LER-1977-019, /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 |
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| 3461977019R01 - NRC Website |
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11/17/77, pTT} l At 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> on l
g l Valves AF 599 and AF 608 wue closed, thus rendering the Steam a l
g l Control System (SFRCS) Stecc Generator to Feedwater Differential There j This placed the station in violation of Tech Spec 3.3.2.2.
ITTTlI inputs inoperable.
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j o j e l l vas no danger to the health and safety of the public or to station personne.
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Yam a diverse steam generator low level input lTJT] l SFRCS would have actuated
.I (NF-32-77-19)
[ o # 8 I I of feedwater occurred.
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CAUSE DESCRIPTION AND CORRECTIVE 10TIONS Feedwater Valves AF 599 and AF 608 were !
o 17, 1977, Auxiliary j,;OglAt 0935 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.557675e-4 months <br /> on Novem'er 2.2.
A orocedural l opened thus rem)ving the station from violation of Tech Soec 3.3.
li,,j ST 5031.14, which failed to reset the !
,,, g l defic.iency was found in the 3FRCS Monthly Test, 1977J ST 5031.14 was last performed on November 14
[, 3 g l valve logic for AF 599 and AF 608.
The test procedure has been revised.
I This is not a repetitive occurrence.
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DAVIS-3 ESSE UNIT ONE NUCLEAn POWER STATION SUPPLEMENTAL INFORMATION FOR LER NP-32-77-19_
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DATE OF EVENT: November 17, 1977 FACILITY: Davis-Besse Unit 1 Isolation of the Steam and Feedwater Rupture IDENTIFICATION OF OCCURREE g:
Control. System's Steam Generator to Feedwater Differential Pressure Switches.
The plant was in Mode 1, with Power (MWT) = 1129 Conditions Prior to Occurrence:
and Load (MWE) = 390.
At 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> on November 17, 1977, Auxiliary Feedwater This iso-Description of Occurrence:
Valves AF 599 and AF 608 t:te discovered closed by Opera This caused (SFRCS) Steam Generator te Feedwater Differential Pressure Switches.
il the pressure differencial witch inputs to the SFRCS to be inoperable, in v o a-i tion of Technical Specification 3.3.2.2 - Table 3.3.11, which placed the stat on under Technical Specificati:n Limiting Condition of Operation 3.0.3.
A procedural deficiency was uncovered s
Designation of Apoarent Cause of Occurrence _:
ST 5031.14. These sections in Sections 6.1 and 6.2 of :he SFRCS Monthly Test, failed to reset the valve logic for Auxiliary Feedwater Valves AF 599 and AF 608 after testing.
Section 6.2 of ST 5031.14, was last performed on November 14, 1977.
There was no danger to the health and safety of the public i
Analysis of Occurrence:
Had a feedwater line ruptured or a loss of feedwater or t5~~statfon personnel.
steam generator low level occurred, the SFRCS would hsve actuated from a redundant input.
17, 1977, Auxiliary Feedwater Valves This removed the station from Technical Specifica-
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At 0935 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.557675e-4 months <br /> on November
Corrective Action
2.2, AF 599 and AF 608 were opened.
tion 3.0.3 and fulfilled the requirements of Technical Specification 3.3.
L l
Table 3.3.11.
l Sections 6:1 and 6.2, has been revised.
SFRCS Monthly Test, ST 5031.14, l
This is not a repetitive occurrence.
l Failure Data:
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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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