ML19210E386

Submits Info Requested by P Erickson Telcon Re 790927 Request to Dismantle & Dispose of AGN-211P Reactor.Outlines Plans for Handling Irradiated Reactor Components & Storage of Source

ML19210E386
Person / Time
Site:	05000129
Issue date:	11/30/1979
From:	Blackshaw G WEST VIRGINIA UNIV., MORGANTOWN, WV
To:	Gammill W Office of Nuclear Reactor Regulation
References
NUDOCS 7912040449
Download: ML19210E386 (2)

Text

College of Engineering Morgantown. West Virginia 26506

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November 30, 1979 W

N West Virginia Mr. Winiam Gamaul University Accing Assistant Director for Operating Reactor Projects Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, DC 20555 Re: License R-58, Docket No. 50-129

Dear Mr. Gammill:

Mr. Peter Erickson from your Division recently called me to ask some specific questions regarding West Virginia University's September 27, 1979 request to dismantle and dispose of its AGN-211P (Serial No.103) Reactor. Presumably, these requests for additional information had come from members of your staff. The paraphrased questions and responses follow:

Question: What is your most sensitive radiation survey instrument?

Response: The University Radiation Safety office has informed me that a Model E-520 Eberline portable gamma probe Geiger counter (with readout) is sensitive to detecting radiation levels as low as 0.02 mR/hr. This is capable of discriminating true sources of low-level radiation from background and noise fluctuations.

Question: You did n t specifically mention contingencies for handling possibly irrcdiated reactor components (other than fuel elements). P -* Jo you plan to do?

Response: We have detected no discernible radiation from any of the components removed from the reactor with the excep-tion of the fuel elements, which was noted in the dismantling request. In particular, the glory hole guide tube, the control and safety rod blades, and the steel " blade guide channels" attached to four of the fuel elements show absolutely no evidence of being radioactive. These would have been located in regions of maximum neutron flux during periods of reactor operation. We see only background fluctuations on the E-520 meter. In brief, we expect no irradiated materials problems with which to contend.

1475 158 Equal Opportunity / Affirmative Action Employer 7 Ek

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Question: What do you intend to do about the Ra-Be neutron start-up source in the graphite reflector element which is presently stored in a 55-gallon water-filled plastic drum, which in turn is located inside the storage vault?

Response: This is unsatisfactory on a long-term basis. Our

.'.nitial reaction was to construct a 1" thick rectangular cross section lead " cover sleeve" for the source bearing element to attenuate the sof t gammas resulting from Ra decay; aid then imbed this sleeve in a 55-gallon steel drum filled v.'th paraffin. We now believe that this approach will be both t.me consuming and costly in terms of materials procurement and labor, and will still not result in a container which meets DOT and *1 shipping regulations.

We thus intend to immediately proceed to secure a DOT approved shipping container for the neutron source bearing element, and transfer the element from the water-filled drum to the shipping container within the confines of the storage vault. A portable electrically operated overhead crane can be set up in the vault to accomplish this. Maximum radiation exposure to any personnel involved in this element transfer will be 5 mrem.

This will be determined by a combination of pencil dosimeters and area survey monitors. Dr. G. L. Blackshaw will be both in charge of and the most active participant in the operation.

Once transfer to the shipping container is accomplished, the container will be stored in the vault until the decision has been reached to send the reactor fuel to Oak Ridge or to North Texas State University. (See Item 5 on page 1 and Justification on page 2 of the September 27, 1979 letter.)

Sincerely, G. Lansing Blackshaw Assistant Dean of Engineering Acting Reactor Director Copies to: Dr. Ray Koppelman Dr. Steve Slack 1475 159