LER-1979-034, /01T-0 on 790103:HPI Pump 1-1 Was Stopped Due to Low Recirculation Flow Indication.Caused by Inability of Heat Trace to Maintain HPI Pump Recirculation Line Temp Above Freezing.Heat Increased |
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EVENT DATE 74 75 REPORT DATE 8J EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on 1/3/79, High Pressure Injection (HPI) Pump 1-1 was started per "Emer-j o 2 l At ST 5051.01. At 1406 hours0.0163 days <br />0.391 hours <br />0.00232 weeks <br />5.34983e-4 months <br />, HPI g
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At 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br /> on 1/5/79 ST 5051.01 was successfully completed and l
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DVR 79-048 NAME OF PREPARER PHON E :
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR PCWER STATION U'IIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-32-79-03 DATE OF EVENT: January 3, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:
Inoperability of High Pressure Injection Pumps 1-1 and 1-2 due to minimum recirculation line freezing Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWT) = 2384, and Load (Gross MWE) = 763.
Description of Occurrence: At 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on January 3,1979, High Pressure Injection (HPI) Pump 1-1 was started per " Emergency Core Cooling System Subsystem Monthly Test",
ST 5051.01. At 1406 hours0.0163 days <br />0.391 hours <br />0.00232 weeks <br />5.34983e-4 months <br />, HPI Pump 1-1 was stopped due to a low ficw indication on the HPI pump to the Borated Water Storage Tank (BWST) minimum recirculation line (3" HCC-91).
Further investigation discovered that this line had frozen outside somewhere between the BWST Pipe Tunnel and the top of the LUST. Maintenance personnel were immediately notified.
Maintcaance personnel increased the thermostat setting for the HPI pump minimum re-circulation line heat trace and built a temporary heated enclosure around the exposed line. The recirculation line was thawed and ST 5051.01 was successfully completed for HPI Pump 1 I at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br /> on January 5, 1979.
At the time of the incident, an analysis of the frozen recirculation line by the station indicated that the minimum flow rate required for pump cooling would flow through the injection line if the HPI pumps were started during a loss of coolant accident. As a result, both HPI Pump 1-1 and HPI Pump 1-2 were considered operable, and the unit was not in violation of any Technical Specifications.
On March 12, 1979 in a discussion between station personnel and TECo Power Engineer-ing personnel, Power Engineering personnel stated that they had done an analysis of a previous IFI initiation event (see Licensee Event Report NP-32-77-16 dated Septem-ber 24, 1977) which indicates that the minimum required HPI flow may not have existed if the recirculation line was plugged. As a result of this analysis, both HPI pumps must now be considered to have been inoperable between 1406 hours0.0163 days <br />0.391 hours <br />0.00232 weeks <br />5.34983e-4 months <br /> on January 3,1979 and 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br /> on January 5, 1979.
The inoperability of the HPI pumps placed the unit in violation of Technical Speci-fication 3.5.2 which requires that two independent Emergency Core Cooling System subsystems shall be operable with each subsystem comprised of cac operable HPI pump, one operable Low Pressurc Injection Pump, one operable Decay Heat Cooler, and one operable flowpath capable of taking suction from the BUST.
Decignation of Apparent Cause of Occurrence: This incident was caused by the inabi-lity of the heat trace on the HPI pump to BWST minimum recirculation line, 3" HCC-91, to maintain a pipe temperature above freezing. As a result, this line froze during sub-zero weather and rendered the HPI pumps inoperable.
LER #79-034
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-32-79-03 Analysis of Occurrence:
There was no danger to the health and safety of the public or unit personnel. No event requiring the actuation of the HPI pumps occurred.
The only situation where the HPI pitmps could have been damaged would be a small sized Reactor Coolant System leak with Reactor Coolant System pressure being main-tained slightly above the HPI pumps shutoff head.
Corrective Action
Maintenance personnel increased the thermostat setting for the HPI pump to BWST minimum recirculation line heat trace and built a temporary heated enclosure around it.
The recirculation line was thawed and ST 5051.01 was success-fylly completed for HP1 Pump 1-1 at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br /> on January 5, 1979.
TECo Power Engineering is continuing its analysis on HPI pump "no flow" conditions.
Station personnel are conducting further investigation into the inability of the recirculation line heat trace to maintain the line temperature above freezing and will initiate Facility Change Requests and/or maintenance work orders to correct the problem.
Failure Data: There have not been any previous reportable occurrences with the HPI pumps recirculation line.
LER #79-034
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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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