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LER-1982-070, Forwards LER 82-070/03L-0.Detailed Event Analysis Encl |
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O PSIEG I
Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station October 6, 1982 f
Mr.
R.
C. Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Haynes:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 82-070/03L Pursuant to the requirements of Salem Generating Station Unit No.
1, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 82-070/03L.
This report is required within thirty (30) days of the occurrence.
Sincerely yours,
}
b H.
J. Midura General Manager -
Salem Operations RF:ksyg,/
l CC:
Distribution l
8210210134 821006 PDR ADOCK 05000272 S
PDR
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The Energy People p#
j miso mesi L
Report Number:
82-070/03L Report Date:
Occurrence Date:
09-12-82 Facility:
Salem Generating Station, Unit 1 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
DNB Parameters - Pressurizer Pressure - Out of Specification.
This report was initiated by Incident Reports82-274 and 82-283.
CONDITIONS PRIOR.TO OCCURRENCE:
Mode 1 - Rx Power 100% - Unit Load 1080 MWe.
DESCRIPTION OF OCCURRENCE:
At 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br />, September 12, 1982, during the performance of functional testing of Pressurizer Pressure Channel ~III instru-ment, the Control Room Operator noticed that pressure was approximately 2205 PSIA and decreasing.
A survey of the control board revealed that the pressurizer controller was'in the manual mode of operation.
The automatic. mode had been selected prior.
to the occurrence.
Control was returned to automatic, the backup heaters energized and pressure started to increase.
With pressure less than the Technical Specification limit of'2220 PSIA, Action Statement 3.2.5 was entered, retroactive to the time of discovery of the problem. ~ Pressurizer pressure increased until 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br /> when it returned within specification limits and Action Statement 3.2.5 was terminated.
The minimum pressure reached during the l
transient was 2200 PSIA.
At 1436 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.46398e-4 months <br />, September 14, 1982, a similar malfunction of the pressurizer pressure controller was observed, and Action Statement 3.2.5 was entered for a'second time. 'The control room operator again returned the controller ' to the automatic mode and pressure was returned to within limits.
The action statement was terminated at 1448 hours0.0168 days <br />0.402 hours <br />0.00239 weeks <br />5.50964e-4 months <br />, September 14, 1982; minimum' pressure observed was 2155' PSIA.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Investigation of the first occurrence showed no link to performance of the surveillance.
In both. instances, the controller tested satisfactorily following the malfunction.
A similar. problem had l
occurred on June 4, 1982'(see~LER 82-038/03L), with no identifiable failure in the controller.
The occurrences were therefore attributed to;an intermittant problem in'either the pressure-l controller or the manual-auto station..
i I
LER 82-070/03L' '
ENALYSIS OF OCCURRENCE:
In accordance with the Technical Specification basis for Limiting Condition for Operation 3.2.5, compliance with the Specification limits assure DNB parameters are within the steady state envelope of operation assumed in the transient and accident analyses of the FSAR.
The limits are consistent-with-the initial FSAR assumptions, and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed _ transient.
The FSAR does not consider, however, events starting during transients which are already in progress.
Action Statement 3.2.5 requires:
With any of the DNB parameters exceeding.its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or reduce thermal power to less than 5% of rated thermal power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.-
The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limit contained in the action statement ensures that, following unexpected transients of the type involved in these
[
occurrences, DNB parameters are returned within the envelope assumed' in the FSAR.
In both instances, pressurizer. pressure was within the DNB limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and consequently, no risk to the health or safety of the public was involved.
These occurrences constituted operation in a degraded mode permitted-by a limiting condition for operation,'and were reportable in' accordance with Technical Specification 6.9.1.9.b.
In the event the operator had failed-to notice the decreasing.
pressure, a Pressurizer Pressure-Low trip would have initiated a reactor shutdown at 1880 PSIA, maintaining a minimum DNBR of 1.30, as demonstrated by the FSAR.
As such, the' occurrence would still not have involved any risk to the health or safety of the public.
CORRECTIVE ACTION
As noted, in both instances pressure'was returned to within limits and the-action statement was terminated within the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> interval.
The manual-auto station was. replaced'and'the channel was satis-factorily' tested on September 16, 1982; no further problems'have been noted.
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FAILURE DATA:
Hagan Corporation Manual-Auto Station Model 124 4
l
- - Prepared By-R.
Frahm Genefal Manager --
Salem Operations SORC Meeting No.
82-88
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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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