LER-1978-126, /03L-0 on 781230:during Startup of Component Cooling Water Pump,Heat Exchanger 1-1 Svc Water Outlet Valve SW-1424 Would Not Open Due to Slippage & Misalignment of Valve Linkage;Led to Continuous Valve Oscillation |
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U.S. NUCLE AR REGULATORY COMMISSION NRC FORM 366 (7 77)
LICENSEE EVENT REPORT CONTROL BLOCK: l l
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8 60 61 DOCKET NUYSER 68 63 EVENT D ATE 74 75 REPORT DATE 80 g
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lDuring the startup of the Component Cooling Water (CCIO Pump 1-1 on 12/30/78. the ener4 o
2 lator noticed that the CCW Heat Exchanger 1-1 Service Water Outlet Valve SW-1424 would I o
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4 inot open. The standby CCW Pump (1-3) was placed in service to replace CCW Pump and
[ Heat Txchanger 1-1.
No cause for the improper operation was found, and CCW Pump and I
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Heat Exchanger 1-1 was returned to service.
On 12/31/78. it was noticed that valve 1
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ISW-1424 would not maintain temnerature oroperiv. The stamibv CCW 1000 was available. I l
lThe reactor was not critical.
(NP-33-7 8-147 )
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CAUSE
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40 41 42 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l Slippage and misalignment of the valve linkage caused the actuator to function in-
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The valve was then placed in service and is j
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l l being monitored for proper performance.
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j TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-78-147 DATE OF EVENT: December 30, 1978 FACILITY:
Davis-Besse Unit 1 TDENTIFICAT10N OF OCCURRENCE: Component Cooling Water Heat Exchanger Service Water Outlet Valve operating improperly.
The unit was in Mode 3, with Power (MWT) = 0, and Conditions Prior to Occurrence:
Load (Gross MWE) = 0.
Cooling Description of Occurrence: On December 30, 1978 at 2242 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.53081e-4 months <br />, Component the operator noticed that During the startup, Water (CCW) Pump 1-1 was started.
open.
CCW the CCW Heat Exchanger 1-1 Service Water Outlet Valve SW-1424 would not This placed the unit in the Pump 1-2 "was started and CCW Pump 1-1 was stopped. Action Statement o loops while the unit is in Modes 1 through 4.
The standby CCW loop (1-3) was lined This removed the unit from the up and placed in service to replace CCW Loop 1-1.
Action Statement of Technical Specification 3.7.3.1.
Instrument and Control personnel investigated the problem under Maintenance Work After satisfactor-No cause for the improper operation was found.
Order 1C-114-79.
ily operating valve SW-1424 both manually and automatically, it was returned to service.
1978, it was noticed that valve SW-1424 would not maintain tempera-On December 31, The valve would have opened if a safety injection had accurred, ture properly.
The cause of occurrences was dis-therefore the loop was not declared inoperable.
covered during the corrective action taken af ter the December 31 incident.
The improper operation of valve SW-1424 Designation of Apparent Cause of Occurrence:
was attributed to a possible design deficiency in the slippage and misalignment of It is believed This led to continuous oscillation of the valve.
the valve linkage.
the vibration of the actuator linkage loosens the nut retaining the two linkage arms.
There was no danger to the health and safety of the public Analysis of Occurrence:
The reactor was not or to unit personnel. The standby CCW loop was available.
critical.
79-1206, the On January 2, 1979, under Maintenance Work Order
Corrective Action
valve linkage was adjusted and calibrated. The valve was then placed in service and is being monitored for proper performance.
LER #78-126
a TOLEDO EDISON COMPNTY DAVIS-BESSE !?UCLEAR POWER STATION UNIT ONE PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-78-147 In order to prevent recurrence of misalignment of valve linkage, a Facility Change Request will be submitted which will request the linkage be modified to prevent vibration from loosening the nut.
There have been two previously reported occurrences of actuator Failure Data:
inoperabilities of a Service Water valve. The inoperabilities reported in Licen-see Event Report (LER) NP-33-78-120 were caused by a nut missing on the actuator and LER NP-33-78-11 was caused by a failure of a solenoid valve.
LER #78-126 4
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| 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 | |
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