LER-1979-100, /03L-0:on 791014,group 7,rod 7 Absolute Position Indication Showed Asymmetric W/O Clearing.Caused by Power Supply Cable.Cable Replaced W/High Temp Cable.Rebuilt Position Indicator Tube Installed |
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| 3461979100R03 - NRC Website |
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NRC FORM 36G (7 77)
LICENSEE EVENT REPORT CONTROL BLOCK: l l
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7 8 9 LICENSEE CODE 14 15 LICENSE NUMt$LH 2h 26 LICENSE TYPE JO 51 CAT 66 CON'T S$n"d lL l@l 0l 5 l 0 l -l 0 l 3 l 4 ] 6 @l 110 l l l 4 l 7 ] 9 ]@l 1 l 1 l 0 l 9 l 0 i 7
8 60 61 DOCKET NUUUER t,d bJ EVENT DATE 14 75 REPORT D ATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l On October 14, 1979 at 1638 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.23259e-4 months <br />, croup 7 rod 7 Absolute Position Indication (API) l
_ l o l 3 l l indicated asymmetric for a period of two minutes, cleared, and again indicated asym-l metric for a period of four minutes and did not clear.
This placed the unit in the l
o 4 l Action Statement of Technical Specification 3.1.3.3.
Unit power was reduced to 60%
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_ l 016 I l and the high_ flux _setpo_ int _r_gduced to 70L There was no danger to the health and o 7 I safety of the public or stalion_ personnel. The Relative Position Indicators and i
j o is l l zcue reference indication were operable.
(NP-33-79-116) l SYSTEM
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[ li l o l l The problem appears to be in the cable which supplies power to the API and returns the[
l signal to the position indication panels. Under Maintenance Work Order 79-3229, the !
i i cable was replaced with a new high temperature cable and a rebuilt PI tube was instal-1
, 7 1ed.
Investigation of recurring API problems continues.
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.DVR 79-150 NAME OF PREPARER PHONE:
4 TOLEDO EDISON COM ANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-116 DATE OF EVENT: October 14, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Group 7 Rod 7 Absolute Position Indication inoperable due to repeated asy= metric alarms Conditions Prior to Occurrence:
The unit was in Mode 1, with Power (MWT) = 2772, and Load (Gross rie) = 923.
Description of Occurrence: On October 14, 1979 at 1638 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.23259e-4 months <br />, Group 7 Rod 7 Absolute Position Indication (API) indicated asymmetric for a period of two minutes, cleared, The and again indicated asy= metric for a period of four minutes and did not clear.
API for Rod 7 of Group 7 was declared inoperable. This placed the unit in the Action Statement of Technical Specification 3.1.3.3 which recuires all regulating control rod API and relative position indications (RPI) be operable and capable of determining
- - the control rod positions within + 6.5% in Mode 1.
The unit power was reduced to 60% and the high flux setpoint was reduced to 70%. The RPI and zone reference indication were operable while the API was inoperable.
Designation of Apparent Cause of Occurrence: The apparent cause of the occurrence appears to be in the cable which supplies power to the API and returns the signal to the position indication panels. During a previous shutdown, the position indicator tube for Rod 7-7 was replaced and the old tube sent to Diamond Power, the PI tube vendor. Their investigation of the tubes sent back was that the PI tubes had exper-ienced a high temperature condition above its rating. This probably occurred when the ventilation f ans for the head were not operating at an earlier date.
Analysis of Occurrence: There was no danger to the health and safety of the public or station personnel. The relative position indication and zone reference indication for the rod was operating and the group position indicator was indicating properly while the API channel was inoperable.
Corrective Action
Under Maintenance Work Order (MWO) 79-3229, the cable from the bulkhead to the reactor head was changed for Rod 7-7 with a new high temperature cable, and a partially rebuilt PI tube was installed.
Since the unit has returned to power, the API has been operable. The station and Babcock and Wilcox are investigating several permanent corrective actions for the replacement of cables and PI tubes.
Procedure modifications to SP 1105.09 have been incorporated to assure that service structure ventilation f ans are in service during final walkdown.
Failure Data: Previous API failures were reported in Licensee Event Reports NP-33-77-63, UP-33-78-144, NP-33-78-149, NP-33-79-31, NP-33-79-90, NP-33-79-97, and NP-33-79-100.
1341 347 LER #79-100
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| 05000346/LER-1979-001-03, /03L-0 on 790102:monthly Functional Test Not Performed on Reactor Protection Sys Channel 2 within Allowable Time.Caused by Breakdown in Communications Between Testing Personnel & Test Coordinator | /03L-0 on 790102:monthly Functional Test Not Performed on Reactor Protection Sys Channel 2 within Allowable Time.Caused by Breakdown in Communications Between Testing Personnel & Test Coordinator | | | 05000346/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000346/LER-1979-002-03, /03L-1 on 790102:main Steam Valves 106 & 106A Failed to Open,Resulting in Auxiliary Feed Pump Afp 1-1 Being Taken Out of Operation.Caused by Dirt Buildup on Valve Stems as Result of New Const | /03L-1 on 790102:main Steam Valves 106 & 106A Failed to Open,Resulting in Auxiliary Feed Pump Afp 1-1 Being Taken Out of Operation.Caused by Dirt Buildup on Valve Stems as Result of New Const | | | 05000346/LER-1979-002, Forwards LER 79-002/03L-1 | Forwards LER 79-002/03L-1 | | | 05000346/LER-1979-003-03, /03L-0 on 790104:control Room Emergency Ventilation Sys Damper HV5311E Inoperable.Caused by Leaking Pneumatic Operator.New Operator Installed.Damper Operated & Tested for Response Time & Declared Operable | /03L-0 on 790104:control Room Emergency Ventilation Sys Damper HV5311E Inoperable.Caused by Leaking Pneumatic Operator.New Operator Installed.Damper Operated & Tested for Response Time & Declared Operable | | | 05000346/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000346/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000346/LER-1979-004-03, /03L-0 on 790105:failure to Post Guards at Entrance to Containment During Periods of Free Access. Caused by Personnel Error.Special Order 84 Revised to Require Posting of Guards | /03L-0 on 790105:failure to Post Guards at Entrance to Containment During Periods of Free Access. Caused by Personnel Error.Special Order 84 Revised to Require Posting of Guards | | | 05000346/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000346/LER-1979-005-03, /03L-0 on 790106:during Surveillance Testing, Borated Water Storage Tank Level Bistable Was Tripped;Valves DH9A Opened & DH7A Closed.Caused by Component Failure of Output Relay K51A & Instrument Drift | /03L-0 on 790106:during Surveillance Testing, Borated Water Storage Tank Level Bistable Was Tripped;Valves DH9A Opened & DH7A Closed.Caused by Component Failure of Output Relay K51A & Instrument Drift | | | 05000346/LER-1979-006-03, /03L-0:on 790105,reviewer Noted 781228 Record of Continuous Alarm at Contact Data Record Point F018.Panel C4705 Not Reset.Caused by Failure of Indicator Lights on Panel C4705.Panel Reset,Clearing F018.Surveillance Modified | /03L-0:on 790105,reviewer Noted 781228 Record of Continuous Alarm at Contact Data Record Point F018.Panel C4705 Not Reset.Caused by Failure of Indicator Lights on Panel C4705.Panel Reset,Clearing F018.Surveillance Modified | | | 05000346/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000346/LER-1979-007-03, /03L-0 on 790110:during Performance of Surveillance Test,Channel 2 of Containment Hydrogen Analyzer Was Found Inoperable.Caused by Defective Zener Diode in Millivolt Converter | /03L-0 on 790110:during Performance of Surveillance Test,Channel 2 of Containment Hydrogen Analyzer Was Found Inoperable.Caused by Defective Zener Diode in Millivolt Converter | | | 05000346/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000346/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000346/LER-1979-008-03, /03L-0 on 790109:during Surveillance Testing, Containment Recirculation Fan 1-1 Failed to Run.Cause Attributed to Buildup of non-conductive Film on Auxiliary Controller Contacts | /03L-0 on 790109:during Surveillance Testing, Containment Recirculation Fan 1-1 Failed to Run.Cause Attributed to Buildup of non-conductive Film on Auxiliary Controller Contacts | | | 05000346/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000346/LER-1979-009-03, /03L-0:on 790112,power to Vital Bus Y2 Lost. False Integrated Control Sys Signal Resulted in Reactor & Full Steam & Feedwater Rupture Control Sys Trip.Caused by Blown 125 Volt DC Fuse to Inverter | /03L-0:on 790112,power to Vital Bus Y2 Lost. False Integrated Control Sys Signal Resulted in Reactor & Full Steam & Feedwater Rupture Control Sys Trip.Caused by Blown 125 Volt DC Fuse to Inverter | | | 05000346/LER-1979-010-03, /03L-0:on 790112,Sys 7 Data Logger Experienced Core Dump,Voiding Computer Memory Bank Which Rendered Remote Monitoring of Fire Detection Sys Inoperable & Placed Unit in Action Statement of Tech Spec 3.3.3.8.Cause Unknown | /03L-0:on 790112,Sys 7 Data Logger Experienced Core Dump,Voiding Computer Memory Bank Which Rendered Remote Monitoring of Fire Detection Sys Inoperable & Placed Unit in Action Statement of Tech Spec 3.3.3.8.Cause Unknown | | | 05000346/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000346/LER-1979-011-03, /03L-0:on 790115,reactor Coolant Pump 1-2-2 Started W/Incorrect Breaker Alignment,Causing Low Voltage Relays to Trip Which de-energized Both 4.16 Kv Essential Buses C1 & D1.Caused by Personnel Error | /03L-0:on 790115,reactor Coolant Pump 1-2-2 Started W/Incorrect Breaker Alignment,Causing Low Voltage Relays to Trip Which de-energized Both 4.16 Kv Essential Buses C1 & D1.Caused by Personnel Error | | | 05000346/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000346/LER-1979-012-03, /03L-0:on 790116,during Surveillance Testing,Heat Traced Line Temp Measurement Points Below 105 F Limit.Caused by Injection of Makeup (Flush) Water After Boron Injection at Temp Lower than 105 F.Tests Rerun Satisfactorily | /03L-0:on 790116,during Surveillance Testing,Heat Traced Line Temp Measurement Points Below 105 F Limit.Caused by Injection of Makeup (Flush) Water After Boron Injection at Temp Lower than 105 F.Tests Rerun Satisfactorily | | | 05000346/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000346/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000346/LER-1979-013-03, /03L-0:on 790116,when Makeup Pump 1 Started for Surveillance testing,1/2 Inch Nipple at Discharge of Attached Gear Driven Lube Oil Pump Failed,Resulting in Oil Spray Which Required Pump Shutdown | /03L-0:on 790116,when Makeup Pump 1 Started for Surveillance testing,1/2 Inch Nipple at Discharge of Attached Gear Driven Lube Oil Pump Failed,Resulting in Oil Spray Which Required Pump Shutdown | | | 05000346/LER-1979-014-03, /03L-0:on 790116,during Shutdown,Boric Acid Addition Tanks (Baat) Total Vol 3-1/3% Below Tech Spec 3.1.2.9 Requirements.Caused by Reduced Baat Vol After Completion of Required Testing Followed by RCS Boration | /03L-0:on 790116,during Shutdown,Boric Acid Addition Tanks (Baat) Total Vol 3-1/3% Below Tech Spec 3.1.2.9 Requirements.Caused by Reduced Baat Vol After Completion of Required Testing Followed by RCS Boration | | | 05000346/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000346/LER-1979-015-03, /03L-0:on 790117,core Flood Tank 1-2 Isolation Valve CF1A Would Not Close by Remote Operation.Caused by Loose Set Screw.Cracked Pinion Gear & Associated Key Replaced Per Maint Work Order 78-2928 | /03L-0:on 790117,core Flood Tank 1-2 Isolation Valve CF1A Would Not Close by Remote Operation.Caused by Loose Set Screw.Cracked Pinion Gear & Associated Key Replaced Per Maint Work Order 78-2928 | | | 05000346/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000346/LER-1979-016-03, /03L-0:on 790124,emergency Lock Failed Leak Rate Test While Unit in Mode 5.Caused by Loosening of Shaft Seal (Teflon Packing) Due to Routine Use of Escape Lock.Packing Will Be Replaced During Next Convenient Outage | /03L-0:on 790124,emergency Lock Failed Leak Rate Test While Unit in Mode 5.Caused by Loosening of Shaft Seal (Teflon Packing) Due to Routine Use of Escape Lock.Packing Will Be Replaced During Next Convenient Outage | | | 05000346/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000346/LER-1979-017-03, /03L-0:on 790130,photoelectric Smoke Detector Ds 8605-E in Emergency Diesel Generator 1-1 Area Not Functional.Caused by Failure of Detector.New Detector Ordered & Fire Watch Patrol Established in Area | /03L-0:on 790130,photoelectric Smoke Detector Ds 8605-E in Emergency Diesel Generator 1-1 Area Not Functional.Caused by Failure of Detector.New Detector Ordered & Fire Watch Patrol Established in Area | | | 05000346/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000346/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000346/LER-1979-018-03, /03L-0:on 790130,valves SP17A2 & SP17B2 Lifted Below Setpoint Range & Declared Inoperable.Caused by Loose Spindle on Main Steam Line Code Safety Valve SP17A2.Valve SP17A2 Gagged & SP17B2 Tested Satisfactorily | /03L-0:on 790130,valves SP17A2 & SP17B2 Lifted Below Setpoint Range & Declared Inoperable.Caused by Loose Spindle on Main Steam Line Code Safety Valve SP17A2.Valve SP17A2 Gagged & SP17B2 Tested Satisfactorily | | | 05000346/LER-1979-019-03, /03L-0 on 790129:suction & Discharge Valves on Containment Spray Pump Were Closed.Caused by Personnel Error | /03L-0 on 790129:suction & Discharge Valves on Containment Spray Pump Were Closed.Caused by Personnel Error | | | 05000346/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000346/LER-1979-020-03, /03L-0 on 790205:10 of 18 Main Steam Safety Valves Found Outside Setpoint Range.Believed Caused by Changing Ambient Conditions at Valve Locations.Valves Adjusted & Retested Satisfactorily | /03L-0 on 790205:10 of 18 Main Steam Safety Valves Found Outside Setpoint Range.Believed Caused by Changing Ambient Conditions at Valve Locations.Valves Adjusted & Retested Satisfactorily | | | 05000346/LER-1979-020, Forwards LER 79-020/03L-0 | Forwards LER 79-020/03L-0 | | | 05000346/LER-1979-021-03, /03L-0 on 790205:containment High Pressure Alarms Were Received & Safety Features Actuation Sys Channel 2 Erroneously Tripped.Cause Unknown.No Deficiencies Found from Surveillance Tests.Channel Returned to Operation | /03L-0 on 790205:containment High Pressure Alarms Were Received & Safety Features Actuation Sys Channel 2 Erroneously Tripped.Cause Unknown.No Deficiencies Found from Surveillance Tests.Channel Returned to Operation | | | 05000346/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000346/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000346/LER-1979-022-03, /03L-0 on 790208:diesel Fire Pump Battery Electrolyte Level in Four Cells Was Below Top of Cell Plates.Caused by Procedural Error.Levels Restored,Pump Declared Operable & Unit Removed from Action Statement | /03L-0 on 790208:diesel Fire Pump Battery Electrolyte Level in Four Cells Was Below Top of Cell Plates.Caused by Procedural Error.Levels Restored,Pump Declared Operable & Unit Removed from Action Statement | | | 05000346/LER-1979-023, Forwards LER 79-023/01T-0 | Forwards LER 79-023/01T-0 | | | 05000346/LER-1979-023-01, /01T-0 on 790228:Startup Transformer 01 Taken Out of Svc;Surveillance Tests Not Performed within One Hour, Contrary to Tech Spec Requirements.Caused by Personnel Error.Testing Completed as Soon as Error Realized | /01T-0 on 790228:Startup Transformer 01 Taken Out of Svc;Surveillance Tests Not Performed within One Hour, Contrary to Tech Spec Requirements.Caused by Personnel Error.Testing Completed as Soon as Error Realized | | | 05000346/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000346/LER-1979-024-03, /03L-0 on 790214:fire Alarm Panel C4706 Signaled, Indicating Laundry Room Detector DS8630 as Source.Detector Declared Inoperable as No Cause for Signal Found.Cause of Event Undetermined.Possibly Due to Gases or Dust | /03L-0 on 790214:fire Alarm Panel C4706 Signaled, Indicating Laundry Room Detector DS8630 as Source.Detector Declared Inoperable as No Cause for Signal Found.Cause of Event Undetermined.Possibly Due to Gases or Dust | | | 05000346/LER-1979-025-03, /03L-0 on 790213:Ohio Edison Relay Testing Actuated Transfer Trip Receiving Relay & Tripped Switchyard Breakers.Caused by Failure of Util to Notify Toledo Edison Before Performing Relay Testing | /03L-0 on 790213:Ohio Edison Relay Testing Actuated Transfer Trip Receiving Relay & Tripped Switchyard Breakers.Caused by Failure of Util to Notify Toledo Edison Before Performing Relay Testing | | | 05000346/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | |
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