LER-1977-106, /03L-0:on 771206,two 345 Kv Air Circuit Breakers on K Bus Tripped Due to Fault on Oh Edison Co Beaver Line. Caused by Galloping Conductors on Transmission Line.Load Dispatcher Opened Air Breaker & Reclosed Circuit Breakers |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461977106R03 - NRC Website |
|
text
' 77)
LICENSEE EVENT REPORT NT'.0L BLOCK: l 1
l I
l dh (PLEASE FRINT OR TYPE REQUIR ED INFORMATION) 8 6
B l S l l '@l 0 l 0 l - l 010 l N l P l F l-l 013 l@l 4 l 1 l 1 l 1 l 1 l@l l
l@
f a 1 lH]D LICENSEE CCOE 14 15 UCENSE NWl5EH 25 26 uCENSE TYPE JG 57 CA T 36 l
alil y'C"7 l L @l 0 l 5 l 0 l-10 l 31416 @l 1121016 l 717 }@li l 212121717 l@
tCN 68 69 EVENT 0 ATE 74 75 REPORT QATE 80
,c 60 68 DOCKET NUMSER 8
EVENT OESCRIPTION AND PRC8 ABLE CONSEQUENCES h breakers I
- 7) ! 21 l At 1741 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.624505e-4 months <br /> on 12/6/77 and 0237 hours0.00274 days <br />0.0658 hours <br />3.918651e-4 weeks <br />9.01785e-5 months <br /> on 12/7/77, two 345 KV air circuit n "K" Bus tripped due to a fault on the Ohio Edison Beaver Line. This de-energized I
o i2I l in the Action Statement of Tech Spec
]
fo,,,;02 Startup Transformer and placed the unit
,o,3, ;3.8.1.1.
There was no danger to the heslth and safety of the public or to unit per-
]
I o is I l sonnel. At the time of the occurrence, the unit was on the Aux 111arv Transformer l
[a37; gand not on the Startup Transformers. -(NP-33-77-106) l I
l0$8l l
Tc"a*E Suec$ce CcMeoNENT CCDE SUSC E S
QE T
I E I A l@ [C_j@ l Z l@ l Z l Z l Z l Z l Z l Z lh I Z l@ [Zj h ioisi 7
8 9
to 11 12 f3 18 19 20 SEQUENTIAL OCOUR RENCE REPORT REVISION gn EVENT YEAR R EPORT NO.
CCQE TYPE No.
@ a(sy,,po I 71 71 1-1 1 11 01 61 1/1 I6l3l ILI l-1 W
g
_ 21 22 23 24 26 27 23 29 30 31 32 N AC CN O P T
ME hours S8 i PoR 8.
SUPP ER MA UPA RER
@lzj@
l Zi@
l Zl@
l 01 01 01 01 I Yl@
l N ]@
y@
l ZI Zl Zl Zl@
34 35 26 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS on the I
- i;o[lThe cause of this occurrence has been attributed to "calionine cnnam *n-="
b r o n tr o-,
4, i
l transmission line which caused a trio of two 345 KV air circuit i,,ij I
,,#21lsvitchvard. The Load Dispatcher opened the n4* b e a,1-wd*ck,na
- - or i m aa - %
---n I
- , #3j l 345 KV air circuit breakers which re-energized "K" Bus from the Toledo Edison I
iii4l l Company Bay Shore Line.
80 1
a o
' TA
% POV,ER OTHER STATUS IS Y
DISCOVERY DESCRIPTION li is 1 I E l@ 10 la 10 l@l NA l
l A[g[ NA l
S
'o l
'2
'Jnv,Ty C#TtNT AucuNT cP ACTiviry @ l LOCATION oP RELEASE l
NA l
utEASEo cP RELEASE -
li is l I Z l @ IZ l@l NA 30 44 45 7
8 9 10 11 PERSONNEL EXPCSURES NUMBER TYPE CESCRIPTICN lIlIl 1
PER$0NNEL INJURIES NUM9ER
DESCRIPTION
l li la l 1010101@l NA 7
8 9 11 12 oSS OP OR DacAGE TO PACILITY E
DESCRIPTION
l l
Zl@l NA 60 l
7 d 9 10 PU8UCITY NRC USE ONLY l
oESCRiPTic~ O,p, 8 o o e o 4 c699 l!llll!!lI!!!!
iSSut0
]
l2lollNl$al NA l
68 69 40 3 F
8 9 10 Tom Beeler (419) 259-5000, Ext. 253)
PHONE:
3 DVR 178-1 & IS@YE OF FREPARER.
TOLEDO EDISON COMPANY DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION p'
SUPPLEMENTAL INFORMATION FOR LER NP-33-77-106
- ()
r 1
DATE OF EVENT: December 6 and 7, 1977 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Loss of 02 Startup Transformer due to fault on the Ohio Edison Beaver Line The unit was in Mode 1, with Power (MWT) = 1100 Conditions Prior to Occurrence:
and Load (MWE) = 365.
Description of Occurrence: At 1741 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.624505e-4 months <br /> on December 6, 1977 and 0237 hours0.00274 days <br />0.0658 hours <br />3.918651e-4 weeks <br />9.01785e-5 months <br /> on December 7,1977, two 345 KV air circuit breakers on "K" Bus tripped due to a fault on the Ohio Edison Beaver Line. This de-energized 02 Startup Transformer and placed the unit into the Action Statement of Technical Specification 3.8.1.I since one of the 345/13.8 KV Startup Transformers was de-energized.
Designation of Apparent Cause of Occurrence: The cause of this occurrence has been attributed to " galloping conductors" on the transmission line.
"Calloping
. conductors" is a movement of transmission lines caused by high winds and ice U uildup on the transmission lines. This caused the protective relaying scheme to btrip two 345 KV air circuit breakers in the switchyard.
Analysis of Occurrence: There was no danger to the health *and safety of the public or to unit personnel.. At the time of the occurrence, the unit was on the Auxiliary Transformer, and not on the Startup Transformers. Also, there was two 345 KV trans-mission linen, one 345/13.8 KV Startup Transformers and two 13.8 KV Buses operable with two independent diesel generators to provide AC power.
Corrective Action
At 1742 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.62831e-4 months <br /> on December 6,1977 and 0237 hours0.00274 days <br />0.0658 hours <br />3.918651e-4 weeks <br />9.01785e-5 months <br /> on December 7, 1977, the Load Dispatcher opened the air break switch which cleared the Beaver Line from "K" Bus and at 1743 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.632115e-4 months <br /> on December 6, 1977 and 0238 hours0.00275 days <br />0.0661 hours <br />3.935185e-4 weeks <br />9.0559e-5 months <br /> on Decem-ber 7, 1977, reclosed the two 345 KV air circuit breakers which re-energized "K" Bus from the Toledo Edison Company Bay Shore Line. This removed the unit from the Action Statement of Technical Specification 3.8.1.1.
The Transaission and Substation Engineering Division is continuing to study and test proposed resolu-tions to the " galloping conductors" problem.
Failure Data: No previous similar events have occurred.
J i
8002040 l
|
|---|
|
|
| | | Reporting criterion |
|---|
| 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 | |
|