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APPROv80 Out No 3190-4104 LICENSEE EVENT REPORT (LER) 1 DOCKET souteSER til PA33 83L FAC8LITV Naast (1?
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On December 11, 1985, at 1200 CST with unit 1 in mode 5 at 0 psig and 124 F and unit 2 in mode 5 at 150 psig and 125 F, it was discovered that reagent air for the unit 2 "A" train containment hydrogen analyzer was connected to a nonessential ~
air source. Because of this condition, the monitor was declared inoperable.'
The monitors reagent air had been changed from an essential air source to the /
nonessential air source as part of a mdification performed during the unit 2, cycle 2 outage. The unit returned to mode 2 from the outage on December 26, 1984, and continued to operate until shutdown on August 21, 1985. This operation is now considered to have been in violation of Limiting Condition for Operation (LCO) 3.0.4 and 3.0.3 which is reportable per =10 CFR M 73, The condition was discovered durinc ? Le system walkdown l erformed by the i
Sequoyah Nuclear Plant's Quality fut 9. P - :e Group. Actions have been implemented%
to reconnect the monitor to the es.entim s.tr supply, and work will be completed prior to unit 2 reentering mode 2.
Due to the existence of a redundant train of containment hydrogen monitoring, post-accident sampling provisions for taking containment hydrogen samples, and the use of the hydrogen ignition system, this ' event is not considered to have affected the public health and safety.
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austC Form 3,4A Ua NUCLE AR LEGutiTOLV CaesasisB400s LICENSEE EVENT REPORT (LER) TEXT CONTINUATION maouo oue Na nio-oio4 EXPIRES. Os31 SB JCauTV Naast tu DOCKET NuesBER 628 ggn etutsBER t61 PAGE831 l
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.m aw wc r assaw im Description of the Event On December 11, 1985, at 1200 CST wigh unit 1 in mode 5 at 0 psig and 124 F and unit 2 in mode 5 at 150 psig and 125 F, it was discovered that the reagent air for unit 2 "A" train containment hydrogen analyzer was connected to the nonessential control air system. This condition was discovered during a plant system walkdown by the Sequoyah Nuclear Plant's (SQN) Quality Surveillance Group. The nonessential air supply is not seismically qualified; therefore, it cannot be considered reliable for providing a safety-related function.
Because the monitor was determined to be connected to an unreliable air supply, it was declared inoperable.
During the unit 2, cycle 2 refueling outage, a modification was performed on the hydrogen analyzer system per Engineering Change Notice (ECN) 6032 to move the test gas bottles and control outside the unit 2 Containment / Shield Building annulus.
Part of the modification caused the "A" train hydrogen analyzer to have its reagent air supply changed from an essential air source to a nonessential air source. Because the monitor is considered inoperable under this condition, reentry q
into mode 2 on December 26, 1984, is now determined to have been in violation of Limiting Condition for Operation (LCO) 3.0.4.
In addition, the unit continued to operate past the 30 days specified in LCO 3.6.4.1 action criteria and, therefore, was also in violation of LCO 3.0.3 until shutdown on August 21, 1985.
.V The hydrogen analyzer does not provide any automatic functions and is normally maintained in the standby mode; therefore, this condition did not have any effect on any additional plant equipment.
Cause of Event
l While scoping out the work to be performed on ECN 6032, the cognizant modifications l
engineer noted that nonessential air was available in the area where units 1 and 2 i
"A" train monitors were to be relocated but essential air would have to be piped in.
He contacted the engineer in charge of the hydrogen analyzer system in the Office of Engineering (OE), the TVA design group, to determine if the nonessential air supply was acceptable for use as reagent air.
The OE engineer verified that it could be used; therefore, the modifications engineer wrote Field Change Request (FCR) 2468 to implement the change. The FCR was processed and approved through the normal channels. The work was completed on unit 2 as specified in ECN 6032 with changes authorized by FCR 2468.
When work was actually started on unit 1, the modifications cognizant engineer discovered that essential air could be supplied to tne "A" train hydrogen analyzer without undue cost impact; therefore, he wrote FCR 3275 to amend FCR 2468 and maintain the reagent air supply for that monitor to the essential air source.
This FCR was processed and approved through normal channels.
The root cause of this event is a cognitive personnel error on the part of the OE engineer performing the technical analysis on the change requested in FCR 2468.
He misinterpreted the hydrogen analyzer technical manual in relationship to the
" function of the reagent air with respect to the analyzer operation.
It was his NicFOmu3ua E43I
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.is4..nn interpretation that reagent air was only used for calibrating the analyzer; therefore, an essential air supply was not required for the performance of its normal safety function. Additionally, the reagent air supply to the hydrogen analyzer was not included in the list of required lusds for the design criteria for the essential air system. Further evaluation has revealed that the reagent air is required at all times for the operability of the analyzer.
Analysis of the Event
This event is considered to have caused unit 2 of SQN to operate in a condition prohibited by its technical specifications. This condition is reportable per 10 CFR 50.73, paragraph a.2.1.B.
The "A" train hydrogen analyzer is technically considered inoperable because the nonessential air supply used for its reagent air is not seismically qualified.
In the event where a loss of coolant accident (LOCA) existed and a seismic event also occurred, the monitor would not be available to perform its design function.
The "B" train monitor was connected to essential air and is fully operational.
Also, the hydrogen ignition system is energized during a LOCA to prevent the buildup of hydrogen in containment. In addition, the postaccident sampling system has provisions for :aking containment air samples which can be analyzed for hydrogen content. Because of the additional provisions made for the detection and rdtigation of a potential hydrogen buildup during a LOCA, this event is not considered to have had any effect on the public health and safety.
Corrective Actions
The reagent air for the unit 2 "A" train hydrogen analyzer is being modified to return its supply source to the essential air system. This work will be completed i
before unit 2 is returned to mode 2, where the analyzer is required operable.
The design criteria for the essential air supply is also being revised to add the hydrogen analyzer to the list of equipment required to be supplied f rom that source.
Additional Information
The hydrogen analyzer that was af fected by this event was manufactured by Consip Delphi Incorporated and its model No. is K-IIIM.
During the investigation process, it was discovered that both vendor and TVA control drawings showed the wrong designation for control of the reagent air supply solenoid valve (FSV-43-210 A). The wiring drawings and all operation and testing instructions for the analyzer have been verified and are correct; therefore, this error does not effect proper operation.
The drawings will be revised to show proper control configuration.
There are no previous events of this kind.
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M TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear,Planti Post Office' Box 2000 :
- - Soddy' Daisy,:. Tennessee. 37379-January 9,.1986 1
J-U.S. Nuclear Regulatory Commission' Document: Control -Desk i~
Washington, - DC 20555
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k Gentlemen:
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' TENNESSEE VALLEYJAUTHORITY - SEQUOYAH NUCLEAR' PLANT-UNIT:2
- - DOCKET NO.
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50-328 FACILITY OPERATING' LICENSE'DPR,79,-~ REPORTABLE,0CCURRENCE REPORT
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SQRO-50-328/85012 Theenclose'dlicensee: event lreportprovidesde$ ails,concerbingthe I
inoperability of the unit'2 "A" train containment ~ hydrogen ulyzer.
j This event'is reported in accordance'with 10'CFRL50.73, paragraph a.2.i..
b Very truly yours, TENNESSEE VALLEY AUTHORITY 4
o. a. LnA- _--
P. R. Wallace Plant Manager.
~
k Enclosure cc (Enclosure):
m J. Nelson Crace Regional Administrator
- - U.S. Nuclear E sgulatory Commission Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 l
t Records Center Institute of! Nuclear Power Operations,-
i si Suite 1500
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1100 Circle 75. Parkway.
Atlanta,. Georgia--30339
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.NRC Inspector,;NUC PR, Sequoyah?
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,1983-TVA 50TH ANNIVERSARY-
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, An Equal Opportunity Employer,c
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| 05000327/LER-1985-001, :on 850109,Surveillance Instruction 143, Control Bldg Emergency Air Cleanup Sys Filter Train Test, Not Performed within Tech Spec Time Limits.Surveillance Instruction Completed Satisfactorily on 850109 |
- on 850109,Surveillance Instruction 143, Control Bldg Emergency Air Cleanup Sys Filter Train Test, Not Performed within Tech Spec Time Limits.Surveillance Instruction Completed Satisfactorily on 850109
| | | 05000328/LER-1985-001-01, :on 850114,reactor Trip Occurred.Caused by Instrument Mechanic Pulling Wrong Fuse.Individual Counseled & Instructed to Follow Procedures.Procedure Reviewed & Revised |
- on 850114,reactor Trip Occurred.Caused by Instrument Mechanic Pulling Wrong Fuse.Individual Counseled & Instructed to Follow Procedures.Procedure Reviewed & Revised
| | | 05000328/LER-1985-002-01, :on 850112,while Operating at 100% Power,Unit Experienced Automatic Reactor Trip from lo-lo Steam Generator Level on Loop.Caused by Failure of Discharge Valve LCV-6-106A on Heater Drain Tank Pump 3 |
- on 850112,while Operating at 100% Power,Unit Experienced Automatic Reactor Trip from lo-lo Steam Generator Level on Loop.Caused by Failure of Discharge Valve LCV-6-106A on Heater Drain Tank Pump 3
| | | 05000328/LER-1985-002-02, :on 850112,reactor Tripped on lo-lo Steam Generator Level & Train a Reactor Trip Breaker Failed to Open Automatically.Caused by Failure of Pump Discharge Valve LCV-6-106A.Valve Repaired |
- on 850112,reactor Tripped on lo-lo Steam Generator Level & Train a Reactor Trip Breaker Failed to Open Automatically.Caused by Failure of Pump Discharge Valve LCV-6-106A.Valve Repaired
| | | 05000327/LER-1985-003, :on 850104,Tech Spec Max Allowable Surveillance Instruction Performance Date Exceeded by 52 Days.Caused by Miscalculation of Date.Use of Std Form to Calculate & Document Max Allowable Dates Initiated |
- on 850104,Tech Spec Max Allowable Surveillance Instruction Performance Date Exceeded by 52 Days.Caused by Miscalculation of Date.Use of Std Form to Calculate & Document Max Allowable Dates Initiated
| | | 05000327/LER-1985-004, :on 850116,Surveillance Instruction SI-261, Visual Insp of Fire Doors, Not Performed within Tech Spec Time Limits.Caused by Addl Deficiencies Inadvertently Omitted from Rept.Instruction Performed |
- on 850116,Surveillance Instruction SI-261, Visual Insp of Fire Doors, Not Performed within Tech Spec Time Limits.Caused by Addl Deficiencies Inadvertently Omitted from Rept.Instruction Performed
| | | 05000327/LER-1985-004-01, :on 850116,surveillance Instructions (SI) on Fire Doors Not Performed within Tech Spec Time Limits.Caused by Personnel Error.Ltr Written to Personnel Stressing Correct Performance of SIs |
- on 850116,surveillance Instructions (SI) on Fire Doors Not Performed within Tech Spec Time Limits.Caused by Personnel Error.Ltr Written to Personnel Stressing Correct Performance of SIs
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000328/LER-1985-004-02, :on 850215 & 17,reactor Trips Occurred Due to lo-lo Steam Generator Water Level.Caused by Personnel Error & Failed Filter Cartridge Cover.New Cover Installed & Personnel Counseled |
- on 850215 & 17,reactor Trips Occurred Due to lo-lo Steam Generator Water Level.Caused by Personnel Error & Failed Filter Cartridge Cover.New Cover Installed & Personnel Counseled
| | | 05000328/LER-1985-005-02, :on 850212,discovered That Loose Equipment & Debris Left Inside Upper Containment.Caused by Personnel Leaving Behind Loose Matls & Equipment in Containment.Maint Personnel Reinstructed |
- on 850212,discovered That Loose Equipment & Debris Left Inside Upper Containment.Caused by Personnel Leaving Behind Loose Matls & Equipment in Containment.Maint Personnel Reinstructed
| 10 CFR 50.73(a)(2)(1) | | 05000328/LER-1985-006-03, :on 850406,air Control Valve for ERCW Valve 2-FCV-67-186 Found in Closed Position.Caused by Improper Back Plate Indications.Back Plates Will Be Modified |
- on 850406,air Control Valve for ERCW Valve 2-FCV-67-186 Found in Closed Position.Caused by Improper Back Plate Indications.Back Plates Will Be Modified
| | | 05000327/LER-1985-006, :on 850120,Limiting Condition for Operation (LCO) 3.3.1.1 Entered Due to Loss of Feedwater Channel. Caused by Frozen Sense Line.On 850121,second Channel Became Inoperable for Same Reason & LCO 3.0.3 Entered |
- on 850120,Limiting Condition for Operation (LCO) 3.3.1.1 Entered Due to Loss of Feedwater Channel. Caused by Frozen Sense Line.On 850121,second Channel Became Inoperable for Same Reason & LCO 3.0.3 Entered
| | | 05000327/LER-1985-007, :on 850131,while Performing Surveillance Instruction 166.21,Train B Emergency Gas Treatment Sys Room Cooler Would Not Start.Caused by Blown Control Fuse.Fuse Replaced |
- on 850131,while Performing Surveillance Instruction 166.21,Train B Emergency Gas Treatment Sys Room Cooler Would Not Start.Caused by Blown Control Fuse.Fuse Replaced
| 10 CFR 50.73(a)(2)(1) | | 05000328/LER-1985-007-04, :on 850712,inadvertent Trip of Normal Feeder Breaker on 6,900-volt Shutdown Board Actuated ESF Sys.Cause Undetermined |
- on 850712,inadvertent Trip of Normal Feeder Breaker on 6,900-volt Shutdown Board Actuated ESF Sys.Cause Undetermined
| | | 05000328/LER-1985-008-03, :on 850423,hourly Fire Watch Not Performed Due to Inoperable Door.Caused by Excessive Pulling on Door Handle to Overcome Door Weight & Pressure Differences. Surveillance Will Be Performed Every 18 Months |
- on 850423,hourly Fire Watch Not Performed Due to Inoperable Door.Caused by Excessive Pulling on Door Handle to Overcome Door Weight & Pressure Differences. Surveillance Will Be Performed Every 18 Months
| | | 05000327/LER-1985-008, :on 850120,21 & 23,hourly Fire Watch Not Performed.All Fire Watches Immediately Reestablished or Completed Upon Detection of Missed Fire Watch |
- on 850120,21 & 23,hourly Fire Watch Not Performed.All Fire Watches Immediately Reestablished or Completed Upon Detection of Missed Fire Watch
| 10 CFR 50.73(a)(2)(1) | | 05000328/LER-1985-009-02, :on 850503,reactor Tripped Due to Main Turbine Trip.Caused by Main Generator Trip Due to Loss of Both Stator Cooling Water Pumps.Point Connector Removed & Wiring Inspected |
- on 850503,reactor Tripped Due to Main Turbine Trip.Caused by Main Generator Trip Due to Loss of Both Stator Cooling Water Pumps.Point Connector Removed & Wiring Inspected
| | | 05000327/LER-1985-009, :on 850128,rod Position Indication Sys Misaligned Beyond Tech Spec Limits.Caused by Puddles of Water Beneath Solatron Line Voltage Regulator.Sys Returned to Svc After Moisture Dissipated |
- on 850128,rod Position Indication Sys Misaligned Beyond Tech Spec Limits.Caused by Puddles of Water Beneath Solatron Line Voltage Regulator.Sys Returned to Svc After Moisture Dissipated
| 10 CFR 50.73(a)(2)(i) | | 05000328/LER-1985-010-03, :on 850522,reactor Trip Received from RCS Over Power/Differential Temp Trip Function at 100% Power.Caused by Personnel Error.Temp Loops Tested.Data Collection Sheet Modified |
- on 850522,reactor Trip Received from RCS Over Power/Differential Temp Trip Function at 100% Power.Caused by Personnel Error.Temp Loops Tested.Data Collection Sheet Modified
| | | 05000327/LER-1985-010, :on 850201,containment Ventilation Isolation Occurred on Train B Valves to Upper & Lower Containment Radiation Monitors RM-90-106 & 112.Caused by Failure of Power Supply.Power Supply Replaced |
- on 850201,containment Ventilation Isolation Occurred on Train B Valves to Upper & Lower Containment Radiation Monitors RM-90-106 & 112.Caused by Failure of Power Supply.Power Supply Replaced
| | | 05000328/LER-1985-011-03, :on 851010,while Placing Upper Containment Radiation Monitor in Svc,Containment Ventilation Isolation Occurred.Caused by Failure to Verify Switch in Block Position.Isolation Reset |
- on 851010,while Placing Upper Containment Radiation Monitor in Svc,Containment Ventilation Isolation Occurred.Caused by Failure to Verify Switch in Block Position.Isolation Reset
| | | 05000327/LER-1985-011, :on 850206,08,12,13,15 & 28,hourly Fire Watch Not Performed within 1 H.Caused by Equipment Failures. Equipment Repaired & Fire Watches Completed 3 H After Last Watch |
- on 850206,08,12,13,15 & 28,hourly Fire Watch Not Performed within 1 H.Caused by Equipment Failures. Equipment Repaired & Fire Watches Completed 3 H After Last Watch
| 10 CFR 50.73(a)(2)(1) | | 05000328/LER-1985-012-04, :on 851211,during Mode 5,Train a Containment Hydrogen Analyzer Connected to Unqualified Reagent Air Source & Declared Inoperable.Caused by Personnel Error. Reagent Air Being Modified |
- on 851211,during Mode 5,Train a Containment Hydrogen Analyzer Connected to Unqualified Reagent Air Source & Declared Inoperable.Caused by Personnel Error. Reagent Air Being Modified
| | | 05000327/LER-1985-012, :on 850312,hourly Fire Watch Not Performed within 1 H,Per Tech Spec 3.7.12.Caused by Inoperable Door. Door Repaired & Fire Watch Reestablished |
- on 850312,hourly Fire Watch Not Performed within 1 H,Per Tech Spec 3.7.12.Caused by Inoperable Door. Door Repaired & Fire Watch Reestablished
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000327/LER-1985-013, :on 850321,on Seven Separate Occasions,Hourly Fire Watch Not Performed Due to Doors Failing in Closed Lock Condition.Caused by Equipment Failure.Fire Watches Reestablished After Doors Repaired |
- on 850321,on Seven Separate Occasions,Hourly Fire Watch Not Performed Due to Doors Failing in Closed Lock Condition.Caused by Equipment Failure.Fire Watches Reestablished After Doors Repaired
| 10 CFR 50.73(a)(2)(1) | | 05000327/LER-1985-014, :on 850404,during Calibr of Auxiliary Bldg Stack Radiation Monitor O-RM-90-101,inadvertent Auxiliary Bldg Isolation Occurred.Caused by Personnel error.SI-82 Revised to Ref 10 Time Delay for Channels |
- on 850404,during Calibr of Auxiliary Bldg Stack Radiation Monitor O-RM-90-101,inadvertent Auxiliary Bldg Isolation Occurred.Caused by Personnel error.SI-82 Revised to Ref 10 Time Delay for Channels
| | | 05000327/LER-1985-015, :on 850404,hourly Fire Watch for Auxiliary Bldg Supply Air Fan Room Not Conducted.Caused by Inoperable Door. Door repaired,post-maint Check Made & Fire Watch Reestablished |
- on 850404,hourly Fire Watch for Auxiliary Bldg Supply Air Fan Room Not Conducted.Caused by Inoperable Door. Door repaired,post-maint Check Made & Fire Watch Reestablished
| | | 05000327/LER-1985-017, :on 850422 & 0506,inadvertent Auxiliary Bldg Isolations (Abis) Occurred.Caused by electro-magnetic Frequency Feedback from Welding Activities.Abi in Both Events Reset |
- on 850422 & 0506,inadvertent Auxiliary Bldg Isolations (Abis) Occurred.Caused by electro-magnetic Frequency Feedback from Welding Activities.Abi in Both Events Reset
| | | 05000327/LER-1985-019, :on 850524,design Review Revealed That During Seismic event,1-inch Demineralized Water Pipe & High Pressure Fire Protection Header Could Have Failed. Demineralized Water Pipe Isolated for Repair |
- on 850524,design Review Revealed That During Seismic event,1-inch Demineralized Water Pipe & High Pressure Fire Protection Header Could Have Failed. Demineralized Water Pipe Isolated for Repair
| | | 05000327/LER-1985-019-01, :on 850524,inadequate Seismic Piping Supports Discovered.Caused by Personnel Errors.Drawing Discrepancies Re Both Pipes Corrected & Sk Series of Prints Superseded by 47W Series of Prints |
- on 850524,inadequate Seismic Piping Supports Discovered.Caused by Personnel Errors.Drawing Discrepancies Re Both Pipes Corrected & Sk Series of Prints Superseded by 47W Series of Prints
| | | 05000327/LER-1985-020, :on 850514,both RHR Trains Inadvertently Isolated by Closure of Train B Suction Valve.Caused by Work Performed on Reactor Vessel Level Instrumentation Sys to Refill Sense Lines.Suction Reestablished |
- on 850514,both RHR Trains Inadvertently Isolated by Closure of Train B Suction Valve.Caused by Work Performed on Reactor Vessel Level Instrumentation Sys to Refill Sense Lines.Suction Reestablished
| | | 05000327/LER-1985-021, :on 850523,inadvertent Main Control Room Ventilation Isolation Occurred.Caused by Bad Power Supply on Radiation Monitor.Power Supply Replaced & Monitor Returned to Svc |
- on 850523,inadvertent Main Control Room Ventilation Isolation Occurred.Caused by Bad Power Supply on Radiation Monitor.Power Supply Replaced & Monitor Returned to Svc
| | | 05000327/LER-1985-022-01, :on 850617 & 22,hourly Fire Watches Not Conducted.Caused by Delay in Revising Fire Watch Check Sheets & Problem W/Card Reader Access Program,Respectively. Fire Watch Established |
- on 850617 & 22,hourly Fire Watches Not Conducted.Caused by Delay in Revising Fire Watch Check Sheets & Problem W/Card Reader Access Program,Respectively. Fire Watch Established
| | | 05000327/LER-1985-023, :on 850530,inadvertent Auxiliary Bldg Ventilation Isolations Occurred.Caused by Electromagnetic Interference on Spent Fuel Radiation Monitors & Personnel Error.No Radiation Levels Above Normal Found |
- on 850530,inadvertent Auxiliary Bldg Ventilation Isolations Occurred.Caused by Electromagnetic Interference on Spent Fuel Radiation Monitors & Personnel Error.No Radiation Levels Above Normal Found
| | | 05000327/LER-1985-024, :on 850524,fire Watch for Supply Air Fan Room Not Conducted Because Door A-123 Inoperable.Caused by Broken Door Handle.Defective Parts Replaced & Hourly Fire Watch Resumed |
- on 850524,fire Watch for Supply Air Fan Room Not Conducted Because Door A-123 Inoperable.Caused by Broken Door Handle.Defective Parts Replaced & Hourly Fire Watch Resumed
| | | 05000327/LER-1985-025, :on 850601,noble Gas Sample Not Taken at Required Frequency.Caused by Analyst Failure to Collect Sample Every 8 H.Analyst Counseled & Sample Taken |
- on 850601,noble Gas Sample Not Taken at Required Frequency.Caused by Analyst Failure to Collect Sample Every 8 H.Analyst Counseled & Sample Taken
| | | 05000327/LER-1985-026, :on 850611,feedwater Isolation Occurred Due to high-heat Steam Generator Level.Caused by Low Operating Temp When Steam Generator Valve Opened.Instruction Used to Open Valves at Pressure Revised |
- on 850611,feedwater Isolation Occurred Due to high-heat Steam Generator Level.Caused by Low Operating Temp When Steam Generator Valve Opened.Instruction Used to Open Valves at Pressure Revised
| | | 05000327/LER-1985-027-01, :on 850625,main Steam Line Isolation Occurred. Caused by Coincident Logic on High Steam Line Flow Monitoring Sys.Setpoint of Ref Controller PC-1-73 Recalibr |
- on 850625,main Steam Line Isolation Occurred. Caused by Coincident Logic on High Steam Line Flow Monitoring Sys.Setpoint of Ref Controller PC-1-73 Recalibr
| | | 05000327/LER-1985-028, :on 850704,hourly Fire Watch for Addl Equipment Bldg Not Conducted Because Door A-183 Would Not Open.Caused by Loose Screws Holding Latch Mechanism Together.Defective Parts Corrected |
- on 850704,hourly Fire Watch for Addl Equipment Bldg Not Conducted Because Door A-183 Would Not Open.Caused by Loose Screws Holding Latch Mechanism Together.Defective Parts Corrected
| | | 05000327/LER-1985-029-01, :on 850719,trip Occurred on lo-lo Steam Generator Level in Loop 3.Caused by Power Loss to Feedwater Pump When Attempting to Transfer Power from Electrical Board.Operators Made Aware of Problems |
- on 850719,trip Occurred on lo-lo Steam Generator Level in Loop 3.Caused by Power Loss to Feedwater Pump When Attempting to Transfer Power from Electrical Board.Operators Made Aware of Problems
| | | 05000327/LER-1985-030-01, :on 850721,ESF Actuations for Auxiliary Feedwater Pump Start Occurred Due to Loss of Both Main Feed Pumps & hi-hi Level in Generator Loop 4.Caused by Failed Condensate Dump Back Valve |
- on 850721,ESF Actuations for Auxiliary Feedwater Pump Start Occurred Due to Loss of Both Main Feed Pumps & hi-hi Level in Generator Loop 4.Caused by Failed Condensate Dump Back Valve
| | | 05000327/LER-1985-031, :on 850729,auxiliary Bldg Isolation Occurred Due to High Radiation Levels from Cracked Chemical & Vol Control Sample Line Weld.Caused by Fatigue of Metal in Weld. Brace Will Be Installed by Next Outage |
- on 850729,auxiliary Bldg Isolation Occurred Due to High Radiation Levels from Cracked Chemical & Vol Control Sample Line Weld.Caused by Fatigue of Metal in Weld. Brace Will Be Installed by Next Outage
| | | 05000327/LER-1985-031-01, :on 850729,auxiliary Bldg Isolation Occurred Due to High Radiation Indicated by Stack Ventilation Monitor.Caused by Leaking Weld at Sample Line Connection Upstream of Valve 62-674.Lines Replaced |
- on 850729,auxiliary Bldg Isolation Occurred Due to High Radiation Indicated by Stack Ventilation Monitor.Caused by Leaking Weld at Sample Line Connection Upstream of Valve 62-674.Lines Replaced
| | | 05000327/LER-1985-032-01, :on 850816,both Trains of Emergency Gas Treatment Sys Declared Inoperable Due to Failure to Meet Environ Qualification for Instrumentation.Setpoint Change Initiated |
- on 850816,both Trains of Emergency Gas Treatment Sys Declared Inoperable Due to Failure to Meet Environ Qualification for Instrumentation.Setpoint Change Initiated
| | | 05000327/LER-1985-033-01, :on 850827,during Weekly Train B Chlorine Detector Function Testing,Esf Actuation Occurred for Main Control Room Isolation.Caused by Personnel Error.Personnel Counseled |
- on 850827,during Weekly Train B Chlorine Detector Function Testing,Esf Actuation Occurred for Main Control Room Isolation.Caused by Personnel Error.Personnel Counseled
| | | 05000327/LER-1985-034-01, :on 850827,diesel Generator 2B-B Performed Incorrectly During Surveillance.Caused by Loose Electrical Connector Between Control Panel & Hydraulic Actuator on Engine Governor.Connector Tightened |
- on 850827,diesel Generator 2B-B Performed Incorrectly During Surveillance.Caused by Loose Electrical Connector Between Control Panel & Hydraulic Actuator on Engine Governor.Connector Tightened
| | | 05000327/LER-1985-035-01, :on 850829,control Power for Diesel Generator 2B-B Lost for Several Seconds.Caused by Personnel Error Resulting in Loose Connector from Test Rig to Breaker Lugs. Suction Valves Returned to Normal |
- on 850829,control Power for Diesel Generator 2B-B Lost for Several Seconds.Caused by Personnel Error Resulting in Loose Connector from Test Rig to Breaker Lugs. Suction Valves Returned to Normal
| | | 05000327/LER-1985-036-01, :on 850825,26,28 & 0913,hourly Fire Watch Not Performed within 1 H.Caused by Improper Shift Relief or Inaccessibility to Areas.Fire Watches Reestablished as Soon as Practical |
- on 850825,26,28 & 0913,hourly Fire Watch Not Performed within 1 H.Caused by Improper Shift Relief or Inaccessibility to Areas.Fire Watches Reestablished as Soon as Practical
| | | 05000327/LER-1985-037-01, :on 850906,main Control Room Ventilation Isolation Occurred Due to Spike on Radiation Monitor (RM) RM-90-125.Caused by RM Controller Either Placed in Trip Ref Mode or Momentary Loss of Power |
- on 850906,main Control Room Ventilation Isolation Occurred Due to Spike on Radiation Monitor (RM) RM-90-125.Caused by RM Controller Either Placed in Trip Ref Mode or Momentary Loss of Power
| | | 05000327/LER-1985-038, :on 850908,auxiliary Bldg Ventilation Isolation Occurred Due to Spike on Spent Fuel Pool (SFP) Radiation Monitor.Caused by Increase in Radiation Level Due to Removal of SFP Filter from Svc |
- on 850908,auxiliary Bldg Ventilation Isolation Occurred Due to Spike on Spent Fuel Pool (SFP) Radiation Monitor.Caused by Increase in Radiation Level Due to Removal of SFP Filter from Svc
| | | 05000327/LER-1985-039-01, :on 851010,containment Ventilation Isolation Occurred.Caused by Instrument Mechanic Mistakenly Running Test on Incorrect Radiation Monitor.Mechanic Counseled. Disciplinary Action Will Be Taken |
- on 851010,containment Ventilation Isolation Occurred.Caused by Instrument Mechanic Mistakenly Running Test on Incorrect Radiation Monitor.Mechanic Counseled. Disciplinary Action Will Be Taken
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