ML20132D244

Safety Evaluation Supporting Order Terminating License R-121

ML20132D244
Person / Time
Site:	05000394
Issue date:	07/19/1985
From:	Office of Nuclear Reactor Regulation
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ML20132D190	List: ML20132D188 ML20132D216 ML20132D226 ML20132D244
References
NUDOCS 8507310254
Download: ML20132D244 (2)

Text

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• July 19, 1985 SAFETY EVALUATION BY THE OFFICE OF NllCLEAR REACTOR REGULATION SUPPORTING ORDER TERMINATING FACILITY LICENSE NO. R-121 CALIFORNIA POLYTECHNIC STATE UNIVERSITY AGN 201 TRAINING REACTOR DOCKET NO. 50-394 1.0 INTFDDUCTION By application dated January 30, 1985, California Polytechnic State University (the licensee) provided radiation measurements and analysis of the dismantled AGN 201 Training Reactor and requested that Facility License No. R-121 be terminated.

2.0 DISCUSSION AND EVALUATION The AGN 201 Reactor has been dismantled and disposed of in accordance with our dismantling Order dated October 6,1981 and with the licensees dismantling plan of April 30, 1981 as revised by letter dated September 8, 1981. All fuel has been removed and shipped to the U.S.

Department of Energy, Oak Ridge Operations, Oak Ridge, TN, for reprocessing.

All radioactive components and the Neutron Sources have been shipped to Richland, Washington to the U.S. Ecology, Inc., Radioactive Waste Disposal Facility.

Following completion of the dismantling operation the licensee performed an extensive radiation survey. The results of surface contamination and oamma level measurements were presented in the licensee's submittal of January 30, 1985. An inspection by the flRC, Region V (letter dated May 15, 1085) confirmed the licensee's surface contamination surveys and garuna level measurements at the dismantled AGN 201 reactor. The NRC Region V inspector also confirmed that the fuel, radioactive sources and radioactive components had been disposed of in accordance with the licensee's dismantling plan and NRC dismantling Order and recommended termination of License No. R-IPl. Contaminatinn surveys by the licensee and the NRC confirmed that fixed and removable contamination levels were vell below the leve; c specified in the licensee's dismantling plan and Regulatory Guide 1.86, and that there was no discernable gamma radiation above background.

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3.0 ENVIRONMENTAL CONSIDERATION

The Comnission has determined that this Order will not result in any significant environmental impact and that it does not constitute a maior Commission action significantly affecting the quality of the human environment. On the basis of the above, the Commission has determined not to prepare an Environmental Impact Statement in connection with the issuance of this termination Order.

4.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that the Facility Operating License R-121 should be terminated. We have further concluded that: (1) because the action does not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a margin of safety, the action does not involve a sionificent hazards consideration, (2) 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 (3) such activities have been conducted in compliance with the Commission's regulations and the issuance of this Order will not be inimical to the common defense and security or to the health and safety of the public.

5.0 ACKNOWLEDGEMENT This Safety Evaluation has been prepared by P. Erickson.

Dated: July 19, 1985 l