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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20062D5401990-11-0505 November 1990 Ro:On 901029,coupling Assembly Connecting Control Rod to Drive Mechanism Misaligned ML20248C6081989-08-0303 August 1989 Ro:On 890726,apparent Release of Fission Products from Fuel Element Occurred.Caused by Spent Fuel Element 6368.Fuel Element Removed from Core & Placed in Spent Fuel Storage ML20244A8531989-04-0606 April 1989 Ro:On 890330,anomaly Discovered at Top End of Rod Worth Curve.Caused by Missing Aluminum Spacer.All Spare Rod Mark F Drive Assemblies Being Checked to Ensure Presence of Aluminum Spacers ML20236T2221987-11-0606 November 1987 Ro:On 871030,deputy physicist-in-charge (DPIC) Bypassed Cylinder Down Limit Microswitch & Failed to Check Action of Interlock Sys When Checking Operation of Maintained Control Transient Rod.Maint Overhaul on Sys Ordered & DPIC Rebuked ML20206G1111987-04-0707 April 1987 Ro:On 870320,operator Incorrectly Lowered Pulse Rod Receiver to Reduce Core Excess Reactivity.Caused by Human Error.Matl Re Problem Will Be Introduced Into Requalification Training Course ML20207P8131987-01-0909 January 1987 Ro:On 870105,safety Rod Did Not Drop After Termination of Customer Irradiation & Reactor Scram.Mesh Screen Protecting Rod Barrel from Debris Discovered to Be Too Tight & Binding Rod.Control Rods Recalibr on 870108 ML20206A8641986-06-0505 June 1986 Ro:On 860527,after Reactor Startup Following 10-day Programmed Shutdown,Readings of Certain Thermionics Data Showed Slightly Higher Secondary Pressure than Desired. Fused Light Circuit Not Operating.Right Fuse Installed ML20137W5811986-02-13013 February 1986 Ro:On 860125,air Pump Which Circulates Air Through Particulate Filter in Continuous Air Monitor Found Not Functioning.Caused by Partially Inserted Power Cord Plug. Plug Inserted Properly & Pump Returned to Operation ML20140C4421986-01-21021 January 1986 Ro:On 851229,cell Top Monitor Exhibited Apparent Loss of Sensitivity During Startup.Electronic Count Rate/Power Supply Package (Eberline RM-14) Replaced ML20136F2511985-11-14014 November 1985 Ro:On 851030-1107,Channel K-3 Scram Level Set 9% Higher than Tech Spec Limit.Caused by Erroneous Entry in Log Book.Scram Setpoint for Channel Corrected ML20062B3051978-09-15015 September 1978 Ro:On 780831,while at Full Power,Control Rod Continued to Withdraw Even When Operator Not Depressing Up Control. Caused by Faulty Switch.Switch Replaced 1990-11-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20210Q9201999-08-12012 August 1999 Safety Evaluation Supporting Amends 36 & 45 to Licenses R-38 & R-67,respectively ML20206F4241999-04-27027 April 1999 Rev 2 to General Atomics Triga Reactor Facility Decommissioning Plan ML20195E6561998-12-31031 December 1998 Triga Mark I Reactor Annual Rept for CY98, Dtd Apr 1999 ML20203C4631998-10-16016 October 1998 Issue a to QAPD-9009-2, Triga Reactor Facility Decommissioning QA Program Document ML20154B4851998-10-0101 October 1998 Safety Evaluation Supporting Amend 44 to License R-67 ML20216G0671997-12-31031 December 1997 Triga Mark I Reactor Annual Rept CY97 ML20212G4201997-10-29029 October 1997 Safety Evaluation Supporting Amend 35 to License R-38 ML20211P3461997-10-0909 October 1997 Safety Evaluation Supporting Amend 34 to License R-38 ML20140D5091997-04-18018 April 1997 Rev 0 to General Atomics Triga Reactor Facility Decommissioning Plan ML20137U1541996-12-31031 December 1996 Triga Mark I Reactor Annual Rept for CY96 ML20134E6351996-06-10010 June 1996 Partially Deleted Commission Paper Re Financial Assurance for General Atomics Facilities ML20062D5401990-11-0505 November 1990 Ro:On 901029,coupling Assembly Connecting Control Rod to Drive Mechanism Misaligned ML20248C6081989-08-0303 August 1989 Ro:On 890726,apparent Release of Fission Products from Fuel Element Occurred.Caused by Spent Fuel Element 6368.Fuel Element Removed from Core & Placed in Spent Fuel Storage ML20244A8531989-04-0606 April 1989 Ro:On 890330,anomaly Discovered at Top End of Rod Worth Curve.Caused by Missing Aluminum Spacer.All Spare Rod Mark F Drive Assemblies Being Checked to Ensure Presence of Aluminum Spacers ML20235Q3751989-02-16016 February 1989 Triga Mark I Annual Rept for 1988 ML20235Q0941989-02-16016 February 1989 Triga Mark F Annual Rept for 1988 ML20055H0191988-12-31031 December 1988 Safety Evaluation Under 10CFR50.59 Microprocessor-Based Instrumentation & Control Sys for General Atomics Triga Mark I Reactor ML20206J2831988-11-18018 November 1988 Safety Evaluation Supporting Amend 40 to License R-67 ML20147A7681988-02-23023 February 1988 Annual Operating Rept for 1987 ML20149N1131988-02-22022 February 1988 Annual Operating Rept for 1987 ML20236T2221987-11-0606 November 1987 Ro:On 871030,deputy physicist-in-charge (DPIC) Bypassed Cylinder Down Limit Microswitch & Failed to Check Action of Interlock Sys When Checking Operation of Maintained Control Transient Rod.Maint Overhaul on Sys Ordered & DPIC Rebuked ML20237G6961987-08-31031 August 1987 Safety Evaluation Report on HIGH-URANIUM Content, LOW-ENRICHED URANIUM-ZIRCONIUM Hydride Fuels for Triga Reactors.Docket No. 50-163.(GA Technologies,Incorporated) ML20235E9981987-07-0606 July 1987 Safety Evaluation Supporting Amend 38 to License R-67 ML20209C4681987-04-10010 April 1987 Safety Evaluation Supporting Amend 27 to License R-38 ML20206G1111987-04-0707 April 1987 Ro:On 870320,operator Incorrectly Lowered Pulse Rod Receiver to Reduce Core Excess Reactivity.Caused by Human Error.Matl Re Problem Will Be Introduced Into Requalification Training Course ML20205A1931987-03-19019 March 1987 Safety Evaluation Supporting Amend 37 to License R-67 ML20212C3341987-02-25025 February 1987 Annual Operating Rept for 1986 ML20207P8131987-01-0909 January 1987 Ro:On 870105,safety Rod Did Not Drop After Termination of Customer Irradiation & Reactor Scram.Mesh Screen Protecting Rod Barrel from Debris Discovered to Be Too Tight & Binding Rod.Control Rods Recalibr on 870108 ML20205Q2101986-09-15015 September 1986 Speech Entitled, Current Status of U Zirconium-Hydride Low Enriched U Fuel Design & Development, Presented at Seventh European Triga Users Conference on 820915-17 in Istanbul, Turkey ML20203F9581986-07-31031 July 1986 Revised Decommissioning Plan ML20206A8641986-06-0505 June 1986 Ro:On 860527,after Reactor Startup Following 10-day Programmed Shutdown,Readings of Certain Thermionics Data Showed Slightly Higher Secondary Pressure than Desired. Fused Light Circuit Not Operating.Right Fuse Installed ML20154B3351986-02-27027 February 1986 Annual Operating Rept for 1985,discussing Operating Experience,Changes in Design,Performance Characteristics & Procedures,Fuel,Control Rod,Pulsing Sys & Reactor Safety Surveillances & Continuous Air Monitor ML20154B4651986-02-27027 February 1986 Annual Operating Rept for 1985 ML20212C2901986-02-25025 February 1986 Annual Operating Rept for 1986 ML20140C3331986-02-20020 February 1986 Safety Evaluation Supporting Amend 36 to License R-67 ML20137X7081986-02-20020 February 1986 Safety Evaluation Supporting Amend 35 to License R-67 ML20137W5811986-02-13013 February 1986 Ro:On 860125,air Pump Which Circulates Air Through Particulate Filter in Continuous Air Monitor Found Not Functioning.Caused by Partially Inserted Power Cord Plug. Plug Inserted Properly & Pump Returned to Operation ML20140C4421986-01-21021 January 1986 Ro:On 851229,cell Top Monitor Exhibited Apparent Loss of Sensitivity During Startup.Electronic Count Rate/Power Supply Package (Eberline RM-14) Replaced ML20136F2511985-11-14014 November 1985 Ro:On 851030-1107,Channel K-3 Scram Level Set 9% Higher than Tech Spec Limit.Caused by Erroneous Entry in Log Book.Scram Setpoint for Channel Corrected ML20133K3261985-10-17017 October 1985 Safety Evaluation Supporting Amend 35 to License R-67 ML20205Q2191985-10-14014 October 1985 Speech Entitled, Final Results of Qualification Testing of Triga Fuel in Oak Ridge Research Reactor Including Post- Irradiation Exam, Presented at 851014-16 Meeting in Petten,The Netherlands ML20128L8261985-06-13013 June 1985 Safety Evaluation Supporting Amend 34 to License R-67 ML20054L9301982-02-25025 February 1982 Annual Financial Rept 1981 ML20062B3051978-09-15015 September 1978 Ro:On 780831,while at Full Power,Control Rod Continued to Withdraw Even When Operator Not Depressing Up Control. Caused by Faulty Switch.Switch Replaced 1999-08-12
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- GATechnologies 7 am
- l l G A Technologies Inc.
PO. BOX 85600 l SAN DIEGO. CAUFORNIA 92138 l (619) 455-3000 November 6, 1987 38-1143 Mr. Harold R. Denton, Director Office of Ibclear Reactor Regulation U.S. !belear Regulatory Cmmission Washington, D.C. 20555 Reference Docket No. 50-89/163: Reactor Facility License No. R Reportable Occurrence
Dear Mr. Denton:
On Monday, November 2,1987, the NRC Office of Region V was notified by telephcne of a reportable occurrence concerning the GA Technologies Inc. (GA) Mark I TRIGA reactor '.R-38) . Details of the occurrence were presented at that time. This written report is being subnitted within 10 days as required by the applicable Technical Specifications. 'Ihe details of the occurrence are presented below.
Secuence of Events gy On Friday, October 20, 1987, following cmpletion of the required daily start-up checks, a senior operator started to conduct a series of runs for reactor custmers. When he attempted to start the first of these runs at about 0820, he fota.3 it impossible to maintain air pressure on the transient rod piston. As a consequence, he could not withdraw the central transient rod (CTR) to its full out position, which is the first step in starting up the reactor. He sought the help of the Deputy Physicist-in-Charge (DPIC) who then initiated a series of microswitch adjustments to attempt to correct the situation. ,
when this proved unsuccessful, the DPIC reasoned that he could bypass the C'IR Air Limit microswitch without interfering with the license required interlocks. After making the temporary bypass, he and the senior operator at the cmsole performed checks to assure that the safety system was still functional. Having satisfied himself that the maintenance was adequate, the DPIC made a proper entry in the Maintenance Log Book and declared the reactor operational.
Subsequently, six steady-state runs and one pulsed operation were conducted during the reainder of the day (until about 1325) and then the reactor was shutdown.
At 2200 on the same day (October 30, 1987) another senior reactor operator was performing the routine weekly checkout of the reactor system when he discovered that air could be applied to the transient py .I D
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rod regardless of the position of its cylinder. This is in violation of the interlock requirement set forth in the Technical Specifications in Table II, Item 3 which states that in steady state this interlock will prevent the a); plication of air to the transient rod unless its mweable' cylinder is fully down. He promptly notified the facility management and received instruction to reove the temporary bypass installed earlier that day by the DPIC and secure the reactor until the following Monday morning.
Discussion We reportable occurrence arose because of two errors on the part of the DPIC. First he mistook the Cylinder.DOWN LIMIT microswitch (which is in the interlock circuit) for the Cm AIR LIMIT microswitch which is not part of the interlock circuit. When the Cylinder DONN LIMIT microswitch was bypassed, air could be applied to the transient rod with the cylinder in any position. % e second error by the DPIC was ,
the failure to check this specific action of the interlock system when he was checking the operation of the maintained control transient rod.
It is very important to note that the method of operation at the TRIGA Facility is such that no safety issues were raised by the bypass of the. cylinder DOWN LIMIT microswitch. This is because the first action of every start-up in steady state is to withdraw fully the transient rod while all other control rods are full down. An experienced Senior Reactor Operator conducted all the runs on the day in question and did in fact follow this procedure. We only deviation fran this procedure was that for the one pulsed operation on October 30. In this operation, it was of course the intent to apply air to the transient rod cylinder and fully withdraw the rod when the reactor was critical at low power (< 1 kw) .
Agtion Taken (1) On Monday, November 2,1987, the Facility management ordered a complete maintenance overhaul of the transient control rod drive system. This included acticns that were planned for the routine annual inspection that occurs in December each year. m is year, those activities will be conducted a month early. We drive systen will be overhauled on the shop bench with all worn or damaged microswitches to be replaced. When all maintenance work has been completed and the drive assenbly has been reinstalled, a complete check of all related safety functions will be conducted as per section 5.3 of the Technical Specifications.
(2) Since the safety checks conducted by, or under the supervision of, the DPIC were inconglete as per Section 5.3, he has been seriously rebuked. After consi& rable discussion, more serious disciplinary action was deemed unnecessary because the DPIC is a very senior and experienced reactor operator with nearly twenty years of experience
rc lj [, s e
at this facility.
His - duty is to maintain .and. ' repair most
. whanical and electrical items and to fabricate:and install most
= new experiments conducted on the reactors. All of' his past performance has demonstrated a careful regard for all aspects of I .
safety. In this light, we- judge' our corrective action to, be'
!< proper.-
If you should have questions on the above reportable occurrence,
' please' contact me at' (619) 455-2823 or Dr. W. Whittemore at the 'IRIGA Facility, (619) -455-3277.
Very truly yours, M c=W Keith E..Asmussen,. Manager i: Licensing, Safety and Nuclear Compliance
- hDf/bb
- oc: Mr. John B. Martin, NRC, Region V
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