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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20151W2321998-09-0808 September 1998 Ro:On 980826,facility Bldg Air Monitor (Fam Channel 4) Failed Daily Fam Alarm Checks Prior to Reactor Operation. Caused by Failed Alarm Relay.Staff Is Preparing Formal Written Procedures for Testing Configurations for Fam Sys ML20217A0891998-03-18018 March 1998 Ro:On 980218,potential Reactor Safety Failure Discovered W/ Reactor Shutdown.Caused by Manual Scram Function Bypassed by Sticking Reset Contact in Console Power key-switch. Protective Action Reset Switches Wired ML20199C5371997-11-11011 November 1997 Ro:On 971030,shim Safety Number 2 Was Found to Be Binding & Became Stuck in Withdrawn Position & Control Rod Failed to Scram.Caused by Incorrect Spacing Between Hold Down Foot & Bundle top-handle.Procedure SOP-II-I Modified ML20129H5191996-10-30030 October 1996 Ro:On 961015,loss of Facility Power Occurred Causing Reactor Scram Due to Lack of Attention to Detail & Excessive Distractions to Operations.Startup Checklist Had Several Individual Instrument Checks Combined Into Single Items ML20079C2481991-06-10010 June 1991 Ro:On 910607,reactor Operated for 30 Minutes at 1 MW W/O Facility Air Monitors in Operation.Operator Removed from Watch Standing Duties.Final Rept Will Be Forwarded Upon Completion ML20066H1401991-02-0808 February 1991 Special Rept 90-01:on 910125,during Annual Fuel Insp of Operational Core VIII-A,fuel Elements 6502 & 8468 Failed to Pass go-no-go Gauge Test for Excessive Transverse Bend. Elements Replaced W/Spare & Fuel Bundles Relocated ML20203B0091986-07-10010 July 1986 Ro:On 860708,no Rod Down Indication Received for Transient Rod Until Carriage Driven In,During Performance of Manual Scram for Reactor Shutdown.Caused by Malfunction of Reactor Safety Sys Component.Repairs Underway ML20199B1171986-06-0404 June 1986 Ro:On 860501,improper Handling of Experiment Discovered Which Could Have Resulted in Serious Operational Event. Caused by Insertion of $1.09 Reactivity.Postulated Accidents & Results & Related Info Encl ML20205Q2921986-05-16016 May 1986 Final Ro:On 860501,unanticipated or Uncontrolled Change in Reactivity Greater than One Dollar Occurred.Caused by Removal of Rotisserie from Face Water Notch.Proposed Changes to SOPs Developed as Listed ML20205J9311986-02-18018 February 1986 RO 86-01:on 860204,temp Recorder Providing LSSS Signal to Scram on High Fuel Temp Malfunctioned.Caused by Defective Motor Bearing.Bearing Replaced & Recorder Calibr ML20137Y6291985-09-24024 September 1985 RO-85-04:on 850912,transient Rod Followed Cylinder Out During Positioning of Transient Rod Cylinder.Air Solenoid for Transient Rod Sys Not Functioning as Designed.Air Solenoid Disassembled,Cleaned & Reassembled ML20127M4151985-05-0909 May 1985 Ro:On 850508,during Restart Following Power Failure,Facility Air Monitoring (Fam) Sys Inoperable for 15 Minutes.Caused by Turning Off High Voltage to Detectors.Procedures Revised to Verify Fam Sys After Power Failure ML20113D5681985-01-21021 January 1985 RO 85-2;on 850111,safety Channel 1 Detector Failed During Reactor Operation.Caused by Loose Connector Pin Making Intermittent Contact.New Connector Installed & Detector Verified Operable Prior to Reinstallation ML20134Q1961985-01-11011 January 1985 Ro:On 850111,reactor Shut Down When Safety Channel 1 Did Not Respond Following Annual Reactor Maint.Cause Undetermined. Detector & Cabling Replaced ML20134P7391985-01-10010 January 1985 RO 85-1:on 850108,fuel Temp Recorder Indicated 600 F Instead of 720 F.Caused by Failure of Reactor Safety Sys Channel. Faulty Slide Wire & Contact Arm Replaced ML20134Q2081985-01-0808 January 1985 Ro:On 850108,fuel Temp Recorder Indicated 600 F Instead of 720 F After Reactor Power Returned to 1 MW Following Sample Positioning.Reactor Shut Down & Faulty Slide Wire & Contact Arm Replaced ML20090E1251984-07-0202 July 1984 RO-84-4:on 840626,reactor Operator Noted That Fuel Element Temp Recorder Did Not Correspond to Digital Indication as Shown on Doric Temp Readout.Cause Not Stated.Failure Spurious & Could Not Be Reproduced ML20090D7841984-06-26026 June 1984 Telecopy Ro:On 840626,fuel Elements Temp Recorder Failed to Respond Following Temporary Reduction in Reactor Power.Cause Not Stated ML20090E1241984-06-15015 June 1984 RO 84-3:on 840604,reactor Operator Observed That Safety Power Measuring Channel 2 Not Responding as Reactor Power Level Increased Beyond 30 Kw.Caused by Loose Safety Channel 2 Signal Cable.Connector Replaced ML20090E5141984-06-11011 June 1984 RO 84-2:on 840528,erratic Performance of Reactor Servo Control Not Noted in Log.Caused by Personnel Error.Operator Cautioned to Be More Observant While Taking Log Readings ML20134Q2511984-06-0505 June 1984 Ro:On 840604,during Startup,Reactor Shut Down When Channel 2 Not Indicating in Expected Power Range.Caused by Faulty Connector.Faulty Signal Cable Connector Replaced & Normal Operations Resumed ML20092N9211984-05-29029 May 1984 Ro:On 840528,operator Received Servo Fault Alarm & Linear Power Channel Indication Failed Low.Caused by High Voltage Supply for Linear Defector de-energized ML20084H6171984-04-0202 April 1984 Ro:On 840319,discovered That Performance of Weekly Electronic Maint Checks Not Performed During Previous Wk of Operation.Caused by Inadequate Procedural Controls ML20078P0111983-10-28028 October 1983 Ro:On 831004,high Power Scram Received During Initial Reactor Startup While Banking Shim Safety Control Rods After Reaching 1 MW Power.Caused by Operator Manipulation of Control Rods.Procedures & Proper Documentation Emphasized ML20070M8101983-01-11011 January 1983 Ro:On 830105,during Fuel Element Insp,Elements 7463 & 7486 Failed Go/No Go Test.Both Elements Had Been in Core Since 1973 & Not Inspected Since That Time.Both Elements Removed from Core ML20070N6471983-01-11011 January 1983 Ro:On 830110,fuel Temp Indication Failed to Respond During Reactor Startup.Caused by Shorted Thermocouple Wires in Terminal Box.Reactor Shut Down & Fuel Temp Instrument Connected to More Conservative Indication ML20072A8231982-12-22022 December 1982 Ro:On 821204,power Calorimetric Performed to Determine Agreement Between Indicated Power & Calculated Actual Power Based on Pool Heatup Rate.Results Showed Minus 30.7% Error. on 821206,calorimetric Showed Plus 56.6% Error ML20067C9721982-10-29029 October 1982 Ro:On 821019,power Level Indication Dropped Approx 15% on Both Safety Channels.On 821027,electromagnet Current for Shim Safety 2 Went to Zero.Causes Not Stated.Electromagnet Coil Replaced ML20066A5731982-10-0505 October 1982 Ro:On 820928,during Operation,Fuel Temp Thermocouple Failed. New Instrumented Fuel Element Installed.Thermocouple Readings Normal ML20066A2491982-09-29029 September 1982 Telecopy Ro:On 820928,erratic Readings Noted on Fuel Temp Indicator.Reactor Shut Down Immediately.On 820929,different If Connected to Fuel Temp Channel & Thermocouple Readings Recorded at 300 Watts & 1 MW ML20063H0731982-07-22022 July 1982 Ro:On 820722,during Initial Startup,Log Power Channel Rate Meter Failed to Respond.Cause Not Stated.Switch Contacts & Amplifier Boards Cleaned.Close Visual Insps Implemented ML20063H0301982-07-22022 July 1982 Telecopy Message of Ro:On 820722,during Initial & Secondary Reactor Startup,Log Power Channel Rate Meter Failed to Respond.Cleaning of Switch Contacts Returned Instrument to Normal Operation ML20126L4481981-04-15015 April 1981 Ro:On 810409 & 0414,during Prestartup Check of Facility, Interlock to Prevent Withdrawal of Shim Safety Control Rods for Low Source Levels Was Not Functioning.Caused by Defective Relay.Relay Replaced Prior to Reactor Operations 1998-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20205Q3481998-12-31031 December 1998 Tx A&M Univ Sys Tx Engineering Experiment Station Nuclear Science Ctr 1998 Annual Rept. with ML20151W2321998-09-0808 September 1998 Ro:On 980826,facility Bldg Air Monitor (Fam Channel 4) Failed Daily Fam Alarm Checks Prior to Reactor Operation. Caused by Failed Alarm Relay.Staff Is Preparing Formal Written Procedures for Testing Configurations for Fam Sys ML20217A0891998-03-18018 March 1998 Ro:On 980218,potential Reactor Safety Failure Discovered W/ Reactor Shutdown.Caused by Manual Scram Function Bypassed by Sticking Reset Contact in Console Power key-switch. Protective Action Reset Switches Wired ML20217K1401997-12-31031 December 1997 Tx A&M Univ Sys Tx Engineering Experiment Station Nuclear Science Ctr 1997 Annual Rept ML20199C5371997-11-11011 November 1997 Ro:On 971030,shim Safety Number 2 Was Found to Be Binding & Became Stuck in Withdrawn Position & Control Rod Failed to Scram.Caused by Incorrect Spacing Between Hold Down Foot & Bundle top-handle.Procedure SOP-II-I Modified ML20149F3901997-07-15015 July 1997 Safety Evaluation Supporting Amend 14 to License R-83 ML20137Y0351997-04-16016 April 1997 Rev 4 to Nuclear Science Center Senior Reactor Operator & Reactor Operator Requalification Program ML20137H0541996-12-31031 December 1996 Tx A&M Univ Sys Tx Engineering Experiment Station Nuclear Science Center 1996 Annual Rept ML20129H5191996-10-30030 October 1996 Ro:On 961015,loss of Facility Power Occurred Causing Reactor Scram Due to Lack of Attention to Detail & Excessive Distractions to Operations.Startup Checklist Had Several Individual Instrument Checks Combined Into Single Items ML20115G5511995-08-31031 August 1995 Engineering Analysis of a Power Upgrade for Tx A&M Nuclear Science Ctr Reactor ML20082D5521994-12-31031 December 1994 Thirty-First Annual Progress Rept of Tx A&M Univ Nuclear Science Ctr, for Period of 940101-1231 ML20069H4271993-12-31031 December 1993 Thirtieth Annual Progress Rept of Nuclear Science Ctr Tx Engineering Experiment Station Tx A&M Univ Sys College Station,Tx ML20059G0301993-10-26026 October 1993 Safety Evaluation Supporting Amend 13 to License R-83 ML20094N5431991-12-31031 December 1991 Nuclear Science Center 28th Annual Rept,CY91 ML20079C2481991-06-10010 June 1991 Ro:On 910607,reactor Operated for 30 Minutes at 1 MW W/O Facility Air Monitors in Operation.Operator Removed from Watch Standing Duties.Final Rept Will Be Forwarded Upon Completion ML20066H1401991-02-0808 February 1991 Special Rept 90-01:on 910125,during Annual Fuel Insp of Operational Core VIII-A,fuel Elements 6502 & 8468 Failed to Pass go-no-go Gauge Test for Excessive Transverse Bend. Elements Replaced W/Spare & Fuel Bundles Relocated ML20070R9351990-12-31031 December 1990 Twenty-Seventh Progress Rept of Texas A&M Univ Nuclear Science Ctr Jan-Dec 1990 ML20070U0201990-12-31031 December 1990 Twenty-Sixth Progress Rept of Texas A&M Univ Nuclear Science Ctr,1990 ML20043F4391990-06-0404 June 1990 Revised Page 1 to Reactor Operator & Senior Reactor Operator Requalification Program,Rev Iii.Item 2.1.6 Changed to Include Physical Security Plan ML20012E0661990-03-0909 March 1990 RO 90-01:on 900228,reactor Operator Received Servo Fault Alarm.After Directed Shutdown,Complete Loss of Linear Power Channel Noted.Caused by Corroded Connector at Detector Leads.Connector Replaced.Part 21 Related ML20248J1691988-12-31031 December 1988 Twenty-Fifth Progress Rept of Texas A&M Univ Nuclear Science Ctr,Jan-Dec 1988 ML20151Y9031988-07-15015 July 1988 Review of Texas A&M Univ Nuclear Science Ctr - Beam Port Experiment ML20151L6591988-03-23023 March 1988 Safety Evaluation Supporting Amend 11 to License R-83 ML20148M5691987-12-31031 December 1987 Twenty-Fourth Progress Rept of Texas A&M Univ Nuclear Science Ctr,1987 ML20205Q8241986-12-31031 December 1986 Twenty-Third Progress Rept of Texas A&M Univ,Nuclear Science Ctr for 1986 ML20203B0091986-07-10010 July 1986 Ro:On 860708,no Rod Down Indication Received for Transient Rod Until Carriage Driven In,During Performance of Manual Scram for Reactor Shutdown.Caused by Malfunction of Reactor Safety Sys Component.Repairs Underway ML20199B1171986-06-0404 June 1986 Ro:On 860501,improper Handling of Experiment Discovered Which Could Have Resulted in Serious Operational Event. Caused by Insertion of $1.09 Reactivity.Postulated Accidents & Results & Related Info Encl ML20205Q2921986-05-16016 May 1986 Final Ro:On 860501,unanticipated or Uncontrolled Change in Reactivity Greater than One Dollar Occurred.Caused by Removal of Rotisserie from Face Water Notch.Proposed Changes to SOPs Developed as Listed ML20205J9311986-02-18018 February 1986 RO 86-01:on 860204,temp Recorder Providing LSSS Signal to Scram on High Fuel Temp Malfunctioned.Caused by Defective Motor Bearing.Bearing Replaced & Recorder Calibr ML20199G0441985-12-31031 December 1985 Twenty-Second Progress Rept of Texas A&M Univ Nuclear Science Ctr,1985 ML20137Y6291985-09-24024 September 1985 RO-85-04:on 850912,transient Rod Followed Cylinder Out During Positioning of Transient Rod Cylinder.Air Solenoid for Transient Rod Sys Not Functioning as Designed.Air Solenoid Disassembled,Cleaned & Reassembled ML20127M4151985-05-0909 May 1985 Ro:On 850508,during Restart Following Power Failure,Facility Air Monitoring (Fam) Sys Inoperable for 15 Minutes.Caused by Turning Off High Voltage to Detectors.Procedures Revised to Verify Fam Sys After Power Failure ML20113D5681985-01-21021 January 1985 RO 85-2;on 850111,safety Channel 1 Detector Failed During Reactor Operation.Caused by Loose Connector Pin Making Intermittent Contact.New Connector Installed & Detector Verified Operable Prior to Reinstallation ML20134Q1961985-01-11011 January 1985 Ro:On 850111,reactor Shut Down When Safety Channel 1 Did Not Respond Following Annual Reactor Maint.Cause Undetermined. Detector & Cabling Replaced ML20134P7391985-01-10010 January 1985 RO 85-1:on 850108,fuel Temp Recorder Indicated 600 F Instead of 720 F.Caused by Failure of Reactor Safety Sys Channel. Faulty Slide Wire & Contact Arm Replaced ML20134Q2081985-01-0808 January 1985 Ro:On 850108,fuel Temp Recorder Indicated 600 F Instead of 720 F After Reactor Power Returned to 1 MW Following Sample Positioning.Reactor Shut Down & Faulty Slide Wire & Contact Arm Replaced ML20100C9651984-12-31031 December 1984 Twenty-First Progress Rept of Texas A&M Univ Nuclear Science Ctr,1984 ML20090E1251984-07-0202 July 1984 RO-84-4:on 840626,reactor Operator Noted That Fuel Element Temp Recorder Did Not Correspond to Digital Indication as Shown on Doric Temp Readout.Cause Not Stated.Failure Spurious & Could Not Be Reproduced ML20090D7841984-06-26026 June 1984 Telecopy Ro:On 840626,fuel Elements Temp Recorder Failed to Respond Following Temporary Reduction in Reactor Power.Cause Not Stated ML20090E1241984-06-15015 June 1984 RO 84-3:on 840604,reactor Operator Observed That Safety Power Measuring Channel 2 Not Responding as Reactor Power Level Increased Beyond 30 Kw.Caused by Loose Safety Channel 2 Signal Cable.Connector Replaced ML20090E5141984-06-11011 June 1984 RO 84-2:on 840528,erratic Performance of Reactor Servo Control Not Noted in Log.Caused by Personnel Error.Operator Cautioned to Be More Observant While Taking Log Readings ML20134Q2511984-06-0505 June 1984 Ro:On 840604,during Startup,Reactor Shut Down When Channel 2 Not Indicating in Expected Power Range.Caused by Faulty Connector.Faulty Signal Cable Connector Replaced & Normal Operations Resumed ML20092N9211984-05-29029 May 1984 Ro:On 840528,operator Received Servo Fault Alarm & Linear Power Channel Indication Failed Low.Caused by High Voltage Supply for Linear Defector de-energized ML20084H6171984-04-0202 April 1984 Ro:On 840319,discovered That Performance of Weekly Electronic Maint Checks Not Performed During Previous Wk of Operation.Caused by Inadequate Procedural Controls ML20087N3381983-12-31031 December 1983 Twentieth Progress Rept of Texas A&M Univ,Nuclear Science Ctr,1983 ML20078P0111983-10-28028 October 1983 Ro:On 831004,high Power Scram Received During Initial Reactor Startup While Banking Shim Safety Control Rods After Reaching 1 MW Power.Caused by Operator Manipulation of Control Rods.Procedures & Proper Documentation Emphasized ML20024E1251983-04-30030 April 1983 Nineteenth Progress Rept of Texas A&M Univ Nuclear Science Ctr for 1982. W/830516 Ltr ML20071H9171983-04-30030 April 1983 Nineteenth Progress Rept of Tx A&M Univ Nuclear Science Ctr 1982 ML20076F0281983-04-30030 April 1983 Nineteenth Progress Rept of Texas A&M Univ Nuclear Ctr, 1982 ML20028E6911983-01-11011 January 1983 Telecopy Ro:On 830110,during Reactor Startup,Fuel Temp Not Tracking Although Normal Temp Indication Displayed.Reactor Shut Down.Caused by Failed Fuel Thermocouple.Reactor Switched to Second Thermocouple 1998-09-08
[Table view] |
Text
a TEXAS ENGINEERING EXPERIMENT STATION 9$
THE TEXAS A&M UNIVERSITY SYSTEM
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COLLEGE STATION. TEXAS 77843-3575 1 !
2 July 1984 NUCLEAR SCIENCE CENTER 409/845-7551 Mr. E. Johnson Office of Inspection and Enforcement $@$$@ b' Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Driva, Suite 1000 M 10 m Arlington, Texas 76012 -
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Dear Mr. Johnson:
l I am forwarding the final report of the reportable occurrence of 26 June 1984. This report is being submitted in accordance with NSC Technical Speci-J fication requirements Section 6.6.2 of the Nuclear Science Center Reactor, License R-83, Texas A&M University.
Respectfully, S
BarryyWil its, Managerxa3 hit.
Reactor Operations BW/ym Enclosure 8407190300 840702 PDR ADOCK 05000128 S PDR CJ
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RESEARCH AND DEVELOPMENT FOR MANKIND i__
7.
Reportable Occurrence #84-4 Failure of Reactor Safety System
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Channel During Reactor Operation
! Reportable Occurrence-I- !0n.26 June 1984 at 1312 during normal reactor operation, the Reactor Operator noted that the Fuel Element Temperature recorder did not correspond to the
- digital indication as shown on the DORIC temperature readout. Reactor power t
had been returned to 950 kw at 1310 following a brief reduction in power E .to load an experiment. The digital temperature for the fuel element thermo-couple #2 indicated 694.4*F (approximately the same reading prior to the transient) yet the temperature recorder indicated approximately 565'F. The
-operator immediately informed the Senior Reactor Operator and Manager of
. Reactor Operations of tha apparent abnormality. The Fuel Element Temperature recorder is hard-wired to monitor thermocouple #2 of the operational Instru-i mented Fuel Element, and the digital instrument (D0RIC) can be selected to !
read thermocouple #1 or #2.- The digital thermocouple. instrument was selected to thermocouple #1 which indicated a temperature consistent with the digital reading of thermocouple #2. The operator observed proper response and indi-1 cation on all other reactor power level indication consistent with both digital thermocouple readings. A visual check of the temperature recorder showed i no apparent binding of the pen or drive mechanism, or any obvious cause for the improper response. At 1313.a reactor shutdown was commenced in accordance with S0P III-B, while closely monitoring the digital thermocouple instrument p and reactor power level instruments in addition to the Fuel Element Temperature
- recorder. All indication, with the exception of the fuel temperature recorder, responded normally. The recorder reading remained at the original indication of 565'F du' ring the shutdown.
4 Corrective Action i
Following the' shutdown, initial troubleshooting-of the recorder caused the pen movement to begin functioning correctly when a slight pressure was applied i to the'slidewire.potentiomet.er control cable.- It should also be 'noted that
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the chart recorder showed the instrument tracked the initial down power ma-neuver to load _the experiment. Then when reactor power was increased, the recorder trace showed a normal increase from approximately 450*F until it
-suddenly stopped at about 565'F. Subsequent troubleshooting failed to dupli-cate the problem, and an operational check of the recorder was performed ,
satisfactorily. :An additional check-of the; instrument consisting of the ~
applicable portion of the Prestartup Checklist,.was made to verify that the !
LSSS scram was functioning. NSC management concluded that the fuel element temperature recorder was functioning correctly and that the-failure was spu-rious and could not be reproduced, i
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A reactor startup was commenced while closely observing the temperature re-
. corder and the digital thermocouple indication. The recorder responded nor-mally, and at 1458 reactor power was stabilized at 950 kw. At this point normal reactor operation was resumed. Subsequent reactor operation has re-sulted in no recurrence of the temperature recorder failure, although the instrument is being closely monitored during reactor startups and power tran-sients. NSC management in review of the reportable occurrence has determined that the operators acted promptly and in accordance with approved S0P's.
The temperature recorder faile!re was a spurious occurrence and that at no point.during the incident was an operational power limit or safety limit exceeded.
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