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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ML20199C5371997-11-11011 November 1997 Ro:On 971030,shim Safety Number 2 Was Found to Be Binding & Became Stuck in Withdrawn Position & Control Rod Failed to Scram.Caused by Incorrect Spacing Between Hold Down Foot & Bundle top-handle.Procedure SOP-II-I Modified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 ML20203G7871986-07-22022 July 1986 RO 86-03:on 860508,no Down Signal Received from Transient Rod During Manual Scram.Caused by Fine Grit in Air Cylinder Causing Friction & Preventing Full Insertion.Cylinder Cleaned & Lubricated & Air Filter Replaced 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 ML20070M7761982-12-20020 December 1982 Telecopy of Ro:On 821204,following Core Change,Power Calorimetric Indicated Power 30% Low.Detectors Adjusted. After Series of Addl Calorimeter Performances,Results Indicated Facility Could Operate in Excess of 35% Power 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 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 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 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 ML20149J9851997-07-22022 July 1997 SAR, Re License Renewal Application of Facility License R-23 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 ML20114D3811992-05-31031 May 1992 Annual Operating Rept of Tx A&M Univ AGN-201M Training Reactor for June 1991 - May 1992 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 ML20082Q1661991-05-31031 May 1991 Annual Operating Rept of Texas A&M Univ AGN-201M Training Reactor,June 1990-May 1991 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 ML20070U0201990-12-31031 December 1990 Twenty-Sixth Progress Rept of Texas A&M Univ Nuclear Science Ctr,1990 ML20070R9351990-12-31031 December 1990 Twenty-Seventh Progress Rept of Texas A&M Univ Nuclear Science Ctr Jan-Dec 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 ML20059D2751990-05-31031 May 1990 Annual Operating Rept of Texas A&M Univ AGN-201M Training Reactor,June 1989 - May 1990 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 ML20246D5291989-05-31031 May 1989 Annual Operating Rept of Texas A&M Univ AGN-201M Training Reactor for June 1988 - May 1989 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 ML20151M6241988-05-31031 May 1988 Annual Operating Rept of Texas A&M Univ AGN-201M Training Reactor, June 1987 - May 1988 ML20149J8731988-05-20020 May 1988 Requalification Program for Licensed Reactor Operators & Senior Reactor Operators Texas A&M Univ AGN-201M Reactor License R-23 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 ML20236K3491987-05-31031 May 1987 Annual Operating Rept of Texas A&M Univ AGN-201M Training Reactor,Nrc License R-23,June 1986 - May 1987 ML20236P2621987-05-31031 May 1987 Annual Operating Rept of Texas A&M Univ AGN-201M Training Reactor,Nrc License R-23,June 1986 - May 1987 ML20205Q8241986-12-31031 December 1986 Twenty-Third Progress Rept of Texas A&M Univ,Nuclear Science Ctr for 1986 ML20203G7871986-07-22022 July 1986 RO 86-03:on 860508,no Down Signal Received from Transient Rod During Manual Scram.Caused by Fine Grit in Air Cylinder Causing Friction & Preventing Full Insertion.Cylinder Cleaned & Lubricated & Air Filter Replaced 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 ML20206P5181986-05-31031 May 1986 Annual Operating Rept of Texas A&M Univ AGN-201M Training Reactor,June 1985 - May 1986 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 ML20129K1231985-05-31031 May 1985 Annual Operations Rept of Texas A&M Univ AGN-201M Training Reactor:Nrc License R-23,June 1984 - May 1985 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 1998-09-08
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, o TEXAS ENGINEEllING EXPEDIM ENT STATION THE TEXAS A&M UNIVERSITY SYSTEM COLLEGE STATION, TEXAS 77843-3575 #
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2 April 1984 NUCLEAR SCIENCE CENTER OIiB 60 409/845-7551 Ik N bY8% >
l i I Mr. E. Johnson Office of Inspection and Enforcement l'h id
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l Region IV U.S. Nuclear Regulatory Commission LU W 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 RE: Reportable Occurrence: Non-Compliance with NSCR Technical Specification Requirements in Conducting Confinement System Surveillance
Dear Mr. Johnson:
In accordance with the Nuclear Science Center (NSC) Technical Specification reporting requirements (section 6.6.2) for the reportable occurrence of 19 March 1984, I am submitting the final report dealing with this matter. You will note, as I dis-cussed in our telephone conversation of 22 March, that I did not include the pro-cedural non-compliance involving the Weekly Intrusion Checks in the report. This item is addressed in the NSC Security Plan and is scheduled and performed on a weekly basis in much the same manner as the Weekly Electronic Maintenance Checks.
It is the determination of the NSC staff that this does not constitute a reportable occurrence as the NSC provides physical protection of SNM in accordance with 10 CFR 73.67(f).
Sincerely,
/ 602fd Barry Willits, Manager Reactor Operations BW/ym i
cc: Dr. C. A. Erdman, liead, Nuclear Eng. Research, TEES Or. W. Arthur Porter, Director, TEES 8405080130 940402 DR ADOCK 0500 T. te
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RESEARCH AND DEVELOPMENr FOR MANKIND
1 Reportable Occurrence Non-Compliance With NSCR Technical Specification Requirements in Conducting Confinement System Surveillance i Reportable Occurrence On 19 March 1984 during preparations to conduct the Weekly Electronic Maintenance Checks (NSC Form 316) it was discovered that the performance of this surveillance was not accomplished during the previous week of operation. The performance of this check includes the weekly surveillance of the Nuclear Science Center Reactor (NSCR) confinement system ventilation. This surveillance is addressed in section i 4.4 of the NSC Technical Specifica^tions. The objective is to assure proper operation
! of the equipment necessary to achieve confinement. The surveillance is specified as being performed on a weekly basis and basically involves a check of the various automatic and manual modes of ventilation system shutdown, such that any release
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of radioactive airborne contamination would be controlled.
The timely completion of this surveillance is the responsibility of the Reactor Supervisor (normally day shift). The surveillance is routinely performed by the Reactor Operations support personnel of the electronics maintenance shop. During the operation week of 12 through 16 March 1984, this check was not performed, despite the fact that the NSCR was operated and normal business was conducted on just two
- days (12 through 13 March). This surveillance was performed satisfactorily during i the previous week on 9 March, and again performed satisfactorily on 20 March, once j it was verified that the check had not been performed the previous week.
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The NSC staff and management has determined that the failure to perform this sur-3 '
veillance does not constitute a safety question-or directly violate a limiting condition for operation. The report of this non-compliance with Technical Specifi-
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cations is being submitted as it involves an inadequacy in procedural controls j that could conceivably have developed into an unsafe condition. This report is
, submitted as specified in section 6.6.2 of the NSC Technical Specifications involving a reportable occurrence, as were the initial mailgram and telephone report, to the USNRC Region IV.
I Corrective Action The completion of a satisfactory surveillance check following the week of r;on-compliance is considered adequate by the NSC staff as initial correctlye action.
As a long term solution, the staff of the NSC feel that the performance of this surveillance should be made more visible as far as completion or non-completion 4 is concerned. A maintenance and surveillance master schedule or planning sheet
_ is to be developed and placed in a location where a review can be readily accom-4 plished by the Reactor Supervisor and Manager of Reactor Operations. Until such a schedule is developed and as a temporary measure, the Manager of Reactor Operations will review and sign the weekly check sheet upon completion by the assigned personnel.
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