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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210Q9201999-08-12012 August 1999 Safety Evaluation Supporting Amends 36 & 45 to Licenses R-38 & R-67,respectively ML20154B4851998-10-0101 October 1998 Safety Evaluation Supporting Amend 44 to License R-67 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 ML20206J2831988-11-18018 November 1988 Safety Evaluation Supporting Amend 40 to License R-67 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 ML20205A1931987-03-19019 March 1987 Safety Evaluation Supporting Amend 37 to License R-67 ML20137X7081986-02-20020 February 1986 Safety Evaluation Supporting Amend 35 to License R-67 ML20140C3331986-02-20020 February 1986 Safety Evaluation Supporting Amend 36 to License R-67 ML20133K3261985-10-17017 October 1985 Safety Evaluation Supporting Amend 35 to License R-67 ML20128L8261985-06-13013 June 1985 Safety Evaluation Supporting Amend 34 to License R-67 1999-08-12
[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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SAFETY E9LUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 35 TO FACILITY OPERATING LICENSE NO. R-67 GA TECHNOLOGIES, INC.
DOCKET NO. 50-163
- 1. Introduction In a letter from GA Technologies, Inc. (GA), dated January 28, 1986, GA requested a change in the Technical Specifications of Operating License No. R-67 for their TRIGA Mark F non-power reactor. This change relates to the use of fueled in-core thermionic direct conversion experimental devices. .The requested change would increase the authorized irradiation time of such devices from a maximum of 10,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> to a maximum of 20,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. A similar change had been previously reviewed and approved in the Technical Specifications for a similar GA TRIGA reactor, Docket No. 50-227, which has been decommissioned.
!!. Background GA initially designed and remains the sole vendor for the TRIGA family of non-power research reactors. In addition, they have installed several such reactors and operated them in their facilities under Nuclear Regulatory Comission operating licenses.
One of these, a Mark !!!, was devoted primarily to tests of thermionic direct conversion devices for the production of electricity for specialized purposes. That Mark !!! was operated under Operating License No. R-100. Docket No. 50-227, from approximately 1966 to 1973, when it was decommissioned. In recent l
years, the continued development of these direct conversion devices has been resumed, using a very similar Mark F reactor, which has i been in operation since the early 1960s. During the years of experimentation on the direct conversion devices, there have been no significant malfunctions or deviations from their predicted l operations that raised unreviewed safety questions.
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. III. Requested Change and Evaluation The specific change requested by the licensee is to section 10.2.6(d) of the Technical Specifications, as follows:
The irradiation time for any one device shall not exceed 20,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
The current section 10.2.6(d) limits the maximum irradiation time to 10,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. In justifying this request, the licensee pointed out that other Technical Specification limitations on the operation and monitoring of the thermionic devices would remain in effect, and referred to the License Conditions of the previous Mark III license R-100. The staff has reviewed the safety analyses and the related safety evaluations for that facility. Amon the safety report (GA 9622, December, 1970)g other considerations, analyzes potential accidents that might involve the thermionic devices. In the licensee's analyses related to the duration of irradiation and the consequent inventory of fission products in such a device, it was assumed that operation would be for 20,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. None of the assumed accident scenarios would have lead to radiological exposures in unrestricted areas that exceeded 10 CFR 20 values. On the basis of the staff's safety evalua-tion for the Mark III reactor it was found that operation for 20,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> was acceptable, and that reactor's license authorized such operation. The staff's review for the current amendment request indicates that all relevant operating conditions of the Mark F and Mark III reactors and the thermionic devices are sufficiently similar so that we reaffirm the previous conclusion that operation of the devices for 20,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> does not present an unacceptable risk to the health and safety of the public.
IV. Environmental Considerations This amendment involves changes in the installation or use of facility.
components located within the restricted area, as defined in 10 CFR Part 20, and changes in inspection and surveillance requirements. The staff has determined that: (1) the amendment involves no significant hazards consideration (as discussed below), (2) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite, and (3) there is no significant increase in individual or cumulative occupational radiation exposure.
Accordingly, this amendment categorical exclusion set forth meets the eligibility) in 10 CFR 51.22(c (9). criteria for to Pursuant 10 CFR 51.22(b), no environmental impact statement or enviror. mental assessment need be prepared in connection with the issuance of this amendment.
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. V. Conclusion The staff has concluded, based on the considerations discussed above, that: .(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously evaluated; or create the possibility of a new or different kind of accident from any accident.previously evaluated; or involve a significant reduction in a margin of safety, this amendment involves no significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed activities, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or the the health and safety of the public.
Dated: February 20, 1986 Principal Contributor: Robert E. Carter c
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