LER-1980-031, /01T-0:on 801116,reactor Core Isolation Cooling Discharge Isolation Valve MO-2-1301-49 Would Not Open from Control Room.Caused by Faulty Torque Switch.Torque & Limit Switches Cleaned,Checked & Exercised |
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| 2651980031R01 - NRC Website |
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U.S. NUCLEAR REGULATORY CU&tMiniUN NRC FORM 366 (7 77; LICENSEE EVENT REPORT CONTRGL BLOCK: l l
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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h During the performance of QOS 1300-3 RCIC Motor Operated Valve Operability Test, l
- 3,;j l the RCIC discharge isolation valve M0-2-1301-49 would not open from the Control l
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, l Room. This caused RCIC to be inoperable. Also, while demonstrating HPCI l
gg., l operability, per Technical Specification 3.5.E.2., it was also found inoperable due l g;;E, ;
to an oil leak. An orderly shutdown was initiated. Automatic Blowdown, LPCI, and l
g;,e ; l l33-ll Core Spray were available as back up systems.
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CAUSE
CAUSE COMP.
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3J 34 Ja 36 31 40 41 42 43 44 17 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 l t21I Upon examination. a faulty torcue switch was found on valv,= MO-9 !301-49.
The I
torque switch was replaced and the limit switch on the operator was cleaned and 1
j: ; ; j checked for proper operation. The valve was exercised satisfactorily three times
,,,-jl and RCIC was demonstrated operable before the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reactor shutdown requirement l
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% POWER OTHER STATUS ISCO RY DISCOVCRY OESCRIPTION NA l
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309-654-2241, ext. 176 PHONE:
N ANTE OF PREPARER
1.
LER NUMBEn:
80-31/0lT-0 ll.
LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station Ill.
FACILITY NAME: Unit Two IV.
DOCKET NUMBER: 050-265 V.
EVENT DESCRIPTION
On November 16, 1980, at 0030, during the routine monthly performance of QOS 1300-3, (RCIC Motor Operated Valve Operability Test), as required by Technica l Speci fications 4. 5.E.1. and 4.3. A. I.d., it was discovered that MO-2-1301-49, RCIC Discharge isolation to the Reactor Feedwater System, would not open from the Control Room. This caused RCIC to be inoperable.
VI.
PROBABLE CONSEQUENCES OF THE OCCURRENCE:
Per Technical Specification 3.5.E.2. continued reactor operation without RCIC availability is allowed for seven days, if all active components of HPCI are operable. Action was taken to verify HPC! availability by the performance of QOS 2300-2 and, QOS 2300-3, HPCI Pump Operability Test and HPCI Motor Operated Valve Operability Test.
Generator load was reduced to 400 MWe for repair cf M0-2-1301-49 While running HPCI, annunciator 902-3-G-10, HPCI Hi/Lo Oil Level, alarmed. This eventually led to HPCI being declared inoperable due to an oil leak in the HPCI Turbine Stop Valve.
Since RCIC was also inoperable, per Technical Specification 3.5.E.3., an orderly shutdown was initiated to bring the reactor pressure to less than 90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if HPCI remained inoperable.
RCIC was returned to service at 1020 and HPCI at 1145 The reactor was returned to normal operation and load was increased at 1340 on 11-16-80.
At all times the unit was operated within the boundaries of the Technical Specifications. The availability of normal feedwater, Automatic Blowdown, LPCI, and Core Spray gives adequate safety protection in the case of this temocrary loss of the RClC and HPCI systems.
Vll.
CAUSE
After examining the MO-2-1301-49 valve and its motor operator, it was found to be a faul ty torque swi tch on the Limitorque Model SMB-000 operator that caused the valve to fall to open.
Vill. CORRECTIVE ACTION:
The torque switch was replaced, and the limit switches on the operator were checked for proper adjustment and their contacts were cleaned.
M0-2-1301-49 was exercised three times at 1020 on November 16, 1980, and QoS 1300-2 (RCIC Pump Operability) was completed.
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| 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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