting Per Commitment in .Submittal Completes Actions Required in Sser 8 +, 05000440/LER-1986-019, :on 860530,Div 2 Diesel Generator Bldg Ventilation Supply Fan Discovered to Be Running Unexpectedly.Cause Unknown.Investigation Continuing W/ Attempt to Replicate Conditions Prior to & Including Event +, 05000000/LER-1986-005-03, Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points +, 05000440/LER-1986-021, :on 860602,discovered That Five Recirculation Damper Actuators in Diesel Generator Bldg Ventilation Sys Inoperable Due to Seal Failures.Caused by Expiration of Seal Life & Improper Storage & Maint.Seals Replaced +, 05000440/LER-1986-009, :on 860504,RWCU Sys Outboard Containment Isolation Occurred.Caused by Personnel Error Due to Cramped Working Location.Engineering Design Change Developed to Alter Wiring Configuration +  and 05000440/LER-1986-008, :on 860430,containment Fire Hose Reel Inboard/ Outboard Supply Isolation Valves Discovered in Open Position.Valves Opened Before Start of Core Alterations on 860321 by Shift Operators.Personnel Counseled +

NRC Bulletin 79-27 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NUREG/CR-3480 +, NUREG/CR-3805 +, NUREG/CR-1649 +, NUREG-1190, Transcript of Commission 860122 Briefing in Washington,Dc Re San Onofre & Status of Rancho Seco.Pp 1-105.Supporting Documentation & NUREG-1190, Loss of Power & Water Hammer Event at San Onofre,Unit 1 on 851121 Encl +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-0887, Forwards Approved Changes to Tech Specs for Full Power License,Per 860618,0718 & 30 Requests.Certification That Changes Consistent W/Fsar,Ser & as-built Plant Requested by 860908 +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, NUREG-887 +, 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-0899, Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 +  and 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 +

CP +  and SAP +

Regulatory Guide 1.60 +, Regulatory Guide 1.61 +  and Regulatory Guide 1.68 +

07-86-001 +, 07-86-033 +, 07-86-009 +, 07-86-019 +, 07-86-010 +, S0IL-STRUCTU +, 07-86-030 +, 07-86-005 +, 07-86-036 +, 07-86-016 +  and 07-86-028 +

NPF-45 +  and NPF-58 +

Ohio +, Pennsylvania +, Colorado +, Maryland +, Washington +, South Carolina +, New York +  and Delaware +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Recirculation Pump +, Safety Parameter Display System +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Shield Building +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Emergency Core Cooling System +, Control Rod +, Main Steam +, Containment Spray +, Low Pressure Coolant Injection +  and Main Turbine Bypass System +

Safe Shutdown +, Shutdown Margin +, Safe Shutdown Earthquake +, Scram Discharge Volume +, Feedwater Controller Failure +, Safeguards Contingency Plan +, Earthquake +, Chernobyl +, Turbine Missile +, Fuel cladding +, Liquid penetrant +, Fire Protection Program +, Power change +, Control Room Habitability +  and Spill +