LER-1980-063, /03L-1:on 800823,safety Features Actuation Sys Indication Panel for Damper HV5442 Was Inoperable.Caused by Blown Fuse in Control Circuit.Fuse Replaced & Sys Returned to Svc |
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| 3461980063R03 - NRC Website |
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' O S. NUCLEAR CEIULAT!RY COMMISSION FORM '366
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. LICENSEE EVENT REPORT 2
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hEPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h thej FoTil l '(NP-33-80-75)' On 8/23/80. at. 0230' hours, the control room operator' discovered that i
o l' indicating-lights on'the' Safety Features Actuation System indication panel for damper l t
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- ]: HV5442 were out.
The' disconnect switch and supply breaker were checked and attempts -]
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'l There was nc l J o ja ; -l Sode 5, the/ station did not enter the action statement of T.S. 3.6.5.1.
- - l ' danger to the public orl station personnel. This event is being reported to document I
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..IoIsI l a component'fallure.
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CODE- ? S SC E COMPONENT CODE '
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42 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h -
40-J1g ] The cause was the random' failure of a fuse in the control circuit for HV5442. - Af ter l
dec:aring HV5442' inoperable,- the ' supply breaker was ' opened failing-HV5442 in - the l
~3TT'n I I
y,,,y l. closed position..Under Maintenance Work Order 80-3053, the blown fuse was discovered l g -l and replaced.' ' Af ter closing the supply breaker, indication of damper -position returnell.
1 l, gg ] Damper HV5442 was declared. operable at 1300. hours on 8/25/80.
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SUPPLEMENTAL"INFORMATION~FOR LER NP-33-80-75
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':i ' <., DATE OF'EVENTi :Augustl 23,;1980o FACILITY:1 Davis-Besse ' Unit 1:
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IIDEN11FICATION OF-OCCURRENCE: Damper HV5442 Inoperable The; unit;was!in:Modej5withPowerj(MRT).=i0andQu,(_,..
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iConditions Prior to Oscurrencei" 5
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.. At:0230 hours;ot0Aupst 23f.1980;[thd control:raou ope.ra c
- - f Description of Occurrence:
^ tor discovernd.that theitndicatin fif6hE W.igthm safety Neatures Act6atiss uyarem,"
[jdf (SFAS) indicdimif p'ashl :.for dampephf >6 Cyd dcift.f HV54423rovides part of -tdiso?!)O [lf
- - lation fori hh 'non1Q.ve'ntilation pipisg. pasing,, through"ECCS Robe--No.::ll5.
Th M ilio-/;j, "
t lat' ion would ;bd'. F :quiredlin'tliesvat of c.t br%akt n"thaE [pi ying:khich57 oui l.RhErlij s7 2 i
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- pre. vent; the emergenby vent'ilation 'sydem from siistaining an
- adequate.negggpres-Qf sure in the roomP 'A"checklof: the dit.corni>c[rvitch ?hnd ~ supply ; break'er reveale? ncitH i '
JmalLeonditions.ahd attempts toL stioke the va'lve locally'.and f remotely were unsuccess'-
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'ful; soEdamper HV5442 was declared inoperable'. :Being inl Mode-5',"the station'did not
'1 enter the action statement @f Technical Specification 3.6.5.1..
The technical-speci-'
.ficaL10s requires two operable emsrgency ventilation systems in Modes 1,~ 2, 3,.and 4.
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. This event.is' being(reported : to document. a component f ailure'. ;
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Designation-of Apparent Cause of-' Occurrence: The apparent cause of the occurrence was
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the random fallure of: a' fuse in' the control circuit for HV5442.
- 1 Analysis of' Occurrence
- . There was no danger to the health and safety of-the public or to: station personnel. TheJemergency ventilation system does not'have to be operable in Mode.~5.
e
. After ' declaring H' V5442 inoperable, the supply breaker was opene d
i
..Corrective' Action:
failing HV5442 in. the closed position, whichtis :the required position Lin the event t 1
- - an SFASl signal.. Troubleshooting commenced-under Maintenance Work Order 80-3053 on
- August 25,11980. :A blownffuse was discovered 11n the control. circuit and was replaced.
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The maintenance vasLeompleted at 104T hours en August 25, 1980. After closing the, i
. supply breaker;Lindication of damper position returned and the damper was cycled
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1sev,eralftimes to" demonstrate operability.' 1 Damper HV5442 was. officially declared 11 :
m Loperableat'-1300 hours on August;25, 1980.:
.' Failure Data: iThere:has been-no other ~ incident where a similar component was declared 4 inoperable;due?to:a. blown (fuses
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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. 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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. 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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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