Similar Documents at Salem |
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LER-1982-101, Forwards LER 82-101/01T-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
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September 22, 1982 l
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 82-101/0lT Pursuant to the requirements of Salem Generating Station Unit No. 2, Technical Specifications, Section 6.9.1.8.c, we are submitting Licensee Event Report for Reportable Occurrence 82-101/0lT.
This report is required within fourteen (14) days of the occurrence.
Sincerely yours, H.
J. Midura General Manager -
Salem Operations RF:ks [ h CC:
Distribution l
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( 821'0070221 B20922 I PDR ADOCK 05000311 C_E PDR The Energy People 95 2189 (20M) 1181
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9 Report Number:
82-101/0lT Report Date:
09-22-82 Occurrence Date:
09-16-82 Facility:
Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Containment Service Water Leak - No. 21 Containment Fan Coil Unit.
This report was initiated by Incident Report 82-278.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 - Rx Power 82% - Unit Load 900 MWe.
DESCRIPTION OF OCCURRENCE:
At 0033 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, September 16, 1982,,during an inspection of the Containment Building, an operator discovered service water leakage of approximately 0.5 GPM on No. 21 Containment Fan Coil Unit (CFCU).
The unit was isolated and the NRC was noti-fied by telephone at 0039 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br />.
Since No. 22 CFCU was in-operable with a service water leak (see LER 82-100/OlT), Technical Specification Action Statement 3.6.2.3.a was in effect.
With two CFCU's inoperable, Action Statement 3.6.2.3.b was entered.
Both containment spray systems were operable throughout the occur-rence providing containment cooling capability.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Investigation of the problem revealed that the leakage was due to erosion of the cooling coils.
The coils are fabricated of copper nickel alloy, which is susceptible to erosion by silt laden service water.
Similar failures of other CFCU's have been noted, with most leaks occurring at bends where erosion is more significant.
ANALYSIS OF OCCURRENCE:
Primary containment is a design feature which ensures that the release of radioactive materials in the event of accident con-ditions will be restricted such that site boundary radiation doses will be within the limits of 10CFR100.
LER 82-101/0lT.
ANALYSIS OF OCCURRENCE:NRC IE Bulletin 80-24 requires that any service water leak inside the containment be considered as a degradation of the containment boundary.
If containment pressure increased to the design pressure of 47 psig during an accident, there is a possibility of the re-lease of radioactivity through the service water discharge.
The occurrence, therefore, constituted an abnormal degradation of the primary containment and is reportable in accordance with Technical Spscification 6.9.1.8.c.
The CFCU's operate in conjunction with the containment spray systems to remove heat and radioactive contamination from the containment atmosphere in the event of a design basis accident.
Operability of either all fan coil groups or of both containment spray systems is necessary to ensure offsite radiation dose is maintained within the limits of 10CFR100.
Action Statement 3.6.2.3a requires:
With one group of CFCU's inoperable and both containment spray systems operable, restore the inoperable group of cooling fans to operable status within 7 days, or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Action Statement 3.6.2.3b requires:
With two groups of containment cooling ft s inoperable, restore at least one group.
cooling fans to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Because the leakage was immediately isolated, containment integrity was maintained.
Containment cooling capability was provided by the containment spray systems.
The occurrence, therefore, involved no risk to the health or safety of the public.
Due to the loss of redundancy in design and engineered safety features, the event constituted operation in a degraded mode permitted by the limiting conditions for operation.
CORRECTIVE ACTION
As noted, the leakage on No. 21 CFCU was immediately isolated and prompt notification of the NRC was performed in accordance with Technical Specification 6.9.1.8.
No. 22 CFCU had beentropaired and declared operable at 1852 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.04686e-4 months <br />, September 16, 1982.
Action Statement 3.6.2.3b was terminated at that time; Action Statement 3.6.2.3a remained in effect, however.
Investigation of the problem with No. 21 CFCU showed that actually five small leaks were in-volved.
The leaks were repaired utilizing Belzona metal filler and a blank in the service water piping.
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LER 82-101/OlT.
CORRECTIVE ACTION
The unit was satisfactorily tested and returned to service.
No. 21 CFCU was declared operable and Action Statement 3.6.2.3.a was terminated at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />, September 18, 1982.
Design Change Request 2EC-0505 has been issued to replaqe the CFCU cooling coils with coils manufactured of AL-6X steel, for improved erosion and corrosion resistance in the service water environment.
This change is scheduled for implementation during the next refueling outage.
A commitment to submit a Supplemental Report upon completion was made in LER 82-070/OlT.
FAILURE DATA:
A number of containment service water leaks due to similar failures of CFCU cooling coils have occurred since January 1,
1982.
Westinghouse Electric Corporation Containment Fan Coi) Unit U-Tube Cooling Coil Prepared By R. Frahm
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'GeWeral Manager -
Salem Operations SORC Meeting No.
82-85 e
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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. 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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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