LER-1977-094, /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested |
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03 kVE*.iCATE 14 75 RE!PCRT OATE JJ EVE'JT DESC!iPT6CN AND PRCSA8d COf.3ECUENCES h jo!:; l0n 11/16/77, during the pe formance or ST 5067.01, Emergency Ventilation System (EVS) i it was found that dampers PDV 5014A and B (on EVS Train 2) were not 3 } l Monthly Test,
- o At 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on 11/16/77, EVS Train j
- modulating correctly to draw down the annulus.
(2 was declared inoperable. This placed the cution in the Action Statement of Tech
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- two operable EVS Trains in Mode 1.
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- to the health and safety of the public or station personnel.
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.3 CAUSE DESCRIPTION AND COPRETlVE ACTICNS h Ii60llThe pressure differcatial :entroller (PDC 5014) which controls damners PDV 5014A and i
Ii!ii iB was found to be defetiv3.
PDC 5014 was replaced and the svstem retested.
EVS I
lii2j l Train 2 was declared C,yerr. ale at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> an November 22, 1977, thus removine the l i I 31 i station from the Action Statement of Technical Specification 3.6.5.1.
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SUPPLEM?NTAL INFORMAT~CN FOR LER NP-33-77-94
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DATE OF EVENT:
November 16, 1977
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l FACILITY:
Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENC2:
E=ergency 'leutilation System Train 1-2 pressure differential controller malfunction.
Conditions Prior to Occurrence: The plant was in Mode 1, with Power (MWT) = 1108 and Load (MWE) = 398.
Description of Occurrence: On November 16, 1977, Surveillance Test ST 5067.01,
" Emergency Ventilation System Monthly Test" was performed and the differential pressure was within specifications.
It was found, however, that dampers PDV 5014A and B were not modulating correctly to draw down the annulus.
Since #2 Emergency Ventilation System (EVS) Train could not serve its intended safety function, r/2 EVS Train was declared. inoperable at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on November 16, 1977.
[
hThis placed the station in the Action Statement of Technical Specification 3.6.5.1
(
/which requires two operable EVS Trains in Mode 1.
An Instrument and Control Work Order (No. 749) was issued to investigate the reason for dampers PDV 5014A and B not modulating properly.
Designation of Apparent Cause of Occurrence: The pressure differential controller (PDC 5014) was then re=oved and a bench check performed. The controller was found to be heat sensitive and would fail intermittently when it was at operating temp-erature.
A new controller (PDC 5014) was installed and energized for more than twelve hours prior to re-performing Surveillance Test ST 5067.01.
EVS Train 2 then functioned properly and was declared operable at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> on November 22, 1977. This removed the station from the Action Statement of Technical Specifica-tion 3.6.5.1.
Analysis of Occurrence: There was no danger to the health and safety of the public
' or to station personnel. The system was inoperable; however, it would not affect the operation of EVS Train 1-1 which would still draw down the annulus to the -0.75 inches of water setpoint if an accident requiring the EVS had occurred.
Corrective Action
The pressure differential controller (PDC 5014) was found to fail intermittently when it was at operating temperature.
Since it was not possi-ble to determine what component was responsible, the entire contraller was replaced.
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Failure Data:
There was one previous occurrence.
EVS Train 2 dampers PDV 5014A and l
B failed to modulate properly on October 19, 1977 (see LER NP-33-77-82).
Since the i
problem was found to be in PDC 5014, and it has been replaced, this occurrence should not recur.
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| 05000289/LER-1977-016-01, /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | | | 05000289/LER-1977-016, Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | | | 05000320/LER-1977-016, /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | | | 05000346/LER-1977-017, Forwards LER 77-017/01T-0 | Forwards LER 77-017/01T-0 | | | 05000346/LER-1977-017-01, /01T-0:on 771020,both Auxiliary Feed Pump Suctions Lined Up to Deaerator Storage Tanks W/O Cooling Water Supply Shifting to Svc Water,Resulting in Water Greater than 200 F as Cooling Water for Auxiliary Feed Pump Bearings | /01T-0:on 771020,both Auxiliary Feed Pump Suctions Lined Up to Deaerator Storage Tanks W/O Cooling Water Supply Shifting to Svc Water,Resulting in Water Greater than 200 F as Cooling Water for Auxiliary Feed Pump Bearings | | | 05000346/LER-1977-018, Forwards LER 77-018/01T-0 | Forwards LER 77-018/01T-0 | | | 05000346/LER-1977-018-01, /01T-0:on 771108,station Review Board Found Auxiliary Feed Pump Turbine Governor Valve Vibrational Closure Design Deficiency.Caused by Lack of Force to Hold Valve Open.Requests Design Mod for Pump Turbines | /01T-0:on 771108,station Review Board Found Auxiliary Feed Pump Turbine Governor Valve Vibrational Closure Design Deficiency.Caused by Lack of Force to Hold Valve Open.Requests Design Mod for Pump Turbines | | | 05000346/LER-1977-019-01, /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised | /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised | | | 05000346/LER-1977-019, Forwards LER 77-019/01T-0 | Forwards LER 77-019/01T-0 | | | 05000346/LER-1977-077-03, /03L-0:on 771010,decay Heat Valve Pit Cover Removed to Inspect Decay Heat Isolation Valves DH11 & DH12 & to Perform Wiring Change on DH12.Insp Required for Leakage & Preventive Maint | /03L-0:on 771010,decay Heat Valve Pit Cover Removed to Inspect Decay Heat Isolation Valves DH11 & DH12 & to Perform Wiring Change on DH12.Insp Required for Leakage & Preventive Maint | | | 05000346/LER-1977-077, Forwards LER 77-077/03L-0 | Forwards LER 77-077/03L-0 | | | 05000346/LER-1977-078-03, /03L-0:on 771011,during Functional Test,Reactor Protection Sys Channel 1 Accidentally de-energized.Caused by Error in Maint Work Order.Personnel Instructed | /03L-0:on 771011,during Functional Test,Reactor Protection Sys Channel 1 Accidentally de-energized.Caused by Error in Maint Work Order.Personnel Instructed | | | 05000346/LER-1977-078, Forwards LER 77-078/03L-0 | Forwards LER 77-078/03L-0 | | | 05000346/LER-1977-079-03, /03L-0:on 771011,source Range Defector NI-1 Indication Failed Low Twice,Then Returned to Normal Operation by Itself.Cause Unknown | /03L-0:on 771011,source Range Defector NI-1 Indication Failed Low Twice,Then Returned to Normal Operation by Itself.Cause Unknown | | | 05000346/LER-1977-079, Forwards LER 77-079/03L-0 | Forwards LER 77-079/03L-0 | | | 05000346/LER-1977-080, Forwards LER 77-080/03L-0 | Forwards LER 77-080/03L-0 | | | 05000346/LER-1977-080-03, /03L-0:on 771016,governor Valve on Auxiliary Feed Pump 1-2 Found Closed During Auxiliary Feedwater Sys Monthly Test Performance.Caused by Possible Design Deficiency. Excessive Vibration Under Investigation by Maint Personnel | /03L-0:on 771016,governor Valve on Auxiliary Feed Pump 1-2 Found Closed During Auxiliary Feedwater Sys Monthly Test Performance.Caused by Possible Design Deficiency. Excessive Vibration Under Investigation by Maint Personnel | | | 05000346/LER-1977-081, Forwards LER 77-081/03L-0 | Forwards LER 77-081/03L-0 | | | 05000346/LER-1977-081-03, /03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified | /03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified | | | 05000346/LER-1977-082-03, /03L-0:on 771019,discharge & Recirculation Dampers of Emergency Ventilation Sys 2 Failed to Open When Fan Started.Caused by Loose & Dirty Controller Contacts.Module Removed & Reinserted, & Contacts Cleaned | /03L-0:on 771019,discharge & Recirculation Dampers of Emergency Ventilation Sys 2 Failed to Open When Fan Started.Caused by Loose & Dirty Controller Contacts.Module Removed & Reinserted, & Contacts Cleaned | | | 05000346/LER-1977-082, Forwards LER 77-082/03L-0 | Forwards LER 77-082/03L-0 | | | 05000346/LER-1977-083, Forwards LER 77-083/03L-0 | Forwards LER 77-083/03L-0 | | | 05000346/LER-1977-083-03, /03L-0:on 771025,stop Valve AF3872 Failed to Stroke When Given Open Signal.Caused by Component Failure. Torque Switch Replaced on 771027 | /03L-0:on 771025,stop Valve AF3872 Failed to Stroke When Given Open Signal.Caused by Component Failure. Torque Switch Replaced on 771027 | | | 05000346/LER-1977-084, Forwards LER 77-084/03L-0 | Forwards LER 77-084/03L-0 | | | 05000346/LER-1977-084-03, /03L-0:on 771025,surveillance Test ST 5080.01 Not Performed.Caused by Personnel Error.Test Performed Immediately & Computer Program Revised | /03L-0:on 771025,surveillance Test ST 5080.01 Not Performed.Caused by Personnel Error.Test Performed Immediately & Computer Program Revised | | | 05000346/LER-1977-086-03, /03L-0:on 771028,safety Features Actuation Sys Channel 4 Radiation Monitor RIS 2007 Failed to Respond to Internal Check Source.Caused by Component Failure.Low Amplifier Board Replaced & Monitor Recalibr | /03L-0:on 771028,safety Features Actuation Sys Channel 4 Radiation Monitor RIS 2007 Failed to Respond to Internal Check Source.Caused by Component Failure.Low Amplifier Board Replaced & Monitor Recalibr | | | 05000346/LER-1977-086, Forwards LER 77-086/03L-0 | Forwards LER 77-086/03L-0 | | | 05000346/LER-1977-087, Forwards LER 77-087/03L-0 | Forwards LER 77-087/03L-0 | | | 05000346/LER-1977-087-03, /03L-0:on 771024,safety Features Actuation Sys Channel 3 Containment Radiation Reaqdings Unreliable . Caused by Design/Fabrication Error.Facility Change Request 77-437 Issued for Permanent Repair | /03L-0:on 771024,safety Features Actuation Sys Channel 3 Containment Radiation Reaqdings Unreliable . Caused by Design/Fabrication Error.Facility Change Request 77-437 Issued for Permanent Repair | | | 05000346/LER-1977-088, Forwards LER 77-088/03L-0 | Forwards LER 77-088/03L-0 | | | 05000346/LER-1977-088-03, /03L-0:on 771027,source Range Detector NI-1 Indication Failed Low.Cause Unknown.Updated Rept Forthcoming | /03L-0:on 771027,source Range Detector NI-1 Indication Failed Low.Cause Unknown.Updated Rept Forthcoming | | | 05000346/LER-1977-089-03, /03L-1:on 771107,radiation Monitor RIS 2007 Was Showing Erratic Readings.Caused by Victoreen Low Range Amplifier Board 847-1-20 Failure.Board Replaced | /03L-1:on 771107,radiation Monitor RIS 2007 Was Showing Erratic Readings.Caused by Victoreen Low Range Amplifier Board 847-1-20 Failure.Board Replaced | | | 05000346/LER-1977-089, Forwards LER 77-089/03L-1.W/o Encl | Forwards LER 77-089/03L-1.W/o Encl | | | 05000346/LER-1977-090-03, /03L-0:on 771107,during Review of Deficiency in Steam & Feedwater Rupture Control Sys Monthly Test,Reactor Coolant Pump Found Inoperable.Caused by Component Failure. Voltage Regulating Diode Replaced | /03L-0:on 771107,during Review of Deficiency in Steam & Feedwater Rupture Control Sys Monthly Test,Reactor Coolant Pump Found Inoperable.Caused by Component Failure. Voltage Regulating Diode Replaced | | | 05000346/LER-1977-090, Forwards LER 77-090/03L-0 | Forwards LER 77-090/03L-0 | | | 05000346/LER-1977-091-03, /03L-0:on 771107,containment Radiation Monitor RIS 2006 Spiked & Reset Twice Causing Safety Features Actuation Sys Incident Level 1 Trips.Caused by Design Error | /03L-0:on 771107,containment Radiation Monitor RIS 2006 Spiked & Reset Twice Causing Safety Features Actuation Sys Incident Level 1 Trips.Caused by Design Error | | | 05000346/LER-1977-091, Forwards LER 77-091/03L-0 | Forwards LER 77-091/03L-0 | | | 05000346/LER-1977-092, Forwards LER 77-092/03L-0 | Forwards LER 77-092/03L-0 | | | 05000346/LER-1977-092-03, /03L-0:on 771101,facility Review Board Meeting Revealed That Surveillance Requirement of Venting Hpis Valve HP 72 Not Performed.Caused by Personnel Error.High Point Valve Vented & Modified | /03L-0:on 771101,facility Review Board Meeting Revealed That Surveillance Requirement of Venting Hpis Valve HP 72 Not Performed.Caused by Personnel Error.High Point Valve Vented & Modified | | | 05000346/LER-1977-093, Forwards LER 77-093/03L-0 | Forwards LER 77-093/03L-0 | | | 05000346/LER-1977-093-03, /03L-0:on 771114,reactor Protection Sys Daily Heat Balance Check Not Completed When Station Above 15% Rated Thermal Power During Oct-Nov 1977.Caused by Personnel Error. Surveillance Test Placed on Daily Testing Schedule | /03L-0:on 771114,reactor Protection Sys Daily Heat Balance Check Not Completed When Station Above 15% Rated Thermal Power During Oct-Nov 1977.Caused by Personnel Error. Surveillance Test Placed on Daily Testing Schedule | | | 05000346/LER-1977-094-03, /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested | /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested | | | 05000346/LER-1977-094, Forwards LER 77-094/03L-0 | Forwards LER 77-094/03L-0 | | | 05000346/LER-1977-095-03, /03L-0:on 771127,control Room Ventilation Isolation Damper HV 5311A Failed to Close on Radiation Monitor Trip.Caused by Component Failure.Damper Dismantled & Sealing Surfaces Cleaned & Lubricated | /03L-0:on 771127,control Room Ventilation Isolation Damper HV 5311A Failed to Close on Radiation Monitor Trip.Caused by Component Failure.Damper Dismantled & Sealing Surfaces Cleaned & Lubricated | | | 05000346/LER-1977-095, Forwards LER 77-095/03L-0 | Forwards LER 77-095/03L-0 | | | 05000346/LER-1977-097, Forwards LER 77-097/03L-0 | Forwards LER 77-097/03L-0 | | | 05000346/LER-1977-097-03, /03L-0:on 771129,radiation Monitor Re 2006 Tripped Safety Features Actuation Sys Channel 3 Containment Radiation Due to Sporadic Spiking.Caused by Component Failure in Radiation Detector.Detector Replaced | /03L-0:on 771129,radiation Monitor Re 2006 Tripped Safety Features Actuation Sys Channel 3 Containment Radiation Due to Sporadic Spiking.Caused by Component Failure in Radiation Detector.Detector Replaced | | | 05000346/LER-1977-100-03, /03L-0:on 771201 & 05,source Range Neutron Detector NI-1 Indication Dropped to Zero & Returned to Normal Operation W/O Assistance.Cause Unknown.After First Failure,Detector Replaced & Retested | /03L-0:on 771201 & 05,source Range Neutron Detector NI-1 Indication Dropped to Zero & Returned to Normal Operation W/O Assistance.Cause Unknown.After First Failure,Detector Replaced & Retested | | | 05000346/LER-1977-100, Forwards LER 77-100/03L-0 | Forwards LER 77-100/03L-0 | | | 05000346/LER-1977-101-03, /03L-0:on 771201,diesel Generator 1-1 Inoperable Due to Failure to Perform Required Surveillance Testing on Diesel Generator 1-2 within Required Tech Spec Interval. Caused by Personnel Error | /03L-0:on 771201,diesel Generator 1-1 Inoperable Due to Failure to Perform Required Surveillance Testing on Diesel Generator 1-2 within Required Tech Spec Interval. Caused by Personnel Error | |
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