ML20149J473

Forwards Proposed Rev 7.0 of Pages iii,12.2 & 12.3 of Application for Renewal of License SNM-1107

ML20149J473
Person / Time
Site:	Westinghouse
Issue date:	07/14/1997
From:	Robert Williams WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Gaskin C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
CON-NRC-97-030, CON-NRC-97-30 NUDOCS 9707280232
Download: ML20149J473 (5)

Text

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NRC-97-030 July 14,1997 U.S. Nuciear Regulatory Commission ATTN:

Mr. Charles Gaskin Licensing Branch (T8D14)

FCS&S Division, NMSS Washington, DC 20555

SUBJECT:

CHANGED PAGES; LICENSE NUMBER SNM-1107: DOCKET 70-1151 The Westinghouse Electric Corporation hereby submits proposed Revision 7.0 of pages iii,12.2 and 12.3 of the Application for Renewal of a Special Nuclear Materials License for the Commercial Nuclear Fuel Division at the Columbia, South Carolina Fuel Fabrication Facility.

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

Sincerely, WESTINGIIOUSE ELECTRIC CORPORATION tq = oq '

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Robert A, Williams, Licensing Project Manager Westinghouse Columbia Plant Docket 70-1151 License SNM-1107 Attachments 9707200232 970714

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ENCLOSURE TO LETTER NRC-97-030 4

Amendment of SNM-1107 a

Docket 70-1151

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In accordance with the telecon between Charles Gaskin (NRC Licensing) and Robert Williams (Westinghouse Licensing) on July 11, 1997, Westinghouse is proposing to add cement manufacturing, to the current SNM-110712.1.6 Authorization for brick manufacturing, as another construction material use for the calcium fluoride industrial waste treatment product of the Columbia Fuel Fabrication Facility.

In addition, Westinghouse is proposing to withdraw the SNM-110712.1.4 Authorization for Use at Off-Site Locations.

The authorization is used so infrequently by the Columbia Fuel Fabrication Facility, that it is felt that future such uses can best be handled on a case-by-case basis.

1 REVISION RECORD REVISIdN DATE OF PAGES NUMBER REVISION REVISED REVISION REASON 1.0 30APR95 All Update to current operations.

2.0 281UN%

iii, 6.8 Clarify Criticality Safety Basis for the compaction operation.

3.0 30AUG96 iii,1.7,1.9,12.6,12.7 Incorporate Safety Condition S-3 into Application; correct reference to Figure 1.3 instead of 2.3, to reflect expansion of the CAA in order to eliminate need for gate.

4.0 30SEP96 iii, 6.11, 6.12 Clarification of Criticality Safety Basis for the Pellet Stripping System Equipme'nt and Hoods & Containment.

5.0 08NOV96 iii,1.12,3.18, and 3.19 Incorporation of a definition, (Reprinted all document and incident notification i

pages in Microsoft Word criteria, recently approved format) by NRC Staff.

6.0 05MAY97 6.12 (Reprinted all Clarify Evaluation document pages in Bounding Assumptions Microsoft Word fonnat.)

for Storage of Annular Pellets 7.0 14JUL97 iii,12.2 and 12.3.

Withdraw an existing authorization, and expand another authorization to enable cement manufacturing with CaF -

2 Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

iii License No. SNM-1107 Revision Submittal Date: 14 JULY 97 Revision No. 7.0

.with the regulations. Operations incident to such loading shall be subject to the control of a licensed activity representative, approved by the Manager of the Regulatory Affairs Component, who shall assure that the completed transport package complies with all requirements of the regulations.

For such operations, the licensed activity shall be exempted from conditions of Title 10, Code of Federal Regulations, Part 70.24; CRITICAllTY ACCIDENT REQUIREMENTS, provided:

As finished fuel arembhes are resolved from their approved storage facilities, they shall be constrained in an arrangement that is no more reactive than that which they will assume in the shipping package.

I The total number of fuel assemblies in process at any one time shall not exceed

' the maximum authorized contents of the packaging being loaded.

If two fuel assemblies are in movement at the same time, a 12-inch minimum edge-to<dge separation shall be maintained between them; and, only one fuel assembly at a time shall be loaded into the shipping package.

4 Loaded packages shall be stored in the approved shipping array, pending delivery to a carrier.

l No more than the maximum number of packages authorized for a single shipment j

shall be loaded and possessed, in conduct of such operations by the licensed j

1 activity, at any one location.

12.1.4 AUTHORIZATION FOR USE AT OFF-SITE LOCATIONS (WITHDRAWN) 1 4

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i Docket No.

70-1151,

Initial Submittal Date:

30APR90 Page No.

12.2 License No SNM-1107 Revision Submittal Date: 14JUL97 Revision No. 7.0

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1 12.1.5. AUTHORIZATION FOR TRANSFER OF HYDROFLUORIC ACID Pursuant to Title 10, Code of Federal Regulations, Part 20.2002; METHOD FOR OBTAINING APPROVAL OF PROPOSED DISPOSAL PROCEDURES, aqueous hydrofluoric acid containing trace quantities of uranium may be transferred to non-licensed receivers provided the following conditions are met:

Prior to first unrestricted sale or other transfer of the subject material to each receiver, a detailed plan for such sale or transfer shall be submitted to the NRC Staff for review and approval.

Prior to transfer of the hydrofluoric acid from Westinghouse, each shipment must i

be representatively sampled and analyzed; and the following maximum permissible concentrations shall not be exceeded: A uranium enrichment of 5 w/o U-235; A uranium concentration of 3-parts-per-million by weight; and, an HF concentration, in the acid solution, of 55-percent by weight, i

Particular attention shall be paid to each sale or transfer to assure that the hydrofluoric acid is not to be used for any purpose resulting in human consumption.

12.1.6 AUTHORIZATION FOR TRANSFERS AS NON-REGULATED MATERIAL Pursuant to Title 10, Code of Federal Regulations, Part 20.2002; METHOD FOR 2

OBTAINING APPROVAL OF PROPOSED DISPOSAL PROCEDURES, industrial waste treatment products from the licensed activity, such as calcium fluoride and other homogeneous mixtures in which the mean concentration of uranium constituents does not exceed 30-picocuries per gram, may be released without continuing NRC licensing controls, to receivers for off-site calcium fluoride drying and briquette manufacturing, or for cement or brick manufacturing, or to disposition at a chemical disposal site or industrial landfill. Calcium fluoride so released to off-site manufacturers shall contain a minimum of 60-percent solids. Prudent efforts shall be made to reduce the radioactive contents of all such transferred materials to levels as low as reasonably achievable.

A sampling plan shall be implemented to characterize the industrial products in accordance with NUREG/CR-2082; MONITORING FOR COMPLIANCE WITH 4

DECOMMISSIONING TERMINATION SURVEY CRITERIA, as follows:

The estimation of the population mean for uranium concentration shall be representative of the industrial products being transferred.

The sample size used to calculate the mean uranium concentration value shall be t

Docket No.

70-1151 Initial Submittal Date:

30APR90 Page No.

12.3 License No. SNM-1107 Revision Submittal Date: 14JUL97 Revision No. 7.0 I

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U.S. Nuclear Regulatory Commission ATTN: Mr. Charles Gaskin Licensing Branch (T8D14)

FCS&S Division, NMSS Washington, DC 20555 5

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