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SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT

10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +

05000416  +  and 00416  +

51 FR 31740 +, 51 FR 30577 +  and 51 FR 15402 +

ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +, ML20215E413 +...

AECM-85-0175, Forwards Rev 6 to Vol 8,Section 3,Procedure 08-S-03-17, Chemistry Procedure Core Damage Estimation Safety-Related, in Response to NRC Request to Incorporate Conservative Fission Product Release Fractions.Fee Paid +, AECM-86-0208, Forwards Addl Info Re Emergency Containment Venting in Response to Item 1.1 of 860527 Request.Encl Rev 1 to ...Emergency Procedures Upgrade Program Procedures Generation Package Addresses Remaining Request +, AECM-85-0306, Responds to Request for Addl Info Re 850812 Application for Amend to License NPF-29.Prompt Resolution of Questions & Approval of Previously Submitted Tech Specs Needed for Outage Scheduled to Start on 851012 +, AECM-86-0006, Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid +, AECM-85-0228, Application for Amend to License NPF-29,changing Tech Specs to Reflect Design Changes & Editorial Clarifications.Fee Paid +, AECM-85-0304, Application for Amend to License NPF-29,supplementing 850812,23 & 30 Submittals,To Provide Justification for Exemption from Tech Spec 6.3.1 & 6.4.1 Requirements for Senior Reactor Operator Qualifications +, AECM-84-0220, Updated Special Rept 83-104/1:on 831024,fire Rated Penetration CE-515D,located on West Wall of Room OC403 on 148-ft Elevation in Control Bldg,Discovered Open.Wrong Penetration Sealed.Permanent Labeling Now in Process +, 05000416/LER-1986-017, :on 860430,wrong Fuse Pulled During Attempt to Deactivate Containment Isolation Valve Causing Actuation of Combustible Gas Control Subsystem A.Fuse Reinserted & Sys Returned to Standby.Operator Disciplined +, 05000416/LER-1986-007, :on 860220,RHR Pump B & Standby Svc Water Pump B Automatically Started Due to Technician Connecting Test Switch to Wrong Terminal.Caused by Inadequate Verification by Contractor.Contract Terminated +  and 05000416/LER-1984-025, :on 840501,drywell Purge Sys Surveillance Performed on 830817 Not Adequate to Insure Tech Spec Flow Requirements Met Prior to 830925 & 840422 Startups.Caused by Use of Incorrect Surveillance Procedure +

NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

SR-4.8.1.1.2 +, SR-4.5.1 +  and SR-4.4.3.2.2 +

1E21-F006 +, Q1E12-F042B +  and 01E12-F042A +

Reactor Coolant System +, Service water +, Emergency Diesel Generator +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Standby Gas Treatment System +, Automatic Depressurization System +, Remote shutdown +, Emergency Core Cooling System +, Safety Relief Valve +, Main Steam +  and Low Pressure Coolant Injection +

Safe Shutdown +  and Earthquake +