ML20137E987

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Safety Evaluation Supporting Order Terminating License R-111 for AGN-201 Reactor
ML20137E987
Person / Time
Site: 05000276
Issue date: 10/03/1985
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20137E959 List:
References
NUDOCS 8601170387
Download: ML20137E987 (2)


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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING ORDER TERMINATING FACILITY OPERATING LICENSE NO. R-111 GEORGIA INSTITUTE OF TECHNOLOGY AGN-201 REACTOR ,

DOCKET NO. 50-276 l

Introduction -

By application dated September 26, 1984, Georgia Institute of Technology (Georgia Tech) requested authorization to dismantle its AGN-201 training

reactor and dispose of the component parts and requested that Facility i Operating License No. R-111 be terminated. The application enclosed a dismantlement plan in support of the request.

Discussion and Evaluation The AGN-201 training reactor, serial No.104, was originally acquired by

. and licensed to the University of Akron in 1956. It was operated by that licensee until 1967, when it was deconmissioned and transferred to Georgia Institute of Technology. With the exception of the fuel and fueled components of the reactor, there was no significant radioactivity at the time that' Georgia Tech acquired it. The reactor is self-contained within its shield tank, and required no special construction, shielding, or utilities in order to be operable. An operating license to operate the reactor at a power -

level of 0.1 watt was issued to Georgia Tech in 1968. In the letter of September 26, 1584, the licensee estimated that the AGN reactor was operated 4

for a total accumulated thermal energy production of 68.4 watt-hours from the time of initial licensing in 1968. The total inventory of fission products in the fuel was estimated to be 0.03 microcuries per gram, or a total of '

30 microcuries. Almost all of these fission products are entrapped within the fuel. Estimates and measurements of neutron-induced radioactivity in the reactor components indicate no significant activity above natural background. The fuel, containing all reactor-associated radioactivity, is still on campus, but is now authorized and controlled by Facility Operating License No. R-97, so there is no potential radiological impact on the u.vironment resulting from the remaining non-fuel components. Also, because the remaining components are essentially portable, requiring no disturbance of the buildings or grounds to remove theim, there will be no significant environmental impact when they are eventtpily disposed of.

Thelicenseesubmittedareportwithan$sgust 15, 1985 letter that summarized the results of measurements of the radio Ngical condition of the component parts of the reactor and of the room in Qich they are located. Within the ,

statistical significance of the measuremepts, no reactor related radioactivity was detected. An inspector from the NRC Cegional Office in Atlanta inspected the Georgia Tech reactor site and perforr.!d independent radiation measurements, and examined licensee records. All of tN! above information was verified, and on October 16, 1985, the Regional Ofi?lce recoisnended that Facility Operating License No. R-111 be terminated.

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Environmental Consideration The Comission has determined that this action will not result in any significant environmental impact and that it does not constitute a major Comission action significantly affecting the quality of the human environment (Notice of Environmental Assessment and Finding of No Significant Impact for Order Terminating a Facility Operating License, dated December 23, 1985). On the basis of the above, the Comission has determined not to prepare an Environmental Impact Statement in connection with theissuance of an Order terminating the Operating License.

Conclusion The Comission has concluded, based on the considerations discussed above, that Facility Operating License No. R-111 should be tenninated. We have further concluded that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by termination of the facility license in the proposed manner, and (2) all activities have been conducted in compliance with the Comission's regulations and the issuance of a Tennination Order will not be inimical to the comon defense and security or the the health and safety of the public.

Principal Contributor: Robert E. Carter Dated: October 3, 1985 l

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