ML20198M909

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SER Supporting Processing of TVA Lead Test Assembly
ML20198M909
Person / Time
Site: Framatome ANP Richland
Issue date: 12/23/1998
From: Emeigh C
NRC
To:
Shared Package
ML20198M894 List:
References
NUDOCS 9901050400
Download: ML20198M909 (2)


Text

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pocreo e-4 UNITED STATES g

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't WASHINGTON, D.C. 20555-0001

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December 23, 1998 DOCKET:

70-1257 LICENSEE:

Siemens Power Corporation (SPC)

Richland, Washington

SUBJECT:

SAFETY EVALUATION REPORT: PROCESSING TVA LEAD TEST ASSEMBLY FUEL EACKGROUND By letters dated November 13 and Dccamber 15,1998, the licensee requested an amendment to Materials License SNM-1227 to process fuel that has a higher transuranic activity limit than the current license allows. This feedstock is for the Tennessee Valley Authority (TVA) Lead Test Assembly Program and was originally high enriched uranium (HEU) owned by the Department of Energy (DOE). Nuclear Fuel Services in Erwin, Tennesseo has downblended the HEU and Siemens Power Corporation (SPC) will produce the uranium dioxide fuel pellets.

Framatome Cogema Fuels in Lynchburg, Virginia will load the pellets into fuel rods and any excess fuel will be returned to SPC to be blended into their regular reactor fuel feedstock. The amount of fuel to be processed is relatively small (2250 kg U 0 ), but this program may lead to 3

future efforts by DOE and the Utilities to downblend HEU and make fuel rods in NRC licensed facilities.

DISCUSSION Siemens Power Corporation is authorized to possess and process uranium (U) enriched to 5% U2as and is currently limited to plutonium and neptunium (Pu/Np) isotopes below 3.3 bequerels per gram of uranium (Bq/gm U). In the amendment application, SPC requested permission to process uranium enriched to 4.35% U 3s and containing Pu/Np isotopes up to 2

50 Bq/gm U.

In the application, SPC has demonstrated the contribution to the annual radiation dose to personnel would be minimally increased by the additional presence of the Pu/Np at 50 Bq/gm U. The staff has reviewed SPC's application and agreed that increasing the Pu/Np limit to 50 Bq/gm U will not significantly change the radiation exposure to the workers or public. The staff also reviewed SPC's current organization and radiological safety procedures as described in the license and has determined that they are adequate to protect the health and safety of the personnel handling the requested material.

In the application, SPC also demonstrated that the Pu and fission products in the requested material are below the 10 CFR 50.2 " Production Facility" criteria of 1 microgram Pu/gm U2as and 0.25 mci of fission products per gm U2as. Therefore, SPC does not need to be licensed under 10 CFR Part 50.

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2 CATEGORICAL EXCLUSION 1

l In the information provided on December 15,1998, SPC determined and the staff agrees that the proposed change does not adversely affect public health and safety or the environment and the amendment should be categorically excluded from the requirements to prepare a site specific environmental assessment. Therefore, in accordance with 10 CFR 51.22(c)(11),

neither an environmental assessment nor an environmental impact statement is warranted.

f.ONCLUSION The staff has determined that the proposed processing does not adversely affect the health and safety of the workers, public, or the environment and that the amendment to Materials License i

SNM-1227 should be approved.

PRINCIPAL CONTRIBUTORS:

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