ST-HL-AE-5333, Forwards Response to NRC Bulletin 96-001, Control Rod Insertion Problems
RA-21-0223, Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report
RA-21-0056, Refueling Outage 32 Steam Generator Tube Inspection Report
05000312/LER-1987-040, :on 870817,discovered That Source Daily Check During Releases Via Regenerant Tank Pathway Not Performed Per Tech Specs.Caused by Inadequate Tech Spec Review. Procedures Revised & Temporary Changes Made
W3P84-3152, Forwards Suppl to Addl Info Re Basemat Hairline Cracks. Muenow & Assoc,Inc Performed Ultrasonic Testing of Interface Between Top of Basemat & Bottom Fill Concrete.Test Confirms Sonic Energy Not Penetrating Fill Concrete
05000352/LER-1985-026, :on 850228,spurious half-scram Signal on Reactor Protection Sys Channel a Occurred.Caused by Voltage Fluctuation from Voltage Regulator board.Half-scram Signal Reset & Hoods & Fans Installed
05000237/LER-1977-014-03, /03X-1 on 770402:during Normal Startup Oper,Crd H-8 Was Found to Uncouple & Overtravel When Withdrawn to Pos 48.Caused by an Unlatched Inner Filter & Abnormally Long Uncoupling Rod
05000353/LER-1989-009-01, :on 890820,eight RCIC Sys Injections Into RCS Occurred Under Purview of Facility start-up Test Program. Caused by Abnormal Plant Conditions Requiring Safety Sys Actuations.Rcic & HPCI Sys Tests Completed
05000333/LER-1979-006-03, /03X-1:on 790124,during Normal Operations,Ground Fault on 125 Station Battery a Noted.Caused by Bellows Failure on Pressure Switch Circuit safety-relief Valve 02-RV-71J.Ground Cleared.Valve Restored to Operation
05000260/LER-1991-019-01, :on 911208,unexpected Loss of One of Offsite Power Supplies Occurred.Caused by Fuse Failure.Util Will Investigate Spurious Tripping of Trinity 1 Line During Event & Correct Identified Deficiencies
ST-HL-AE-2771, Forwards Response to NRC Bulletin 88-005,Suppls 1 & 2 Re Matls Supplied by West Jersey Mfg Co,Piping Supplies,Inc & Chews Landing Metal Mfgs Inc
A06401, Forwards Responses to Questions on Pumps & Valves Inservice Testing Program,Per 870602 & 03 Meetings
NSD-NRC-98-5649, Forwards Rev 4 to Section 2.2, Nuclear Safety Sys of AP600 Certified Design Matl,Dtd 980406.Changes Made as Result of W Responses to NRC Questions Re Rev 3 & Include Rais,Fser Open Items & Meeting Open Items from ITAAC Task Group Mee
05000237/LER-1985-020-02, :on 850424,during HPCI Steam Line High Flow Isolation Surveillance,Hpci Valve 2301-H Failed to Close. Caused by Dirty Breaker Auxiliary Contacts.Contacts Cleaned & Later Replaced
05000374/LER-1984-022-01, :on 840521,Door 213,controlling Access to Area Behind Turbine Shield Walls,Found Open.Caused by Personnel Error.Security Contacted to Determine Which Individuals Passed Through Door