ML20207E331

Forwards Request for Addl Info Re 860520 Application as Supplemented on 860520 for Amend to License R-67.Response Requested within 30 Days of Ltr Date

ML20207E331
Person / Time
Site:	General Atomics
Issue date:	12/23/1986
From:	Rozier Carter Office of Nuclear Reactor Regulation
To:	Asmussen K GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
References
NUDOCS 8701020142
Download: ML20207E331 (4)

Text

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D:cemb:r 23, 1986 Docket No. 50-163 Mr. Keith E. Asmussen, Manager Licensing, Safety, and Nuclear Compliance GA Technologies. Inc.

P. O. Box 85608 San Diego, California 92138

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - GA TECHNOLOGIES, INC.

In our review of documentation that has been submitted in support of your application for amendment of the operating license of your research reactor facility, dated May 20, 1986, as supplemented on September 5, 1986, some questions have arisen for which we require answers. Please prr, vide written responses to the enclosed questions no later than 30 days from the date of this letter. Following receipt of this infonnation we will continue our review.

If you have any questions concerning this request, please contact me (301) 492-8206.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, original signed by Robert E. Carter, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page DISTRIBUTION:

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• q% , , , , , #p December 23, 1986 Docket No. 50-163 Mr. Keith E. Asmussen, Manager Licensing, Safety, and Nuclear Compliance GA Technologies, Inc.

P. O. Box 85608 San Diego, California 92138

SUBJECT:

REQUE5T FOR ADDITIONAL INFORMATION - GA TECHNOLOGIES, INC.

In our review of documentation that has been submitted in support of your application for amendment of the operating license of your research reactor facility, dated May 20, 1986, as supplemented on September 5, 1986, some questions have arisen for which we require answers. Please provide written responses to the enclosed questions no later than 30 days from the date of this letter. Following receipt of this information we will continue our review.

If you have any questions concerning this request, please contact me at (301) 492-8206.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OM8 clearance is not required under P.L.96-511.

Sincerely, Robert E. Carter, Project Manager Standardization and Special Projects Directorate Olvision of PWR Licensing-B Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page

se .

GA Technologies, Inc. Docket No. 50-163 e

cc: Attorney General 555 Capitol Mall Sacramento, California 95814 California Department of Health ATTN: Chief. Environmental Radiation Control Unit Radiologic Health Section 714 P Street, Room 498 Sacramento, California 95814 Director Energy Facilities Siting Division Energy Resources Conservation &

Development Commission 1516 - 9th Street Sacramento, California 95814

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Enclosure a

GA Technologies, Inc.

Docket No. 50-163 LEU TRIGA Fuel Request For Additional Information *

1. With the increased uranium loading in 20, 30 and 45 weight-percent LEU fuel, there might be an enhanced potential for formation of eutectic reactions between the uranium and components of the cladding, such as fron and nickel. Please discuss further any evidence of such reactions in your fuel tests, the potential for such reactions under accident conditions that could lead to high fuel and cladding temperatures, and the potential consequences to integrity of fuel cladding.

2. As fuel burn-up increases, changes in morphology, such as porosity distribution, might change parameters in the fission product diffusion process. With sufficiently large quantities of fission products escaping into the fuel-clad gap, internal gas pressures at high temperature might add significantly to the hydrogen-only pressure. Please discuss your measurements related to gaseous fission product escape from the fuel meat both during extensive burn-up and while the fuel is hot as a result of a transient, and implications for integrity of cladding at the usually accepted safety limit of 1150'C. Do the gamma scan burn-up results of fuel rod Number 1086 have any bearing on this issue?

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