LER-1980-072, /03L-0:on 801002,during Testing,Smoke Noted Issuing from Valve Operator Motor on CV5011E,air Sample Return Inlet Valve to Containment.Caused by Component Failure in Valve.New Parts Installed |
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U. S. NUCLEAR REGULATORY COMMISSION NRC FGAM 366 (121)
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8 60 61 DOCKET NUMSER 68 63 EV ENT CATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l 0 l 2 l l (NP-33-80-90) On October 2, 1980 at 0625 hours0.00723 days <br />0.174 hours <br />0.00103 weeks <br />2.378125e-4 months <br /> during the performance of surveillance l l013 l 1 test'ing, the local observer noticed smoke issuing from the valve operator motor on l
Power was removed from thel 10141 l CV5011E, the air sample return inlet
loIslivalve operator.
The valve could not be manually stroked.
It was declared inoperable.l 1016 l l Being in Mode 5, the station did not enter the action statement of T.S. 3.6.3.1.
Therq l 0 l 71 l vas no danger to the public or station personnel. The air sample line into contain-l l
FO i s l l ment was isolated by closing CV341 and CV205.
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40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS failure in the valve. The spindle l Itl0ll The cause of the motor overheating was a component [i li l 1 had broken away from the compression disc. As the motor turned the spindle, the disc i
,,,,,l Jammed and would not turn. Under BM0 80-3341 a temporary repair was made by welding ths l broken parts together. Two days later new parts were received and under FM0 80-3350, l g,,,,gl they were installed. On 10/3/80 and again on 10/5/80, CV5011E was declared operable. l 7-6 9 ST S
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-90 DATE OF EVENT: October 2, 1980
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FACILITY:
Dcvis-Besse Unit 1 IDENTIFICATION OF OLCURRENCE: Failure of CV50llE, the air sample return inlet valve to containment
, Conditions Prior to Occurrence: The unit was in Pode 5 with Power (MWT) = 0 and Load (Gross MWE) = 0.
Description of Occurrence: On October 2, 1980 at 0625 hours0.00723 days <br />0.174 hours <br />0.00103 weeks <br />2.378125e-4 months <br /> during the performance of the Miscellaneous Valves Quarterly Test, ST 5099.08, the local observer noticed smoke issuing from the valve operator motor on CV50llE, the air sample return inlet valve to containment. Power was removed from the valve operator.
An attempt was made to manu-ally close the valve but it would not move. The valve was isolated by closing CV341 and CV205.
Being in Mode 5, the station did not enter the action statement of Technical Specifica-tion 3.6.3.1, which requires the containment isolation valve to be operable in Modes 1, 2, 3, and 4.
This event is being reported to document a component, failure.
Designation of Apparent Cause of Occurrence: The cause of the failure was component failure in the valve.
The compression disc broke off the spindle.
During proper opera-tion, the compressor is firmly mounted on the spindle. When the spindle is turned and travels inward, it pushes the compressor against the diaphragm material which in turn seals the normal flowpath through the valve. With the spindle loose from the compres-sion disc, the valve was jammed and caused the motor winding to fail. There is no overload cutout of this motor by design since during an emergency it is more desirable to have the motor fail trying to open rather than cutout and leave the valve failed out of position.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. CV5011E is not required to be operable in Mode 5.
Corrective Action
Under Maintenance Work Order (MWO) 80-3341 the valve was temporari-ly repaired by welding the compressor to the spindle.
The failed motor and wiring were replaced.
The requirements of ST 5099.08 were met on October 3, 1980 and CV5011E wcs declared operable.
On October 5, 1980 under MWo 80-3350 new parts were received and installed to replace the welded parts.
Containment Isolation Valves Post Maintenance Test ST 5064.01 was successfully completed and CV5011E again declared operable.
The valve vendor has been contteted to help determine the cause of the disc breaking off of the spindle.
LER #80-072
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-90 PAGE 2 Failure Data: There have been no previous similar reportable occurrences.
LER #80-072 s
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| 05000346/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000346/LER-1980-001-01, /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | /01T-0:on 800103,during Plant Heatup,Safety Features Actuation Sys Channels 1 & 3 Tripped at 1,600 Psig, Causing Level 2 Actuation.Operators Correctly Tripped Reactor Coolant Pumps.Caused by Procedural Deficiency | | | 05000346/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000346/LER-1980-002-03, /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | /03L-0:on 800103,after Actuating of Safety Features Actuation Sys Level 2,demin Water Valve DW68318 Did Not Indicate Closed & Monitor Light Did Not Indicate Properly.Caused by Maladjusted Position Indicator Switch | | | 05000346/LER-1980-003-03, /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | /03L-0:on 800103,during Auxiliary Feedwater Pump Test,Pump l-1 Was Declared Inoperable.Caused by Improperly Adjusted Slip Clutch Between Governor Manual Speed Adjustment Shaft & Remotely Controlled Speed Changer Motion | | | 05000346/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000346/LER-1980-004-03, /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | /03L-0:on 800107,control Rod 5-11 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals.Possibly Caused by Isolation of Position Indication Cabling & Electrical Penetration | | | 05000346/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000346/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000346/LER-1980-005-03, /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | /03L-0:on 800110,Tech Spec Late Date Passed W/O Performance of Boric Acid Flowpath Heat Tracing Weekly Test. Caused by Known Deficiency in Design of Sys Resulting in Inability to Maintain Min Temp Necessary During Startup | | | 05000346/LER-1980-006-03, /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | /03L-0:on 800112,found Fiberglass Insulation Stuffed Into Open Wall Ventilator Between Water Treatment Bldg & Svc Water Valve Room,Causing Fire Damper to Be Inoperable.Figerglass Removed | | | 05000346/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000346/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000346/LER-1980-007-03, /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | /03L-0:on 800116,ref Position Verification for Group 5,rod 11,was Made 1-h & 40 Minutes Late.Caused by Operator Oversight Due to Lack of Adequate Reminder Sys. Multiple Timer Sys Will Prevent Recurrence | | | 05000346/LER-1980-008-03, Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | Gap Discovered in Wall Where Five two-inch Conduits Go from Electrical Penetration Room 2 to Cable room.Six-inch Gap Around Ventilation Duct Also Found.Caused by Improper Initial Installation | | | 05000346/LER-1980-008, Forwards Revised LER 80-008/03L-1 | Forwards Revised LER 80-008/03L-1 | | | 05000346/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000346/LER-1980-009-03, /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | /03L-0:on 800122,discovered That NI-7 Indication on Computer Group 38 Was Reading Less than Heat Balance Power,Putting NI-7 Below Instrumentation Operability Limit Line.Caused by Extremely Tight Calibr Band at 100% Power | | | 05000346/LER-1980-010-01, /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | /01T-0:on 800214,reanalysis of RCS Pipe Restraints Per IE Insp Rept 50-346/79-23 Revealed Design Deficiency on Two Reactor Coolant Hot Leg Pipe Whip Restraints at Top of Each RCS Hot Leg.Caused by Design Error | | | 05000346/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000346/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000346/LER-1980-011-03, /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | /03L-0:on 800131,during Normal Operation, Operations Personnel Received Half Trip on Steam & Feedwater Rupture Control Sys Channels 1/3.Caused by Spurious Trip from +25 Volt Dc Power Supply PS03 in Sglic Channel 1 | | | 05000346/LER-1980-012-03, /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Reposition | /03L-0:on 800201,operator Noticed Loss of Control Room Position Indication for Letdown Cooler Isolation Valve MU2A.Caused by Design Deficiency.Apparently,Someone Brushed Up Against Disconnect Breaker Switch.Switch Repositioned | | | 05000346/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000346/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000346/LER-1980-013-03, /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel | | | 05000346/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000346/LER-1980-014-03, /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | /03L-0:on 800208,pressurizer Sample Sys Containment Isolation Valve RC240B Failed to Close Twice. Caused by Improper Torque Switch Setting & Stripped Screw on Closing Contactor.Settings Readjusted & Switch Replaced | | | 05000346/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000346/LER-1980-015-03, /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | /03L-0:on 800210,during Normal Startup,Control Rod 5-11 Absolute Position Indication Declared Inoperable.Caused by Numerous Asymmetric Rod Alarms.Data from Current Failure Evaluated | | | 05000346/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000346/LER-1980-016-03, /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | /03L-0:on 800213,while Reviewing Station Log,Shift Foreman Discovered That Containment Airlock Seal Leakage Test Had Not Been Performed After Last Entry Into Containment During Startup.Caused by Procedural Inadequacy | | | 05000346/LER-1980-017-03, /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | /03L-0:on 800217,operations Personnel Noted That Safety Features Actuation Sys Channel 3 Borated Water Storage Tank Level Indication Was Six Feet Higher than Other Meters.Caused by Freezing of Transmitter Sensing Line | | | 05000346/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000346/LER-1980-018-03, /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | /03L-0:on 800226,safety Features Actuation Sys Channel 3 Borated Water Storatge Tank Level Indication Was Discovered Reading Four Feet Higher than Other Three Channels.Caused by Inadequate Design of Freeze Protection | | | 05000346/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000346/LER-1980-019, Forwards LER 80-019/01T-0 | Forwards LER 80-019/01T-0 | | | 05000346/LER-1980-019-01, /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | /01T-0:on 800325 Reactor Flux/Flow Trip Setpoints Were Not Verified to Be Properly Reset within 4-h of Manual Shutdown of Rcp.Caused by Attention Given to Feedwater Swings.Trip Setpoints Verified Later | | | 05000346/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000346/LER-1980-020-03, /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | /03L-0:on 800306,control Operator Noted No Control Room Indication for Containment Vacuum Relief Isolation Valve CV5072.Caused by Breaker BE1139 Being Closed,Probably Resulting from Someone Bumping Into Breaker | | | 05000346/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000346/LER-1980-021-03, /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | /03L-0:on 800313,during Diesel Fire Protection Pump Weekly Test,Pump Could Not Be Stopped W/Control Button. Once Stopped,Pump Could Not Be Started.Cause Not Determined by Scheme Check.Retrial of Pump Proved Successful | | | 05000346/LER-1980-022-03, /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | /03L-0:on 800317,operations Personnel Noticed Loss of Control Room Indication for Containment Dihydrogen Analyzer 2 Discharge Line Valve CV5010E.Caused by Const Personnel Accidentally Opening Breaker | | | 05000346/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000346/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000346/LER-1980-023-03, /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | /03L-0:on 800327,discovered That Control Rod Groups 3 & 4 Were Moving in on Their Own.Group 3 Was 0% Withdrawn.Group 4 Was 90% Withdrawn.Caused by Component Failure.Component Replaced | | | 05000346/LER-1980-024-03, /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | /03L-0:on 800327,following Normally Initiated Reactor Trip,Auxiliary Feed Pump Turbine 1-2 Main Steam Isolation Valve MS-107 Closed.Cause Unknown.Further Investigation of Valve & Operator Will Be Pursued | | | 05000346/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000346/LER-1980-025-03, /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | /03X-1:on 800330,control Rod Group 5,rod 11 Absolute Position Indication Declared Inoperable.Caused by Fluctuating Signals Resulting in Numerous Asymmetric Rod Alarms Due to Defective Reed Switch Assemblies | | | 05000346/LER-1980-025, Forwards LER 80-025/03X-1 | Forwards LER 80-025/03X-1 | |
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