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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20210Q8661999-08-12012 August 1999
Amends 36 to License R-38 & 45 to License R-67,respectively Approving Decommissioning Plan for Ga Triga Mark 1 & Mark F Research Reactors & Authorizing Approved Decommissioning Plan to Be Included as Suppl to Sar,Per 10CFR50.52(b)(5)
ML20154G9851998-10-0101 October 1998
Errata to Amend 44 to License R-67 Providing Signed Amend Replacing Criticality Safeguards Committee with Criticality Radiation Safety Committee & Decreases Frequency of Audits from Quarterly to Annually
ML20154B4731998-10-0101 October 1998
Amend 44 to License R-67,replacing Criticality Safeguards Committee with Criticality & Radiation Safety Committee, Decreasing Frequency of Audits from Quarterly to Annually & Changing Administrative Requirements Section of TSs
ML20212G4141997-10-29029 October 1997
Amend 35 to License R-38,removing Authority from License to Operate Reactor,Authorizing Possessing Only of Reactor & Changing TSs to Remove Operational Requirements Not Needed for Possession Only Status
ML20211P3291997-10-0909 October 1997
Amend 34 to License R-38,changing Requirement for Calibration of Power Measuring Channels to Require Calibrations Only If Reactor Could Achieve Criticality
ML20206J2791988-11-18018 November 1988
Amend 40 to License R-67,adding Requirements for Site Boundary Allowing Reactor Bldg Air Leakage & Verification Thereof & Installation,Availability & Surveillance of Operability of Reactor Room Activated Charcoal Filter Sys
ML20238A6621987-08-28028 August 1987
Amend 39 to License R-67,adding Triga Fuel Containing Max U Content of 30 Weight Percent W/Enrichment of Less than 20% to Category of Std Triga Fuel
ML20235E9811987-07-0606 July 1987
Amend 38 to License R-67,authorizing Increase in Irradiation Time for Fueled Incore Thermionic Direct Conversion Devices W/Irradiation Time Not to Exceed 40,000 H for Any One Incore Thermionic Direct Conversion Device
ML20209C4501987-04-10010 April 1987
Amend 27 to License R-38,changing License & Tech Specs to Include Max Reactivity Insertion Allowed in Pulsing Mode
ML20205A1791987-03-19019 March 1987
Amend 37 to License R-67,authorizing Increase in Number of Fueled in-core,thermionic,direct Conversion Devices Which May Be Irradiated Simultaneously from Two to Seven
ML20137X6341986-03-0505 March 1986
Amend 35 to License R-67,changing Tech Specs to Increase Irradiation Time of Fueled in-core Thermionic Direct Conversion Devices to 20,000 H
ML20140C3171986-03-0505 March 1986
Amend 36 to License R-67,revising Tech Spec Page 14 Re Irradiation Time Per Device
ML20133K3241985-10-17017 October 1985
Amend 35 to License R-67,authorizing Substitution of Temporary Radiation Detectors & Temporary Bypass of Certain Radiation Detector Scram Functions During Calibr & Maint on Permanent Detectors
ML20128L7881985-06-24024 June 1985
Amend 34 to License R-67,authorizing Performance of Calibr of Power Channels by Calorimetric or Heat Balance Methods Semiannually,But W/No Interval Greater than 7 1/2 Months
1999-08-12
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20210Q8661999-08-12012 August 1999
Amends 36 to License R-38 & 45 to License R-67,respectively Approving Decommissioning Plan for Ga Triga Mark 1 & Mark F Research Reactors & Authorizing Approved Decommissioning Plan to Be Included as Suppl to Sar,Per 10CFR50.52(b)(5)
ML20196C3491999-06-16016 June 1999
Application for Amend to License R-67,deleting License Conditions 3 & 4 Which Duplicate Requirements Now in Proposed TS
ML20196D3791999-06-15015 June 1999
Application for Amends to Licenses R-38 & R-67,to Revise Proposed TS & Request Deletion of License Condition 2.B.(2). Mark-up of Previously Submitted strike-out Version of TS Showing Latest Changes Made
ML20154G9851998-10-0101 October 1998
Errata to Amend 44 to License R-67 Providing Signed Amend Replacing Criticality Safeguards Committee with Criticality Radiation Safety Committee & Decreases Frequency of Audits from Quarterly to Annually
ML20154B4731998-10-0101 October 1998
Amend 44 to License R-67,replacing Criticality Safeguards Committee with Criticality & Radiation Safety Committee, Decreasing Frequency of Audits from Quarterly to Annually & Changing Administrative Requirements Section of TSs
ML20236Q5751998-07-16016 July 1998
Application for Amend to License R-67,revising Section 8.0 of Mark F Triga TS to Be Consistent W/Mark I Reactor TS
ML20212G4141997-10-29029 October 1997
Amend 35 to License R-38,removing Authority from License to Operate Reactor,Authorizing Possessing Only of Reactor & Changing TSs to Remove Operational Requirements Not Needed for Possession Only Status
ML20211P3291997-10-0909 October 1997
Amend 34 to License R-38,changing Requirement for Calibration of Power Measuring Channels to Require Calibrations Only If Reactor Could Achieve Criticality
ML20198H4501997-09-15015 September 1997
Application for Amend to License R-38,changing TS 5.2.5 to Read as Listed
ML20140D4921997-04-18018 April 1997
Application for Amends to Licenses R-38 & R-67,terminating Triga Reactor Operations at Main Site in San Diego,Ca & Requesting Possession Only License for Ga Mark I Reactor License.Decommissioning Plan Encl
ML20132F1971996-12-17017 December 1996
Application for Amend to License R-38,withdrawing Authorization to Operate Triga Mark I non-power Reactor
ML20059G2891994-01-0707 January 1994
Application for Amend to License R-38,revising Paragraph (a) of Section 9.4 of TS to Reflect Elimination of Position of Associate Physicist-in-Charge,as Result of Reduced Funding/ Utilization of Triga Reactors
ML20206J2791988-11-18018 November 1988
Amend 40 to License R-67,adding Requirements for Site Boundary Allowing Reactor Bldg Air Leakage & Verification Thereof & Installation,Availability & Surveillance of Operability of Reactor Room Activated Charcoal Filter Sys
ML20148H9901988-03-25025 March 1988
Application for Amends to Licenses R-38 & R-67,changing Name of Licensee.Fee Paid
ML20237D8251987-12-22022 December 1987
Application for Amend to License R-67,revising Tech Specs to Add Activated Charcoal Filter When Testing Thermionic Devices in Core Whenever Distance to Nearest Site Boundary Is Less than 350 Meters.Safety Analysis Encl.Fee Paid
ML20238A6621987-08-28028 August 1987
Amend 39 to License R-67,adding Triga Fuel Containing Max U Content of 30 Weight Percent W/Enrichment of Less than 20% to Category of Std Triga Fuel
ML20235E9811987-07-0606 July 1987
Amend 38 to License R-67,authorizing Increase in Irradiation Time for Fueled Incore Thermionic Direct Conversion Devices W/Irradiation Time Not to Exceed 40,000 H for Any One Incore Thermionic Direct Conversion Device
ML20210A3131987-04-30030 April 1987
Application for Amend to License R-67,revising Tech Specs to Extend Irradiation Time for Direct Conversion Devices to Beyond 20,000 H for Uninterrupted Continuation of DOE Research Program on Thermonic Devices.Safety Analysis Encl
ML20209C4501987-04-10010 April 1987
Amend 27 to License R-38,changing License & Tech Specs to Include Max Reactivity Insertion Allowed in Pulsing Mode
ML20205A1791987-03-19019 March 1987
Amend 37 to License R-67,authorizing Increase in Number of Fueled in-core,thermionic,direct Conversion Devices Which May Be Irradiated Simultaneously from Two to Seven
ML20212D3481987-02-26026 February 1987
Application for Amends to Licenses R-38 & R-67,eliminating Inconsistency Between Max Licensed Power & Testing of Power Scrams at 110% of Licensed Power
ML20213G6981986-11-14014 November 1986
Application for Amend to License R-67,revising Tech Spec Section 10.2.6 to Permit Simultaneous Irradiation of Up to Four Thermionic Devices.Fee Paid
ML20205Q1751986-05-20020 May 1986
Application for Amend to License R-67,defining Triga Low Enriched U Fuels as Std Fuel & Permitting Continued Tests Under Special Fuel Provisions for Fuel W/U Loadings in Range from 30% to 45% Weight
ML20140C3171986-03-0505 March 1986
Amend 36 to License R-67,revising Tech Spec Page 14 Re Irradiation Time Per Device
ML20137X6341986-03-0505 March 1986
Amend 35 to License R-67,changing Tech Specs to Increase Irradiation Time of Fueled in-core Thermionic Direct Conversion Devices to 20,000 H
ML20205J2511986-01-28028 January 1986
Resubmits Application for Amend to License R-67,changing Tech Spec Section 10.2.6 (D) to Allow Uninterrupted Continuation of Thermionic Experiment Now in Progress & to Extend Irradiation Time to 20,000 H
ML20137K4061985-11-26026 November 1985
Application for Amend to License R-67,changing Tech Specs to Allow Uninterrupted Continuation of Thermionic (Direct Conversion Device) Experiment in Progress.Fee Paid
ML20133K3241985-10-17017 October 1985
Amend 35 to License R-67,authorizing Substitution of Temporary Radiation Detectors & Temporary Bypass of Certain Radiation Detector Scram Functions During Calibr & Maint on Permanent Detectors
ML20132G8141985-09-24024 September 1985
Revised Application for Amend to License R-67,amending Tech Spec 10.2.6(f)(2) to Clarify Justification & Discussion in 850826 Application,Authorizing Routine Calibr or Maint of Radiation Monitors During Extended Operations
ML20134M4771985-08-26026 August 1985
Application for Amend to License R-67,changing Tech Specs Re Performance of Routine Calibr or Maint on Radiation Monitors,Including Continuous Air Monitor,During Extended Operations.Fee Paid
ML20134C5531985-08-12012 August 1985
Application for Amend to License R-67,revising Tech Specs to Authorize Performance of Routine Calibr or Maint on Radiation Monitors During Extended Operations.Fee Paid
ML20128L7881985-06-24024 June 1985
Amend 34 to License R-67,authorizing Performance of Calibr of Power Channels by Calorimetric or Heat Balance Methods Semiannually,But W/No Interval Greater than 7 1/2 Months
ML20129J4151985-06-0404 June 1985
Application to Amend License R-67,revising Tech Spec Section 6.2.5 to Perform Calibr of Power Channels by Calorimetric or Heat Balance Methods Semiannually.Fee Paid
ML20054L9171982-06-23023 June 1982
Application for Amend of Licenses R-38 & R-67 to Reflect Change of Ownership from Ga Co to Ga Technologies,Inc. One Oversize Preliminary Parcel Map Encl.Aperture Card Is Available in PDR
1999-08-12
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Text
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~' UNITED STATES NUCLEAR REGULATORY COMMISSION j ,j
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GA TECHNOLOGIES, INC.
DOCKET NO. 50-163 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. R-67
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendrent to Facility Operating License No R-67, filed by GA Technologies, Inc. (the licensee), dated June 4,1985, complies with the standards and reovirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's Regulations as set forth in 10 CFR Chapter I:
B. The facility will operate in conformity with the amended license, the provisions nf the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Cermission's regulations; D. The issuance of this amendnent will not be inimical to the common defense and security or to the health and safety of the public; E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirenents have been satisfied; and F. Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
- 2. Accordingly, the license is amended by changes to the technical specifications as indicated in the attachment to this license amendment, and paragraph P.C.2 of License No. R-67 is hereby amended to read as follows:
Technical Specifications The technical specifications contained in Appendix A, as revised through Amendment No. 34, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the technical specifications.
8507110459 850624 PDR ADOCK 05000163 p PDR
j 3. .This license arerdrent is effective as of its date of issuance.
4 FOR TPE NUCLEAR REGULATORY COMMISSION j C eo d==
- Cecil 0. TFrnas, Chief Standardication T. Special i Projects Branch Division of Licensirp
Attachment:
- Appendix A Technical
! Specifications Changes 4
Da'.c nf Issuance: June 24,1985 i
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ATTACHMENT TO LICENSE At1Ef:Dt'EP'T NO. 34 FACILITY OPERATING LICENSE NO. R-67
.D_O_CEET FT. 50 163 3 Revised Appendix A technical specifications are as follows:
Renove Page Add Page .
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r i Changes on the revised page are identified by marginal lines.
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(a) An area radiation monitoring syster renable of activating the evacuation elarm. During short periods of repair to this nonitorina system, reactor operations may continue while portable gamma-sensitive ion chanbers, having their own alarms, are in operation near the reactor.
(b) A continuous moni+cring system for airborne radioactivity having a readout and audible alarm which can be heard in both the reactor and control rooms.
(c) The monitoring systens in (a) erd (b) shall be calibrated anruelly and their set points verified weekly.
6.7.4 The reactor safety systems shall be verified to be opereF'c at least once each day the reactor is operated, unless the operation cy.terds cortinuously beyond one day, in which case the operability of the reactor safety system need only be verified prier to tho extended operation.
6.2.5 The reactor power measuring channels shall be calibrated by the calorimetric or heat balance nethod semiannually but at interva's net to exceed seven and one-half (7}) months.
6.3 Following maintenance or modification of the control or reactor safety systems, the af#ccted system shall be verified to be operable be#cre commencing reactor operation.
7.0 FilFL STORAGE 7.1 All fuel elements or fueled devices shall be stored in a safe geonetry (kgf, less thar 0.P under all conditions of moderation).
7.? Irradiated fuel elements and fueled experiments shall be stored in an array which will permit sufficient natural convection
- coolino by water or air such that the temperature of tha fuel element or fueled device will not exceed design values.
8.0 ADt!!NISTP/TIVF PEOUIREMENTS I
l 8.1 The facility shall be under the supervision of the Physicist-in Charge or his designated alternate, who shall be a licensed senior l operator of the facility. Fe shell be responsible to a Vice President whose duties irclude responsibility for research and development, or his designated alternate, for safe operation of the reactor and its associated equipment. The Criticality Safeouards Committee shall review and approve safety standards associated with operation and use of the facility. The Criticality Sefenuards Committee or a Subcomnittee thereof must audit reactor operations at least ouarterly.
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Anendment No. 3a
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