Pages that link to "NRC Form 3E6A"
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The following pages link to NRC Form 3E6A:
Displayed 10 items.
- 05000461/LER-2020-003, Reactor Core Isolation Cooling System Card Fuse Failure Results in a Condition Prohibited by Technical Specifications and That Could Have Prevented Fulfillment of a Safetv Function Needed to Control (← links)
- 05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources (← links)
- 05000423/LER-1997-056, :on 971107,SWS Drainage Following Containment Depressurization Actuation & Loss of Power Resulted in Condition Outside Design Basis.Caused by Design Deficiency in Sws.Design Mod Will Be Implemented Prior to Mode 4 (← links)
- 05000336/LER-1996-023, :on 960425,discrepancies Found in Various TS Required Valve Lineups.Caused by Failure to Incorporate TS SRs Into Plant Surveillance Procedures.Isolation Valves Had Been Inspected & Verified to Be in Closed Position (← links)
- 05000336/LER-1995-009, :on 950304,determined That RBCCW Sys Outside of Design Basis.Caused by Failure to Update FSAR Prior to Initial Startup.Ist Has Been Written to Obtain & Adjust Flow Rates,As Needed,To Various RBCCW Loads (← links)
- 05000498/LER-1993-023, :on 931231,inadvertent ESF Actuation of Sdg 12 Occurred During Testing.Sdg Will Be Placed in Pull-to-Stop Whenever Maint Activities Performed Involving Connecting Measuring or Test Equipment to Sdg Electrical Circuits (← links)
- 05000331/LER-1993-009, :on 931005,HPCI Valve Tripped Breaker After Being Closed.Caused by Incorrect Torque Setting.Torque Switch & Motor Replaced (← links)
- 05000482/LER-1993-014, :on 900501,essential Svc Water Low Flow Prior to Refueling Outage Occurred.Cause Unknown.Reportability Determination Process Revised,Rers Logged & Entered Into Tracking Database (← links)
- 05000482/LER-1993-004-01, :on 930316,broken Fuel rod,11-12 Inches in Length,Protruded Out of Fuel Assembly F67 at Core Position FH-6.Caused by Grid to Rod Fretting Failures.Util Evaluating Fluid Elastic Instability (← links)
- 05000324/LER-1991-001-03, :on 910125,reactor Scram Occurred During Calibr of Feedwater Computer Point.Caused by Incorrect Procedure in Summary Sheet.Maint Procedures Reviewed & Revised (← links)