ML20062B305
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ML20062B305 | |
Person / Time | |
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Site: | General Atomics |
Issue date: | 09/15/1978 |
From: | Mowry W GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
To: | |
Shared Package | |
ML20062B302 | List: |
References | |
NUDOCS 7810270107 | |
Download: ML20062B305 (2) | |
Similar Documents at General Atomics | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20062D5401990-11-0505 November 1990
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARML20210Q9201999-08-12012 August 1999
[Table view]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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