ML20155K260
| ML20155K260 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 04/23/1986 |
| From: | Nardi A WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 26917, LA-86-36, NUDOCS 8605280014 | |
| Download: ML20155K260 (4) | |
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Westinghouse Water Reactor g,ge Pennsywaniais2ao 0355 Electric Corporation Divisions '86 M7 -5 All :22 RECEIVED April 23, 1986
'85 MY -7 P1 :35 U. S. Nuclear Regulatory Commission U 5. :..
Office of Nuclear Materials Safety and Safeg65'rds[ WWI ' W r ATTN:
Mr. W. T. Crow, Acting Chief Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety Washington, DC 20555 Gentlemen:
Westinghouse Electric Corporation hereby submits a
license amendment application which requests a
limited exemption from the continuous surveillance portion of Section 4.2 of StN-1107 for materials which meet the concentration limits of Section 4.5 of StN-1107.
The purpose of this request is to authorize the transfers of low level materials to vendors for demonstrating and testing as a precursor to developing treatment methods for-eventually free releasing this material for recycle rather than Durial.
Any such free release will be the subject of a future license amendment application.
The enclosure to this letter lists the proposed vendors and the criteria which apply to these transfers.
If additional vendors are identified, their names and addresses will be sent to you for information purposes since they will be subject to the same criteria.
We are currently negotiating with our vendors and would appreciate a timely review of this request.
Enclosed is a check for $150.00 to cover the costs of an administrative amenoment.
Very truly yours,
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Page 2 April 22, 1986 6.
Following the demonstration and testing, aqueous and solid materials shall be returned to the Columbia Plant for proper dispositioning.
DISCUSSION Waste treatment products are currently processed at the Columbia Plant in a non-contamination controlled area.
This is made possible by an advanced waste treatment process which removes uranium from the process stream to levels approaching 0.3 ppm.
Consequently, uranium contamination levels from these materials are minimal as demonstrated by on-site contamination surveillance.
It is expected that the above referenced activities will result in the same low levels.
However, this will be verified by a close-out survey following completion of the work.
WP0604E:3p.56 l
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ENCLOSURE TO SUBMITTAL OF APRIL 22, 1986 StN-1107, DOCKET 70-1151 USE OF MATERIALS AT OFFSITE LOCATIONS PURPOSE The purpose of this request is to authorize the use of certain materials at offsite locations for demonstration and testing purposes which meet the limits specified in Section 4.5 of License SNM-1107.
LOCATION Materials are authorized at the following locations:
EIMCO Process Equipment Company, 669 West Second South, Salt Lake City, Utah 84110-0300 Bird Centrifuge, South Walpole,.MA 02071 Progress Technology, 2940 Orane Field Road,.Lakeland, FL 33803 CRITERIA The following criteria shall apply:
1.
Materials shall be limited - to industrial waste treatment products (primarily ammonium and calcium fluorioes) and other homogenous mixtures in which the mean concentration of uranium constituents does not exceed 30 picoeuries per gram (dry basis)..
2.
Vendors shall be appraised of the chemical contents of the materials, including uranium, and precautions to be taken curing handling operations.
3.
Demonstration and testing. procedures shall be limited to those that preclude the chemical separation of uranium from the matrix (centrifuging, filtration, briquetteing, etc.).
4.
Materials shall be ~ appropriately sampled and analyzed to assure that the above concentration limit is not-exceeaed prior' to the transfers.
The limits and controls in Sect' on 4.2 of StN-ll07 shall be followed i
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5.
except (a) the material will not be under continuous control by a Westinghouse employe approved by the Manager of the Radiation Protection Component.
Westinghouse personnel shall be present during the initial phases of the demonstration and testing to assure that appropriate procedures and controls are established and shall perform a close-nut contamination and radiation survey to assure that the limits referenced in Section 4.1 of StN-1107 are not exceeded, and (b) the total quantity autnorized for each vendor shall be less than 1 gram U-235.
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