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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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3 st,# Kf G UNITED STATES
. [ g NUCLEAR REGULATORY COMMISSION I 5 .[ WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 27 TO FACILITY OPERATING LICENSE NO. R-38 GA TECHNOLOGIES, INC.
DOCKET NO. 50-89
1.0 INTRODUCTION
In' a letter dated February 26, 1987, GA Technologies, Inc. (GA) requested a change to Facility Operating License No. R-38 and to the Technical Specifications Appendix A. To make the license condition more complete, Paragraph 2.C.(1) was amended to add the maximum reactivity insertion
- allowed in the pulse mode. This limit has always existed but was not stated explicitly in Paragraph 2.C.(1). Also, a change to Technical Specification 7.1 was made to eliminate an inconsistency between the license condition for the maximum power level at which the reactor may
{ operate ard the Technical Specification for the maximum operating power i
level and testing of the reactor over-power trip setpoint. This action follows similar changes that were made to GA's other TRIGA research reactor, a Mark F (Docket 50-163, Amendment 37).
2.0 EVALUATION 2.1 Addition of the Maximum Reactivity insertion Limit to the Operating License The purpose of this change is to bririg the Facility Operating License into conformity with current practice by stating in the body of the
- license both the maximum themal power level and the maximum reactivity l insertion pemitted in pulsing mode. The maximum reactivity insertion limit was previously stated only in the Technical Specifications. This I change is editorial in nature and does not modify any actual license conditions.
2.2 Inconsistency in Maximum Thermal Power Level Between the Facility Oper6 ting
} License and the Technical Specifications, Appendix A Technical Specification 7.1 -viously permitted steady-state thermal i
power to reach a maximum c' ' for purposes of testing the full power j scram safety circuits. T' .nconsistent with the license condition-that limited power to 250 kw. sesting of these safety circuits can be accomplished by other methods. GA. tests these safety circuits by the i
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!s introduction of an electrical signal. To achieve consistency, the _
maximum operating power level under any conditions will be restated in the Technical Specifications to be 250 kW. This does not constitute a change in the authorized licensed power limit.
3.0 ENVIRONMENTAL CONSIDERATION
We have determined that these changes are in the category of recordkeeping,
- reporting, and administrative procedures and requirements. Accordingly, ,
this amendment meets the eli set forth.in 10 CFR 51.22(c)gibility (10). Pursuant criteriatofor10categorical exclusion CFR 51.22(b), no Environmental Impact Statement or Environmental Assessment need be prepared in connection with the issuance of this amendment.
4.0 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, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that' the health and safety of the public will ?pt be endangered by the
- proposed activities, and (3) such act'ivities will be conducted in i compliance with the Commission's regulations and the issuance of this t amendment will not be inimical to the connon defense and security or the health and safety of the public.
Principal Contributor: Alexander Adams, Jr.
Da ted: April 10, 1987 -
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