|
|---|
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
[Table view] |
Text
.
UNITED STATES
^ #f %,,
8~ n NUCLEAR REGULATORY COMMISSION
' j . ,E WASHINGTON, D. C. 20555 g
t . . . . . .o GA TECHNOLOGIES, INC DOCKET NO. 50-163 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. R-67
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The application for amendment to Facility Operating License No. R-67, filed by GA Technologies, Inc. (the licensee), dated November 14, 1986, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements
, and the Comission's of the Atomic regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the amended license, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D. The issuance of this amendment 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 requirements 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).
8703270395 B70319 PDR ADOCK 05000163 P PDR
y
- 2. Accordingly, paragraph 2.C.I. of License No. P-67 is hereby amended tc read as follows:
- 1. Maximum Power Level GA Techrologies may operate the reactor at pcwer levels not in excess of 1500 kilowatts (thermal) and, in the _ pulsing mode, with reactivity insertions not to exceed 5.50$.
- 3. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2. of License No. R-67 is hereby amended to read as follows:
- 2. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 37, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
4 This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMPISSION erbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Attachment:
Appendix A Technical Specifications Changes Date of Issuance: March 19, 1987
4 ATTACHMENT TO LICEFSE AMENDMENT NO. 37
- FACILITY OPERATING LICENSE NO. R-67 DOCKET NO. 50-163 4
Revised Appendix A Technical Specifications are as follcws:
Remove Pages Add Pages 8 8 13 13 Changes on the revised pages are identified by marginal lines.
_..,m ,, _...,, _ , , _ , - _ _ , _.-__y ._v,_ , _ . - _. .. . , . , , _ _ , _ _ - _ . _ _
6+
~
8.2 The Criticality Safeguards' Committee shall be composed of not less than four qualified persons who are not directly involved in the TRIGA Reactor Program and who are selected by the Vice-
- President, or his designated alternate, identified in Section 8.1.
Overall qualifications of the members of the Criticality Safeguards Committee shall be at least equal to those in effect at.the time of issuance of these specifications.
8.3 The operations of the Criticality Safeguards Co=mittee shall be in accordance with a written charter, including provisions for:
(a) Meeting frequency (b) Voting rules (c) Quorums (d) Submission of mincrity reports (e) Hethod of submission and content of presenpacions,to the Com=ittee (f) Use of subcom=ittees (g) Review, approval and dissemination of cinutes.
S.4 Write == Instructions shall be in effact for:
(a) Testing and calibration of reactor operating instrumenta-tion and control, control rod drives, and area radiation
~
monitors and air particulate monitors.
(b) Reactor startup, routine operation cnd reactor shutdoun.
(c) Emergency and abnormal conditiens includin3 evacuation, reentry, and recovery.
(d) Fuel loading or unloading.
(e) Control rod removal or replacecent.
(f) lbintenance of the reactor, control rod drives and reactor safety and interlock-systems.
9.0 REACTOR OPERATIOMS 9.1 Maximum Operating Power Level 9.1.1 The operating power level of the reactor shall not be intentionall operations (ySpecification see raised above 9.2). 1500 kilowatts except for pulsing Amendment No. 28, 37 i
(
10.2.4 Fueled experiments which are not covered.elsewhere in these Technical Specifications, shall be controlled such that the. total inventory of iodine isotopes 131 through 135 in iesch experiment is no greatei chan 1.5' curies.
10.2.5 An-in-core electrically heated furnace may be used'in conjunction with the irradiati.on of caterials with the fellowing limitations:
(a) Experiments involving fissionable caterial:
(1) The total fissions produced during_ steady state 16 or transient operations shall not exceed 2 x 10 for =aterials containing fissionable caterial subjected to a burn-up of less than 1%, or 2 x 10 15 fissions for caterials containing fissionable cater.ials subjected to a burn-up of 1% or greater.
(2) Ihe helium purge from the furnace shali (1) vent through a liquid nitrogen cooled charcoal trap, and (ii)have a ra'te within the range of approxi=stely 0.2 and 10.0 liters per minute.
(3) The furnace tpaperature shall not exceed 20000C.
(4) Experi=ent safety systems to provide the following scrams shall be operable:
(i) internal furnace pressure less than 11 psig, and (ii) set' points 10% above and. below the operating current setting for the furnace.
(b) Experiments involving solely non-fissionable material:
(1) Experiment safety syste=s to provide the following scrams shall be operable:
(i) internal furnace pressure less than 11 psig, and (ii) set points 10% above and below the operating current setting for the furnace.
10.2.6 Direct conversion devices shall be irradiated only under the following conditions:
(a) The number of devices which may be irradiated simultaneously shall not exceed seven. f (b) The U-235 contained in an individual device shall not exceed 100 grams.
(c) The device shall be contained within a sealed primary containment which in turn is contained within a secondary containment which may have provisions for purging opera-tions. The static overpressure in secondary containment shall not exceed 1 psi.
Amendment No. JL 37