LER-1981-065, /03L-0:on 810826,during Normal Operation,Plant Computer Failed,Rendering Incore Monitoring Sys Inoperable. Caused by High Temp in Computer Room Causing Rapid Access Disc Transmission Error.Computer Restarted When Cooled |
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| 3171981065R03 - NRC Website |
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NRC F ORM 366 U. S. NUCLE AR REGULATORY COMMISSION (7 77) s LICENSEE EVENT REPORT coNTROLuLoCx:
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1 M 9 LICENSEE CODE I4 15 LICENSE NUYBE H 25 W
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EVENT DECCRIPTION A JD Pr40B AB C SEr ENCES I o 12 I l At 0950, during normal operation, the plant computer failoa rnnanrin,e
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the incore monitoring system inoperable (T.S. 3.3.3.2).
Commenced de-I [n[4ll creasing reactor power at 1105 per Abnormal Operating Procedure - 13.
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The computer was returned to service at 1230. The excore monitoring i
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system remained operable during this event.
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S Y S' E M C AUSE C A USE COYP VALVE CODE CODE SUBCODE COYPONE NT CODE SVBCODE SU 8C O'M 1o191 I RI Bl@ W@ IC l@ l zl zl zl zl zl zl@ W@ W@
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COMPONENT SUBYl TT E D F OHM bUH.
SUPP LIE H MANUFACTUHER TAkEN ACTION ON Pt. ANT YETHOD HOURS n
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40 41 42 13 44 41 c AUSE DESCRIPTION AND CORRECTIVE ACTIONS l
11 101 l Air conditionino complpysors were securva for n nne-mnafficnrinn tme [i j i l l Iligh temperature
- omputer Room resulted in Ranid Access Disc I
i,,,,, j transmission error. No failure was found. The computer was restarted I
g,y3, l when cabinet internals cooled. Maintenance Supervisors were informed l
l of this event and the need to monitor appropriate temperatures.
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8 9 UE THOO GF F ACILITV r
STATUS s03WEH OTHE H S t T IUS DISCOV E H Y DISCOVEHY DESCHIPTION NA l
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7 Fi 9 10 12 11 44 45 46 80 ACTIVITY CONTENT HE L.E ASE D OF HE LF A51 AYOUN T OF ACTIVI TY LOC A TION OF HE L E ASE u^
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8 9 11 17 13 PiHSONNE1 INJUHIES NUYHEH DESClllPilON I
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8 9 11 17 i O'6 0f OH DAMAGE TO F ACILI TY TYPE DE SC Hip i u )N NA l
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Do o!oob!7 on J. s. Lagiewski/P. G. Rizz PHONE:
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PDR
LER NO.
81-65/ 3L DOCKET No.
50-317 LICENSE NO.
DPR-53 EVENT DATE 08-26-81 REPORT DATE 09-25-81 ATTACRMEN,T CAUSE DESCRIPTION AND CORRECTIVE ACTIONS The cause of computer failure was high ambient Computer Room tempera-ture. The Computer Room is supplied by the Control Room Heating, Ventilating and Air Conditianing System.
No. 11 Control Room Air Conditioning Compressor had been modified in accordance with an approved Facility Change and was being tested under load on the t
'ing of the event.
Operating personnel had granted p 'rmiscion to the maintenance contractor to cycle system compressors off, allowing Control Root air temperature to rise slightly and insure a full heat load for No. 11 Compressor.
Although Control Room temperature was maintained less than 85 degrees Fahrenheit, the smaller plant Computer Room temperature reached approx-imately 87 degrees during the event.
The plant computer stopped after experiencing a Rapid Access Disc (RAD) transmission error. High ambient room temperature is believed to have caused merginal RAD circuit operation. The computer was abic to be restarted after internal cabinet temperatures were lowered following the return to full operation of the Control Rc,om Air Conuitioning System. Troubleshooting revealed no hardware or software failures.
As a temporary measure, cabinet doors on the RAD, Control and External Memory cabinets are being left open until seasonal high outside air temperatures lower. A sign is posted on the door of the Computer Room to remind pernonnel entering the room that the cabinet doors should remain open.
A copy of this event report has been distributed to plant operations and maintenance supervisors with responsibility for air conditioning system status to irfnrm them of the need to insure adequate computer cooling.
Of greater impact in preventing recurrence of this type of event are measures to increase Control Room Air Conditioning component reliability.
A survey of system problems, begun la 1980, has resulted in several planned Pacility Changes to:
1.
Increase compressor reliability.
2.
Improve system controls and indications.
3.
Add cooling capacity to improve operation in peak load conditions.
Work has begun cn changes to increase reliability of existing compressors.
New instrumentation control components are ordered. Additional capacity has been initially scheduled for completion by the end of 1982.
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| 05000317/LER-1981-001-01, /01T-0:on 810114,feedwater Transmitter Out of Calibr,Resulting in Erroneous Adjustments to ex-core Nuclear Instrument Channels.Transmitter Failed to Maintain Calibr. Transmitter Replaced.Cause of Shift in Calibr Not Stated | /01T-0:on 810114,feedwater Transmitter Out of Calibr,Resulting in Erroneous Adjustments to ex-core Nuclear Instrument Channels.Transmitter Failed to Maintain Calibr. Transmitter Replaced.Cause of Shift in Calibr Not Stated | | | 05000317/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000318/LER-1981-001-03, /03L-0:on 810107,Channel B Reactor Protective Sys Trip Units for High Power,Thermal Margin/Low Pressure & Axial Flux Offset Bypassed for Troubleshooting Linear Power Range Instrument.Detector Output Faulty | /03L-0:on 810107,Channel B Reactor Protective Sys Trip Units for High Power,Thermal Margin/Low Pressure & Axial Flux Offset Bypassed for Troubleshooting Linear Power Range Instrument.Detector Output Faulty | | | 05000318/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000318/LER-1981-002-03, /03L-0:on 810108,diesel Generator 12 Started Automatically.Possibly Caused by Control Relays in Abnormal State.Generator Reset & Tested | /03L-0:on 810108,diesel Generator 12 Started Automatically.Possibly Caused by Control Relays in Abnormal State.Generator Reset & Tested | | | 05000318/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000317/LER-1981-002-03, /03L-0:on 810111,auxiliary Feedwater Flow to Steam Generators Found Set Below Normal Limit.Caused by Feed Regulating Valve Stroke Limitation Implemented Under Mods Required by NUREG-0578.Restriction Removed on 810122 | /03L-0:on 810111,auxiliary Feedwater Flow to Steam Generators Found Set Below Normal Limit.Caused by Feed Regulating Valve Stroke Limitation Implemented Under Mods Required by NUREG-0578.Restriction Removed on 810122 | | | 05000317/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000317/LER-1981-003-03, /03L-0:on 810217,engineered Safety Features Actuation Sys Channel 2D 12 Steam Generator Pressure Isolator Found Out of Spec.Caused by Transmation Isolator w/non-liner Output.Isolator Replaced | /03L-0:on 810217,engineered Safety Features Actuation Sys Channel 2D 12 Steam Generator Pressure Isolator Found Out of Spec.Caused by Transmation Isolator w/non-liner Output.Isolator Replaced | | | 05000317/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000318/LER-1981-003-03, /03L-0:on 810123,shutdown Cooling Return Header Isolation valve,MOV-652,lost Valve Position Indication & Flow Was Stopped.Caused by Motor Control Center Power Transfer.Transfer Completed,Indication & Flow Restored | /03L-0:on 810123,shutdown Cooling Return Header Isolation valve,MOV-652,lost Valve Position Indication & Flow Was Stopped.Caused by Motor Control Center Power Transfer.Transfer Completed,Indication & Flow Restored | | | 05000318/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000317/LER-1981-004-03, /03L-0:on 810119,containment Cooler 8-inch SRW Discharge valve,1-CV-1593,failed to Open.Caused by Solenoid valve,1-SV-1593,not Allowing 1-CV-1593 to Open.Solenoid Valve Replaced W/Spare & Parts Kit Installed | /03L-0:on 810119,containment Cooler 8-inch SRW Discharge valve,1-CV-1593,failed to Open.Caused by Solenoid valve,1-SV-1593,not Allowing 1-CV-1593 to Open.Solenoid Valve Replaced W/Spare & Parts Kit Installed | | | 05000317/LER-1981-004-01, Containment Cooler 8-inch SRW Discharge Valve Failed to Open.Apparently Caused by Low Differential Pressure Rating of Solenoid Valve That Would Not Vent to Allow Discharge Valve to Open | Containment Cooler 8-inch SRW Discharge Valve Failed to Open.Apparently Caused by Low Differential Pressure Rating of Solenoid Valve That Would Not Vent to Allow Discharge Valve to Open | | | 05000318/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000318/LER-1981-004-03, /03L-0:on 810204, While Conducting Preventive Maint,Shutdown Cooling Flow Lost.Caused by Procedure Not Containing Sufficient Info.Flow Lost Due to de-energized Vital Ac Bus Causing Valve to Shut.Procedure Revised | /03L-0:on 810204, While Conducting Preventive Maint,Shutdown Cooling Flow Lost.Caused by Procedure Not Containing Sufficient Info.Flow Lost Due to de-energized Vital Ac Bus Causing Valve to Shut.Procedure Revised | | | 05000317/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000318/LER-1981-005, Forwards LER 81-005/01T-0 | Forwards LER 81-005/01T-0 | | | 05000318/LER-1981-005-01, /01T-0:on 810118,w/reactor Coolant Sys at 220 F & 230 Psia,Presssure Transmitter Failed High,Causing Power Relief Valve RC-404-ERV to Open.Caused by Loose Oscillator/ Amplifier Assembly within Transmitter 2-PT-103-1 | /01T-0:on 810118,w/reactor Coolant Sys at 220 F & 230 Psia,Presssure Transmitter Failed High,Causing Power Relief Valve RC-404-ERV to Open.Caused by Loose Oscillator/ Amplifier Assembly within Transmitter 2-PT-103-1 | | | 05000317/LER-1981-005-03, /03L-0:on 810119,during Surveillance Testing, Containment Cooler 14 Would Not Start in Slow Speed.Caused by Contacts Not Closing on Slow Speed Motor Starter Interlock Contact Assembly Due to Cracked Case | /03L-0:on 810119,during Surveillance Testing, Containment 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of Transmation Isolator (230IT) 1-E/E-1023B.Isolator Output Found Low | | | 05000317/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000318/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000317/LER-1981-008, Forwards LER 81-008/01T-0 | Forwards LER 81-008/01T-0 | | | 05000318/LER-1981-008-03, /03L-0:on 810113,steam Generator 22 Low Pressure Bistable Meter 2D Found Out of Calibr & Signal Isolator 2-E/E-1023A Failed.Caused by Natural Wear & Aging.Cause of Isolator Failure Not Stated | /03L-0:on 810113,steam Generator 22 Low Pressure Bistable Meter 2D Found Out of Calibr & Signal Isolator 2-E/E-1023A Failed.Caused by Natural Wear & Aging.Cause of Isolator Failure Not Stated | | | 05000317/LER-1981-008-01, /01T-0:on 810203,discovered That When Fire Hose Stations in Auxiliary Bldg & Unit 2 Containment Bldg Were Isolated,Backup Fire Hose Not Routed as Required.Caused by Personnel Error.Backup Hoses Routed as Required | /01T-0:on 810203,discovered That When Fire Hose Stations in Auxiliary Bldg & Unit 2 Containment Bldg Were Isolated,Backup Fire Hose Not Routed as Required.Caused by Personnel Error.Backup Hoses Routed as Required | | | 05000318/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000318/LER-1981-009-03, /03L-0:on 810330,during Normal Power Operation, Motor Operated Isolation Valve in Saltwater Sys Would Not Operate Electrically.Caused by Tripped Overload Devices on Phase a & C.Devices Reset | /03L-0:on 810330,during Normal Power Operation, Motor Operated Isolation Valve in Saltwater Sys Would Not Operate Electrically.Caused by Tripped Overload Devices on Phase a & C.Devices Reset | | | 05000317/LER-1981-009-03, /03L-0:on 810205,reactor Protector Sys Channel D Trip Units Bypassed.Caused by Increase in Temp Detector Resistance,Probably Due to Increased Connection Resistance in Containment.Input Removed from Channel D | /03L-0:on 810205,reactor Protector Sys Channel D Trip Units Bypassed.Caused by Increase in Temp Detector Resistance,Probably Due to Increased Connection Resistance in Containment.Input Removed from Channel D | | | 05000318/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000317/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000318/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000318/LER-1981-010-03, /03L-0:on 810301,power-operated Relief Valve ERV-402 Failed to Seat Resulting in Valve Isolation.Caused by Insufficient Pressure in Sys While Filling Rcs.Pressure Raised & Valve Seated | /03L-0:on 810301,power-operated Relief Valve ERV-402 Failed to Seat Resulting in Valve Isolation.Caused by Insufficient Pressure in Sys While Filling Rcs.Pressure Raised & Valve Seated | | | 05000317/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000317/LER-1981-010-03, /03L-0:on 810123,nipple Broken on Valve CV-5178, Salt Water Emergency Return Isolation from ECCS Pump Room Coolers.Caused by Lead Brick Fall During Const of Lead Shield Wall.Valve Isolated & Nipple Replaced | /03L-0:on 810123,nipple Broken on Valve CV-5178, Salt Water Emergency Return Isolation from ECCS Pump Room Coolers.Caused by Lead Brick Fall During Const of Lead Shield Wall.Valve Isolated & Nipple Replaced | | | 05000317/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000317/LER-1981-011-03, /03L-0:on 810212,thermal Margin/Low Pressure & Steam Generator Low Pressure Trip Units Bypassed While Investigating Intermittent Failures of Reactor Protective Sys Channel D Steam Generator Pressure | /03L-0:on 810212,thermal Margin/Low Pressure & Steam Generator Low Pressure Trip Units Bypassed While Investigating Intermittent Failures of Reactor Protective Sys Channel D Steam Generator Pressure | | | 05000318/LER-1981-011-03, /03L-0:on 810404,steam Generator 21 Pressure Instrument 2-PY-1013D Failed,Causing Channel D Thermal Margin/Low Pressure Trip.Caused by Failure of Sealed, Nonadjustable,Solid State Load Isolator.Device Discarded | /03L-0:on 810404,steam Generator 21 Pressure Instrument 2-PY-1013D Failed,Causing Channel D Thermal Margin/Low Pressure Trip.Caused by Failure of Sealed, Nonadjustable,Solid State Load Isolator.Device Discarded | | | 05000318/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000317/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000317/LER-1981-012-03, /03L-0:on 810213,while Shifting from 1 to 2 Running Charging Pumps,Letdown Relief Valve CVC-345-RV Lifted & Failed to Reseat.Possibly Caused by Pressure Surge in Line.Valve Matls Review Being Conducted | /03L-0:on 810213,while Shifting from 1 to 2 Running Charging Pumps,Letdown Relief Valve CVC-345-RV Lifted & Failed to Reseat.Possibly Caused by Pressure Surge in Line.Valve Matls Review Being Conducted | | | 05000317/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000317/LER-1981-013-03, /03L-0:on 810217,inboard Turbine Bearing Journal in Auxiliary Feedwater Pump 11 Was Found Heavily Heat Scored & Babbit Matl Was Suspended in Oil.Probably Caused by Improper Oil Level or Contaminated Oil.Procedures Changed | /03L-0:on 810217,inboard Turbine Bearing Journal in Auxiliary Feedwater Pump 11 Was Found Heavily Heat Scored & Babbit Matl Was Suspended in Oil.Probably Caused by Improper Oil Level or Contaminated Oil.Procedures Changed | | | 05000318/LER-1981-013-03, /03L-0:on 810304,while Installing Instrumentation, Temporary Shunt Opened,Causing Loss of Power to Low Pressure Safety Injection Pump 22 & Momentary Loss of Shutdown Cooling Flow.Caused by Opened Lead on One End of Shunt | /03L-0:on 810304,while Installing Instrumentation, Temporary Shunt Opened,Causing Loss of Power to Low Pressure Safety Injection Pump 22 & Momentary Loss of Shutdown Cooling Flow.Caused by Opened Lead on One End of Shunt | |
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