05000298/LER-1992-019, Forwards Corrected LER 92-019-00,including Event Date Inadvertently Omitted from 930128 Memo

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Forwards Corrected LER 92-019-00,including Event Date Inadvertently Omitted from 930128 Memo
Person / Time
ML20128B861
Site:	Cooper
Issue date:	01/29/1993
From:	Gardner R NEBRASKA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20128B866	List: 05000298/LER-1992-019, Forwards Corrected LER 92-019-00,including Event Date Inadvertently Omitted from 930128 Memo 05000298/LER-1992-019-01, :on 921230,design Deficiency W/Ac Electrical Sys Confirmed When Single Nonaccident Event Could Result in Common Mode Failure of Both Dgs.Permanent Electrical Jumper Installed in Each Breaker Trip Circuit
References
CNSS933019, NUDOCS 9302030197
Download: ML20128B861 (1)
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LER-1992-019, Forwards Corrected LER 92-019-00,including Event Date Inadvertently Omitted from 930128 Memo

Event date:
Report date:
2981992019R00 - NRC Website
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CMSS933019 January 29, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555 L, ear S!r:

Cooper Nuclear Station Licensee Event Report (LER)92-019, Revision 0, was previously submitted to you under cover memo CNSS9330ltt, dated January 28, 1993.

Subsequent to the transmittal, it was discovered that the Report Date information had inadvertently been omitted.

Enclosed is a corrected copy of the LER.

Sincerely, s

R. L. Gardner Plant Manager RLG/j u Attachment 02007G 1

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9302030197 930129 PDR ADOCK 05000298 l

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Licensee Event Report

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		Reporting criterion
05000298/LER-1992-001, :on 920111,both Pumps Exceeded Setpoints of High Flow Isolation Switch.Caused by Insufficient Throttling of Valve.Group 3 Isolation Was Reset & B Pump Placed Into Operation	on 920111,both Pumps Exceeded Setpoints of High Flow Isolation Switch.Caused by Insufficient Throttling of Valve.Group 3 Isolation Was Reset & B Pump Placed Into Operation	10 CFR 50.73(a)(2)(iv), System Actuation
05000298/LER-1992-002, :on 920203 & 4,reactor Vessel Water Setpoint Inaccuracy Resulted from Reference Leg Temp Effects That Had Not Been Correctly Addressed.Setpoint Calculations Were Performed	on 920203 & 4,reactor Vessel Water Setpoint Inaccuracy Resulted from Reference Leg Temp Effects That Had Not Been Correctly Addressed.Setpoint Calculations Were Performed	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)(1)
05000298/LER-1992-003, Provides Supplemental Info on Rev 0 to LER 92-003 Re Degradation in safety-related Battery Cells,Per NRC Info Notice 89-017.Existing Monitoring of Battery Cells Provides Ample Advanced Notification of Need to Replace Cells	Provides Supplemental Info on Rev 0 to LER 92-003 Re Degradation in safety-related Battery Cells,Per NRC Info Notice 89-017.Existing Monitoring of Battery Cells Provides Ample Advanced Notification of Need to Replace Cells
05000298/LER-1992-004, :on 920210,Group 3 Isolation Occurred on High Reactor Water Cleanup Temp.Caused by Failure to Maintain Interim Corrective Actions.Operating Procedures Revised & Isolation Was Reset	on 920210,Group 3 Isolation Occurred on High Reactor Water Cleanup Temp.Caused by Failure to Maintain Interim Corrective Actions.Operating Procedures Revised & Isolation Was Reset	10 CFR 50.73(a)(2)(iv), System Actuation
05000298/LER-1992-005, :on 920325,RCIC Sys Declared Inoperable Due to Evidence of Water in Turbine Casing.Caused by Malfunctioning Turbine Exhaust Line Steam Trap.Steam Trap Removed & Cleaned & Internals Installed	on 920325,RCIC Sys Declared Inoperable Due to Evidence of Water in Turbine Casing.Caused by Malfunctioning Turbine Exhaust Line Steam Trap.Steam Trap Removed & Cleaned & Internals Installed
05000298/LER-1992-006, :on 920407,250-volt Battery Charger 1B Input Breaker Tripped.On 920408,250-volt Battery Charger 1A Tripped.Charger 1A Trip Due to Inadequate Preventive Maint. Relay K-3 Replaced & Calibr	on 920407,250-volt Battery Charger 1B Input Breaker Tripped.On 920408,250-volt Battery Charger 1A Tripped.Charger 1A Trip Due to Inadequate Preventive Maint. Relay K-3 Replaced & Calibr	10 CFR 50.73(a)(2)(1)
05000298/LER-1992-007, :on 920420,Shutdown Cooling Isolation Valves Automatically Closed.Caused by Void Formation & Collapse in RHR Lines.Pressure in Vessel Was Increased & Isolation Valve Opened	on 920420,Shutdown Cooling Isolation Valves Automatically Closed.Caused by Void Formation & Collapse in RHR Lines.Pressure in Vessel Was Increased & Isolation Valve Opened	10 CFR 50.73(a)(2)(iv), System Actuation
05000298/LER-1992-008, :on 920611,HPCI Sys Determined Inoperable When Pump Suction Valve from Torus Would Not Stroke Properly. Caused by Worn Bronze Stem Nut Internal Diameter Threads. Nut Replaced,Operator Reinstalled & Settings Adjusted	on 920611,HPCI Sys Determined Inoperable When Pump Suction Valve from Torus Would Not Stroke Properly. Caused by Worn Bronze Stem Nut Internal Diameter Threads. Nut Replaced,Operator Reinstalled & Settings Adjusted	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000298/LER-1992-008-01, :on 920611,HPCI Sys Discovered Inoperable Due to Stem Nut Wear of Mov.Worn Stem Nut Replaced.Independent Failure Evaluation of Stripped Stem Nut Being Performed.W/	on 920611,HPCI Sys Discovered Inoperable Due to Stem Nut Wear of Mov.Worn Stem Nut Replaced.Independent Failure Evaluation of Stripped Stem Nut Being Performed.W/
05000298/LER-1992-009, :on 920611,noncompliance w/10CFR50 App R, Failure of Post Fire Safe Shutdown Equipment Discovered. Caused by Inadequate Alternate Shutdown (ASD) Design Criteria.Asd Procedures Revised	on 920611,noncompliance w/10CFR50 App R, Failure of Post Fire Safe Shutdown Equipment Discovered. Caused by Inadequate Alternate Shutdown (ASD) Design Criteria.Asd Procedures Revised	10 CFR 50.73(a)(2)
05000298/LER-1992-010, :on 920621,during Performance of Surveillance Procedure CR HVAC Emergency Bypass Inlet Valve Failed to Actuate Correctly.Caused by Failure of Pneumatic Relay in Control Circuit.Temporary Mod Installed	on 920621,during Performance of Surveillance Procedure CR HVAC Emergency Bypass Inlet Valve Failed to Actuate Correctly.Caused by Failure of Pneumatic Relay in Control Circuit.Temporary Mod Installed	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000298/LER-1992-011, :on 920625,two Installations of Thermo-Lag 330 Fire Barrier Matl,Used to Provide 1 H Protection,Identified Per Review of NRC Bulletin 92-001.Caused by Inadequate Qualification Testing.Restoration Underway	on 920625,two Installations of Thermo-Lag 330 Fire Barrier Matl,Used to Provide 1 H Protection,Identified Per Review of NRC Bulletin 92-001.Caused by Inadequate Qualification Testing.Restoration Underway
05000298/LER-1992-012, :on 920715,RCIC Sys Declared Inoperable Due to Intrusion Into Motor Operator.Caused by Packing Leak & Defective Conduit Shield.Mov Motor Replaced.Conduit Will Be Replaced During 1993 Refuleing Outage	on 920715,RCIC Sys Declared Inoperable Due to Intrusion Into Motor Operator.Caused by Packing Leak & Defective Conduit Shield.Mov Motor Replaced.Conduit Will Be Replaced During 1993 Refuleing Outage	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000298/LER-1992-013, :on 920730,error Discovered in Limiting Single Failure Assumption for ECCS Performance Analysis.Analysis in 1976 Contained Erroneous Evaluation of Eccs.Plant Mods Will Be Made to Restore Validity of Previous Assumptions	on 920730,error Discovered in Limiting Single Failure Assumption for ECCS Performance Analysis.Analysis in 1976 Contained Erroneous Evaluation of Eccs.Plant Mods Will Be Made to Restore Validity of Previous Assumptions	10 CFR 50.73(a)(2)(i)
05000298/LER-1992-014, :on 920731,HPCI Sys Declared Inoperable Due to Severe Oil Leak from Diaphragm Area of Mechanical/Hydraulic Overspeed Trip Auto Reset Control Assembly.Valve Assembly Replaced & HPCI Sys Tested Satisfactorily & Returned to Svc	on 920731,HPCI Sys Declared Inoperable Due to Severe Oil Leak from Diaphragm Area of Mechanical/Hydraulic Overspeed Trip Auto Reset Control Assembly.Valve Assembly Replaced & HPCI Sys Tested Satisfactorily & Returned to Svc
05000298/LER-1992-015, :on 920911,RV Level Fell Below Low Level Setpoint Initiating Group 2,3 & 6 Isolations.Caused by Procedures Governing Normal Shutdown of Plant.Procedure Changes & Training Will Be Provided	on 920911,RV Level Fell Below Low Level Setpoint Initiating Group 2,3 & 6 Isolations.Caused by Procedures Governing Normal Shutdown of Plant.Procedure Changes & Training Will Be Provided	10 CFR 50.73(a)(2)(iv), System Actuation
05000298/LER-1992-016, :on 921001,identified Inadequate Isolation of DG 2 Differential Protection.Caused by Failure of Alternate Shutdown Design Review.Issued Change to Procedure for Operation of DG 2 from DG Room	on 921001,identified Inadequate Isolation of DG 2 Differential Protection.Caused by Failure of Alternate Shutdown Design Review.Issued Change to Procedure for Operation of DG 2 from DG Room	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1)
05000298/LER-1992-017, :on 921209,HPCI-MOV-MO058 Automatically Opened,Resulting in Closure of Pump Suction Valve from Emergency Condensate Storage Tank.Caused by Procedural Deficiency.Valves Realigned & Event Reviewed	on 921209,HPCI-MOV-MO058 Automatically Opened,Resulting in Closure of Pump Suction Valve from Emergency Condensate Storage Tank.Caused by Procedural Deficiency.Valves Realigned & Event Reviewed	10 CFR 50.73(a)(2)(iv), System Actuation
05000298/LER-1992-018, :on 921217,HPCI,RCIC & SLC Sys Declared Inoperable Due to Missed Insps of Pump Suction Piping.Caused by Lack of Scheduling Info for Class 3 Piping.Addl Enhancement Will Be Implemented for Program	on 921217,HPCI,RCIC & SLC Sys Declared Inoperable Due to Missed Insps of Pump Suction Piping.Caused by Lack of Scheduling Info for Class 3 Piping.Addl Enhancement Will Be Implemented for Program	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1)
05000298/LER-1992-019, Forwards Corrected LER 92-019-00,including Event Date Inadvertently Omitted from 930128 Memo	Forwards Corrected LER 92-019-00,including Event Date Inadvertently Omitted from 930128 Memo
05000298/LER-1992-019-01, :on 921230,design Deficiency W/Ac Electrical Sys Confirmed When Single Nonaccident Event Could Result in Common Mode Failure of Both Dgs.Permanent Electrical Jumper Installed in Each Breaker Trip Circuit	on 921230,design Deficiency W/Ac Electrical Sys Confirmed When Single Nonaccident Event Could Result in Common Mode Failure of Both Dgs.Permanent Electrical Jumper Installed in Each Breaker Trip Circuit	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000298/LER-1992-020, :on 920130,containment Level Instruments Were Removed & re-installed Without Being Declared Inoperable. Caused by Personnel Failure to Follow Procedures.Operators Retrained	on 920130,containment Level Instruments Were Removed & re-installed Without Being Declared Inoperable. Caused by Personnel Failure to Follow Procedures.Operators Retrained	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)

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