ML20202D227

Forwards Response to RAI Re Licensee Request for Amend to Release Industrial Waste Treatment Product to Cement Mfgs

ML20202D227
Person / Time
Site:	Westinghouse
Issue date:	11/17/1997
From:	Robert Williams WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Gaskin C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
CON-NRC-97-054, CON-NRC-97-54 TAC-L31003, NUDOCS 9712040196
Download: ML20202D227 (2)

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Wesiinghouse Commercial Nuclear Drawer R Electric Corporation Fuel Division yjfpiasgmCarchna 29250 3

g NRC-97-054 November 17,1997 U.S. Nuclear Regulatory Commission ATTN:

Mr. Charles Gaskin Licensing Branch (T8Dl4)

FCS&S Division, NMSS Washington, DC 20555

Dear Mr. Gaskin:

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SUBJECT:

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (TAC NO. L31003)

The Westinghouse Electric Corporation hereby submits a response to your request for additional information regarding our request for an amendment to release industrial waste treatment product j

(calcium fluoride) to cement manufacturers.

If you have any questions, please contact me at (803) 776-2610, Extension 3393.

Sincerely, WESTINGHOUSE ELECTRIC CORPORATION Robert A, Williams, Licensing Project Manager

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Westinghouse Columbia Plant Docket 70-115 l License SNM-1107 I

Attachment I

cc:

Rodney Wingard South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 IllBIMI[Il.iRI' m

9712040196 971117

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i ENCLOSURE TO LETTER NRC-97-054 1.

The chemical form of the uranium in the calcium fluoride will likely be a mix of the following highly insoluble species:

UO2(Nil 4)2-Solid ADU from the plant that is not captured by the waterglass process.

UO2(Na)2-Sodium uranate residual solubility from uranate that reacts with sodium from waterglass.

UO2SiO3 OR (UO2)2SiO42H20-Solubility of materials dissolved from waterglass solids e

CaSiO3/UO2SiO3 Formed in the NH3 still from the excess sodium silicate and the e

Ca(OH)2 2.

The only radionuclides other than uranium in the waste treatment products would be progeny of the uranium series. No radionuclides cther than uranium are used in the Plant in such a manner that they would find their way into the v aste treatment products.

The variability in the uraniam measurement is stated for the current batch ofCaF2 and presented as two cases:

c case one: n samples are randomly selected from a batch ofCaF2, The mean, x = 1.463 +/-

e 0.179 ppm U, i.e, any me an will fall within the range of 1.283 to 1.642 ppm U 99% of the time.

case two: one sample taken at random from a typical batch ofCaF2: the individual result, e

X(i) = 1.463 +/- 0.4571 ppm U, i.e., any individual sample result will fall within the range of 0.092 to 2.834 ppm U 99% of the time.

3.

Radionuclide concentration for each batch will be included on the MSDS for the material and provided to the recipient.

4.

The cei ent manufacturer will use the material as a filler and as a fluxing agent in the cement. The CaF2 lowers the melting point of the cementatious materials since it remains as a stable fluoride in the oxide matrix of the cement. This is analogous to the use of CaF2 in the steel industry (a previously licensed use) where it serves exactly the same purpose. A maximum of 0.25% will be used per batch.

5.

The following assumptions were made to calculate the dose to an individual at a cement manufacturer who is working with the calcium fluoride:

lie is exposed to a nuisance dust concentration of 1.5E-02 gm/m3 for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per day,50 e

weeks per year.

The activity of the calcium fluoride is 30 picoeuries per gram, or 3.0E-05 microcuries per gram.

There are 1E06 mi per m3.

The volume of air breathed in a year is 2.4E09 ml.

The dose conversion factor is 1.25E05 MREM per microcurie inhaled.

The calcium fluoride represents 10% of the dust inhaled.

Dose = 1.5E-02 x 3E-05 x 1E-06 x 2.4E09 x 1.25E05 x 0.1 MREM / year = 13.5 MREM / year or 13.5/100 = 13.5% of the 10CFR20 limit for a member of the public.

This information was provided by Dr. Edward J. Lahoda, Westinghouse Science and Technology Center, and Edward K. Reitler, Jr., CHP, Westinghouse Columbia Fuel Fabrication Facility.

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