Forwards LER 80-033/03L-0
Person / Time
ML19340E127
Site:	Quad Cities
Issue date:	12/29/1980
From:	Kalivianakis N COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19340E128	List: 05000265/LER-1980-033, Forwards LER 80-033/03L-0 05000265/LER-1980-033-03, /03L-0:on 801201,RHR Sys II Supply from Diesel Generator Alarmed.Caused by Blown Fuse F11 Due to Grounded Wire in Unit 2 Diesel Generator to Bus 24-1 Circuit Breaker Auxiliary Contacts.Wire Repaired & Fuse Replaced
References
NJK-80-526, NUDOCS 8101060472
Download: ML19340E127 (1)
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LER-1980-033, Forwards LER 80-033/03L-0

Event date:
Report date:
2651980033R00 - NRC Website
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text

DSB Comm:nwealth Edison Cuad Cit.es Nuc ear Pcwer Station 22710 206 A.enue Ncrth Cerceva. in. nets 61242 Teleoncre 309 654-2241 NJK-80-526 December 29, 1980 J. Keppler, Regional Director Office of Inspection and Enforcement Region ill U. S. Nuclear Regulatory Commission 799 Rooseveit Road Glen Ellyn, IL 60137 Reference: Quad-Cities Nuclear Power Station Docket Number 50-265, DPR-30, Unit Two Appendix A, Sections 3.5.A.5. and 6.6.B.2.b.

Enclosed please find Reportable Occurrence Reoort Number R0 80-33/03L-0 for Quad-Cities Nuclear Power Station.

This report is submitted to you in accordance with the requirements of Technical Specification 6.6.B.2.b., as a condition leading to operation in a degraded mode permitted by a 1imiting condition for operation.

I Very truly yours, COMMON'nEALTH CDISON COMPANY l

j QUAD-CITIES NUCLEAR POWER STATION l

f6/'

/;), /,fLfkG'YW l

N. J. Kalivianakis Station Superintendent NJK:JRW/bb Enclosure cc R. F. Janecek N. Chrissotimos tjg '0 2 M A

Blot ooo 3

Ill 47 1

Licensee Event Report

Quad Cities

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		Reporting criterion
05000265/LER-1980-001, Forwards LER 80-001/03L-0	Forwards LER 80-001/03L-0
05000254/LER-1980-001, Forwards LER 80-001/03L-0	Forwards LER 80-001/03L-0
05000254/LER-1980-001-03, /03L-0:on 800111,while Performing Suppression Chamber to Drywell Pressure Separation Test,Differential Pressure Transmitter 1-8741-51 Was Not Indicating Properly. Caused by Personnel Error Due to Drawing Error	/03L-0:on 800111,while Performing Suppression Chamber to Drywell Pressure Separation Test,Differential Pressure Transmitter 1-8741-51 Was Not Indicating Properly. Caused by Personnel Error Due to Drawing Error
05000254/LER-1980-002, Forwards LER 80-002/03L-0	Forwards LER 80-002/03L-0
05000254/LER-1980-002-03, /03L-0:on 800111,while Performing in-place Charcoal Absorber Leak Rate Test on Standby Gas Treatment sys,1.93% Leakage Found.Caused by Damaged Gasket on 4x4 Inch Access Plate.Gasket Replaced	/03L-0:on 800111,while Performing in-place Charcoal Absorber Leak Rate Test on Standby Gas Treatment sys,1.93% Leakage Found.Caused by Damaged Gasket on 4x4 Inch Access Plate.Gasket Replaced
05000265/LER-1980-002, Forwards LER 80-002/03L-0	Forwards LER 80-002/03L-0
05000265/LER-1980-002-03, /03L-0:on 800108,while Leak Testing RHR Svc Water Vault Penetrations,Observed Leakage from Electrical Penetration P-12.Caused by Loose hold-down bolts.Hold-down Bolts Tightened & Penetration Retested Satisfactorily	/03L-0:on 800108,while Leak Testing RHR Svc Water Vault Penetrations,Observed Leakage from Electrical Penetration P-12.Caused by Loose hold-down bolts.Hold-down Bolts Tightened & Penetration Retested Satisfactorily
05000265/LER-1980-003, Forwards LER 80-003/03L-0	Forwards LER 80-003/03L-0
05000265/LER-1980-003-03, /03L-0:on 800213,while Performing Procedure Qis 35-2,reactor Bldg Ventilation Sys Would Not Reset After Test Isolation.Caused by Burnt CR 120 Relay.Relay 1705-105 Replaced & Functional Test Sucessfully Completed	/03L-0:on 800213,while Performing Procedure Qis 35-2,reactor Bldg Ventilation Sys Would Not Reset After Test Isolation.Caused by Burnt CR 120 Relay.Relay 1705-105 Replaced & Functional Test Sucessfully Completed
05000254/LER-1980-003, Forwards LER 80-003/03L-0	Forwards LER 80-003/03L-0
05000254/LER-1980-003-03, /03L-0:on 800206,while Performing Procedure Qos 1000-3,RHR to Suppression Chamber Dump Valve,Mo 1-1001- 36A,circuit Breaker Tripped Out.Caused by Burned Out 480/120-volt Transformer in Circuit Breaker Cabinet	/03L-0:on 800206,while Performing Procedure Qos 1000-3,RHR to Suppression Chamber Dump Valve,Mo 1-1001- 36A,circuit Breaker Tripped Out.Caused by Burned Out 480/120-volt Transformer in Circuit Breaker Cabinet
05000254/LER-1980-004-03, /03L-0:on 800215,while Performing Reactor low-low Water Level Calibr Test,Procedure QIS-11,level Switch LIS-1-263-72A Failed.Caused by Slight Misalignment of Mercury Wetted Magnetic Switch W/Actuating Magnet	/03L-0:on 800215,while Performing Reactor low-low Water Level Calibr Test,Procedure QIS-11,level Switch LIS-1-263-72A Failed.Caused by Slight Misalignment of Mercury Wetted Magnetic Switch W/Actuating Magnet
05000254/LER-1980-004, Forwards LER 80-004/03L-0	Forwards LER 80-004/03L-0
05000265/LER-1980-004, Forwards LER 80-004/03L-0	Forwards LER 80-004/03L-0
05000265/LER-1980-004-03, /03L-0:on 800219,while Performing Procedure Qms 700-1,automatic Blowdown Timer 287-105A Took 122-s to Time Out,Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Timer Adjusted & Verified to Be 100-s	/03L-0:on 800219,while Performing Procedure Qms 700-1,automatic Blowdown Timer 287-105A Took 122-s to Time Out,Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Timer Adjusted & Verified to Be 100-s
05000265/LER-1980-005, Forwards LER 80-005/03L-0	Forwards LER 80-005/03L-0
05000265/LER-1980-005-03, /03L-0:on 800303,while Performing LPCI & Containment Cooling Modes of Rhrs Logic test,5-s Delay Timer 10A-M2A for 1002B RHR Pump Failed to Actuate Relay K21A.Relay Failed to Energize.Caused by Microswitch Drift	/03L-0:on 800303,while Performing LPCI & Containment Cooling Modes of Rhrs Logic test,5-s Delay Timer 10A-M2A for 1002B RHR Pump Failed to Actuate Relay K21A.Relay Failed to Energize.Caused by Microswitch Drift
05000254/LER-1980-005-03, /03L-0:on 800224,while Performing Misv Closure Timing,Valve AD 1-203-1B Failed to Close When Control Switch Was Operated.Caused by Blockage of Exhaust Restrictor on on Pilot Valve.Exhaust Restrictor Cleaned	/03L-0:on 800224,while Performing Misv Closure Timing,Valve AD 1-203-1B Failed to Close When Control Switch Was Operated.Caused by Blockage of Exhaust Restrictor on on Pilot Valve.Exhaust Restrictor Cleaned
05000254/LER-1980-006-03, /03L-0:on 800222,while Doing Routine Panel Checks, Reactor Core Isolation Cooling Supply Valves Mo 1-1301-16 & 17 Were Found in Closed Position.Caused by Procedural Inadequacy & Personnel Performance.Procedures Revised	/03L-0:on 800222,while Doing Routine Panel Checks, Reactor Core Isolation Cooling Supply Valves Mo 1-1301-16 & 17 Were Found in Closed Position.Caused by Procedural Inadequacy & Personnel Performance.Procedures Revised
05000254/LER-1980-006, Forwards LER 80-006/03L-0	Forwards LER 80-006/03L-0
05000265/LER-1980-006-01, /01T-0:on 800308,while Performing Reactor Vessel Pressure Test,Several Crack Indications Were Discovered in Pipe to Elbow Welds.Cause Not Determined.Affected Pipe Sections Will Be Replaced W/Carbon Steel Piping	/01T-0:on 800308,while Performing Reactor Vessel Pressure Test,Several Crack Indications Were Discovered in Pipe to Elbow Welds.Cause Not Determined.Affected Pipe Sections Will Be Replaced W/Carbon Steel Piping
05000265/LER-1980-006, Forwards LER 80-006/01T-0	Forwards LER 80-006/01T-0
05000254/LER-1980-007-03, /03L-0:on 800308,while Performing Control Room Insp & Panel Check,B Main Steam Line Radiation Monitor Found Reading Low.Caused by Logarithmic Radiation Monitor Chassis Electronically Drifting Out of Calibr.Chassis Recalibr	/03L-0:on 800308,while Performing Control Room Insp & Panel Check,B Main Steam Line Radiation Monitor Found Reading Low.Caused by Logarithmic Radiation Monitor Chassis Electronically Drifting Out of Calibr.Chassis Recalibr
05000254/LER-1980-007, Forwards LER 80-007/03L-0	Forwards LER 80-007/03L-0
05000265/LER-1980-007-03, /03L-0:on 800316,while Ultrasonically Inspecting Jet Pump Fixture Beam Assemblies One Through 20,width-wise Crack Indication Discovered Along Upper Surface of Pump 16 Near Bolt.Caused by Intergranular Stress Corrosion	/03L-0:on 800316,while Ultrasonically Inspecting Jet Pump Fixture Beam Assemblies One Through 20,width-wise Crack Indication Discovered Along Upper Surface of Pump 16 Near Bolt.Caused by Intergranular Stress Corrosion
05000265/LER-1980-007, Forwards LER 80-007/03L-0	Forwards LER 80-007/03L-0
05000254/LER-1980-008-03, /03L-0:on 800308,after Performing Preventive maint,1/2 Diesel Generator Would Not Start from Control Room.Caused by Poor Electrical Contact Between Fuse & Clip. Fuse Clip Adjusted	/03L-0:on 800308,after Performing Preventive maint,1/2 Diesel Generator Would Not Start from Control Room.Caused by Poor Electrical Contact Between Fuse & Clip. Fuse Clip Adjusted
05000265/LER-1980-008-03, /03L-0:on 800305,while Performing LPCI & Containment Cooling Modes,Two 5-S Delay Timers for Starting 1002D RHR Pump Failed to Actuate Timer Contacts.Caused by Microswitch Arm Being Out of Alignment	/03L-0:on 800305,while Performing LPCI & Containment Cooling Modes,Two 5-S Delay Timers for Starting 1002D RHR Pump Failed to Actuate Timer Contacts.Caused by Microswitch Arm Being Out of Alignment
05000265/LER-1980-008, Forwards LER 80-008/03L-0	Forwards LER 80-008/03L-0
05000254/LER-1980-008, Forwards LER 80-008/03L-0	Forwards LER 80-008/03L-0
05000265/LER-1980-009-03, /03L-0:on 800322,while Performing Pci Simulated Automatic Closure Initiation Test,Procedure Qos 1600-13, Transient in-core Probe 2,failed to Respond to Group 2 Isolation Signal.Caused by Dirty Contacts on Relay K21	/03L-0:on 800322,while Performing Pci Simulated Automatic Closure Initiation Test,Procedure Qos 1600-13, Transient in-core Probe 2,failed to Respond to Group 2 Isolation Signal.Caused by Dirty Contacts on Relay K21
05000265/LER-1980-009, Forwards LER 80-009/03L-0	Forwards LER 80-009/03L-0
05000254/LER-1980-009-03, /03L-0:on 800410,while Performing Motor Operated Valve Operability Test,Thermal Overload Relay for B-loop Suppression Chamber Cooling Valve Tripped.Caused by High Motor Starting Currents.Torque Switch Adjusted	/03L-0:on 800410,while Performing Motor Operated Valve Operability Test,Thermal Overload Relay for B-loop Suppression Chamber Cooling Valve Tripped.Caused by High Motor Starting Currents.Torque Switch Adjusted
05000254/LER-1980-009, Forwards LER 80-009/03L-0	Forwards LER 80-009/03L-0
05000254/LER-1980-010-03, /03L-0:on 800423,while Performing Loss of Electrohydraulic Control Fluid Pressure Scram Surveillance, Pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Limit. Caused by Instrument Setpoint Drift.Switch Adjusted	/03L-0:on 800423,while Performing Loss of Electrohydraulic Control Fluid Pressure Scram Surveillance, Pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Limit. Caused by Instrument Setpoint Drift.Switch Adjusted
05000254/LER-1980-010, Forwards LER 80-010/03L-0	Forwards LER 80-010/03L-0
05000265/LER-1980-010-03, /03L-0:on 800517,while Performing Quartlerly MSIV Closure Timing Surveillance Procedure Qos 250-4,MSIV AO 2-203-1C Closed in 2.5-s & MSIV AO 2-203-2D Closed in 9.1-s. Caused by Equipment Failure.Speed Control Valves Adjusted	/03L-0:on 800517,while Performing Quartlerly MSIV Closure Timing Surveillance Procedure Qos 250-4,MSIV AO 2-203-1C Closed in 2.5-s & MSIV AO 2-203-2D Closed in 9.1-s. Caused by Equipment Failure.Speed Control Valves Adjusted
05000265/LER-1980-010, Forwards LER 80-010/03L-0	Forwards LER 80-010/03L-0
05000265/LER-1980-011-03, /03L-0:on 800420,while Performing Manual Operation of Relief Valves,Valve 2-203-3C Failed to Open.Caused by Component Failure Due to Excessive Solenoid Plunger to Pilot Valve Stem Clearance	/03L-0:on 800420,while Performing Manual Operation of Relief Valves,Valve 2-203-3C Failed to Open.Caused by Component Failure Due to Excessive Solenoid Plunger to Pilot Valve Stem Clearance
05000265/LER-1980-011, Forwards LER 80-011/03L-0	Forwards LER 80-011/03L-0
05000254/LER-1980-011-03, /03L-0:on 800429,main Feed Breaker to MCC 19-1 Tripped.Caused by Excessive Current Trip Time Which Allowed phase-to-phase Short Internal to Be Carried Back to MCC 19-1.Motor & Circuit Breaker Replaced	/03L-0:on 800429,main Feed Breaker to MCC 19-1 Tripped.Caused by Excessive Current Trip Time Which Allowed phase-to-phase Short Internal to Be Carried Back to MCC 19-1.Motor & Circuit Breaker Replaced
05000254/LER-1980-011, Forwards LER 80-011/03L-0	Forwards LER 80-011/03L-0
05000254/LER-1980-012, Forwards LER 80-012/03L-0	Forwards LER 80-012/03L-0
05000265/LER-1980-012-03, /03L-0:on 800428,reactor Water Conductivity Exceeded 10 Umhos/Cm Tech Spec Limit.Caused by Depleted Demineralizers.Unit Shutdown Initiated.Demineralizers Regenerated & Low Conductivity Coolant Added to Reactor	/03L-0:on 800428,reactor Water Conductivity Exceeded 10 Umhos/Cm Tech Spec Limit.Caused by Depleted Demineralizers.Unit Shutdown Initiated.Demineralizers Regenerated & Low Conductivity Coolant Added to Reactor
05000254/LER-1980-012-03, /03L-0:on 800429,reactor Recirculation Motor Generator Set 1A Tripped Due to Low Oil Pressure from Lube Oil Pump 1A1 Trip.Possibly Caused by Contractor Personnel Dropping Matl on Generator Set Control Cabinet	/03L-0:on 800429,reactor Recirculation Motor Generator Set 1A Tripped Due to Low Oil Pressure from Lube Oil Pump 1A1 Trip.Possibly Caused by Contractor Personnel Dropping Matl on Generator Set Control Cabinet
05000265/LER-1980-012, Forwards LER 80-012/03L-0	Forwards LER 80-012/03L-0
05000254/LER-1980-013-03, /03L-0:on 800415,while Performing High,Low & low-low Reactor Water Level Functional Test,Procedure Qis 10-1,reactor Water Level Switch LIS-1-263-57A Was Found to Trip Below Tech Spec Limit.Caused by Instrument Drift	/03L-0:on 800415,while Performing High,Low & low-low Reactor Water Level Functional Test,Procedure Qis 10-1,reactor Water Level Switch LIS-1-263-57A Was Found to Trip Below Tech Spec Limit.Caused by Instrument Drift
05000265/LER-1980-013, Forwards LER 80-013/03L-0	Forwards LER 80-013/03L-0
05000254/LER-1980-013, Forwards LER 80-013/03L-0	Forwards LER 80-013/03L-0
05000265/LER-1980-013-03, /03L-0:on 800428,while Performing LPCI Motor Operated Valve Operability Test & RHR to Suppression Chamber Test,Cooling Valve Mo 2-1001-36A Failed to Close.Caused by Binding of Plunger Arm on Auxiliary Interlock Contacts	/03L-0:on 800428,while Performing LPCI Motor Operated Valve Operability Test & RHR to Suppression Chamber Test,Cooling Valve Mo 2-1001-36A Failed to Close.Caused by Binding of Plunger Arm on Auxiliary Interlock Contacts
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05000265/LER-1980-033, Forwards LER 80-033/03L-0

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