ML20127P214

Application for Amend to License SNM-1227,permitting Const & Operation of Demonstration Facilities for Recovery of U from Chemical Waste Solutions.Fee Paid

ML20127P214
Person / Time
Site:	Framatome ANP Richland
Issue date:	03/20/1985
From:	Malody C SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:	Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
25228, NUDOCS 8505230723
Download: ML20127P214 (12)

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-Uranium Process Licensing Branch Division of Fuel Cycle and Material Safety U.S. Nuclear Regulatory Commission Washington, D.C.

20555 o " " ').C License No. SNM-1227 Docket No. 70-1257

Dear Mr. Crow:

Exxon Nuclear Company, Inc. hereby requests that License No. SNM-1227 be amended to provide for const ruction and' operation of facilities for the recovery of uranium from chemical process waste solutions.

Amendment No.11 to License No. SNM-1227 permitted the construction and operation of. demonstration facilities for the recovery of uranium from stored process waste.

The demonstration has been successfully completed and we are preparing to expand these facilities to provide capability for the recovery of uranium from liquid process wastes now being held.

The process flow sheet as originally proposed was demonstrated with little change. The new produc-tion facility will use the same equipment as the demonstration unit and add a second parallel processing line as well as office / change room, paved access road and other peripherals.

Uranium Recovery Process Description l'

The six existing lagoons (Drawing XN-606,370) allow for the segregation of high uranium cont ent liquid waste and for'collec-tion, sampling, and discard of low uranium, low ammonia content l

liquid waste. High uranium content liquid waste is transferred to Lagoon 2 for temporary storage and accountability. Waste solution from Lagoon 2 is periodically transferred to Lagoon 3 for storage while awaiting f urther processing for uranium recovery. Following uranium recovery, these waste solutions will be processed for ammonia removal and ultimate discharge to sewer via Lagoons SA and

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58. Lagoon 1 holds low uranium content waste solution prior to I

ammonia removal and discharge.

l A process flow diagram for the uranium recovery system is presented in Drawing XN-606,643.

Approximately 4000-6000 gallons of high uranium content waste is pumped into the precipitator.

The uranium is precipitated from solution and allowed to set t le for approxi-8505230723 850320 ama t armorexxowconconavion PDR ADOCK 07001257 C

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c' mately 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.- ' At the.end of the settling period, the superna-ctant 'is decanted to Lagoon Storage..This procedure is repeated untillthe total; precipitate accumulated'in the precipitator vessel

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reaches - the desired batch size.-

The uranium precipitate is slurried to the washer tank and receives three separate water Uwashes for extraneous chemical removal.

The washed precipitate is -

then' slurried into a container,' dissolved in aluminum nitrate L

solution, transferred to a plastic lined. 55-gallon ' drum and placed (i

into: storage. The recovered uranium values will be purified for

're-use through existing solvent extrection facilities.

Facility Description

' The. Lagoon Uranium Recovery facility is located adjacent to Lagr m 1 4.- Equipment' layout is depicted in; Drawing 606,944.

The' equipment consists of six process vessels, one chemical makeup

-vessel, and the associated pumps, piping and filters.. The equip -

ment.will be out~in the open and not housed.

Status of Techn_ ology

'The technology for 'the process has been developed by Exxon Nuclear and is considered proprietary.. Several full scale demonstration runs have been completed. The precipitate formed'is crystalline in

. nature and settles-rapidly and completely. :The concent ration of uranium in the supernate ~is consistently less than 15 ppm.

The precipitate is fairly. dense, easily slurried, and.readily dissolved -

in aluminum nit rate solution. Chemicals employed'are not hazard-

- ous, flammable, nor explosive with no-special safety : precautions being required.-

1 Radiological Safety Protection.of employees will be. by routine monitoring 'and Radiation Work Permit icquirements similar to those employed in other Exxon Nuclear facilities... No special precautions will be necessary or

. required over and above those normally used when processing low 3 enriched uranium compounds.

Criticality Safety

- The f acility. layout has been subject ed to a cr i'. tcality safety

. analysis and found to be safe for~ enrichment levels up to 5 wt".

'UL235.. Criticalit y control will be' accomplished by batch control as described in. License No. SNM-1227 ' based,upon the enrichment

, heing processed at the time. Enrichment levels are expected to be

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Mr. W. 1. Crow March 20, 1985 Page 3 in the range of 2.8 to 3.2 percent._ No more than 45% of-a minimum critical mass will be allowed in any tank at any one time.

The facility will be operated within appropriate criticality safety specifications and monitored by an extension of the existing.

criticality detection and alarm system.

Environmental Impact Any environmental impact associated'with construction will be minimal. The liquid wastes will 'be processed to within existing waste-discard limits.

No solid waste will be created from this process. Construction and operations of this production scale unit will allow recovery and recycle of uranium currently stored in waste solutions. Stored waste volumes can then > be reduced which

-should reduce the amounts of radioactive waste which could potentially leak to the groundwater.

.Your timely review and approval of this application is appreciated.

' Please find enclosed a check for $150 to cover the initial fee ;for a minor amendment.

Very truly yours,-

C. W. Malody Licensing Special Corporate Licensing CWM:jrs Enclosure As Stated n

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