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'**"'s_er3ies LICENSEE EVENT REPORT (LER) f ACILITY NAME til 00CILIT NUISER (2)
PAGE (El Joseph M. Farley - Unit 1 0 l5 lo lo lol3 $ l 8 1 ]OFl 0 l2
't ITLE 448 Reactor Trip EVENT DATE (S)
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At 2328 on 1/9/84, the reactor tripped due to LoLo level in IB steam generator.
This was a result of lA Steam Generator Feedwater Pump tripping due to low bearing oil pressure while the reactor was at 100% power. The low bearing oil pressure re-sulted f rom a trip of the operating AC lube oil pump motor due to an overload condi-tion.
IIcalth/ safety of the public was not af fected.
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,6 PDR ADOCK8402080350 840203 g:
05000348 S
PDR MRC Form 300 (9 03)
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NAC Feem 3eGA U S. NUCLEAR EEGULATOT4V COMMIS&lON UCENSEE EVENT REPORT (LER) TEXT CONTINUATION AreRovEO. m no siso-m4 EXPIRES. 8'31/85 F ACf LITV NAME (It DOCKET NUMBER (2)
LER NUMGER 16)
PAGE(3)
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"%*,0 Joseph M. Farley - Unit 1 0 l5 [0 l0 l0 l 1[ 4l8 8l 4 0l0 jl
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mc r mr.nm During steady state operation with the unit in Mode I at 100% power, the operating AC lube oil pump motor for IA SGFP tripped due to an overload condi-tion. The backup AC lube oil pump started, as designed, preventing damage to the SGFP bearings. The plant operator took proper actions in an attempt to avert a reactor trip by ramping the turbine load down. After a few initial steps in, the rod control system failed preventing automatic or manual rod motion. The operator initiated a boration to maintain Reactor Coolant System temperature as the power decrease continued. At 2328 on 1/9/84, the reactor tripped when the level in IB steam generator reached the Lo Lo level setpoint.
The plant operators implemented FNP-1-EOP-5 (Reactor Trip) to place the unit safely in Mode 3.
As the power level decayed, the source range monitors energized when required, however, neither channel indicated any source range counts. The source range monitors were declared inoperable and the proper shutdown margin was verified in accordance with Tech. Spec. 3.3.1.
The cause for the operating AC lube oil pump motor tripping was the lube oil pump (SL,P) impeller rubbing against the pump casing which caused the motor to draw excessive running current. This was due to the impeller lift setting adjustment pin loosening and allowing the shaf t to move down. This excessive current resulted in an overload condition. The pump lif t was properly adjusted.
In addition, the lift settings on the remaining Unit 1 SGFP AC lube oil pumps were checked and minor adjustments made. Following adjustment, the motor run-ning currents were measured with satisfactory results. The Unit 2 motor running currents were also checked and found satisfactory.
The failare of the rod control system to produce rod motion was caused by an inhibit signal from the slave cycler card for power cabinet 2BD. During troubleshooting, it was determined that a problem exists in the automatic rod control circuitry (JD,CNV), which causes this inhibit signal to be generated.
Automatic rod control has been declared inoperable and will be repaired during the up coming cycle V-VI refueling outage, currently scheduled to begin on 2/10/84. This failure did not prevent the fulfillment of any safety function.
The failure of the source range channels to indicate auy source range counts was caused by failure of both source range detectors (IG,DET). The detectors were replaced. This failure did not prevent the fulfillment of any safety function.
FAILED COMPONENT IDENTIFICATION Component Manufacturer I.D. Number 1B SGFP lube oil pump Ingersol-Rand 3-EVT-1 Source range detectors Westinghouse WL 23706 Automatic rod control Westinghouse N/A circuitry groau au.
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m Alabama Power Company 600 North 98th Strrat Post Office Box 2641 Birmingham, Alabarna 35291 Telephone 205 783-6081 O
s F. L Clayton, Jr.
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AlabamaPbwer the souttum elocurc system February 3,1984 Docket No. 348 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Sir:
Joseph M. Farley Nuclear Plant, Unit 1, Licensee Event Report i:
No. LER 84-001-00 is forwarded in accordance with 10CFR50.73 to provide 30 day written notification of this occurrence. This report was prepared using a draft version of IEEE Std. 805-1984 since a final version has not been published.
If you have any questions, please advise.
Yours very tru M\\
/Q. L. Clayton, Jr.
F J
FLCJ r/KWM:nac Enclosures xc: IE, Region II I
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| 05000364/LER-1984-001-01, :on 840118,reactor Tripped.Caused by Personnel Allowing Steam Generator 2B Level to Reach hi-hi Setpoint While Operating Feedwater Sys Manually.Personnel Counseled Re Steam Generator Maint |
- on 840118,reactor Tripped.Caused by Personnel Allowing Steam Generator 2B Level to Reach hi-hi Setpoint While Operating Feedwater Sys Manually.Personnel Counseled Re Steam Generator Maint
| | | 05000348/LER-1984-001, :on 840109,reactor Tripped Due to low-low Level in Steam Generator 1B.Caused by Low Bearing Oil Pressure Tripping Pump 1A.Automatic Rod Control to Be Repaired & Source Range Detectors Replaced |
- on 840109,reactor Tripped Due to low-low Level in Steam Generator 1B.Caused by Low Bearing Oil Pressure Tripping Pump 1A.Automatic Rod Control to Be Repaired & Source Range Detectors Replaced
| | | 05000364/LER-1984-002, :on 840123,hourly Firewatch Patrol in Train B Auxiliary Bldg Battery Charger Room Not Performed During 1300-1400 & 1400-1500 H.Caused by Personnel Error. Individual Counseled |
- on 840123,hourly Firewatch Patrol in Train B Auxiliary Bldg Battery Charger Room Not Performed During 1300-1400 & 1400-1500 H.Caused by Personnel Error. Individual Counseled
| | | 05000348/LER-1984-002-01, :on 840210,reactor Tripped from Approx 10% Power Due to Intermediate Range High Flux Signal.Caused by Overly Conservative Trip Setpoints.New Trip Setpoints Inputed |
- on 840210,reactor Tripped from Approx 10% Power Due to Intermediate Range High Flux Signal.Caused by Overly Conservative Trip Setpoints.New Trip Setpoints Inputed
| | | 05000364/LER-1984-002-01, Revised LER 84-002-01:on 840124,hourly Firewatch Patrol in Train B Auxiliary Bldg Battery Charger Room Not Performed at Specified Times.Caused by Personnel Error.Personnel Counseled & Firewatch Patrol Immediately Performed | Revised LER 84-002-01:on 840124,hourly Firewatch Patrol in Train B Auxiliary Bldg Battery Charger Room Not Performed at Specified Times.Caused by Personnel Error.Personnel Counseled & Firewatch Patrol Immediately Performed | | | 05000348/LER-1984-003-01, :on 840218,detensioning of Reactor Vessel Head Studs Begun W/Rcs Boron Concentration Greater than Tech Spec Limits.Caused by Misinterpretation of Tech Specs.Personnel Counseled |
- on 840218,detensioning of Reactor Vessel Head Studs Begun W/Rcs Boron Concentration Greater than Tech Spec Limits.Caused by Misinterpretation of Tech Specs.Personnel Counseled
| | | 05000364/LER-1984-003, :on 840130,reactor Tripped Due to low-low Level in Steam Generator 2C.Caused by Closure of Main Feedwater Regulating Valve 2C Due to Instrumentation Channel Spiking Low.Nlp Card Replaced |
- on 840130,reactor Tripped Due to low-low Level in Steam Generator 2C.Caused by Closure of Main Feedwater Regulating Valve 2C Due to Instrumentation Channel Spiking Low.Nlp Card Replaced
| | | 05000364/LER-1984-004-01, :on 840327,reactor Tripped from 100% Power Due to Power Range Neutron High Flux Negative Rate.Caused by Control Rods Dropping Into Core Due to Voltage Surge Caused by Severe Lightning.Power Supplies Reset |
- on 840327,reactor Tripped from 100% Power Due to Power Range Neutron High Flux Negative Rate.Caused by Control Rods Dropping Into Core Due to Voltage Surge Caused by Severe Lightning.Power Supplies Reset
| | | 05000348/LER-1984-004, :on 840229,during Planned Maint on Msivs, Surface Indications in Operator Side Packing Bland Area Discovered on Three of Six Shafts.Investigation Ongoing.All Six Shafts Will Be Replaced |
- on 840229,during Planned Maint on Msivs, Surface Indications in Operator Side Packing Bland Area Discovered on Three of Six Shafts.Investigation Ongoing.All Six Shafts Will Be Replaced
| | | 05000348/LER-1984-005, :on 840409,reactor Tripped Due to Low Level in Steam Generator 2A in Conjunction W/Loop 1 Steam Flow Greater than Feed Flow.Caused by Operator Error During Performance of FNP-2-STP-33.1.Relay Replaced |
- on 840409,reactor Tripped Due to Low Level in Steam Generator 2A in Conjunction W/Loop 1 Steam Flow Greater than Feed Flow.Caused by Operator Error During Performance of FNP-2-STP-33.1.Relay Replaced
| | | 05000348/LER-1984-006, :on 840223,w/unit in Mode 6,both Containment Personnel Airlock Doors Opened Simultaneously for 30 S. Cause Undetermined.Inner Door Immediately Closed |
- on 840223,w/unit in Mode 6,both Containment Personnel Airlock Doors Opened Simultaneously for 30 S. Cause Undetermined.Inner Door Immediately Closed
| | | 05000364/LER-1984-006-01, :on 840519,diesel Generator 2B Tripped on High Jacket Water Temp.Review Revealed Generator Output Breaker Would Not Open If Trip Followed Nonemergency Test Start. Design Implemented to Correct Condition |
- on 840519,diesel Generator 2B Tripped on High Jacket Water Temp.Review Revealed Generator Output Breaker Would Not Open If Trip Followed Nonemergency Test Start. Design Implemented to Correct Condition
| | | 05000364/LER-1984-006, Forwards Pertinent Design Drawings for Diesel Generator 2B, in Response to N Merriweather Request Re LER 84-006-00. Oversized Aperture Card Encl | Forwards Pertinent Design Drawings for Diesel Generator 2B, in Response to N Merriweather Request Re LER 84-006-00. Oversized Aperture Card Encl | | | 05000348/LER-1984-007, :on 840220,during Troubleshooting,Automatic Actuation Portion of Diesel Bldg Cardox Fire Supression Sys Deemed Inoperable.Caused by Wiring Error.Wiring Error Corrected |
- on 840220,during Troubleshooting,Automatic Actuation Portion of Diesel Bldg Cardox Fire Supression Sys Deemed Inoperable.Caused by Wiring Error.Wiring Error Corrected
| | | 05000364/LER-1984-007-01, :on 840801,continuous Fire Watch Not Maintained.Caused by Personnel Error.Fire Watch Immediately Posted.Personnel Counseled, |
- on 840801,continuous Fire Watch Not Maintained.Caused by Personnel Error.Fire Watch Immediately Posted.Personnel Counseled,
| | | 05000364/LER-1984-008-01, :on 840831,two Tubes in Steam Generator 2B Discovered W/Defects Exceeding Limit for Tube Plugging During Eddy Current Exam.Cause Undetermined.Unit Shut Down Per Tech Spec 3.0.3 & Tubes Plugged |
- on 840831,two Tubes in Steam Generator 2B Discovered W/Defects Exceeding Limit for Tube Plugging During Eddy Current Exam.Cause Undetermined.Unit Shut Down Per Tech Spec 3.0.3 & Tubes Plugged
| | | 05000348/LER-1984-008, :on 840302,determined That Control Room Fire Barrier Penetration for NRC Red Phone Cable Not Properly Sealed.Caused by Personnel Error.Penetration Sealed. Personnel Reinstructed on Proper Installation |
- on 840302,determined That Control Room Fire Barrier Penetration for NRC Red Phone Cable Not Properly Sealed.Caused by Personnel Error.Penetration Sealed. Personnel Reinstructed on Proper Installation
| | | 05000348/LER-1984-009, :on 840311,spare Containment Electrical Penetrations WC02,EB02,EB04,EC05 & EC10 Opened for Mods Designed to Comply W/Reg Guide 1.97 & Enhance Outage Work. Firewatch Performed.Mods Completed 840322 |
- on 840311,spare Containment Electrical Penetrations WC02,EB02,EB04,EC05 & EC10 Opened for Mods Designed to Comply W/Reg Guide 1.97 & Enhance Outage Work. Firewatch Performed.Mods Completed 840322
| | | 05000364/LER-1984-009-01, :on 840908,two Tubes in Steam Generator 2B Identified W/Tube Wall Degradation Exceeding Pluggable Limit.Unit Shut Down on 840831 to Plug Tubes |
- on 840908,two Tubes in Steam Generator 2B Identified W/Tube Wall Degradation Exceeding Pluggable Limit.Unit Shut Down on 840831 to Plug Tubes
| | | 05000364/LER-1984-010-01, :on 840915,steam Generator 2A Steam Flow Channel F1-475 Not Tripped Until 4 H After Channel Declared Inoperable.Caused by Personnel Error.Transmitter Equalizing Valve Closed |
- on 840915,steam Generator 2A Steam Flow Channel F1-475 Not Tripped Until 4 H After Channel Declared Inoperable.Caused by Personnel Error.Transmitter Equalizing Valve Closed
| | | 05000348/LER-1984-010, :on 840406,discovered Adequate Local Leak Rate Testing Not Performed on Fuel Transfer Tubes Since 790529. Caused by Use of Improper Test Connection Due to Procedural inadequacy.FNP-1-STP-627 Revised |
- on 840406,discovered Adequate Local Leak Rate Testing Not Performed on Fuel Transfer Tubes Since 790529. Caused by Use of Improper Test Connection Due to Procedural inadequacy.FNP-1-STP-627 Revised
| | | 05000364/LER-1984-011-01, :on 841023,review of 841020 Calibr Test Determined That Potentiometer Settings for Inputs from Power Range Channel N43 to Loop 3 Overtemp Delta T Circuit Not within Tech Specs.Potentiometers Reset |
- on 841023,review of 841020 Calibr Test Determined That Potentiometer Settings for Inputs from Power Range Channel N43 to Loop 3 Overtemp Delta T Circuit Not within Tech Specs.Potentiometers Reset
| | | 05000348/LER-1984-011, :on 840501,train B Svc Water Battery Declared Inoperable.Caused by Cell 42 Having Specific Gravity Below Limits.Affected Cell & Two Neighboring Cells Replaced |
- on 840501,train B Svc Water Battery Declared Inoperable.Caused by Cell 42 Having Specific Gravity Below Limits.Affected Cell & Two Neighboring Cells Replaced
| | | 05000348/LER-1984-012, :on 840421,train B Reactor Trip Signal Occurred During Response Time Test.Caused by Improper Performance of Surveillance Test Procedure.Personnel Involved Counseled Re Adherence to Procedures |
- on 840421,train B Reactor Trip Signal Occurred During Response Time Test.Caused by Improper Performance of Surveillance Test Procedure.Personnel Involved Counseled Re Adherence to Procedures
| | | 05000364/LER-1984-012-01, :on 841026,reactor Tripped Due to General Warnings in Both Trains of Solid State Protection Sys. Caused by Operator Error During Operability Test.Operator Counseled |
- on 841026,reactor Tripped Due to General Warnings in Both Trains of Solid State Protection Sys. Caused by Operator Error During Operability Test.Operator Counseled
| | | 05000348/LER-1984-013, :on 840716,continuous Fire Watch Not Posted in Closed Cooling Water HX & Pump Room While Maint Personnel Performing Grinding & Welding Operations.Watch Posted & Maintained Until No Longer Required |
- on 840716,continuous Fire Watch Not Posted in Closed Cooling Water HX & Pump Room While Maint Personnel Performing Grinding & Welding Operations.Watch Posted & Maintained Until No Longer Required
| | | 05000364/LER-1984-013-01, :on 841107,fire Patrol Not Posted When Main Control Room Annunciation Capability for Smoke Detectors Rendered Inoperable.Caused by Personnel Error.Fire Watch Established & Individual Involved Counseled |
- on 841107,fire Patrol Not Posted When Main Control Room Annunciation Capability for Smoke Detectors Rendered Inoperable.Caused by Personnel Error.Fire Watch Established & Individual Involved Counseled
| | | 05000348/LER-1984-014, :on 840804,found Potentiometers for Channel NI-43 Input to OT-delta-T Circuit Not Adjusted.Caused by Procedural Inadequacy in Adjustments.Rev to Procedures Planned |
- on 840804,found Potentiometers for Channel NI-43 Input to OT-delta-T Circuit Not Adjusted.Caused by Procedural Inadequacy in Adjustments.Rev to Procedures Planned
| | | 05000364/LER-1984-014-01, :on 841206,containment Purge Supply Fill Line Isolation Valve Found Opened & Line Uncapped.Caused by Personnel Error.Personnel Counseled Re Procedure Adherence |
- on 841206,containment Purge Supply Fill Line Isolation Valve Found Opened & Line Uncapped.Caused by Personnel Error.Personnel Counseled Re Procedure Adherence
| | | 05000348/LER-1984-015, :on 840121 & 0202,hourly Fire Watch Patrol Posted Instead of Continuous Fire Watch.Caused by Personnel Error.Individual Reinstructed.Administrative Procedures Revised |
- on 840121 & 0202,hourly Fire Watch Patrol Posted Instead of Continuous Fire Watch.Caused by Personnel Error.Individual Reinstructed.Administrative Procedures Revised
| | | 05000364/LER-1984-015-01, :on 841213,continuous Fire Watch Not Maintained Per Tech Specs.Caused by Personnel Error in Not Notifying Shift Foreman Before Leaving Station.Personnel Reinstructed in Fire Watch Requirements |
- on 841213,continuous Fire Watch Not Maintained Per Tech Specs.Caused by Personnel Error in Not Notifying Shift Foreman Before Leaving Station.Personnel Reinstructed in Fire Watch Requirements
| | | 05000348/LER-1984-016, :on 840815,discovered Surveillance Test Procedure for Measuring Stroke Time of Reactor Coolant Drain Tank Discharge Containment Isolation Valve LCV-1003 to Be Inadequate |
- on 840815,discovered Surveillance Test Procedure for Measuring Stroke Time of Reactor Coolant Drain Tank Discharge Containment Isolation Valve LCV-1003 to Be Inadequate
| | | 05000364/LER-1984-016-01, :on 841220,reactor Trip Occurred Due to Manual Tripping of Main Turbine.Caused by Failure of Heater Drain Tank 2A Level Control Sys.Unit Returned to Power Operation |
- on 841220,reactor Trip Occurred Due to Manual Tripping of Main Turbine.Caused by Failure of Heater Drain Tank 2A Level Control Sys.Unit Returned to Power Operation
| | | 05000348/LER-1984-017, :on 840815,main Feedwater Regulating Valve 1A Placed on Manual Jack for Repair of Leaking Diaphragm, Rendering Feedwater Isolation Inoperable.Caused by Air Leak. Diaphragm Replaced |
- on 840815,main Feedwater Regulating Valve 1A Placed on Manual Jack for Repair of Leaking Diaphragm, Rendering Feedwater Isolation Inoperable.Caused by Air Leak. Diaphragm Replaced
| | | 05000348/LER-1984-018, :on 840211,RHR Sys Trains a & B Made Inoperable.Caused by Sys Being Placed in Recirculation Mode. Both Trains Returned to Normal Lineup |
- on 840211,RHR Sys Trains a & B Made Inoperable.Caused by Sys Being Placed in Recirculation Mode. Both Trains Returned to Normal Lineup
| | | 05000348/LER-1984-019, :on 840217,during Control Room Insp,Seven Cables in Fire Barrier Penetration Not Sealed Internally. Caused by Procedural Inadequacy.Procedures Revised to Provide Specific Guidance for Installation |
- on 840217,during Control Room Insp,Seven Cables in Fire Barrier Penetration Not Sealed Internally. Caused by Procedural Inadequacy.Procedures Revised to Provide Specific Guidance for Installation
| | | 05000348/LER-1984-020, :on 840907,control Room Fire Barrier Penetrations 01-155-02 & 06-155-03 Found Not to Be Sealed Per Tech Specs.Cause Not Stated.Penetrations Sealed & Declared Operable on 840912 |
- on 840907,control Room Fire Barrier Penetrations 01-155-02 & 06-155-03 Found Not to Be Sealed Per Tech Specs.Cause Not Stated.Penetrations Sealed & Declared Operable on 840912
| | | 05000348/LER-1984-021, :on 841008,hourly Fire Watch Not Conducted in Accordance W/Tech Spec 3.3.3.9 When Fire Alarm for Svc Water Intake Structure Cut Out.Caused by Personnel Error.Personnel Counseled & Fire Alarm Returned to Svc |
- on 841008,hourly Fire Watch Not Conducted in Accordance W/Tech Spec 3.3.3.9 When Fire Alarm for Svc Water Intake Structure Cut Out.Caused by Personnel Error.Personnel Counseled & Fire Alarm Returned to Svc
| | | 05000348/LER-1984-022, :on 841024,isolation Valve for Fire Protection Sys 1SW-111 Closed & No Fire Watch Posted.Caused by Personnel Failure to Follow Procedures.Valve Opened. Individual Counseled |
- on 841024,isolation Valve for Fire Protection Sys 1SW-111 Closed & No Fire Watch Posted.Caused by Personnel Failure to Follow Procedures.Valve Opened. Individual Counseled
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