:on 841229,daily Health Physics Surveillance of Waste Gas Decay Tank Not Completed within 24 H Interval. Caused by Personnel Error.Use of Duties Checklist Required & Documentation of Duties Will Be Reviewed| ML20106B296 |
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| Site: |
McGuire  |
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| Issue date: |
02/04/1985 |
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| From: |
Gewehr S, Tucker H DUKE POWER CO. |
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| To: |
NRC OFFICE OF ADMINISTRATION (ADM) |
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| References |
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| LER-85-001, LER-85-1, NUDOCS 8502110536 |
| Download: ML20106B296 (4) |
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text
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APf1tOVED Otse esO. at30410s UCENSEE EVENT REPORT (LER)
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AeSTR ACT (Limer s. f* IIP assees. ta, espremenessty Rrasen siastew syssoverten Anart pel On December 29, 1984, the daily Health Physics s" veillance of the Waste Gas Decay Tank (WGDT) was not completed within the nour interval as required by technical specifications. The cause of the ev is personnel error.
Corrective acticas will emphasize the use of checklists in nerformance of routine duties, and documentation of the performance of duties wu reviewed by appropriate supervision.
The surveillances performed on the day before and che day after the missed surveillance show WGDT radioactivity levels of 118 and 122 curies, respectively.
It is, therefore, highly improbable that radioactivity levels exceeded the Technical Specifications limit of 49,000 curies on December 29.
The health and safety of the public were not affected.
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NRC Perm No
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For; 304A U.S. NtJLEAR KEIUL* TORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION aRovfo OMS No 3 iso-oio4 J,
f xPlZES: 8/3145 F ACILITY NAME (1)
DOCKET NUM81R (21 LER NUM8ER 44 PAGE (3)
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TEXT IM more space a renwred, use e&enormer NRC form 366Kni(17l
Introduction
On December 29, 1984, the daily Health Physics (H. P.) surveillance of the Waste Gas Decay Tank (WGDT) in service was not performed within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time interval as specified by Technical Specification (T. S.)' 3/4.11.2.6.
The surveillance was successfully completed the day before and the day afer the missed surveillance.
This event is classified as a Personnel Error. The person designated the responsibility of the WGDT daily surveillance did not perform it as required nor did they notice the oversight while revieuing the logbook during shift turnover.
Supervision was not available on the day of the incident to provide an additional check of logbooks and ensure that all required work was completed.
Evaluation: The procedure Radioactive Gaseous Effluent Sampling and Analysis Frequency, is used daily by Health Physics personnel to evaluate the quantity of radioactivity in the WGDT in service as required by T. S.
The T. S. surveillance is performed with the assistance of Radwaste Chemistry personnel. When Health Physics personnel sample a WGDT, Radwaste Chemistry personnel make the necessary valve alignments as required by Radwaste Procedure for Waste Gas Decay Tank Sampling, to provide gas flow to the sampling apparatus.
On the day of the incident, the Saturday after Christmas Holidays, Health Physics Technician A was responsible for the Health Physics day shift duties, one of which was the daily surveillance of the WCDT. This same technician had also been responsible for the WGDT daily surveillance in the days preceding and following the incident. On weekends the day shift duties involve more non-routine tasks and this day was busier than usual due to a reduction in manpower for the holidays.
To assist the technician in completing the required daily shift duties, a copy of the Station Health Physics Duties Checklist is available in the work area under a plastic cover. On this sheet the daily shift duties are listed and are crossed off and initialed as they are completed.
The plastic cover is wiped clean at the end of each day. On the day of the incident, Health Physics Technician A was busy with non-routine work and did not utilize the Duties Checklist. The technician did not notice and missed surveillance when reviewing the logbooks at the end of the day during shift turnover.
Supervision was not available during the day of the incident to provide an additional check of logbooks and ensure that all required work had been completed. The senior Health Physics technician had gone home early and the Health Physics shift supervisor was taking a vacation day. As a result of all these factors, the WGDT surveillance was missed.
As the daily surveillance of the WGDT was being performed on December 30. Technician A noticed that the WGDT surveillance had been missed the day before and the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grace period had been passed. Technician A verified that the quantity of radioactivity in the WGDT in service had not exceeded the T. S. acceptance criteria of 49,000 Curies on the days preceding and following the missed surveillance. The technician reported this to the Health Physics supervisor that was coming on duty at shif t change.
Corrective Action
The use of the Duties Checklist is now required to complete all shift duties. In addition, documentation of performance of duties will be reviewed at the end of each shift to ensure that all Technical Specification requirements have been completed for that shift.
NJaC FOIM 3MA (9 83)
. - -U S. NUCLEAR REGULATO3Y COMMISSION LICENZEE EVENT REPORT (LER) TEXT CONTINUATION AreRovEo oua No. siso-om p
ERPIRES 8/3155 FACILITY NAME 110 DOCKET NUMBER (2)
LER NUMBER ($1 PAGE(31 McGuire Nuclear Station - Unit 1 015l010101316] 9 815 O l Ol 1 01 0 Ol3 OF l3 TEXT (M more space e mqwed, une adhtena!NRC form MKs)(1h
Safety Analysis
Technical Specifications require a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance to verify that the quantity of radioactivity in the WGDT in service does not exceed 49,000 Curies. Since the level in the WGDT was 118 Curies the day before the incident and 122 Curies the day after the incident, it is improbable that the WGDT could have exceeded the 49,000 Curie limit on the day of the missed surveillance, i
NRC ?ORM 366A ts S31
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DUKE POWER GOMPANY P.O.110X 33180 011AltLOTTE, N.C. 28242 HALH. TUCKER TELEPHONE vra parement (701) 373-4531 January 31, 1985
= = = = < = = =
Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Subject: McGuire Nuclear Station, Unit 2 Docket No. 50-370 LER 369/85-01' Gentlemen:
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report 369/85-01 concerning a Missed Technical Specification surveillance, which is submitted in accordance with $50.73 (a)(2)(1). This event was considered to be of no significance with respect to the health and safety of the public.
Very truly yours, f.8. Y
/g Hal B. Tucker SAG /mjf Attachment cc:
Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 M & M Nuclear Consultants 1221 Avenue of the Americas New York, New York 10020 Mr. W. T. Orders NRC' Resident Inspector McGuire Nuclear Station American Nuclear Insurers c/o Dottie Sherman, ANI Library The. Exchange, Suite 245 270 Farmington Avenue [b11 Farmington, CT 06032 ll
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| 05000369/LER-1985-001, :on 841229,daily Health Physics Surveillance of Waste Gas Decay Tank Not Completed within 24 H Interval. Caused by Personnel Error.Use of Duties Checklist Required & Documentation of Duties Will Be Reviewed |
- on 841229,daily Health Physics Surveillance of Waste Gas Decay Tank Not Completed within 24 H Interval. Caused by Personnel Error.Use of Duties Checklist Required & Documentation of Duties Will Be Reviewed
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1985-002-01, :on 850113,required Quarterly Surveillance Not Performed within Allowable Interval.Caused by Personnel Error.Fuel Oil Transfer Pump Performance Test for Each Diesel Will Be Added to Computer Listing |
- on 850113,required Quarterly Surveillance Not Performed within Allowable Interval.Caused by Personnel Error.Fuel Oil Transfer Pump Performance Test for Each Diesel Will Be Added to Computer Listing
| 10 CFR 50.73(a)(2)(i) | | 05000369/LER-1985-003-01, :on 850120,erroneous Signals to Reactor Protection Sys Created Likelihood of Spurious Trip.Caused by Freezing Temps in Area.On 850121,jumper Installed on Bistable Circuit to Thaw Instruments |
- on 850120,erroneous Signals to Reactor Protection Sys Created Likelihood of Spurious Trip.Caused by Freezing Temps in Area.On 850121,jumper Installed on Bistable Circuit to Thaw Instruments
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000369/LER-1985-003, Advises of Delay of Commitment in LER 85-003 to Reroute Instrument Impulse Lines & to Heat Trace & Insulate by Dec 1985,due to Design & Matl Lead Times.Implementation of Mods Delayed Until 1986 Outage | Advises of Delay of Commitment in LER 85-003 to Reroute Instrument Impulse Lines & to Heat Trace & Insulate by Dec 1985,due to Design & Matl Lead Times.Implementation of Mods Delayed Until 1986 Outage | | | 05000369/LER-1985-004-01, :on 850128,reactor Tripped on lo-lo Steam Generator Level When Main Feedwater Pump Tripped on Low Suction Pressure Signal.Caused by Failure of Pneumatic Pressure Transmitter.Components Replaced |
- on 850128,reactor Tripped on lo-lo Steam Generator Level When Main Feedwater Pump Tripped on Low Suction Pressure Signal.Caused by Failure of Pneumatic Pressure Transmitter.Components Replaced
| | | 05000369/LER-1985-005-01, :on 850201,determined Plant Outside Design Analyses Assumptions,Based on Westinghouse Response Re Negative Flux Rate Trip Setpoint.Bistable Setpoint Reduced to 2.5% Rated Thermal Power |
- on 850201,determined Plant Outside Design Analyses Assumptions,Based on Westinghouse Response Re Negative Flux Rate Trip Setpoint.Bistable Setpoint Reduced to 2.5% Rated Thermal Power
| 10 CFR 50.73(a)(2) | | 05000369/LER-1985-006-01, :on 850205,reactor Tripped on High Negative Flux Rate Signal.Cause unknown.Post-trip Review Performed & Electronic Recorders Used to Monitor Possible Spikes |
- on 850205,reactor Tripped on High Negative Flux Rate Signal.Cause unknown.Post-trip Review Performed & Electronic Recorders Used to Monitor Possible Spikes
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000369/LER-1985-007-03, :on 850205,two ESF Actuations Occurred During Work on Reactor Protection & Nuclear Instrumentation Sys Channels.Caused by Procedures Allowing Simultaneous Sys Work.Procedures Revised |
- on 850205,two ESF Actuations Occurred During Work on Reactor Protection & Nuclear Instrumentation Sys Channels.Caused by Procedures Allowing Simultaneous Sys Work.Procedures Revised
| 10 CFR 50.73(a)(1), Submit an LER 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000369/LER-1985-008-01, :on 850206,discovered That Reactor Trip Switchgear Wiring Did Not Satisfy Separation Criteria for safety-related Circuits.Caused by Administrative/Procedural Deficiency.Procedures Revised |
- on 850206,discovered That Reactor Trip Switchgear Wiring Did Not Satisfy Separation Criteria for safety-related Circuits.Caused by Administrative/Procedural Deficiency.Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000369/LER-1985-009-01, :on 850219,estmated 1 Cubic Ft of Contaminated Spent Resin Released from Vent.Resin Discovered on 850220 on Roof of Auxiliary Bldg & Other Bldgs.Caused by Personnel Error |
- on 850219,estmated 1 Cubic Ft of Contaminated Spent Resin Released from Vent.Resin Discovered on 850220 on Roof of Auxiliary Bldg & Other Bldgs.Caused by Personnel Error
| | | 05000369/LER-1985-010-01, :on 850320,keyswitch for Door on Reactor Side of Containment Personnel Airlock in Bypass Position.Caused by Procedural Deficiency.Procedures Will Be Changed to Ensure Switches Returned to Active Position |
- on 850320,keyswitch for Door on Reactor Side of Containment Personnel Airlock in Bypass Position.Caused by Procedural Deficiency.Procedures Will Be Changed to Ensure Switches Returned to Active Position
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000369/LER-1985-011-01, :on 850409,samples Taken from Cold Leg Accumulator a Prior to Unit Shutdown Revealed Low Boron Concentration.Caused by Component Failure.Boron Concentration Returned to within Specs |
- on 850409,samples Taken from Cold Leg Accumulator a Prior to Unit Shutdown Revealed Low Boron Concentration.Caused by Component Failure.Boron Concentration Returned to within Specs
| 10 CFR 50.73(a)(2)(1) | | 05000369/LER-1985-012-01, :from 850214-0425,fire Doors Normally Locked Closed Were Unlocked & Not Verified Closed Daily Nor Was Fire Watch Posted.Caused by Administrative/Procedural Deficiency.Required Surveillance Implemented |
- from 850214-0425,fire Doors Normally Locked Closed Were Unlocked & Not Verified Closed Daily Nor Was Fire Watch Posted.Caused by Administrative/Procedural Deficiency.Required Surveillance Implemented
| | | 05000369/LER-1985-013-01, :on 850502,during Refueling,Gearcase Lubricating Grease Found in Electrical Compartments of Limitorque Motor Operated Valve Actuators 1VX-1A & 1VX-2B. Caused by Error During Previous Maint Work |
- on 850502,during Refueling,Gearcase Lubricating Grease Found in Electrical Compartments of Limitorque Motor Operated Valve Actuators 1VX-1A & 1VX-2B. Caused by Error During Previous Maint Work
| | | 05000369/LER-1985-014-01, :on 850507,core Alterations Started W/O Completion of Required Surveillance on Source Range Neutron Flux Monitors While in Mode 6.Caused by Administrative/ Procedural Deficiency.New Procedure Planned |
- on 850507,core Alterations Started W/O Completion of Required Surveillance on Source Range Neutron Flux Monitors While in Mode 6.Caused by Administrative/ Procedural Deficiency.New Procedure Planned
| | | 05000369/LER-1985-015-02, :on 850508,auxiliary & Reactor Bldg Side Door Lower Airlock Seals Deflated,Causing Loss of Containment Integrity.Caused by Maladjustment of Airlock Door Pin Limit Switches Combined W/Design Deficiency |
- on 850508,auxiliary & Reactor Bldg Side Door Lower Airlock Seals Deflated,Causing Loss of Containment Integrity.Caused by Maladjustment of Airlock Door Pin Limit Switches Combined W/Design Deficiency
| | | 05000369/LER-1985-016-01, :on 850508,discovered That Temp Compensation Chart Not Incorporated in Hydrogen Analyzer Operation Emergency Procedure.Caused by Procedural Deficiency.Temp Compensation Charts Incorporated in Procedure |
- on 850508,discovered That Temp Compensation Chart Not Incorporated in Hydrogen Analyzer Operation Emergency Procedure.Caused by Procedural Deficiency.Temp Compensation Charts Incorporated in Procedure
| | | 05000369/LER-1985-017-01, :on 850515,diesel Generator 1A Experienced Invalid Automatic Start Due to Unit Blackout Signal.Caused by Electrical Disturbance to Power Transmission Sys During Severe Storm & Listed Design Deficiency |
- on 850515,diesel Generator 1A Experienced Invalid Automatic Start Due to Unit Blackout Signal.Caused by Electrical Disturbance to Power Transmission Sys During Severe Storm & Listed Design Deficiency
| | | 05000369/LER-1985-018-01, :on 850525,valve 1RV-429 in Containment Ventilation Cooling Water Sys Outside Containment Found Open,Allowing Flow Path Between Auxiliary Bldg & Upper Containment Through Inside Containment Valve |
- on 850525,valve 1RV-429 in Containment Ventilation Cooling Water Sys Outside Containment Found Open,Allowing Flow Path Between Auxiliary Bldg & Upper Containment Through Inside Containment Valve
| | | 05000369/LER-1985-019-01, :on 850530,cable Transits Penetrating Units 1 & 2 Reactor Bldg Walls Discovered to Be Fire Barriers.Caused by Oversight During Development of Fire Barrier Insp Procedure.Procedures Revised |
- on 850530,cable Transits Penetrating Units 1 & 2 Reactor Bldg Walls Discovered to Be Fire Barriers.Caused by Oversight During Development of Fire Barrier Insp Procedure.Procedures Revised
| | | 05000369/LER-1985-020-01, :on 850607,diesel Generator 1B Experienced Two Invalid Automatic Starts.Caused by Power Distribution Sys Disturbances Due to Severe Weather.Start Sys Will Be Modified |
- on 850607,diesel Generator 1B Experienced Two Invalid Automatic Starts.Caused by Power Distribution Sys Disturbances Due to Severe Weather.Start Sys Will Be Modified
| | | 05000369/LER-1985-021, :on 850605,personnel Overexposure Occurred. Calculations Indicate Dose of 10.6 Rems to Skin & 0.03 Rem to Whole Body.Control & Disposal of Protective Clothing Revised to Prevent Recurrence of Incident |
- on 850605,personnel Overexposure Occurred. Calculations Indicate Dose of 10.6 Rems to Skin & 0.03 Rem to Whole Body.Control & Disposal of Protective Clothing Revised to Prevent Recurrence of Incident
| | | 05000369/LER-1985-021-01, Forwards LER 85-021-01 Re Personnel Exposure,Initially Determined to Be Overexposure.Revised Calculation Indicates No Overexposure Occurred | Forwards LER 85-021-01 Re Personnel Exposure,Initially Determined to Be Overexposure.Revised Calculation Indicates No Overexposure Occurred | | | 05000369/LER-1985-022-01, :on 850623,unplanned ESF Actuation Occurred on Loss of Both Main Feed Pumps Signal.Caused by Voltage Transient When Trend Chart Recorder Reinserted.Recorder Will Be Replaced |
- on 850623,unplanned ESF Actuation Occurred on Loss of Both Main Feed Pumps Signal.Caused by Voltage Transient When Trend Chart Recorder Reinserted.Recorder Will Be Replaced
| | | 05000369/LER-1985-023-01, :on 850703,violation of Electrical Channel Separation Requirements by Temporary Cable Routing Discovered.Caused by Administrative/Procedural Deficiency. Cable Removed from Blue Channel Cable Tray |
- on 850703,violation of Electrical Channel Separation Requirements by Temporary Cable Routing Discovered.Caused by Administrative/Procedural Deficiency. Cable Removed from Blue Channel Cable Tray
| | | 05000369/LER-1985-024-01, :on 850723,determined That Operability Test Not Performed on Station Standby Battery Charger.On 850813, Found That Standby Charger Placed in Svc Twice Supplying Vital Loads on Channels 2 & 4 |
- on 850723,determined That Operability Test Not Performed on Station Standby Battery Charger.On 850813, Found That Standby Charger Placed in Svc Twice Supplying Vital Loads on Channels 2 & 4
| | | 05000369/LER-1985-025-01, :on 850909,train Chillers & Air Handling Unit for Control Ventilation Area Sys Tripped.Caused by Design Deficiency Allowing Both Chillers to Become Inoperable Due to Blown Fuse.Fuse Replaced.Wiring Reviewed |
- on 850909,train Chillers & Air Handling Unit for Control Ventilation Area Sys Tripped.Caused by Design Deficiency Allowing Both Chillers to Become Inoperable Due to Blown Fuse.Fuse Replaced.Wiring Reviewed
| | | 05000369/LER-1985-026-01, :on 850911,vendor-employed Minor Exposed in Excess of Quarterly Dose Limit of 125 Mrem.Caused by Individual Misrepresenting Age to Work in Radiation Control Area.Birth Dates Will Be Verified |
- on 850911,vendor-employed Minor Exposed in Excess of Quarterly Dose Limit of 125 Mrem.Caused by Individual Misrepresenting Age to Work in Radiation Control Area.Birth Dates Will Be Verified
| | | 05000369/LER-1985-027-01, :on 850911,pressurizer Heater Group 1B Inoperable While Diesel Generator 1A Inoperable.Caused by Personnel Error.Generator Returned to Operable.Rept Will Be Reviewed W/Personnel |
- on 850911,pressurizer Heater Group 1B Inoperable While Diesel Generator 1A Inoperable.Caused by Personnel Error.Generator Returned to Operable.Rept Will Be Reviewed W/Personnel
| | | 05000369/LER-1985-028-01, :on 850919,environmentally Sealed Valcor Model 526 Inside Containment Valve Failed.Caused by Ruptured Seal as Result of Improper Installation.Four Valves Resealed & Returned to Svc.New Design Being Studied |
- on 850919,environmentally Sealed Valcor Model 526 Inside Containment Valve Failed.Caused by Ruptured Seal as Result of Improper Installation.Four Valves Resealed & Returned to Svc.New Design Being Studied
| | | 05000369/LER-1985-029-01, :on 851001,Westinghouse Notified Util That Reanalysis of Peak Containment Pressure Calculation Resulted in Greater Value than Internal Pressure of 15 Psig.Emergency Procedure for Nd Spray Initiation Revised |
- on 851001,Westinghouse Notified Util That Reanalysis of Peak Containment Pressure Calculation Resulted in Greater Value than Internal Pressure of 15 Psig.Emergency Procedure for Nd Spray Initiation Revised
| 10 CFR 50.73(a)(2)(vi) | | 05000369/LER-1985-030-01, :on 851009,valve 1RN-33 Found in Locked Closed Position Instead of Locked Open Due to Reversed Local Valve Position Indicator.Cause Unknown.Valve Opened & Properly Labeled |
- on 851009,valve 1RN-33 Found in Locked Closed Position Instead of Locked Open Due to Reversed Local Valve Position Indicator.Cause Unknown.Valve Opened & Properly Labeled
| | | 05000369/LER-1985-031-01, :on 851017,Train B Chiller for Control Area Ventilation/Chilled Water Sys Tripped on Low Yc Flow While Train B Sys Inoperable.Cause Could Not Be Determined. Pressure Switch Repaired & Tubes Cleaned |
- on 851017,Train B Chiller for Control Area Ventilation/Chilled Water Sys Tripped on Low Yc Flow While Train B Sys Inoperable.Cause Could Not Be Determined. Pressure Switch Repaired & Tubes Cleaned
| | | 05000369/LER-1985-032-01, :on 851018,QA Surveillance Revealed That Chemical & Vol Control Sys Valves 1NV-223 & 2NV-223 Not Partially Stroked.Caused by Lack of Relevant Procedures. Partial Stroke Requirement Will Be Deleted |
- on 851018,QA Surveillance Revealed That Chemical & Vol Control Sys Valves 1NV-223 & 2NV-223 Not Partially Stroked.Caused by Lack of Relevant Procedures. Partial Stroke Requirement Will Be Deleted
| | | 05000369/LER-1985-033-01, :on 851030,momentary Blackout on Train B Occurred.Caused by Nuclear Control Operator Inadvertently Opening Diesel Generator Breaker.Procedures for Blackout Implemented.Collars Installed on Generator |
- on 851030,momentary Blackout on Train B Occurred.Caused by Nuclear Control Operator Inadvertently Opening Diesel Generator Breaker.Procedures for Blackout Implemented.Collars Installed on Generator
| | | 05000369/LER-1985-034-01, :on 851102,reactor/turbine Trip on Steam Generator 1A lo-lo Level Occurred.Caused by Loss of Instrument Air Due to Rupture of Welded Seam on Flexible Pipe on Discharge Air Compressor B |
- on 851102,reactor/turbine Trip on Steam Generator 1A lo-lo Level Occurred.Caused by Loss of Instrument Air Due to Rupture of Welded Seam on Flexible Pipe on Discharge Air Compressor B
| | | 05000369/LER-1985-035-01, :on 851030,B&W Fuel Assemblies Determined Incorrectly Stored Side by Side in Spent Fuel Pool.Caused by Inadequate Personnel Review of Tech Spec.Assemblies Placed in Checkerboard Pattern |
- on 851030,B&W Fuel Assemblies Determined Incorrectly Stored Side by Side in Spent Fuel Pool.Caused by Inadequate Personnel Review of Tech Spec.Assemblies Placed in Checkerboard Pattern
| | | 05000369/LER-1985-036-01, :on 851119,reactor Tripped Due to Feedwater Pump Turbine Trip on High Discharge Pressure.Caused by Rod Control Sys Not Lowering Power Enough During Turbine Runback.Failed Fuse Will Be Replaced |
- on 851119,reactor Tripped Due to Feedwater Pump Turbine Trip on High Discharge Pressure.Caused by Rod Control Sys Not Lowering Power Enough During Turbine Runback.Failed Fuse Will Be Replaced
| | | 05000369/LER-1985-037-01, :on 851210,Train a ESF Actuation Occurred Due to Actuation of Slave Relay in Reactor Protection Sys.Caused by Personnel Error.Safeguards Safety Injection Signal & Sequencer 1A Reset & Pumps Secured |
- on 851210,Train a ESF Actuation Occurred Due to Actuation of Slave Relay in Reactor Protection Sys.Caused by Personnel Error.Safeguards Safety Injection Signal & Sequencer 1A Reset & Pumps Secured
| | | 05000369/LER-1985-038-01, :on 851222,reactor Tripped Due to Turbine Trip from 93% Power.Caused by Ground Fault within Motor Operated Disconnect (MOD) on Main Power Busline 1B.Unit Stabilized & MOD Repaired |
- on 851222,reactor Tripped Due to Turbine Trip from 93% Power.Caused by Ground Fault within Motor Operated Disconnect (MOD) on Main Power Busline 1B.Unit Stabilized & MOD Repaired
| | | 05000369/LER-1985-039-01, :on 860101,discovered That Spent Fuel Pool Ventilation Performance Test Not Performed by Required Date of 851210.Caused by Personnel Error.Test Performed for Exhaust Fan 1A |
- on 860101,discovered That Spent Fuel Pool Ventilation Performance Test Not Performed by Required Date of 851210.Caused by Personnel Error.Test Performed for Exhaust Fan 1A
| | | 05000369/LER-1985-039, :on 851210,spent Fuel Ventilation Performance Test Not Performed by Required Date.Caused by Personnel Error.Personnel Responsibility Will Be Assigned for Each Performance Test |
- on 851210,spent Fuel Ventilation Performance Test Not Performed by Required Date.Caused by Personnel Error.Personnel Responsibility Will Be Assigned for Each Performance Test
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