LER-1978-122, /03L-0 on 781208:control Rod 4 of Group 3 Absolute Position Indication Was Erratic Due to Intermittent Failure of a Component within the Position Indicator Tube |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461978122R03 - NRC Website |
|
text
U.S. NUCLEAR REGULATORY COMMISSION RC FORM 366 17M LICENSEE EVENT REPORT v
l l
l lh (PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I u
l 0l H Dj Bl Sl 1l@150 l0 l-l0 l@ lN lP lF l-l0 l3 l@l4lll1l1l1l@l l
j@
LICENSE NUMdER h
26 LICEN3E T vFE M
$7 LAT 58
'o 1
LICENSEE CODE 14 8 9 0[ 5l 0l -l 0l 3l 4l 6l@l1 l2 [0 l8 l7 l8 l@l0 l1 l0 l5 l7 j9 l@
CON'T L
gORT 68 63 EVENT DATE 74 75 REPORT DATE 80 io i
60 61 DOCKET NUvS ER 8
EVENT DESCRIPTI,0N AND, PROBABLE CONSEQUENCES h Control Rod 4 of Group 3's Absolute Position Indication (API)l g g l On 12/8/78 and 12/11/78, The absolute position indication channel was declared inoperable, plac-I l was erratic.
g 3
ing the unit in the Action Statement of Technical Specifice.ian 3.1.3.3.
There was I
o 4
Reintive posi-l l o i s ] l no danger to the health and safety of the public or to unit personnel.
the period!
l tion, as well as zone reference indication for Rod 3-4 were operable during o
6 l
l the API was inoperable.
(NP-33-78-144)
O 7
l 80 0
8 l C DE CODE SUSCO E COYPONENT CODE SL9C dE SJ CE lol9l lR lB l@ W@ l A l@ lI lN l S lT lR lU lh lZ lh lZ [h 13 19 2J 7
8 9
10 11 12 13 REVISION OCCURRENCE REPORT SEQUENTI AL
_ EVENT YE AR REPORT NO.
CODE TYPE N o.
L 1 81 l-l 111 2 2; jfl l 0l 3l lt l g
g O SSP.g'Ro LER 7
a
_ 21 22 23 24 26 27 26 23 JJ 31 32 S$sNiTND Fod P.
$ PLIE MAP UFA ER AK ACT ON CN PLANT ETH HOURS 22 l Xl@34 g g
jZ Q l0l0l0l l
g l42Nl@l Zl@
lZ lZ lZ lZ lQ 33 3L 36 31 40 41 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i
the cause of the occurrence hasi l By testing the individual components of the PI string, i
g been determined to be an intermittent failure of a component within the position indi-l y,;3, Diamond Power, the position
[
y,;7, g cator tube.
The position indicator tube was replaced.
g, ; 3 g l indicator vendor, was contacted and will further investigate the f ailure of the posi-j l tion indicator tube.
80 g,,4i 7
8 9 OISCOVERY DESCRIPTION ST S
% POWER oTHER STATO IS O RY l
I1l5l bh l0 l 0 l0 lhlNA l
W g Erratic Indication ACTIVITY CO TENT LOCATION OF RELE ASE RELE ASED OF REL.E ASE AMOUNT OF ACTivlTY j
l1 l6 l ] g l Zjg NA l
l NA 80 44 45 7
8 9 10 11 PERSONNEL CxPOSURES N
TYPE
DESCRIPTION
l l0lUYnERl0lZ l NA 1
7 PERSONNEL INP HIES OEsCRiPTiONh j
li l a l I 0'suvaER01 Ol@l NA l
7 8 9 11 12 LOSS OF OR DAYAGE TO F ACILITY l
TYPE DESCRIP TION l'lol Lzl @l "^
790112 Nf/
NRC USe ONov PUBLi Y
ca iS9 f D DEscuiP TION U l
ll ll!!!!!!!
68 69 80 5 419-259-5000, Ext. 253
{
7 8 9 10 DVR 7J-183 Rick Naylor
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR PG?ER STATION UNIT ONE SUPPLEMENTAL I'; FORMATION FOR LER NP-33-78-144 DATE OF EVENT:. December 8 and 11,1978 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Absolute Position Indication for CorJ-ral Rod 4 at Group 3 Inoperable.
Conditions Prior to Occurrence: On December 8,1978, the unit was in Mode 3, with Power (MWT) = 0, and Load (Gross MWE) = 0.
On December 11, 1978, the unit was in Mode 1, with Power (MUT) = 2514, and Load (Gross MWE) = 835.
Description of Occurrence:
On December 8, 1978, during a unit startup, Control Rod 4 of Group 3's Absolute Position Indication (API) was erratic. At 1112 hours0.0129 days <br />0.309 hours <br />0.00184 weeks <br />4.23116e-4 months <br />, an asymmetric rod alarm was received, and the rod absolute position was declared in-operable, placing the unit in the Action Statement of Technical Specification 3.1.3.3.
The Technical ~,ecification requires all position indication channels to be operable whenever th unit is in Modes 1 or 2.
The reactor was shutdown and the unit entered Mode 3 at approximately 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br /> on December 8,1978.
On December 11,1978, Rod 3-4 experienced several rod withdrawal inhibit interlock actuations due to the erratic operation of the API. The position indication was declared inoperable at 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br />, placing the unit in the Action Statement of Technical Specification 3.1.3.3.
At 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br />, this API signal for Rod 3-4 was placed in asymmetric bypass.
Unit operation continued under Action Statement (a.2) of Technical Specification 3.1.3.3.
Designation of Apparent Cause of Occurrence:
By testing the individual components of the PI string, the cause of the occurrence has been determined ~to be an inter-mittent failure of a ccaponent within the position indicator tube.
There was no danger to the health and safety of the public Analysis of Occurrence:
or to unit personnel.
Relative position, as well as zone reference indication for Rod 3-4 were operable during the period the API was inoperable.
Corrective Action
On December 7,1978, work had been completed per Facility Change 78-501 to relocate API cable CCCRD110 for Rod 3-4 to a different cable in Request the penetration PCCSU.
ST 5013.03, " control Rod Program Verification", was completed satisfactory.
LER #78-122
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-78-144 On December 8,1978, under Maintenance Work Order 78-2364, Maintenance personnel The cleaned and dried the connections on the position indicator for Rod 3-4.
cable from the position indicator to the bulkhead was replaced with a new cable.
Sections 6.5, 6.7 and 6.10 f or Rod 3-4 " Rod Program Verification" was ST 5013.03 The API for Rod 3-4 was declared operable.
completed satisf actory at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />.
On December 19, 1978, under Maintenance Work Order 78-2873, the position indicator tube was replaced.
i 20, 1978, under Maintenance Work Order 78-2908, and Facility Change On Deccaber 78-538, the API cable CCCRD130 was returned to its original location.
Request the position indicator vendor, was contacted and will further in-Diamond Power, vestigate the failure of the position indicator tube.
Previous occurrences of API failures on Rod 3-4 were reported in Failure Data:
Licensee Event Report NP-33-78-135; r eports on other API failures were reported in NP-33-78-02, NP-33-78-19, NP-33-78-26, and NP-33-78-38.
LER #78-122
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000346/LER-1978-002-03, /03L-0:on 780103,control Rod Group 5 Rod 12 Absolute Position Indication Declared Inoperable.Caused by Component Failure of Absolute Position Indicator Reed Switch.Switch Replaced | /03L-0:on 780103,control Rod Group 5 Rod 12 Absolute Position Indication Declared Inoperable.Caused by Component Failure of Absolute Position Indicator Reed Switch.Switch Replaced | | | 05000346/LER-1978-002, Forwards LER 78-002/03L-0 | Forwards LER 78-002/03L-0 | | | 05000346/LER-1978-003-03, /03L-0:on 780103,unidentified RCS Leakage Greater than 1,66 Gallon Per Minute.Caused by Loose Packing on Valve DH2735.Valve Repacked & Stroked | /03L-0:on 780103,unidentified RCS Leakage Greater than 1,66 Gallon Per Minute.Caused by Loose Packing on Valve DH2735.Valve Repacked & Stroked | | | 05000346/LER-1978-003, Forwards LER 78-003/03L-0 | Forwards LER 78-003/03L-0 | | | 05000346/LER-1978-004, Forwards LER 78-004/03L-0 | Forwards LER 78-004/03L-0 | | | 05000346/LER-1978-004-03, /03L-0:on 780105,inlet Balancing Dampers to Emergency Ventilation Sys Fans 1-1 & 1-2 Found Closed.Cause Unknown.Dampers Returned to Balance Position & Locknut Tightened | /03L-0:on 780105,inlet Balancing Dampers to Emergency Ventilation Sys Fans 1-1 & 1-2 Found Closed.Cause Unknown.Dampers Returned to Balance Position & Locknut Tightened | | | 05000346/LER-1978-005-03, /03L-0:on 780106,auxiliary Feed Pump Turbine 1-1 Speed Control Lost & Declared Inoperable.Caused by Short Circuits & Blown Fuses Due to Design Deficiency.Higher Current Rated Relays Installed & Circuit Modified | /03L-0:on 780106,auxiliary Feed Pump Turbine 1-1 Speed Control Lost & Declared Inoperable.Caused by Short Circuits & Blown Fuses Due to Design Deficiency.Higher Current Rated Relays Installed & Circuit Modified | | | 05000346/LER-1978-005, Forwards LER 78-005/03L-0 | Forwards LER 78-005/03L-0 | | | 05000346/LER-1978-006-03, /03L-0:on 780107,computer Alarm Indicated That Steam & Feedwater Rupture Control Sys Steam Generator to Feedwater Differential Pressure Channel 1 Had Tripped.Caused by Component Failure.Input Buffer 1-3 in Channel 1 Replaced | /03L-0:on 780107,computer Alarm Indicated That Steam & Feedwater Rupture Control Sys Steam Generator to Feedwater Differential Pressure Channel 1 Had Tripped.Caused by Component Failure.Input Buffer 1-3 in Channel 1 Replaced | | | 05000346/LER-1978-006, Forwards LER 78-006/03L-0 | Forwards LER 78-006/03L-0 | | | 05000346/LER-1978-007-03, /03L-0:on 780109,during Monthly Surveillance Test ST 5081.01,diesel Generator 1-1 Tripped on High Crankcase Pressure.Caused by Dirty Crankcase Vent Oil Collector.Vent Oil Collector Disassembled & Cleaned | /03L-0:on 780109,during Monthly Surveillance Test ST 5081.01,diesel Generator 1-1 Tripped on High Crankcase Pressure.Caused by Dirty Crankcase Vent Oil Collector.Vent Oil Collector Disassembled & Cleaned | | | 05000346/LER-1978-007, Forwards LER 78-007/03L-0 | Forwards LER 78-007/03L-0 | | | 05000346/LER-1978-008-03, /03L-0:on 780112,both Containment Spray Pumps Found Inoperable.Caused by Personnel Error.Spray Pump Circuit Breakers re-energized | /03L-0:on 780112,both Containment Spray Pumps Found Inoperable.Caused by Personnel Error.Spray Pump Circuit Breakers re-energized | | | 05000346/LER-1978-008, Forwards LER 78-008/03L-0 | Forwards LER 78-008/03L-0 | | | 05000346/LER-1978-009-03, /03L-0:on 780112,component Cooling Water Heat Exchanger 1-1 Outlet Isolation Valve SW 1424 Declared Inoperable.Caused by Component Failure.Solenoid Valve in Control Scheme Found Burned Out.Unit Removed | /03L-0:on 780112,component Cooling Water Heat Exchanger 1-1 Outlet Isolation Valve SW 1424 Declared Inoperable.Caused by Component Failure.Solenoid Valve in Control Scheme Found Burned Out.Unit Removed | | | 05000346/LER-1978-009, Forwards LER 78-009/03L-0 | Forwards LER 78-009/03L-0 | | | 05000346/LER-1978-010-03, /03L-0:on 780115, Reactor Coolant Pump Monitor on Channel 1 Found Out of Tolerance & Reactor Protection Sys Declared Inoperable.Caused by Defective Module.New Module Calibr & Installed | /03L-0:on 780115, Reactor Coolant Pump Monitor on Channel 1 Found Out of Tolerance & Reactor Protection Sys Declared Inoperable.Caused by Defective Module.New Module Calibr & Installed | | | 05000346/LER-1978-010, Forwards LER 78-010/O3L-0 | Forwards LER 78-010/O3L-0 | | | 05000346/LER-1978-011, Forwards LER 78-011/03L-0 | Forwards LER 78-011/03L-0 | | | 05000346/LER-1978-011-03, /03L-0:on 780116,during Surveillance Test,Decay Heat Pump 1-1 Failed to Start.Caused by Fuses in Breaker for Decay Heat Motor Failing to Make Proper Contact.Control Power Fuese Pulled & Reinserted.Pump Returned to Svc | /03L-0:on 780116,during Surveillance Test,Decay Heat Pump 1-1 Failed to Start.Caused by Fuses in Breaker for Decay Heat Motor Failing to Make Proper Contact.Control Power Fuese Pulled & Reinserted.Pump Returned to Svc | | | 05000346/LER-1978-012, Forwards LER 78-012/03L-0 | Forwards LER 78-012/03L-0 | | | 05000346/LER-1978-012-03, /03L-0:on 780124,personnel Airlock Failed Leak Rate Test.Caused by Loose Shaft Seal Due to Routine Use of Personnel & Escape Lock (Exit/Entry to Containment).Shaft Seals Tightened to Prevent Excessive Leakage | /03L-0:on 780124,personnel Airlock Failed Leak Rate Test.Caused by Loose Shaft Seal Due to Routine Use of Personnel & Escape Lock (Exit/Entry to Containment).Shaft Seals Tightened to Prevent Excessive Leakage | | | 05000346/LER-1978-013-03, /03L-0:780119,Cell 32 in Station Battery 1N Electrolyte Specific Gravity Decreased 0.003 Greater than Allowed by Tech Spec 3.8.2.3.Caused by Electrolyte Stratification Due to Low Battery Loading | /03L-0:780119,Cell 32 in Station Battery 1N Electrolyte Specific Gravity Decreased 0.003 Greater than Allowed by Tech Spec 3.8.2.3.Caused by Electrolyte Stratification Due to Low Battery Loading | | | 05000346/LER-1978-013, Forwards LER 78-013/03L-0 | Forwards LER 78-013/03L-0 | | | 05000346/LER-1978-014, Forwards LER 78-014/03L-0 | Forwards LER 78-014/03L-0 | | | 05000346/LER-1978-014-03, /03L-0:on 780123,quandrant Power Tilt in Excess of Steady State & Transient Limits Indicated by Unit Process Computer.Caused by Detector Inadvertently Left Off Scan After Testing.Test Procedure Being Modified | /03L-0:on 780123,quandrant Power Tilt in Excess of Steady State & Transient Limits Indicated by Unit Process Computer.Caused by Detector Inadvertently Left Off Scan After Testing.Test Procedure Being Modified | | | 05000346/LER-1978-015, Forwards LER 78-015/03L-0 | Forwards LER 78-015/03L-0 | | | 05000346/LER-1978-015-03, /03L-0:on 780131,feedwater Steam Generator 1 Channel 2 Pressure Differential Switch Did Not Actuate at Desired Setpoint During Surveillance Test.Caused by Pressure Differential Switch Out of Tolerance | /03L-0:on 780131,feedwater Steam Generator 1 Channel 2 Pressure Differential Switch Did Not Actuate at Desired Setpoint During Surveillance Test.Caused by Pressure Differential Switch Out of Tolerance | | | 05000346/LER-1978-016-03, /03L-1:on 780202,absolute Position Indicator for Group 5,Rod 12,declared Inoperable.Caused by Component Failure in Penetration Area.Containment Conductors Connected to Spare Penetration Connector | /03L-1:on 780202,absolute Position Indicator for Group 5,Rod 12,declared Inoperable.Caused by Component Failure in Penetration Area.Containment Conductors Connected to Spare Penetration Connector | | | 05000346/LER-1978-016, Forwards LER 78-016/03L-1,LER 78-021/03L-1,LER 78-100/03L-1, LER 78-034-03L-1 & LER 78-024/03L-1 | Forwards LER 78-016/03L-1,LER 78-021/03L-1,LER 78-100/03L-1, LER 78-034-03L-1 & LER 78-024/03L-1 | | | 05000346/LER-1978-017, Forwards LER 78-017/03L-0 | Forwards LER 78-017/03L-0 | | | 05000346/LER-1978-017-03, /03L-0:on 780126,all Meteorological Channels Became Inoperable During Blizzard.Caused by Instrumentation Power Loss Due to Tripped Breaker at Meteorological Tower. Breaker Reset on 780128 | /03L-0:on 780126,all Meteorological Channels Became Inoperable During Blizzard.Caused by Instrumentation Power Loss Due to Tripped Breaker at Meteorological Tower. Breaker Reset on 780128 | | | 05000346/LER-1978-018-03, /03L-0:on 780208,diesel Generator 1-1 Making Unusual Noises During Monthly Test.Unusual Noise Traced to Turbocharger.Exact Cause Undetermined.Turbocharger Replaced & Diesel Generator Monthly Test Completed | /03L-0:on 780208,diesel Generator 1-1 Making Unusual Noises During Monthly Test.Unusual Noise Traced to Turbocharger.Exact Cause Undetermined.Turbocharger Replaced & Diesel Generator Monthly Test Completed | | | 05000346/LER-1978-018, Forwards LER 78-018/03L-0 | Forwards LER 78-018/03L-0 | | | 05000346/LER-1978-019-03, /03L-1:on 780210,decay Heat Cooler Outlet Valve DH14A & DH14B Mechanical Stops Found Incorrectly Opened. Caused by Personnel Incorrectly Resetting Stops After Previous Work Completion.Stops Tagged & Records Marked | /03L-1:on 780210,decay Heat Cooler Outlet Valve DH14A & DH14B Mechanical Stops Found Incorrectly Opened. Caused by Personnel Incorrectly Resetting Stops After Previous Work Completion.Stops Tagged & Records Marked | | | 05000346/LER-1978-020, Forwards LER 78-020/03L-0 | Forwards LER 78-020/03L-0 | | | 05000346/LER-1978-020-03, /03L-0:on 780210,reactor Protection Sys Channel 3 Hot Leg Temp String TI-RC3B4 Declared Inoperable.Caused by Loose Wire Connection.Loose Terminal at Temp Element Tightened,Rendering TI-RC3B4 Operable | /03L-0:on 780210,reactor Protection Sys Channel 3 Hot Leg Temp String TI-RC3B4 Declared Inoperable.Caused by Loose Wire Connection.Loose Terminal at Temp Element Tightened,Rendering TI-RC3B4 Operable | | | 05000346/LER-1978-021-03, /03L-1:on 780220,absolute Position Indicator for Control Rod 12 of Group 5 Declared Inoperable.Caused by Component Failure in Penetration Area.Conductors Connected W/Spare Penetration Connectors | /03L-1:on 780220,absolute Position Indicator for Control Rod 12 of Group 5 Declared Inoperable.Caused by Component Failure in Penetration Area.Conductors Connected W/Spare Penetration Connectors | | | 05000346/LER-1978-022-03, /03L-0:on 780223,flow Transmitter FTRC1A3 Found Inoperable.Caused by Defective Flow Transmitter Amplifier. Amplifier Replaced & Flow Transmitter FTRC1A3 Returned to Svc on 780226 | /03L-0:on 780223,flow Transmitter FTRC1A3 Found Inoperable.Caused by Defective Flow Transmitter Amplifier. Amplifier Replaced & Flow Transmitter FTRC1A3 Returned to Svc on 780226 | | | 05000346/LER-1978-022, Forwards LER 78-022/03L-0 | Forwards LER 78-022/03L-0 | | | 05000346/LER-1978-023-03, /03L-0:on 780224,temp Indication for Reactor Protection Sys Channel 2 Spiked Tripping Channel & Shut Down Reactor.Caused by Faulty Connector Due to Dirt on Contacts. Channel 2 Temp String Modules Removed & Connectors Cleaned | /03L-0:on 780224,temp Indication for Reactor Protection Sys Channel 2 Spiked Tripping Channel & Shut Down Reactor.Caused by Faulty Connector Due to Dirt on Contacts. Channel 2 Temp String Modules Removed & Connectors Cleaned | | | 05000346/LER-1978-023, Forwards LER 78-023/03L-0 | Forwards LER 78-023/03L-0 | | | 05000346/LER-1978-024-03, /03L-1:on 780228,MSIV MS-101 Rendered Inoperable to Allow Maint Personnel to Remove Raised Metal on Two of Four Spring Guide Tubes.Cause of Raised Metal Unknown.Metal Filed Down,Valve Closing Time Adjusted & Valve Tested | /03L-1:on 780228,MSIV MS-101 Rendered Inoperable to Allow Maint Personnel to Remove Raised Metal on Two of Four Spring Guide Tubes.Cause of Raised Metal Unknown.Metal Filed Down,Valve Closing Time Adjusted & Valve Tested | | | 05000346/LER-1978-025-03, /03L-0:on 780304,RCS Leakage Found Greater than 1 Gallon Per Minute.Leakage Cause Undetermined.Leakages Processed Through Normal Containment Sump.Unidentified RCS Leakage Reduced Below 1 Gallon Per Minute in 5.5-h | /03L-0:on 780304,RCS Leakage Found Greater than 1 Gallon Per Minute.Leakage Cause Undetermined.Leakages Processed Through Normal Containment Sump.Unidentified RCS Leakage Reduced Below 1 Gallon Per Minute in 5.5-h | | | 05000346/LER-1978-025, Forwards LER 78-025/03L-0 | Forwards LER 78-025/03L-0 | | | 05000346/LER-1978-026, Forwards LER 78-026/03L-0 | Forwards LER 78-026/03L-0 | | | 05000346/LER-1978-026-03, /03L-0:on 780309,radiation Monitor Re 5029 Found Inoperable Due to Low Sample flow.12 Previous Radiation Monitor Inoperabilities Not Reported.Caused by Pump Motor Bearing Seizure Due to High Ambient Temp | /03L-0:on 780309,radiation Monitor Re 5029 Found Inoperable Due to Low Sample flow.12 Previous Radiation Monitor Inoperabilities Not Reported.Caused by Pump Motor Bearing Seizure Due to High Ambient Temp | | | 05000346/LER-1978-027, Forwards LER 78-027/03L-0 | Forwards LER 78-027/03L-0 | | | 05000346/LER-1978-027-03, /03L-0:on 780316,stop Valve AF3870 Failed to Open During Testing.Caused by High Differential Pressure Due to Check Valve AF39 & AF72 Leakage.Motor Operator Initially Not Adjusted for This Pressure,Causing Operator to Torque | /03L-0:on 780316,stop Valve AF3870 Failed to Open During Testing.Caused by High Differential Pressure Due to Check Valve AF39 & AF72 Leakage.Motor Operator Initially Not Adjusted for This Pressure,Causing Operator to Torque Out | | | 05000346/LER-1978-028-03, /03L-0:on 780318,channel 1 Steam Generator 1-1 Declared Inoperable.Caused by Water in Level Transmitter SP09B8 Connecting Box Due to Steam Leak.Connection Box Cleaned & Dried.Waterproof Fitting Will Be Installed | /03L-0:on 780318,channel 1 Steam Generator 1-1 Declared Inoperable.Caused by Water in Level Transmitter SP09B8 Connecting Box Due to Steam Leak.Connection Box Cleaned & Dried.Waterproof Fitting Will Be Installed | |
|