RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RA-18-018, Submittal of Changes to Technical Specifications Bases
PNO-I-90-073, on 900830,licensee Identified That Reactor Vessel Level Monitoring Instruments Reading About 10 Inches Higher than Expected.Caused by Ref Leg Being Less than Completely Full.Manual Scram from Low Power Initiated
05000254/LER-1997-019-01, :on 970808,TS 3.0.C Was Entered Because No LCO Was Available for Secondary Containment When Both Doors for Interlock Were Opened Simultaneously.Verified Proper Operation
05000278/LER-1986-021-02, :on 861021,water Vol in Suppression Chamber Exceeded Max Tech Spec Limit.Caused by Delay in Performance of HPCI Surveillance Test.Procedure Will Be Revised to Record Water Level During Test
05000277/LER-1987-001-01, :on 870311,suppression Pool Water Vol Exceeded Max Tech Spec Limit.Caused by Leaking Check Valve in RHR Loop A.Suppression Pool Water Vol Restored within Tech Spec Limits
05000309/LER-1996-039, :on 961207,both Diesel Generators Were Declared Inoperable & TS Remedial Action 3.12.A Entered.Caused by Oversight in Original Surveillance Procedure Development. Surveillance Procedures Modified
05000282/LER-1996-014, :on 960726,CW Pumps Simultaneously Stopped Operating.Caused by Normal Performance of Surveillance Test. Counseled Operations Personnel Involved in Event
05000277/LER-1992-005, :on 920326,2B Reactor Water Level Reference Leg Condensing Chamber Was Declared Inoperable.Caused by Loss of Inventory in 2B Condensing Chamber.Leaks Were Repaired & Instrument Lines Were Backfilled
05000278/LER-1991-012-03, :on 910724,controlled Shutdown Initiated Due to Loss of auto-start Capability of Div II Core Spray Sys Concurrent W/Loss of LOCA Signal.Caused by Blown Fuse & Shorting in Light Socket.Fuse Replaced
05000277/LER-1991-020, :on 910607,two Diesel Generators Discovered Inoperable Due to Mispositioned Valve.Caused by Personnel Error.Valve Immediately Restored & Involved Operator & Chemist Counseled
05000282/LER-1991-004-01, :on 910509,failure of Redundant Heat Trace Circuits Occurred as Result of Electrical Fault.Caused by Operator Stepping on Insulated Section of piping.ET-53R Heat Trace Circuit Repaired
05000277/LER-1991-018, :on 910523,Tech Spec 3.0.C Entered & Plant Shutdown Initiated Due to Belief That Diesel Generators Inoperable.Caused by Misclassification of EDG Day Tank. Engineering Review Performed
05000277/LER-1994-008-02, :on 940909,discovered That ECCS & EDG May Have Been TS Inoperable on 940803 When ESW Outlet Valve MO-0498 Closed & Left Unattended,Causing ECT to Overflow.Valve Opened & ECT Level Restored to Normal Range.W/Undated Ltr
05000277/LER-1990-035, :on 901115,discovered That Multiple Safety Sys Could Be Inoperable as Result of 4 Kv Emergency Bus Undervoltage Relays Outside Acceptable Calibr Limits.Caused by Inadequate Design.Relays Modified
05000306/LER-1990-011-02, :on 901009,entrance Into Tech Spec 3.0.C During AMSAC post-installation Testing Occurred
05000277/LER-1990-012-01, :on 890815,discovered Valves Left Closed After Removal of Blocking Permit & on 890813,emergency Cooling Water Pump & Emergency Diesel Generator Removed from Svc. Caused by Inadequate Procedures
05000278/LER-1990-006-03, :on 900511,blown Fuse from Battery Charger 3B Resulted in Declaring HPCI Sys,Core Spray B Logic,Rhr B Logic,Core Spray Subsystem B,Rhr Subsystem B & E2 & E4 Emergency Diesel Generators Inoperable
05000306/LER-1997-003-01, :on 970517,Unit 2 Was Brought to Planned Hot Shutdown Condition to Perform Valve Maint in 22 RCP Containment Vault.Caused by Inattention to Detail.Will Evaluate Revising Plant Operating Procedures
05000277/LER-1990-021, :on 900830,reactor Level Instrumentation Associated W/Ref Leg 2B Condensing Chamber Declared Inoperable.Caused by Loss of Inventory in Ref Leg Due to Erroneous Reactor Water Level Readings