| | | Reporting criterion |
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| 05000328/LER-1996-001-05, :on 960418,inadvertent ESF Actuation & Loss of Power Signal & Load Sequencing Occurred During Maint. Caused by Personnel Error.Individual Involved in Event Was Counseled & Lessons Were Discussed |
- on 960418,inadvertent ESF Actuation & Loss of Power Signal & Load Sequencing Occurred During Maint. Caused by Personnel Error.Individual Involved in Event Was Counseled & Lessons Were Discussed
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000327/LER-1996-001-02, :on 960121,discovered Fire Watch Patrol Did Not Patrol Some Assigned Areas in Control Bldg & on 960126,fire Watch Patrol Not Performed within Timeframe Required by Ts. Appropriate Disciplinary Action Taken |
- on 960121,discovered Fire Watch Patrol Did Not Patrol Some Assigned Areas in Control Bldg & on 960126,fire Watch Patrol Not Performed within Timeframe Required by Ts. Appropriate Disciplinary Action Taken
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000327/LER-1996-002-01, :on 960215,SRs Associated W/Fire Protection Hose Stations Not Performed as Required by Ts.Caused by Inadequate Procedure Rev.Entered Action of LCO & Established Measures to Address Issue |
- on 960215,SRs Associated W/Fire Protection Hose Stations Not Performed as Required by Ts.Caused by Inadequate Procedure Rev.Entered Action of LCO & Established Measures to Address Issue
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) |
| 05000328/LER-1996-002-05, :on 960822,discovered Failure to Properly Identify Steam Generator Tube May Have Exceeded Tech Spec Plugging Criteria.Caused by Misjudgement by Two Independent Analysts.Evaluation Performed |
- on 960822,discovered Failure to Properly Identify Steam Generator Tube May Have Exceeded Tech Spec Plugging Criteria.Caused by Misjudgement by Two Independent Analysts.Evaluation Performed
| |
| 05000327/LER-1996-003-01, :on 960325,failure to Perform Surveillance Requirements for Penetration Fire Barrier Insps as Required by Tech Specs Occurred.Caused by Personnel Error.Appropriate Disciplinary Action Taken W/Individuals |
- on 960325,failure to Perform Surveillance Requirements for Penetration Fire Barrier Insps as Required by Tech Specs Occurred.Caused by Personnel Error.Appropriate Disciplinary Action Taken W/Individuals
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000328/LER-1996-003-05, :on 960605,reactor Trip Breakers Manually Opened Because Shutdown Bank D Dropped Into Reactor Core.On 960607 Manual Reactor Trip Initiated Due to Dropped Rod. Added Caution Statement to Apropriate Operations Prcedure |
- on 960605,reactor Trip Breakers Manually Opened Because Shutdown Bank D Dropped Into Reactor Core.On 960607 Manual Reactor Trip Initiated Due to Dropped Rod. Added Caution Statement to Apropriate Operations Prcedure
| |
| 05000328/LER-1996-004-02, :on 960919,reactor Trip Breaker Was Removed After It Was Found to Have Inoperable Auxiliary Contacts. Caused by Inadequate Procedure.Revised Breaker Procedure & Reemphasized Requirements for Working Steps Out of Sequence |
- on 960919,reactor Trip Breaker Was Removed After It Was Found to Have Inoperable Auxiliary Contacts. Caused by Inadequate Procedure.Revised Breaker Procedure & Reemphasized Requirements for Working Steps Out of Sequence
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) |
| 05000328/LER-1996-004-04, :on 960919,after Reactor Trip Breaker Was Removed Breaker Found to Have Inoperable Auxiliary Contacts. Caused by Inadequate Evaluation of Procedural Change. Procedures Revised |
- on 960919,after Reactor Trip Breaker Was Removed Breaker Found to Have Inoperable Auxiliary Contacts. Caused by Inadequate Evaluation of Procedural Change. Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) |
| 05000328/LER-1996-004-01, Forwards LER 96-004-01 Which Discusses Details Concerning Replacement of Reactor Trip Breaker B | Forwards LER 96-004-01 Which Discusses Details Concerning Replacement of Reactor Trip Breaker B | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000327/LER-1996-004-02, :on 960509,normal Feeder Breaker Unexpectedly Tripped,Resulting in Loss of Power Signal & Start of Four Dgs.Caused by Failure of Breaker Mechanism.Spare Breaker Operating Mechanism Refurbished & Installed |
- on 960509,normal Feeder Breaker Unexpectedly Tripped,Resulting in Loss of Power Signal & Start of Four Dgs.Caused by Failure of Breaker Mechanism.Spare Breaker Operating Mechanism Refurbished & Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000328/LER-1996-005-04, :on 961011,manual Trip Occurred.Caused by Unexpected Loss of Load.Stabilized Unit,Replaced Turbine Impulse Pressure Switches & Replaced Failed Feedwater Isolation Valve Motor & Brake Assembly |
- on 961011,manual Trip Occurred.Caused by Unexpected Loss of Load.Stabilized Unit,Replaced Turbine Impulse Pressure Switches & Replaced Failed Feedwater Isolation Valve Motor & Brake Assembly
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) |
| 05000327/LER-1996-005-02, :on 960526,ESF Actuation Occurred Resulting in DG Start.Cause Unknown.Diagnosed Condition,Reset Start Signal & Secured Actuated Equipment |
- on 960526,ESF Actuation Occurred Resulting in DG Start.Cause Unknown.Diagnosed Condition,Reset Start Signal & Secured Actuated Equipment
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000328/LER-1996-006-04, :on 961206,automatic Reactor Trip Occurred. Caused by Loss of Power to Start Bus 2A,start of Four EDG & Loading of EDG 2B-B.Refurbished Breaker Installed in 2A Start Bus & Breaker Tested Acceptable |
- on 961206,automatic Reactor Trip Occurred. Caused by Loss of Power to Start Bus 2A,start of Four EDG & Loading of EDG 2B-B.Refurbished Breaker Installed in 2A Start Bus & Breaker Tested Acceptable
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii) |
| 05000327/LER-1996-006-02, :on 960623,failed Coupled Capacitor Potential Device Caused Actuation of Generator Backup/Transfomer Feeder Relay Tripping Turbine & Reactor.Removed & Replaced Ccpd |
- on 960623,failed Coupled Capacitor Potential Device Caused Actuation of Generator Backup/Transfomer Feeder Relay Tripping Turbine & Reactor.Removed & Replaced Ccpd
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000328/LER-1996-007-03, :on 961207,ESF Actuation,Start of Feedwater Sys,Occurred as Result of Inadequate Return of Equipment to Svc.Refresher Training on Filling & Venting Fundamentals Will Be Conducted in Yrs Training Cycle |
- on 961207,ESF Actuation,Start of Feedwater Sys,Occurred as Result of Inadequate Return of Equipment to Svc.Refresher Training on Filling & Venting Fundamentals Will Be Conducted in Yrs Training Cycle
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) |
| 05000327/LER-1996-007-01, :on 960614,rod Position Indicators for Control Bank D Rods M4 & M12 More than Required 12 Steps Out from Respective Demand Position Indicators.Caused by Incorrect Position Indication on Rod.Response Reduced |
- on 960614,rod Position Indicators for Control Bank D Rods M4 & M12 More than Required 12 Steps Out from Respective Demand Position Indicators.Caused by Incorrect Position Indication on Rod.Response Reduced
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) |
| 05000327/LER-1996-008-01, :on 960709,failed to Perform Quarterly Backseat/Closure Test on Five Check Valves.Caused by Personnel Error.Test Procedure Written & Performed on Subject Check Valves |
- on 960709,failed to Perform Quarterly Backseat/Closure Test on Five Check Valves.Caused by Personnel Error.Test Procedure Written & Performed on Subject Check Valves
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) |
| 05000327/LER-1996-009-01, :on 960718,auxiliary Building Secondary Containment Boundary/Fire Barrier Not Maintained as Required by Design.Caused by Failure to Follow Design Control Process |
- on 960718,auxiliary Building Secondary Containment Boundary/Fire Barrier Not Maintained as Required by Design.Caused by Failure to Follow Design Control Process
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
| 05000327/LER-1996-010-01, :on 961116,manual Reactor Trip Occurred.Caused by Unexpected Feedwater Heater Isolation.Informed Personnel of Effects Changing Proportional Band on Operating Range of Associated Valve Controllers |
- on 961116,manual Reactor Trip Occurred.Caused by Unexpected Feedwater Heater Isolation.Informed Personnel of Effects Changing Proportional Band on Operating Range of Associated Valve Controllers
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) |
| 05000327/LER-1996-011-01, :on 961118,discovered Rod Position Indication Sys Was Out of Step W/Demand Position Indication Sys.Caused by Incorrect Position Indication on Analog Rod Position. Began Dilution of Reactor Coolant Sys |
- on 961118,discovered Rod Position Indication Sys Was Out of Step W/Demand Position Indication Sys.Caused by Incorrect Position Indication on Analog Rod Position. Began Dilution of Reactor Coolant Sys
| 10 CFR 50.73(a)(2)(i) |
| 05000327/LER-1996-012-01, :on 960330,two Cold Leg Accumulator Sample Isolation Valves & Missing Data Sheet in Surveillance Package Were Inoperable.Caused by LCO Not Being Entered. Isolation Valves Were Tested |
- on 960330,two Cold Leg Accumulator Sample Isolation Valves & Missing Data Sheet in Surveillance Package Were Inoperable.Caused by LCO Not Being Entered. Isolation Valves Were Tested
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) |