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LER-1982-026, Forwards LER 82-026/03L-0.Detailed Event Analysis Encl |
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- - O PSIEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge New Jersey 08038 Salem Generating Station April 28, 1982 co Mr.
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Dear Mr. Haynes:
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/)]g o LICENSE NO. DP R-7 0 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 82-026/03L 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 82-026/03L.
This report is required within thirty (30) days of the occurrence.
Sincerely yours, f ~d N*
H. J. Midura General Manager -
Salem Operations RF:ks CC:
Distribution 8205110538 820428 DR ADOCK 03000272 f6,W PDR j, y
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Deport Number:
82-026/03L Report Date:
04-28-82 Occurrence Date:
04-09-82 Facility:
Salem Generating Station, Unit 1 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Boric Acid Storage Tanks and Boron Injection Tank -
Concentration Out of Specification.
This report was initiated by Incident Reports82-077, 82-082,82-083 and 82-084.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 3 - Rx Power 0% - Unit Load 0 MWe.
DESCRIPTION OF OCCURRENCE:
On three different occasions, Nos. 11 and 12 Boric Acid Storage Tanks (BAST's) and Boron Injection Tank (BIT) boron con-centrations decreased below the Technical Specification limit of 20,100 ppm boron.
On April 9, 1982, sample results from the BAST's and BIT were 19,580 ppm, 19,597 ppm and 19,272 ppe respectively.
Nos. 11 and 12 BAST's and the BIT were declared inoperable, and at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />, Action Statements 3.1.2.8.a and 3.5.4.1 were entered.
The BAST's and BIT were restored to an operable status, and on April 13th, the boron concentrations again decreased below the specification limits.
Nos. 11 and 12 BAST's and the BIT were l
j declared inoperable at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, and Action Statements 3.1.2.8.a and 3.5.4.1 were entered for a second time.
Later that day, after batching had increased tank boron con-centrations, sample results showed the BIT was belcw speci-fication for a third time.
The BAST's and BIT were declared inoperable, and at 2020 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.6861e-4 months <br />, Action Statements 3.1.2.8.a and 3.5.4.1 were entered.
These occurrences constituted operation in a degraded mode in accordance with Technical Specification 6.9.1.9.b.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
The decreases in the BAST and BIT boron concentration resulted from the leakage of charging water past a damaged seat on Valve 1SJ4.
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c LER 82-026/03L..
ANALYSIS OF OCCURRENCE:
Technical Specification 3.1.2.8.a requires:
With the boric acid storage system inoperable and being used as one of the required borated water sources, restore the storage system 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 borated to a shugdown margin-equivalent to at least 1%
delta k/k at 200 F; restore the boric acid storage system to operable status within the next 7 days or be in cold shutdown within the'next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Technical Specification 3.5.4.1 requires:
With the BIT inoperable, restore the tank to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or be in hot standby and borated to a shutdown margin equivalent to 1% delta k/k at 200 F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the tank to operable status within the next 7 days or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
CORRECTIVE ACTION
On April 9, 1982, the Reactor Coolant System was alreagy borated to a shutdown margin equivalent to 5% delta k/k at 200 F, in compliance with Action Statement 3.5.4.1.
At 2340 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br />, sample results showed No. 11 BAST boron concentration was 20,610 ppm.
The tank was declared operable, and Action State-ment 3.1.2.8.a was terminated.
At 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />, April 10, 1982, results of the BIT boron analysis indicated 20,665 ppm.
The BIT was declared operable, and Action Statement 3.5.4.1 was terminated.
On April 13, 1982, boric acid addition to the BAST's and BIT was commenced.
The shutdown margin was increased by control red in-sertion, and Mode 3 was entered in preparation for complianen with Action Statement 3.5.4.1.
At 1921 hours0.0222 days <br />0.534 hours <br />0.00318 weeks <br />7.309405e-4 months <br />, sample results showed No. 11 BAST was within specification.
The tank was de-clared operable, and Action Statement 3.1.2.8.a was terminated.
At 1956 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.44258e-4 months <br />, sampling indicated BIT boron to be within limits.
The BIT was declared operable, and Action Statement 3.5.4.1 was terminated.
An investigation was initiated to determine the source of the BAST and BIT dilution.
When, at 2020 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.6861e-4 months <br />, sample results showed the BIT boron concen-tration had decreased for a third time, the Reactor Coolant System was immediately gorated to a shutdown margin equivalent to 1%
delta k/k at 200 F.
It was determined that the dilution flow path was through Valves 1SJ4 and/or 1SJ5, and a plant cooldown was commenced to repair the valve (s).
Mode 4 was entered at 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br />, April 14, 1982, and Action Statement 3.5.4.1 was terminated.
At 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />, Mode 5 was entered, and Action Statement 3.1.2.8.a was terminated.
Valve 1SJ4 was found to have a damaged seat, and was properly repaired.
LER 82-026/03L - ~
FAILURE DATA:
Darling Valve and Mfg. Co.
4 inch Motor Operated Gate Valve
. Type S350WDD i
Prepared By R. Frahm
/.h Genefal Manager -
Salem Operations SORC Meeting No.
82-45 I
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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. 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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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