Similar Documents at Salem |
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LER-1982-110, Forwards LER 82-110/03L-0.Detailed Event Analysis Encl |
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"O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station October 20, 1982 Mr. R.
C. Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Haynes:
LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-110/03L Pursuant to the requirements of Salem Generating Station Unit No.
2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 82-110/03L.
This report is required within thirty (30) days of the occurrence.
Sincerely yours,
/I h"
H.
J. Midura General Manager -
Salem Operations RF:ks Afg CC:
Distribution 1
8211020126 821020 PDR ADOCK 05000311 4
S PDR The Energy People g@
% 2189 GOM) 1181
Report Number:
82-110/03L Report Date:
10-20-82 Occurrence Date:
09-26-82 Facility:
Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
100' Elevation Containment Air Lock - Inoperable.
This report was initiated by Incident Reports82-306 and 82-307.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 - Rx Power 81% - Unit Load 820 MWe.
DESCRIPTION OF OCCURRENCE:
At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />, September 26, 1982, during routine operation of the 100' Elevation Containment Air Lock, an operator observed that there was no indication of seal interspace air pressure.
The air lock was declared inoperable and Action
- - Statement 3.6.1.3.a was entered.
The air lock doors were maintained closed to provide for containment integrity.
Later that day, an operator was able to restore air pressure to the seals by manually relocating the air interlock linkage, and the air lock was satisfactorily tested.
The 100' Elevation Air Lock was declared operable at 0838 hours0.0097 days <br />0.233 hours <br />0.00139 weeks <br />3.18859e-4 months <br />, September 26, 1982, and Action Statement 3.6.1.3.a was terminated.
Adjustment of the linkage.was subsequently checked and found to be correct; it was assumed that the linkage had jammed in an apparently isolated occurrence.
At 0628 hours0.00727 days <br />0.174 hours <br />0.00104 weeks <br />2.38954e-4 months <br />, September 27, 1982, during the performance of surveillance on the 100 ' Elevation Air Lock seals, the leakage i
on the exterior door seals was found to be greater than the l
test specification.
The air lock was declared inoperable and Action Statement 3.6.1.3.a was entered for a second time.
The l
excessive leakage had resulted from the failure of the inner rubber seal and a new seal was installed.
During retesting of the door, however, a failure of the test air supply similar to that of the previous day was observed.
Containment integrity was maintained by insuring the inner door was closed throughout the occurrence.
LER 82-110/03L,
DESIGNATION OF APPARENT'CAUSE OF OCCURRENCE:-
Investigation ~of the problem with the air supply to the 100' Elevation Air Iack revealed-that one of the pivot assemblies for the' air interlock-linkage was loose; the-problem had been overlooked in the inve'stigation following the first occurrence.
The. excessive leakage in the second case apparently involved a parting of the bonded joint in the seal.
No previous. failures of either type have been~ observed and the events were assumed to be isolated in nature.
ANALYSIS OF OCCURRENCE:
The containment air lock doors allow fo. personnel access to the Containment Building while providing a redundant boundary as part of overall containment integrity.
This barrier prevents the release of. radioactive contamination to the environment in the event of a design basis accident.
Since one door was main-tained closed, pr)viding containment integrity, no risk to the health and safety of the public was involved.
Therefore, this event constituted operation in a degraded mode permitted by a limiting conditon for operation, and is reportable in_accordance with Technical Specification 6.9.1.9.b.
Action Statement 3.6.1.3.a requires:
With one containment air lock door inoperable, maintain at least the operable air lock door closed and either restore the inoperable. door to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or lock the operable air lock door closed.
CORRECTIVE ACTION
As noted, in both instances an operable air lor?- door was main-tained closed, in compliance ~with the action statement.
In the l
first case, as mentioned, the air lock tested satisfactorily, was declared operable and the action statement terminated.- On the second occasion, the inner door _was locked closed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, in compliance with the action statement.
The failed seal was replaced, the loose pivot bracket was tightened, and the linkage was readjusted.
The air lock was satisfactorily tested'for a second time.
It was declared operable at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />, September 28, 1982, and Action Statement 3.6.1.3.a was terminated.
A number of previous problems with air lock _ operating linkage and door seals have been encountered.
Efforts.are presently underway to correct the problems including improved operator training, installation of snubbers on the doors, relocation'of air supply isolation valves and revision of the surveillance test to more accurately simulate desired air lock performance.
F-l LER 82-110/03L..
FAILURE DATA:
Chicago Bridge and. Iron Company Personnel Air Lock Door Seal.
Prepared By R.
Frahm
-/[ MS efh[W t
Generaf Man'ager -
Salem Operations SORC Meeting No.82-94B
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| 05000311/LER-1982-001, Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed | Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed | | | 05000272/LER-1982-001-03, Pressurizer Overprotection Sys Valve 1PR1 Was Isolated Due to Leakage. on 820107,while Draining Rcs,Valve 1RP2 Would Not Open. Caused by Generic Problem.Reactor Vessel Head Removed | Pressurizer Overprotection Sys Valve 1PR1 Was Isolated Due to Leakage. on 820107,while Draining Rcs,Valve 1RP2 Would Not Open. Caused by Generic Problem.Reactor Vessel Head Removed | | | 05000311/LER-1982-001-03, /03L-0:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Sticking Open,Freezing Pressure Sensing Line.Damper Freed & Closed. Line Thawed | /03L-0:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Sticking Open,Freezing Pressure Sensing Line.Damper Freed & Closed. Line Thawed | | | 05000272/LER-1982-001, Forwards Revised LER 82-001/03X-1.Detailed Event Analysis Encl | Forwards Revised LER 82-001/03X-1.Detailed Event Analysis Encl | | | 05000272/LER-1982-002-01, /01T-0:on 820119,indications of Tube Thinning Were Detected by Eddy Current Exam.Steam Generators 12 & 14 Required Two & Three Sample Insp,Respectively.All Defective Tubes & Tubes Degraded Above 30& Plugged | /01T-0:on 820119,indications of Tube Thinning Were Detected by Eddy Current Exam.Steam Generators 12 & 14 Required Two & Three Sample Insp,Respectively.All Defective Tubes & Tubes Degraded Above 30& Plugged | | | 05000311/LER-1982-002-03, /03L-0:on 820111,2A1 Battery Charger Tripped, Was Reset & Tripped Again.No Problem Found.Subsequent Trip Caused by Difference Between Battery Voltage & Battery Charger Voltage Setting.Personnel Instructed | /03L-0:on 820111,2A1 Battery Charger Tripped, Was Reset & Tripped Again.No Problem Found.Subsequent Trip Caused by Difference Between Battery Voltage & Battery Charger Voltage Setting.Personnel Instructed | | | 05000272/LER-1982-002, Supplemental LER 82-002/01X-2:on 820119,during Surveillance, Indications of Tube Thinning Detected by Eddy Current Exam. Tubes Above 30% Degradation Plugged.Tube R44C62 Sent to Westinghouse for Chemical & Metallurgical Testing | Supplemental LER 82-002/01X-2:on 820119,during Surveillance, Indications of Tube Thinning Detected by Eddy Current Exam. Tubes Above 30% Degradation Plugged.Tube R44C62 Sent to Westinghouse for Chemical & Metallurgical Testing | | | 05000311/LER-1982-002, Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Vo | Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Voltage | | | 05000311/LER-1982-003, Forwards LER 82-003/03L-0.Detailed Event Analysis Encl | Forwards LER 82-003/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1982-003-03, /03L-0:on 820106,1B & 1C Diesels Locked Out, Rendering Diesels Inoperable at Same Time.On 820106,diesel Generator 1C Declared Inoperable While Diesel 1B Out of Svc for Maint.Caused by Misinterpretation of Lockout Switch Tag | /03L-0:on 820106,1B & 1C Diesels Locked Out, Rendering Diesels Inoperable at Same Time.On 820106,diesel Generator 1C Declared Inoperable While Diesel 1B Out of Svc for Maint.Caused by Misinterpretation of Lockout Switch Tag | | | 05000311/LER-1982-003-03, /03L-0:on 820112,during Routine Calibr Testing, Radiation Monitor 2R11A Found Out of Calibr.Caused by Instrument Drift.Monitor Recalibr & Tested Satisfactorily | /03L-0:on 820112,during Routine Calibr Testing, Radiation Monitor 2R11A Found Out of Calibr.Caused by Instrument Drift.Monitor Recalibr & Tested Satisfactorily | | | 05000272/LER-1982-004-03, /03L-0:on 820109,primary Coolant Water Sample Results Indicated Excessive Boron Concentration,Constituting Positive Reactivity Change.Caused by Water Draining Out of Steam Generator Tubes.Rcs Rapid Boration Initiated | /03L-0:on 820109,primary Coolant Water Sample Results Indicated Excessive Boron Concentration,Constituting Positive Reactivity Change.Caused by Water Draining Out of Steam Generator Tubes.Rcs Rapid Boration Initiated | | | 05000272/LER-1982-004, Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration | Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration | | | 05000311/LER-1982-004, Forwards LER 82-004/03X-1.Detailed Event Analysis Encl | Forwards LER 82-004/03X-1.Detailed Event Analysis Encl | | | 05000272/LER-1982-005-01, /01X-1:on 820131,degradation of Fuel Cladding on Fuel Assembly C-04 Discovered.Caused by Fuel Lockup Due to Wedged Fuel Pellet.Fuel Assembly Placed in Spent Fuel Pit. All C Assemblies Scheduled for Reuse in Core | /01X-1:on 820131,degradation of Fuel Cladding on Fuel Assembly C-04 Discovered.Caused by Fuel Lockup Due to Wedged Fuel Pellet.Fuel Assembly Placed in Spent Fuel Pit. All C Assemblies Scheduled for Reuse in Core | | | 05000272/LER-1982-005, Forwards LER 82-005/01X-1.Detailed Event Analysis Encl | Forwards LER 82-005/01X-1.Detailed Event Analysis Encl | | | 05000311/LER-1982-005, Forwards LER 82-005/03L-0.Detailed Event Analysis Encl | Forwards LER 82-005/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1982-005-03, /03L-0:on 820121,during Performance of M3T Maint Surveillance Test Undervoltage Relay on 2C Vital Bus Actuated at 5.5 Volts Instead of 77.3 Volt Trip Setpoint Value.No Defects Found.Relay Recalibr | /03L-0:on 820121,during Performance of M3T Maint Surveillance Test Undervoltage Relay on 2C Vital Bus Actuated at 5.5 Volts Instead of 77.3 Volt Trip Setpoint Value.No Defects Found.Relay Recalibr | | | 05000272/LER-1982-006-03, /03L-0:on 820113,air Particulate Detector Failed. Cause Not Stated.All Required Containment Purge & Pressure Vacuum Relief Penetrations Isolated.High & Low Speed Filter Paper Drives Replaced | /03L-0:on 820113,air Particulate Detector Failed. Cause Not Stated.All Required Containment Purge & Pressure Vacuum Relief Penetrations Isolated.High & Low Speed Filter Paper Drives Replaced | | | 05000272/LER-1982-006, Forwards LER 82-006/03L-0.Detailed Event Analysis Encl | Forwards LER 82-006/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1982-006, Forwards LER 82-006/03L-0.Detailed Event Analysis Encl | Forwards LER 82-006/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1982-006-03, /03L-0:on 820128,svc Water Flow Indicator Indicated No Flow Condition.Caused by Svc Water Discharge Valve 22SW223 Being Stuck Shut.Valve Opened,Locally Tested & Returned to Svc | /03L-0:on 820128,svc Water Flow Indicator Indicated No Flow Condition.Caused by Svc Water Discharge Valve 22SW223 Being Stuck Shut.Valve Opened,Locally Tested & Returned to Svc | | | 05000272/LER-1982-007-01, /01X-2:on 820211,during Design Review,Discovered That Check Valves 1AF71 & 1AF72 & Associated Piping Not Seismically Analyzed & Protected.Protective Steel Structures Provided Off Seismic Wall | /01X-2:on 820211,during Design Review,Discovered That Check Valves 1AF71 & 1AF72 & Associated Piping Not Seismically Analyzed & Protected.Protective Steel Structures Provided Off Seismic Wall | | | 05000272/LER-1982-007, Forwards LER 82-007/01X-2 | Forwards LER 82-007/01X-2 | | | 05000272/LER-1982-008, Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added | Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added | | | 05000272/LER-1982-008-03, /03L-0:on 820126,sample Results from Boric Acid Tanks Indicated Boric Acid Concentration Below Tech Specs. Refueling Water Storage Tank Low.Core Alterations & Positive Reactivity Changes Suspended.Level Adjusted | /03L-0:on 820126,sample Results from Boric Acid Tanks Indicated Boric Acid Concentration Below Tech Specs. Refueling Water Storage Tank Low.Core Alterations & Positive Reactivity Changes Suspended.Level Adjusted | | | 05000311/LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Encl | Forwards LER 82-008/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1982-008-03, /03L-0:on 820128,overpower Delta T Indication for Channel 21 Failed High.Caused by Signal Summator 2T-M412E Having No Output Due to Failed Capacitors. Five Capacitors Replaced | /03L-0:on 820128,overpower Delta T Indication for Channel 21 Failed High.Caused by Signal Summator 2T-M412E Having No Output Due to Failed Capacitors. Five Capacitors Replaced | | | 05000311/LER-1982-009, Forwards LER 82-009/03L-0.Detailed Event Analysis Encl | Forwards LER 82-009/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1982-009, Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage | Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage | | | 05000272/LER-1982-009-03, /03L-0:on 820118 & 25,switches for Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Tank Area 12 Had Been in Manual Position for Greater than 14 Days Due to Maint Outage | /03L-0:on 820118 & 25,switches for Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Tank Area 12 Had Been in Manual Position for Greater than 14 Days Due to Maint Outage | | | 05000311/LER-1982-009-03, /03L-0:on 820129,air Particulate Detector Pump Low Flow Alarm Annuniciated.Caused by Incorrect Normal Flow Valve Lineup to Pump.Pump Removed from Normal Flow & Placed in Backup Flow Lineup | /03L-0:on 820129,air Particulate Detector Pump Low Flow Alarm Annuniciated.Caused by Incorrect Normal Flow Valve Lineup to Pump.Pump Removed from Normal Flow & Placed in Backup Flow Lineup | | | 05000311/LER-1982-010-03, /03L-0:on 820201,discrepancy Between Individual Rod Position Indicator (Irpi) & Control Rod Bank Demand Indicator for Rod 2C2 Exceeded 12 Steps in Either Direction. Caused by Incorrect Calibr of Irpi.Irpi Calibr | /03L-0:on 820201,discrepancy Between Individual Rod Position Indicator (Irpi) & Control Rod Bank Demand Indicator for Rod 2C2 Exceeded 12 Steps in Either Direction. Caused by Incorrect Calibr of Irpi.Irpi Calibr | | | 05000272/LER-1982-010-03, /03X-1:on 820201,temporary Hose Connection from Unit 1 Spent Fuel Pool to Unit 2 Exchanger Found Leaking on Auxiliary Bldg 84-ft Elevation.Caused by Improper Clamp Installation.Hose Disconnected | /03X-1:on 820201,temporary Hose Connection from Unit 1 Spent Fuel Pool to Unit 2 Exchanger Found Leaking on Auxiliary Bldg 84-ft Elevation.Caused by Improper Clamp Installation.Hose Disconnected | | | 05000311/LER-1982-010, Forwards LER 82-010/03L-0.Detailed Event Analysis Encl | Forwards LER 82-010/03L-0.Detailed Event Analysis Encl | | | 05000272/LER-1982-010, Forwards LER 82-010/03X-1.Detailed Event Analysis Encl | Forwards LER 82-010/03X-1.Detailed Event Analysis Encl | | | 05000311/LER-1982-011, Forwards LER 82-011/03L-0.Detailed Event Analysis Encl | Forwards LER 82-011/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1982-011-03, /03L-0:on 820205,during Radiological Survey of Hot Laundry Trailer Area,Technician Discovered Lint from Dryer Exhaust of Trailer B Revealing Traces of Cs-137,Co-60 & Co-58.New Trailer & Lint Collector Installed | /03L-0:on 820205,during Radiological Survey of Hot Laundry Trailer Area,Technician Discovered Lint from Dryer Exhaust of Trailer B Revealing Traces of Cs-137,Co-60 & Co-58.New Trailer & Lint Collector Installed | | | 05000272/LER-1982-011, Forwards LER 82-011/03X-1.Detailed Event Analysis Encl | Forwards LER 82-011/03X-1.Detailed Event Analysis Encl | | | 05000272/LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Encl | Forwards LER 82-012/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1982-012, Forwards LER 82-012/03X-1.Detailed Event Analysis Encl | Forwards LER 82-012/03X-1.Detailed Event Analysis Encl | | | 05000311/LER-1982-012-03, /03X-1:on 820209,steam Generator Level Channel 2 Displayed Erratic Behavior,Indicating Drift.Apparently Caused by Intermittent Ground on Signal Lead.Ground Eliminated by Lifting Leads While Troubleshooting Problem | /03X-1:on 820209,steam Generator Level Channel 2 Displayed Erratic Behavior,Indicating Drift.Apparently Caused by Intermittent Ground on Signal Lead.Ground Eliminated by Lifting Leads While Troubleshooting Problem | | | 05000272/LER-1982-012-03, /03L-0:on 820223,operator Found Significant Amount of Chromated Water on Floor in Diesel Generator 1B Cubicle. Caused by Leakage on Right Side Jacket Water Heater.Jacket Water Heaters Replaced | /03L-0:on 820223,operator Found Significant Amount of Chromated Water on Floor in Diesel Generator 1B Cubicle. Caused by Leakage on Right Side Jacket Water Heater.Jacket Water Heaters Replaced | | | 05000272/LER-1982-013-03, /03L-0:on 820301,control Room Operator Closed Pressurizer Relief Valve 1PR1 When Valve 1PR2 Was Still Closed.Caused by Operator Error.Operator Counseled by Senior Shift Supervisor | /03L-0:on 820301,control Room Operator Closed Pressurizer Relief Valve 1PR1 When Valve 1PR2 Was Still Closed.Caused by Operator Error.Operator Counseled by Senior Shift Supervisor | | | 05000311/LER-1982-013, Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1982-013-03, L-0:on 820215,shift Supervisor Informed That Two 4-inch Core Bores Opened on 78-ft Elevation Between Mechanical & Electrical Penetration Areas.No Fire Watch Posted.Caused by Inadvertently Posting Watch on Wrong Unit | L-0:on 820215,shift Supervisor Informed That Two 4-inch Core Bores Opened on 78-ft Elevation Between Mechanical & Electrical Penetration Areas.No Fire Watch Posted.Caused by Inadvertently Posting Watch on Wrong Unit | | | 05000272/LER-1982-013, Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | | | 05000311/LER-1982-014-03, /03L-0:on 820219,steam Generator 21 Level Channel 2 Read 20% Higher than Channels 3 & 4.Channel 2 Declared Inoperable.Cause Unknown.Transmitter Tested & Found Satisfactory.Sensing Lines Blown Down to Remove Solids | /03L-0:on 820219,steam Generator 21 Level Channel 2 Read 20% Higher than Channels 3 & 4.Channel 2 Declared Inoperable.Cause Unknown.Transmitter Tested & Found Satisfactory.Sensing Lines Blown Down to Remove Solids | | | 05000272/LER-1982-014-03, /03L-0:on 820306,wind Speed Indications for 150 & 300-ft Elevations Failed.Local Indications Also Failed. Caused by iced-up Anemometers.Anemometers Thawed & Declared Operable | /03L-0:on 820306,wind Speed Indications for 150 & 300-ft Elevations Failed.Local Indications Also Failed. Caused by iced-up Anemometers.Anemometers Thawed & Declared Operable | | | 05000311/LER-1982-014, Forwards LER 82-014/03L-0.Detailed Event Analysis Encl | Forwards LER 82-014/03L-0.Detailed Event Analysis Encl | |
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