Similar Documents at Salem |
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LER-1982-075, Forwards LER 82-075/01T-0.Detailed Event Analysis Encl |
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O PSIEG Public Service Electric and Gas Company P.O. Box E Hancockr Bridge, New Jersey 08038 Salem Generating Station August 18, 1982 Mr.
R.
C.
Haynes Regional Administrator USNRC i
Region 1 631 Park Avenue King of Prussia, Pennsylvania 1940C
Dear Mr. Haynes:
LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-075/0lT 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 82-075/0lT.
This report is required within fourteen (14) days of the occurrence.
Sincerely yours, lw
/l s
H.
J.
Midura General Manager -
Salem Operations RF:ks.f[
CC:
Distribution 8208310150 820818
~
DR ADOCK 05000311 PDR The Energy People
. g 6*
manuvaon
I Report Number:
82-075/0lT Report Date:
08-18-82 Occurrence Date:
08-14-82 Facility:
Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Containment Service Water Leak - Nos. 22 and 24 -
Containment Fan Coil Units.
This report was initiated by Incident Reports82-216 and 82-217.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 - Rx Power 82% - Unit Load 900 MWe.
DESCRIPTION OF OCCURRENCE:
At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, August 14, 1982, during a visual inspection of the Containment Building, an operator discovered a 1 GPM service water leak from a cooling coil on No. 22 Containment Fan Coil Unit (CFCU).
At the time of discovery, No. 25 CFCU was i. operable due to a failed cooling coil, and Technical Specification Action Statement 3.6.2.3.a was in effect.
No. 22 CFCU was also declared inoperable, and Action Statement 3.6.2.3.b was entered.
Service water to the unit was immediately isolated, and prompt notification to the NRC was made.
No. 25 CFCU was repaired, and was declared operable at 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br />, August 14, 1982.
Action Statement 3.6.2.3.b was terminated; however, with No. 22 CFCU still inoperable, Action Statement 3.6.2.3.a remained in effect.
At 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br />, August 15, 1982, during a similar inspection, an operator discovered a 1 GPM leak from No. 24 CFCU.
The unit was declared inoperable, but since the unit is in the same group as No. 22 CFCU, Action Statement 3.6.2.3.b did not apply.
Service water to the unit was immediately isolated, and prompt notification was performed.
Written confirmation of both incidents was transmitted on August 16, 1982, the next working day after the occurrences.
Both containment spray systems were operable throughout the occurrences.
LER 82-075/0lT.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Investigation of the problem in both cases showed that the leakage was from the cooling coils.
The coils are fabricated from copper-nickel alloy which is susceptible to erosion by silt particles in the service water.
Similar failures of other CFCU's have been noted, with most leaks occurring at bends where erosion is more significant.
Corrosion involving dissimilar metals in the service water piping may also be involved.
ANALYSIS OF OCCURRENCE:
Primary containment is a design feature which ensures that the release of radioactive materials in the event of accident conditions will be restricted such that site boundary radiation doses will be within the limits of 10CFR100.
NRC IE Bulletin 80-24 requires that any service water leak inside the contain-ment 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 release of radioactivity through the service water discharge.
The
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occurrences therefore constituted abnormal degradation of the primary containment and are reportable in accordance with Technical Specification 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.
Because in both cases the leakage was immediately isolated, containment integrity was maintained.
Redundant containment cooling capability was provided by the containment spray systems.
The occurrences therefore involved no risk to the health or safety of the public.
Due to the inoperability of the CFCU's, the event constituted operation in a degraded mode permitted by a limiting condition for operation.
Action Statement 3.6.2.3.a requires:
With one group of containment cooling fans inoperable, restore the inoperable group of cooling fans to operable status within the next 7 days, or be in hot standby l
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 I
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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LER 82-075/0lT.
ANALYSIS OF OCCURRENCE:Action Statement 3.6.2.3.b requires:
With two groups of containment cooling fans inoperable, restore at least one group of 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 />.
CORRECTIVE ACTION
As noted, Action Statement 3.6.2.3.b was terminated with the repair of No. 25 CFCU.
In the cases of No. 22 and 24 CFCU's, leakage was immediately isolated, and prompt notification was performed in accordance with Technical Specification 6.9.1.8.
The leaky cooling coil on No. 22 CFCU was isolated by blanking the flanges in the service water piping.
The unit was satis-factorily tested and declared operable.
Action Statement 3.6.2.3.a remained in effect, however, since No. 24 CFCU was still inoperable.
The failed coil on the unit was repaired utilizing Belzona metal filler and was tested satisfactorily.
No. 24 CFCU was declared operable, and at 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />, August 16, 1982, Action Statement 3.6.2.3.a was terminated.
Design Change Request 2EC-0505 has been issued to replace 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 82-070/0lT.
FAILURE DATA:
Containment service water leaks due to erosion of Service Water System components on CFCU's have occurred 7 times since January 1, 1982.
l l
[
Westinghouse Electric Corporation I
Containment Fan Coil Unit U-Tube Cooling Coil Prepared By R.
Frahm 4
ex <s General' Manhger -
Salem Operations SORC Meeting No.
82-77 r
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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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