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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 GA Technologies Inc.
PO. BOX 85608 SAN DIEGO. CAUFORNIA 92138 (619) 455-3000
! April 7, 1987 38-1055 Mr. Harold R. Denton Director Office of Mclear Reactor Regulation U.S. E clear Regulatory Commission j Washington, D.C. 20555
Reference:
Docket No. 50-89/163; License No. R-38
Dear Mr. Denton:
! On Monday, April 6,1987, the NRC Office of Region V was notified by telephrne of a reportable occurrence concerning the GA Technologies Inc. (CA) Mark I 'IRIGA reactor (R-38) . Details of the occurrence were presented at that time. Bis written report is being subnitted within j 10 days as required by the applicable Technical Specifications. %e details of the occurrence are presented below.
i on March 20,1987, at 1438, a senior reactor operator set up and
- performed a pulse on GA's Mark I TRIGA reactor for a visiting tour group. In filling out the usual pulse stang data record, the operator discovered that the core excess reactivity was measured to be $3.33 which is above the $3.25 license limit set forth for pulsing in Section 7.2(b) of the Technical Specification. In an attempt to lower
. the core excess reactivity, the operator lowered the receiver for the pulse rod (thus reducing the length of the stroke of the pulse rod).
q Wis had the effect of reducing what would have been a $2.64 pulse to j a $2.54 pulse for the pulse actually performed, but left the core j excess reactivity at the original $3.33. The operator was under the impression that his action had reduced the core excess reactivity.
%e correct procedure for the operator would have been to secure the reactor prior to the pulse, remove one of the outer-most fuel elements and store it, and reneasure the core excess to assure that it was then less than $3.25.
On April 3, a senior staff member was reviewing the operations conducted during the previous few days when he discovered the above incorrect operation. Bis event was reported to Region V during the next working day.
It may be noted that the fundamental method to limit the size of the pulse is to assure that the transient rod is limited, as in this case l of the R-38 reactor, to no more than $3.00. For many years the 8704140453 87o4o7
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transient rod in this reactor has been worth about $2.75 or less. Now it is worth only about $2.65. Consequently, we cannot under any circumstances perform a pulse that now exceeds $2.65. 'Ihe requirement that the core excess not exceed $3.25 during pulsing operation is an additional safety requirement, but does not alter the fact that the pulse size is limited by the reactivity worth of the transient rod.
For carpleteness, the recorded pulse (No.11,097) produced a peak power of 695 m, the released energy was 15.8 Mf-sec, and the ==vi==
fuel tenperature was 4100C. All of these values are consistent for the $2.54 pulse.
As a corrective measure, the facility management will introduce material specific to the above problem into the requalification operator training course. In addition, a memorandtsu has been issued to all facility reactor operators calling attention to the above error in operator procedure.
If you have any questions concerning the above, you may call me at (619) 455-2823 or Dr. W. Whittemore at (619) 455-3277.
Very truly yours, Keith E. Asmussen, Manager Licensing, Safety and Nuclear Compliance KEA/mk cc: Mr. John B. Martin, NRC Region V
e transient rod in this reactor has been worth about $2.75 or less. Now it is worth only about $2.65. Consequently, we cannot under any circumstances perform a pulse that now exceeds $2.65. '1he requirement that the core excess not exceed $3.25 during pulsing operation is an additional safety requirenent, but does not alter the fact that the pulse size is limited by the reactivity worth of the transient rod.
For ccmipleteness, the recorded pulse (No.11,097) produced a peak I power of 695 m, the released energy was 15.8 Mf-sec, and the maximum fuel temperature was 4100C. All of these values are consistent for the $2.54 pulse, g As a corrective measure, the facility management will introduce material specific to the above problem into the requalification operator training course. In addition, a memorandum has been issued to all facility reactor operators calling attention to the above error in operator procedure.
If you have any questions concerning the above, you may call me at (619) 455-2823 or Dr. W. Whittemore at (619) 455-3277.
Very truly yours, Keith E. Asmussen, Manager Licensing, Safety and Nuclear Ccunpliance KEA/mk cc: Mr. John B. Martin, NRC Region V