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APPR0vED CMS NC 3150-0104 g
LICENSEE EVENT REPORT (LER) l i
F ACILITY NAME til C*
DOCKET NUMSER (2)
Joseph M. Farley - Unit 1 015 I O 10 t o l 3l4 8 i jopl 0; 2 j 1
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Technical Specification Action Statements Not Met When R-ll Was Inoperable g
tv4NT DATE 151 LEM NUM8Em 166 AEPORT DATE 171 CTMER F ACILIYifs INVOLV ED tal wQ NT s.
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.,.. n At 1426 on 1-10-86, it was discovered that the containment atmosphere particulate radioactivity monitor (R-ll) was inoperable due to improper valve alignment. The valve misalignment was the result of two valves having been mislabeled.
Investigation revealed that R-11 had been inoperable since 1030 on 1-9-86.
Since it had not been realized at the time that R-11 was inoperable, the Technical Specification 3.4.7.1 requirement to obtain and analyze samples of the containment atmosphere once per twenty four hours was not met. Upon discovery on 1-10-86, R-11 was returned to service The inoperability of R-ll was caused by personnel error.
The valves had been Enislabeled at some time. However, it has not been possible to determine exactly when the valves were mislabeled or who mislabeled the valves.
It hns been determined that the valves had been labeled properly up until 12-3-85.
Since R-ll had operated properly until 1-9-86, it is believed that the valves were inadvertently mislabeled at some time between 12-3-05 and 1-9-86.
The health / safety of the public was not affected by this event.
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4RcPe. AsA u s. NucLEA2 KEcutAfo2Y couusssioN LICENSEE EVENT REPORT (LER) TEXT CONTINUATION unovEo ous No asso-cios E xhRES 8/31 T,3 F ACILITY NAME III DOCKET NLMSER '2' (gg hyM31R (g)
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Joseph M. Farley - Unit 1 0 l5 l0 [0 [0 l 3l4 [ 8 8l 6 Oj 0 l 1 0l 0 0l 2 OF 0l 2 TEXT ut more space a recured, use addraat AAC Fwm J66NsJ tlh At 1426 on 1-10-86, it was discovered that the containment atmosphere particulate radioactivity ranitor (R-11) was inoperable due to improper valve clignment.
Investigation revealed that R-ll had been inoperable since 1030 on 1-9-86. 'Since it had not been realized at the time that R-11 was inoperable, the Technical Specification 3.4.7.1 requirement to obtain and analyze samples cf the containment atmosphere once per twenty four hours was not met.
Upon discovery on 1-10-86, R-ll was returned to service.
On 1-9-86, two Health Physics technicians were assigned to switch R-ll and R-12 (the containment atmosphere gaseous radioactivity monitor) from the inboard pump to the outboard pump so that the inboard pump could be lubricated. This operation was completed at approximately 1030 and was performed according to procedure. However, two valves had been mislabeled previously. This led to VI (the R-ll bypass valve) being opened and V2 (the R-ll inlet valve) being closed. Therefore, R-11 was bypassed.
The operation of R-12 was not affected by the valve misalignment.
Later in the day on 1-9-86, R-ll and R-12 were switched back to the inboard pump after the lubrication had been completed. At 1426 on 1-10-86, during an investigation of problems with the operation of the inboard pump, it was discovered that valves VI and V2 had been mispositioned due to the valves
- - having been mislabeled.
L*pon discovery, R-Il was returned to proper operation by positioning the valves correctly and placing the outboard pump in operation. The identification tags on VI and V2 were placed properly and v;rified. As a precaution, the valve alignment on other radiation monitors on both units covered by Technical Specifications was verified to be correct.
Due to the valve misalignment, the R-ll reading decreased from cpproximately 6000 to approximately 1500 counts per minute during the period from 1030 on 1-9-86 to 1426 on 1-10-86.
The R-ll readings are logged by Operations personnel at least once per twelve hours and by Health Physics personnel on a daily basis.
The shift supervisor and the plant operators had n:ticed the decrease in the count rate but failed to investigate fully.
The cppropriate personnel have been counseled concerning their failure to recognize the low count rate and take appropriate corrective action.
The inoperability of R-11 was caused by personnel error. The valves had been mislabeled at some time.
However, it has not been possible to determine cxactly when the valves were mislnbeled or who mislabeled the valves.
It has been determined that the valves had been labeled properly up until 12-3-85.
Since R-11 had operated properly until 1-9-86, it is believed that the valves w;re inadvertently mislabeled at some time between 12-3-85 and 1-9-86.
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3 Malling Address Atibam2 Powst Comp 2ny 600 North 18th Strset Post Office Box 2641 Birmingham. Alabama 35291 Telephone 205 783-6090 R. P. Mcdonald Senior Vice President Flintridge Building
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February 7, 1986 Docket No. 50-348 Document Control Desk U. S. Nuclear Regulatory Comission Washington, D.C.
20555 Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report No. LER 86-001-00
Dear Sir:
Joseph M. Farley Nuclear Plant, Unit 1, Licensee Event Report No. LER 86-001-00 is being submitted in accordance with 10CFR50.73.
If you have any questions, please advise.
Yours very tru
>& b n
R. P. Mcdonald RPM / JAR: dst-030 Enclosure cc:
IE, Region II ZGrz-
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| 05000348/LER-1986-001, :on 860110,discovered That Containment Atmosphere Particulate Radioactivity Monitor Inoperable Due to Improper Valve Alignment.Caused by Personnel Error. Monitor Returned to Svc Upon Discovery |
- on 860110,discovered That Containment Atmosphere Particulate Radioactivity Monitor Inoperable Due to Improper Valve Alignment.Caused by Personnel Error. Monitor Returned to Svc Upon Discovery
| | | 05000364/LER-1986-001-01, :on 860117,reactor Tripped Due to Manual Tripping of Main Turbine.Caused by Loss of Redundant Power Supplies for Speed Controller.Affected Relay & Light Bulb Replaced.Engineering Study Being Conducted |
- on 860117,reactor Tripped Due to Manual Tripping of Main Turbine.Caused by Loss of Redundant Power Supplies for Speed Controller.Affected Relay & Light Bulb Replaced.Engineering Study Being Conducted
| | | 05000364/LER-1986-002, :on 860116,post-accident Hydrogen Analyzer 2A Declared Inoperable Because Internal Tubing of Analyzer Inconsistent W/Drawings.Analyzer 2B Also Had Same Inconsistencies.Tubing Configuration Corrected |
- on 860116,post-accident Hydrogen Analyzer 2A Declared Inoperable Because Internal Tubing of Analyzer Inconsistent W/Drawings.Analyzer 2B Also Had Same Inconsistencies.Tubing Configuration Corrected
| | | 05000348/LER-1986-002-01, :on 860214,Train a & B post-accident Hydrogen Analyzers on Both Units Inoperable.Caused by Inappropriate Design Change.Analyzers Rewired to Original Configuration |
- on 860214,Train a & B post-accident Hydrogen Analyzers on Both Units Inoperable.Caused by Inappropriate Design Change.Analyzers Rewired to Original Configuration
| | | 05000348/LER-1986-003, :on 860220,inadequate Design Calculation Re post-LOCA Cooldown by Westinghouse for Cycle 7 Reload Discovered.Util Working W/Westinghouse to Ensure Adequate Calculations for Future Reload Designs |
- on 860220,inadequate Design Calculation Re post-LOCA Cooldown by Westinghouse for Cycle 7 Reload Discovered.Util Working W/Westinghouse to Ensure Adequate Calculations for Future Reload Designs
| | | 05000364/LER-1986-003-01, :on 860302,containment Spray Pump 2A Determined to Be Inoperable Due to Defective Microswitch.Caused by Slippage of Roll Pin Holding Actuator Arm in Place.Defective Microswitch Returned to Vendor |
- on 860302,containment Spray Pump 2A Determined to Be Inoperable Due to Defective Microswitch.Caused by Slippage of Roll Pin Holding Actuator Arm in Place.Defective Microswitch Returned to Vendor
| | | 05000364/LER-1986-004-01, :on 860428 Prior to Fourth Refueling Outage, Eddy Current Insp Plan Identified 70 Steam Generator Tubes Plugged.Causes for Tube Degradation Include Antivibration Bar Wear & Stress Corrosion |
- on 860428 Prior to Fourth Refueling Outage, Eddy Current Insp Plan Identified 70 Steam Generator Tubes Plugged.Causes for Tube Degradation Include Antivibration Bar Wear & Stress Corrosion
| | | 05000348/LER-1986-004, :on 860228,while Operating in steady-state at 99% Power,Reactor Trip Occurred Due to High Negative Flux Rate Detected by Power Range Nuclear Detectors.Caused by Dropped Control Rod.Fuses Replaced |
- on 860228,while Operating in steady-state at 99% Power,Reactor Trip Occurred Due to High Negative Flux Rate Detected by Power Range Nuclear Detectors.Caused by Dropped Control Rod.Fuses Replaced
| | | 05000348/LER-1986-005, :on 860430,Westinghouse Notified Util That 27 Fuel Rods in Region 9 Had U Weights in Excess of Tech Specs. Subsequent Checks Identified 289 Rods W/Excess Weight.Tech Spec Amend Will Be Submitted |
- on 860430,Westinghouse Notified Util That 27 Fuel Rods in Region 9 Had U Weights in Excess of Tech Specs. Subsequent Checks Identified 289 Rods W/Excess Weight.Tech Spec Amend Will Be Submitted
| | | 05000364/LER-1986-005-01, :on 860513,reactor Tripped While Performing Trip Testing on Main Turbine.Caused by lo-lo Level in Steam Generator 2B.Procedures Revised to Require Increased Attention to Fluid Pressure |
- on 860513,reactor Tripped While Performing Trip Testing on Main Turbine.Caused by lo-lo Level in Steam Generator 2B.Procedures Revised to Require Increased Attention to Fluid Pressure
| | | 05000348/LER-1986-006, :on 860429,RHR Sys Train B Inoperable.Caused by Personnel Error,Resulting in Improper Opening & Tagging of Breaker.Personnel Counseled & Main Control Board Verification Procedures Developed |
- on 860429,RHR Sys Train B Inoperable.Caused by Personnel Error,Resulting in Improper Opening & Tagging of Breaker.Personnel Counseled & Main Control Board Verification Procedures Developed
| | | 05000364/LER-1986-006-01, :on 860521,during Heatup After Maint Outage, Fire Damper in Penetration 05-139-06 Inoperable Due to Routing of Headphone Cable Through Damper.Caused by Personnel Error.Individual Counseled |
- on 860521,during Heatup After Maint Outage, Fire Damper in Penetration 05-139-06 Inoperable Due to Routing of Headphone Cable Through Damper.Caused by Personnel Error.Individual Counseled
| | | 05000364/LER-1986-007-01, :on 860608,reactors Tripped Due to Malfunction of Both CRD Motor Generator Sets.Directional Overcurrent Relays on All Motor Generator Sets Checked & Readjusted as Required |
- on 860608,reactors Tripped Due to Malfunction of Both CRD Motor Generator Sets.Directional Overcurrent Relays on All Motor Generator Sets Checked & Readjusted as Required
| | | 05000348/LER-1986-007, :on 860518,reactor Tripped Due to Turbine Trip. Caused by Deteriorated Diaphragm on Turbine Interface Valve Allowing auto-stop Oil Pressure to Drop Below Trip Setpoint. Valve Replaced & Preventive Maint Task Created |
- on 860518,reactor Tripped Due to Turbine Trip. Caused by Deteriorated Diaphragm on Turbine Interface Valve Allowing auto-stop Oil Pressure to Drop Below Trip Setpoint. Valve Replaced & Preventive Maint Task Created
| | | 05000364/LER-1986-008-01, :on 860915,failure to Post Fire Watch Per Tech Spec 3.7.11.2 Discovered.Caused by Personnel Propping Open Fire Door W/O Control Room Approval.Personnel Counseled Re Fire Door Opening Procedures |
- on 860915,failure to Post Fire Watch Per Tech Spec 3.7.11.2 Discovered.Caused by Personnel Propping Open Fire Door W/O Control Room Approval.Personnel Counseled Re Fire Door Opening Procedures
| | | 05000348/LER-1986-008, :on 860702,reactor Trip Occurred Due to High Negative Flux Rate & Rod F-14 Dropping Into Core.Caused by Electrical Short in Containment Penetration Module Supplying Power to Stationary Gripper Coil of Rod |
- on 860702,reactor Trip Occurred Due to High Negative Flux Rate & Rod F-14 Dropping Into Core.Caused by Electrical Short in Containment Penetration Module Supplying Power to Stationary Gripper Coil of Rod
| | | 05000364/LER-1986-009-01, :on 860717,unit Shut Down Due to Charging Pump 2B Trip.Caused by Electrical Failure of Motor While Charging Pump 2C Removed from Svc for Repair.Charging Pump Returned to Svc on 860722 |
- on 860717,unit Shut Down Due to Charging Pump 2B Trip.Caused by Electrical Failure of Motor While Charging Pump 2C Removed from Svc for Repair.Charging Pump Returned to Svc on 860722
| | | 05000348/LER-1986-009, :on 860714,ESF Actuated When Penetration Room Filtration Sys Started Automatically.Caused by Personnel Error During Removal of Radiation Monitor R-25A from Svc for Maint.Technician Counseled |
- on 860714,ESF Actuated When Penetration Room Filtration Sys Started Automatically.Caused by Personnel Error During Removal of Radiation Monitor R-25A from Svc for Maint.Technician Counseled
| | | 05000348/LER-1986-010, :on 860716,penetration Room Filtration Sys Started Automatically Due to Inadvertent Actuation of ESF Equipment.Caused by Inadequate Procedures.Procedures Revised |
- on 860716,penetration Room Filtration Sys Started Automatically Due to Inadvertent Actuation of ESF Equipment.Caused by Inadequate Procedures.Procedures Revised
| | | 05000364/LER-1986-010-01, :on 860804,reactor Tripped During Testing of Solid State Protection Sys.Caused by Faulty Secondary Disconnecting Contacts on Train B Reactor Trip Bypass Breakers.Contacts Replaced as Needed |
- on 860804,reactor Tripped During Testing of Solid State Protection Sys.Caused by Faulty Secondary Disconnecting Contacts on Train B Reactor Trip Bypass Breakers.Contacts Replaced as Needed
| | | 05000348/LER-1986-011, :on 860715,Train a HVAC Dampers in Control Room & Computer Room Tripped Causing Inadvertent Actuation of ESF Equipment.Caused by Personnel Error While Replacing Recorder for Radiation Monitor R-35A |
- on 860715,Train a HVAC Dampers in Control Room & Computer Room Tripped Causing Inadvertent Actuation of ESF Equipment.Caused by Personnel Error While Replacing Recorder for Radiation Monitor R-35A
| | | 05000364/LER-1986-011-01, :on 861015,Tech Spec 3.0.3 Entered Due to Inoperability of Both Trains of Control Room Emergency Air Cleanup Sys.Caused by Inadequate Draining of Train B Svc Water Sys.Train a Sys Returned to Svc |
- on 861015,Tech Spec 3.0.3 Entered Due to Inoperability of Both Trains of Control Room Emergency Air Cleanup Sys.Caused by Inadequate Draining of Train B Svc Water Sys.Train a Sys Returned to Svc
| | | 05000348/LER-1986-012, :on 860723,reactor Protection Sys Actuation Occurred in One Train While in Test.Caused by Cognitive Personnel Error.Worker Involved Counseled |
- on 860723,reactor Protection Sys Actuation Occurred in One Train While in Test.Caused by Cognitive Personnel Error.Worker Involved Counseled
| | | 05000348/LER-1986-013, :on 860804,fire Watch Not Established as Required by Tech Spec.Caused by Cognitive Personnel Error. Failure to Station Fire Watch Discussed W/Individual Involved |
- on 860804,fire Watch Not Established as Required by Tech Spec.Caused by Cognitive Personnel Error. Failure to Station Fire Watch Discussed W/Individual Involved
| | | 05000348/LER-1986-014, :on 860801,both Trains of Charging Pumps Inoperable.Caused by Clogged Gear Oil Coolers.Svc Water Task Force Established to Investigate Problem |
- on 860801,both Trains of Charging Pumps Inoperable.Caused by Clogged Gear Oil Coolers.Svc Water Task Force Established to Investigate Problem
| | | 05000348/LER-1986-015, :on 860805,reactor Trip & Subsequent Main Steam Line Isolation Occurred.Caused by Reduction in Feedwater Flow to Steam Generator 1C Due to Failed Printed Circuit Card.Card Replaced |
- on 860805,reactor Trip & Subsequent Main Steam Line Isolation Occurred.Caused by Reduction in Feedwater Flow to Steam Generator 1C Due to Failed Printed Circuit Card.Card Replaced
| | | 05000348/LER-1986-016, :on 860819,fire Protection Sys 1A-108 Disabled to Support Extensive Architectural Mods.Sys Could Not Be Returned to Svc within 14 Days Per Tech Specs Due to Scope of Mods.Sys Returned to Svc on 860916 |
- on 860819,fire Protection Sys 1A-108 Disabled to Support Extensive Architectural Mods.Sys Could Not Be Returned to Svc within 14 Days Per Tech Specs Due to Scope of Mods.Sys Returned to Svc on 860916
| | | 05000000/LER-1986-017, :on 860821,containment Smoke Detector Sys 1A-22 Declared Inoperable Due to Spurious Alarm Which Would Not Clear.Caused by Faulty Smoke Detector.Further Investigation & Repair Will Be Performed During Next Outage |
- on 860821,containment Smoke Detector Sys 1A-22 Declared Inoperable Due to Spurious Alarm Which Would Not Clear.Caused by Faulty Smoke Detector.Further Investigation & Repair Will Be Performed During Next Outage
| | | 05000348/LER-1986-018, :on 860808,09 & 0923,hourly Firewatch Patrol Not Performed Per Tech Spec 3.7.12.Caused by Cognitive Personnel Errors.Personnel Counseled |
- on 860808,09 & 0923,hourly Firewatch Patrol Not Performed Per Tech Spec 3.7.12.Caused by Cognitive Personnel Errors.Personnel Counseled
| | | 05000348/LER-1986-019, :on 861028,six Tubes Exceeded Pluggable Limit Based on Eddy Current Testing Results.Cause Not Stated.Two Tubes Plugged in Steam Generator 1C & Four Tubes Plugged in Steam Generator 1A |
- on 861028,six Tubes Exceeded Pluggable Limit Based on Eddy Current Testing Results.Cause Not Stated.Two Tubes Plugged in Steam Generator 1C & Four Tubes Plugged in Steam Generator 1A
| | | 05000348/LER-1986-020, :on 861107,RCS Pressure Increased Uncontrollably Prior to Reactor Coolant Pump Startup.Caused by Operator Error.Rhr Loop Suction Pressure Relief Valve Opened |
- on 861107,RCS Pressure Increased Uncontrollably Prior to Reactor Coolant Pump Startup.Caused by Operator Error.Rhr Loop Suction Pressure Relief Valve Opened
| | | 05000348/LER-1986-021, :on 861105,containment Equipment Hatch Left as Nonfunctional Fire Barrier Longer than seven-day Period. Continuous Fire Watch Established.Hatch Closed on 861108.W/ |
- on 861105,containment Equipment Hatch Left as Nonfunctional Fire Barrier Longer than seven-day Period. Continuous Fire Watch Established.Hatch Closed on 861108.W/
| | | 05000348/LER-1986-022, :on 861117,automatic Isolation Capability of RHR Sys Loop Suction Valves Required W/O Operability of Function.Caused by Personnel Errors.Personnel Reinstructed in Duty Performance & Event Discussed |
- on 861117,automatic Isolation Capability of RHR Sys Loop Suction Valves Required W/O Operability of Function.Caused by Personnel Errors.Personnel Reinstructed in Duty Performance & Event Discussed
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