LER-1980-025, /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 |
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U. S. tiUCLE AN REGOLAT@CW CO%%ilsFord NRC FORM 3GG (7 77)
LICENSEE EVENT REPORT
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8 63 63 OOCKET NUveER 68 69 EVENT DATE 74 75 REPORT DATE to EVENT DESCRIPTION AND PROSABLE CONSEQUENCES h [TITl I (NP-33-80-35) on 3/30/80 at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />. Control Rod Group 5, Rod 11 absolute position l lo t a l l indication (API) was declared iaoperable due to fluctuating signals which caused num-l [ol4llerous " asymmetric rod" alarms. This placed the unit in the sction state =ent of T.S.
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The rod position was verified at its 100% withdrawn position per the action l [o TTl I statement and the red positten indication was placed in asymmetric-bypass. There was I The rod did I
g l no danger to the health and safety of the public or station personnel.
not vary from its intended position, only the API was faulty.
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34 36 3s 40 43 42 43 to 47 33 CAUSE DESCRIPTION AND CCRRECTIVE ACTIONS h i o lInvestigation has revealed'the apparent cause to be defective API reed switch assem-I to I
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A new "R4C" API system with g lwhich the assemblies and their cables were subjected.
j y Ibuilt in channel redundancy and new high temperature API cables was installed under I
IFacil'.ty Change R.,uest'79-413.
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR PCUER STATION UNIT ONE SUPPLEMENTAL INFO?.MATION FOR LER NP-33-80-35 DATE OF EVENT: March 30, 1980 FACILITY: Davis-Besse Unit 1 IDENIIFICATION OF OCCURRENCE:
Fluctuating indication on the absolute position indica-tion (AP1) for Control Rod Group 5-11 Conditions Prior to Occurrence: The unit was in Mode 1, with Power (M'4T) = 305 and Load (Gross L'E) = 0.
Description of Occurrence: On March 30, 1980 at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />, Control Rod Group 5, Rod 11 API was declared inoperable due to fluctuating signals which caused numerous "asy=-
retric rod" alarna. This placed the unit in the action statement of Technical Speci-fication 3.1.3.3 which requires the position of the control cod and its group be prriodically verified and maintained at one of the zone reference positions. The rod position was verified at its 100% withdrawn position per the action statement, and the rod position indfeation was placed in asy=netric bypass.
Designatien of Apparent Cause
- Occurrence: After several months of collecting data on control rod 5-11, the apparent cause has been determined to be defective API reed switch essemblics. A rajor contributing cause to this failure is the excessive temperatures to 1
which the asse blies and tneir cables were subjected. This occurred during several months of operation in which the head assembly cooling fans were not in operation due to d:ficient procedure which s11cwed restart following the 1978 outage without reconnecting cooling fan power cablec. The Reactor Vessel Closure Head Removal and Replacement Pro-c dure, SP 1504.01, was corrected.
Analysis of Occurrence:
There was no danger to the health and safety of the public or to station personnel. The rod did not vary fror its intended position, only the API was f aulty.
Corrective Action
During the last shutdown in March, 1980, a seccion of the position indication (PI) cable was replaced from the top of the PI assembly to the bulk 1: cad for Control Rod Group 5 Rod 11.
This was acco=plished under Maintenance Work Order 80-1930, cnd done as a continuing corrective action for the similar occurrences reported under the previous Licensee Event Reports NP-33-79-141, NP-33-80-07, and NP-33-80-21.
As a result of the investigation, it vaa determined that the reed switch asse=blies of the present "C" style API systen would have to be replaced. A new "R4C" API system was 1
installed under Facility Change Request 79-413.
This systen features built in channel redundancy and new high tenperature API cables.
8 LER #80-025 I
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4 TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-80-35 Failure Data: There have been previous failures of control rod APIS.
Control Rod Group 5 Rod 11's current symptoms were reported in Licensee Event Reports NP-33-79-141 (79-116), NP-33-80-07 (80-004), and NP-33-80-21(60-015).
LER #80-025 9
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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. 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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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