ML20041G071

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Application for Amend to License SNM-1174,to Permit Operation of Ion Exchange Sys to Decontaminate Solutions Generated During Decontamination Activities
ML20041G071
Person / Time
Site: 07001193
Issue date: 01/11/1982
From: Shelley W
KERR-MCGEE CORP.
To: Rouse L
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20041G072 List:
References
20200, NUDOCS 8203190166
Download: ML20041G071 (4)


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KERR-McGEE CORPORM/DN f $$ COV MERR-McGEE CENTER. OKLAHOMA CITY, OKLAHOMA T3MS 01 t

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DockErto N JM g5 ENVIRGeMENT AND NEALT*4 MANAGEMENT DIVIF'ON vbk8C A

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  1. 3 CERTIFIED MAIL - RETURN RECEIPT REQUESTED o[c)lfCLERK Cnov L

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as Mr. L. C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety dg * '-- J[..l._ @[/jp, Q-US Nuclear Regulatory Commission Washington, D.C.

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Re:

License SNM-ll74 2~'"

Docket No. 70-1193

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Dear Mr. Rouse:

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In accordance with the current standby license, we have not performed processing of Special Nuclear Material during the decontamination period commencing in 1976.

At this time, we wish to request an amendment to the referenced license to permit the operation of the ion exchange system in Room 127 of the Plutonium plant to decontaminate solutions generated during decontamination activities.

During the demolition and decontamination of the solvent extraction system, it was necessary to generate cleanup (mop) water to maintain low air concent-rations. Generation of this waste is expected to continue until subsequent phases of the demolition and decontamination are accomplished.

As you are aware, the disposal of scrap containing Plutonium has been eliminated at commercial burial sites. Alterantive burial sites are now operated by DOE. There is some consideration of. permitting these sites to accept contaminated waste for eventual geological disposal. The costs for such disposal, however, make it imperative that every volume reduction technique be applied to contaminated scrap.

Therefore, we have examined the feasibility of reducing gloveboxes to essentially pieces of scrap metal which can then be packed in 55-gallon drums. This technique would permit us to reduce the expected total volume to approximately one-half of that initially forecast. To operate the cutting equipment (plasma torch), the interior of the glovebox must be cleaned of any loose material and subsequently painted with a clear varnish to prevent the generation of high airborne concentrations of Plu N Removal of loose material with appropriate decontamination sol de'rierates liquids which can be decontaminated by ion exchange.

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January 7, 1982 Page 2 We estimate that this technique will permit a 26-fold reduction in volume of waste to be eventually stored. We believe this proposed activity meets the intent of the " Policy Statement on Low-Level Waste Volume Reduction" published October 16, 1981, in the Federal Register,46-200, page 51100 and request its prompt consideration.

t If additional information is required beyond that of the attachment to this letter, please let me know.

Sincerely,

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. Shelley,Vicefresident fuclearLicensi nd Regulation ps Attachment t

REQUEST FOR AMENDMENT TO LICENSE SNM-1174, DOCKET NO. 70-1193 Kerr-McGee requests modification to Amendment No. 9 of License SNM-ll74 dated i

May 18, 1977, as follows:

Paragraph 2 License condition Item 7.A.(1), delete, "there shall be no processing operation performed with this Special Nuclear Material."

Number 6 Delete subparagraph a.

"All decentamination activities inside gloveboxes or equipment, except for that necessary and incidental to maintenance or loss of control of radioactive material of SNM.

Renumber subparcgraphs b and c to a and b.

Number 7 The following activities are authorized.

Paragraph F The operation of the ion exchange column located in glovebox 31A, Room 127 for the purpose of removing Plutonium contamination froa waste I

cleanup solutions to reduce volume of waste generated. Regeneration of l

ion exchange resins by removal of the Plutonium and subsequent concentrations of the SNM is not included.

Loaded resins shall be

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discharged from the column and packaged for shipment to an appropriate burial site.

l Description of Operations It is planned to adapt two five-inch ion exchange columns in glovebox 31A,

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Room 127, by the addition of a pump to the cleanup of waste solutions generated by decontamination.

These solutions will receive a one-pass m,r-i-e

treatment through two IX columns and effluent concentrations will be reduced to dischargable levels.

Upon complete loading of the column resins, the resins will be discharged into 4" ID two-liter bottles for preparation for burial. It is planned to dry the resins by the attachment of a vacuum circuit to the column, thus removing surplus moisture.

Alternatively, if this procedure requires excessive time or does not achieve the goal of elimination of all liquids, the resins will be combined with appropriate amounts of vermiculite or cement to ensure that no free liquid remains in the package prepared for disposal.

_ Justification In view of the amount of liquids generated as a result of:

1. area cleanup to reduce the possibility of high airborna contamina-tion, and
2. the decontamination of inner surfaces of gloveboxes prior to fixing any remaining contamination with varnish prior to subdivision by plasma and cutting, the removal of the cantamination in these waste solutions is expected to reduce the volume of waste requiring disposal by a factor of approximately 26.

The demolition of the glovebox, by subdividing into pieces small enough to fit into a 55-gallon drum, will reduce the waste volume by approximately a factor of two.

This reduction of volume represents a significant saving in the amount of volume required for eventual subsurface disposal and, consequently, Kerr-McGee Nuclear's cost.

The additional cost for this processing is not an additional burden to the decommissioning activity.

This product meets the intent in " Policy Statement on Low-Level Waste Volume Reduction" FR,46-200, p. 51100, 10/16/81.

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