LER-1978-012, /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 |
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";GuiT b?.3ER 94 6J Ev ENT GATg 74 EVENT DESCRIPTION AND PRCS ABLE CONSEC'.,ENCES h 13121 l Cn 1/21/73, the personnel airlock failed i:s leak race test.
This olaced the unit inl
- o ;3, ; the Action Statenent (A.S. ) of Tech Spec 3.6.1.3.
The leak was stopped and the unit l l o 14 I I recoved from the A.S. within seven hours.
On 1/25/78, the escape airlock failed its l l a ! 3, ; leak rate test, again placing the unit in the A.S. ot Tech Spec 3.6.1.3.
This leak [
[a ;g ; ; was also stopped, removing the unit from the A..S. within ten hours.
In both cases, s
- 3;7l l only the exterior door leaked excessively; the interior door maintained containment I io;g, ; integrity.
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- i jo1] The apparent cause of this occurrence is that the shaft seal (teflon cackinc) loosenad N
f l jil l due to routine use of cersonnel and escace lock (exit /entrv to e,ontainment).
tit 7!l shaft seals were ti2htened to erevent excessive leaks 2e.
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DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION (V
j SUPPLDIENTAL INFORMATION FOR LER NP-33-78-15 DATE OF EVENT:
January 24 and 25,.1978 FACILITY:
Davis-Besse Unit 1 IDENTIFICATION OF GCCURRENCE: Overall air lock leakage rate for personnel and escape lock exceeded Technical Specification limit.
Conditions Prior to Occurrence:
The unit was in Mode 1, with Power (MWT) = 2079 and Load-OCIE) = 700.
Description of Occurrence: 'At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on January 24, 1978, during the perfor-mance of Surveillance Test, ST 5061.02, " Volumetric Leakage Test", for the per-sonnel lock, the leakage race exceeded the allowable leakage rate of Technical Specification 3.6.1.3.
This placed the unit in the Action Statement of Technical Specification 3.6.1.3,, which requires both containnent airlocks operable in Modes 1, 2, 3, and 4 Leakage was detected at the shaft seal on the lower handwheel of the exterior door.
O At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on January 25, 1978, during the performance of the Volumetric
!\\s 'j Leakage Test, ST 5061.02, of the escape lock, the leakage race exceeded the allowable leakage rate of Technical Specification 3.6.1.3, placing the unit in the Action Statement of Technical Specification 3.6.1.3.
Leakage was detected at the shaft seal on the lower and upper handwheel of the exterior door.
Designation of Accarent Cause of Occurrence:
The apparent cause of this occur-rence is the shaft seal (teflon packing) loosened due to routine use of per-sonnel and escape lock (exit / entry to containment).
Analysis of Occurrence:
There was no danger to the health 2nd safety of the public or to unit personnel.
There was no leakage detected on the interior door on both the personnel and escape lock which would have prevented any leak-age from containment leaking to an outside area if containment isolation had been needed.
Corrective Action
The shaft seal of the lower exterio'r door handwheel on the personnel lock was tightened per Maintenance Work Crder 78-213 and the Volume-tric Leakage Test, ST 3061.02 was successfully completed at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on Janu-ary 25, 1978.
This removed the unit from the Action Statement of Technical Specification 3.6.l.3.
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The shaft seals on the lower and upper exterier door handwheel on the escape t
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lock were tightened per Maintenance Work Order 78-219 and the Volumetric Leakage x.y l'
LER #78-012 l
1 TOLEDO EDISON CCMPANY I
DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION SUPPLEMENTAL ITT00tATION FOR LER NP-33-78-L5 PAGE 2 4
Test was successfully completed at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on January 25, 1978.
This removeo che unit from the Action Statement of Technical Specification 3.6.1.3.
For both incidents, the test was completed well within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ti=e re-i quirement of the Action Statement. Maintenance is investigating the replacement of the seals to prevent recurrence.
l Failure Data: There have been no previously reportable occurrences of excessive personnel hatch leakage.
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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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