ML20238E439

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Application for Amend to License SNM-1107,authorizing Free Release of Industrial Products,Including Hydroflouric Acid Solutions,Per Conditions Specified in Section 4.8
ML20238E439
Person / Time
Site: Westinghouse
Issue date: 05/13/1987
From: Nardi A
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Rouse L
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
28197, LA-87-22, NUDOCS 8709140344
Download: ML20238E439 (13)


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RECEWED May 13,1987 MAY181987 );

9 U s.nuatun necu w ag7 :i Comssion U. S. Nuclear Regulatory Commission 5

m ATTN: Mr. Leland C. Rouse, Chief 9/

"'"as Uranium Fuel Licensing Branch 4%

office of Nuclear Material Safety and Safeguards

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Division of Fuel Cycle and Material Safety USNRQ Washington, D. C.

20555 93 MAY 181987 ) y 12 Gentlemen:

Nuss Amt stcDON s

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SUBJECT:

Amendment Application, S m-1107, Docket 70-1151 ocm am

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REFERENCE:

U.S.N.R.C. " Environmental Review" Dated October 25, 1979 W

Westinghouse Electric Corporation Commercial Nuclear Fuel Division hereby submits an amendment request to License SNM-1107 to authorize the free release of industrial products (specifically hydrofluoric, HF, acid solutions) in which the conditions specified in the enclosed new Section 4.8 are met.

The proposed use of HF at Western Zirconium is similar to that at Brush-Wellman in that the HF remains in aqueous form throughout the process, and the uranium is eventually precipitated in a lagoon with zero discharge except for evaporation.

Attached is a letter dated April 15, 1987 from Dr. Donald Kaczynski of Brush Wellman affirming that their process has not changed since the above referenced NRC " Environmental Review" was performed.

Note that t

this letter references a maximum enrichment of 5% in U-235.

We believe that the higher enrichment does not modify the environmental analysis as l

documented in the October 25, 1979 NRC Environmental Review.

Westinghouse believes that this industrial use will have no significant adverse effects on members of the public or the environment since there are no pathways for the uranium to be introduced into a human ingestion

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chain.

The above referenced NRC " Environmental Review" is site specific to Brush-Wellman and indicates that "it is not expected that the proposed program has significant impact on the environment."

A check for $150 is included to cover the costs of this application. #

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Page 2 May 13, 1987

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Westinghouse intends to begin transfer of the liquid HF solutions from our Columbia Plant to the receivers as soon as possible.

We would be pleased to discuss this matter further with you and your staff as you may deem necessary.

Please contact Mr. Edward Reitler, Manager, Radiological and Environmental Engineering ~ (803) 776-2610, Extension 3247 if you have any questions.

Very truly yours, br A. J..Nardi, Manager NES License Administration WP1434E:3p.2 si J

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~ TABLE OF CONTENTS -

-Section Page j

.I 4.

Authorizations.and Exemptions ~

Table of Contents 4.0-1 4.1 Release for Unrestricted Use 4.1-1 4.2 Authorization for Use of Materials at Offsite 4. 2-1 Locations 4.3 -

Record Storage 4.3-1 4.4 Exemptions frcm the Requirements of 10CFR70.24' 4.4-1 4.5 Nonradioactive Industrial Waste 4. 5,-l 4.6 Possession of Licensed Material at Reactor 4.6-1 Sites 4.7 Leak Testing Sealed Plutonium Sources 4.7-1 4.8 Disposal of Aqueous Products 4.8-1 i

l Docket No. 70-1151 Initial Submittal Date:

4/30/83 Page No.

11 License No. SNA-1107 Revision Submittal Date:

5/13/87 Revision No.

9 l

l

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4 SCHEDULE OF REVISIONS

.Page' Revision Page Revision Number Number Number--

Number 3.2-5 2

3.2-6 2

1 3.2-7 2

3.2-8 3'

' 3.2 3 3.2-10 2

13.2-11 3

3.2 3

3. 3-2 2

3.3-2 2

3.3-3 2

4.0-1 3

'4.1-1 3

4.2-1 3

4.3-1 2

4.4-1 3

4.5 2

- 4. 6-l '

2 4.6-2 2-4.7-l' 8

. 4-. 8-1 9

l l

Docket No. 70-1151 Initial Submittal Date:

4/30/83 Page No.

vil b

l License No. StN-1107 Revision Submittal Date:

5/13/87 Revision No.

9

s REVISION RECORD Revision.

Date of Number Revision Pages Revised Revision Reason 1

12/12/83-1.9-52 through 1.9-76 Respond to NRC questions inclusive, 2.2-10, in NRC letter dated 2.2-11, 2.3-1, 4.8-1 April 6,1983.

2 3/26/84 All pages resubmitted' Respond to NRC questions as Revision 2.

See in NRC letters dated submittal letter January 26, 1984 and attachment for de-February 23, 1584.

scription of changes.

3

'1/4/85 All pages resubmitted Respond to'NRC as Revision 3.

See re-questions.

. vision lines in right hand columns of each page for specific changes.

4 6/25/85

.New pages 2.2-12'and Licensing of uranyl 2.2-13 and revised.

nitrate storage tanks, pages 2.3.1 and 2.3.2.

See revision lines in right hand columns of each page for specific changes.

5 5/14/86

2. 5-1 and 2.6-1.

Update of Emergency Plan Section.

6 8/8/86 2.2-3 Added criteria for positive pressure gloveboxes.

7-9/22/86 2.5-1 Update of Emergency Plan Section.

.8 4/1/87 4.7-1 Added ' criteria for leak testing sealed plutonium sources.

9 5/]3/87 4.8-1 Added criteria for disposal of aqueous products.

1 Docket No. 70-1151 Initial Submittal Date:

4/30/83 Page No.

vili License'No. SN4-1107 Revision Submittal Date:

5/13/87 Revision No.

9 l

SECTION 4 TABLE OF CONTENTS Authorizations'and Exemptions' Page.

4.1.

Release for Unrestricted Use 4.1-1 4.2 Authorization for Use of Materials at 0ffsite' 4 '. 2-1 Locations 4.3 Record' Storage 4.3-1 4.4 Exemptions from the Requirements of 10 CFR 70.24 4.4-1 4.4.1-Isolated Areas 4.4-1 4.4.2 Low Concentration Storage Areas 4.4-1 4.4.3 Shipping Package Storage Areas 4.4-1

4. 5 -

Nonradioactive Industrial Wastes 4.5-1 4.6 Possession of Licensed Materials'at Reactor Sites 4.6-1 4.7 Leak Testing Sealed Plutonium Sources 4.7-1 4.8 Disposal of Aqueous Products 4.8-1 i

l 1

l l

Docket No. 70-1151 Initial Submittal Date:

4/30/83 Page No.

4.0-1 License No. StN-1107 Revision Submittal Date: 5/13/87 Revision No.

9

i4.8' Disposal'of Aqueous Products

4. 8.1 -

Hydrofluoric (HF) Acid Solutions Pursuant.to 10CFR20.302, authorization to transfer aqueous HF-acid solutions containing trace quantities of uranium to nonlicensed (NRC or Agreement State) facilities specified in 4.8.1.1 is granted provided the conditions in 4.8.1.2 through

-4.8.1.5 are also met.

4.8.1.1 Receiver (s)

BRUSH-WELLMAN, INCORPORATED-WESTERN ZIRCONIUM South River Road P. O. Box 3208 J

Elmore, Ohio 43416 Ogden, Utah 84409 4.8.1.2-Condition (s)

The HF acid is transferred and used in such a manner that the minute quantity of uranium does not enter into any human

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ingestion chain.

Prior to such

transfer, each shipment will be representatively sampled and analyzed and the following maximum permissible concentrations shall not be exceeded:

Uranium:

less than or equal to 3 PPM (by weight)

Uranium-235:

less than or equal to 5% U-235 (by weight)

HF:

less than or equal to 50%

(by weight) 4.8.1.3 Quantities The estimated volume of this aqueous hydrogen fluoride solution is less than 50,000 gallons per year.

With a maximum. permissible uranium concentration of 3 ppm and a maximum enrichment of 5% in U-235, the maximum quantities of uranium and.U-235 in the 50,000 gallons that would be transferred would be approximately 334 grams uranium and 17 grams U-235 based upon the following:

Density 9.8 pounds per gallon Concentration 50% HF, 3' ppm U Enrichment 5% U-235 These quantities are insignificant, especially since the uranium and U-235 are not removed from the solution during l

Occket No. 70-1151 Initial Submittal Date:

4/30/83 Page No.

4.8-1 1

License No. SN4-1107 Revision Submittal Oate:

5/13/87 Revision No.

9 i

1

-L~-__-_-_----_'_--

its use and since the solution is not to be used in l

. manufacturing a product for human ingestion.

4.8.1.4 Brush-Wellman_

See: attached letter dated April 15, 1987 from. Dr. Donald Kaczynski to Mr.

Edward Reitler and previous NRC

" Environmental Review" dated October 25, 1979.

4.8.1.5 Western Zirconium Dilute HF is used to pickle zirconium products in aqueous baths where.the HF is diluted' by approximately 9 to 1 with nitric acid (i.e., nine parts nitric acid to one part HF).

Following the pickling step, the zirconium products are rinsed with deionized water.

It is expected that the uranium will remain in the aqueous phase'. to the next step in the process (neutralization) 'where slaked lime is added to the.

aqueous waste.

Other Western Zirconium aqueous wastes are.

added to this stream' prior to neutralization, resulting in a total dilution of approximately 1,000 to 1.

Neutralized wastes are transferred. to ' evaporation - only lagoons for. long term storage.

These lagoons are currently licensed with the State of Utah.

A composite sludge sample from the lagoons shall be collected on a. quarterly basis and analyzed for isotopic uranium with an action level of 15 pCi (total uranium) per gram of dry sludge.

If the. total uranium in the sludge sample exceeds 30 pCi/ gram, the NRC Regional Office shall be notified within 30 days of the completion of the analysis-There are no pathways for the uranium to be introduced into a human ingestion chain.

The zirconium products are used in the nuclear fuel cycle or in the chemical processing industry.

l Docket No. 70-1151 Initial Submittal Date:

4/30/83 Page No.

4.8-2 License No. St&l107 Revision Submittal Date:

5/13/87 Revision No.

9

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BRUSHWMLLMAN

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ENGseE=E: vrews Phone 419/862-2745 April 15, 1987 Mr. Ed Reitler Westinghouse Nuclear Fuel Division Bluff Road Columbia, SC 29205 1

Dear Mr. Reitler:

1 The extraction plant owned and operated by Brush Wellman Inc. in Elmore, Ohio consumes large quantities of aqueous hydrogen fluoride each year.

In June of 1979, Brush.Wellman's Dr. Ken Walsh, Asso-ciate Director of Technology, assisted General Electric in obtain-ing a NRC license to transfer about 100,000 gallons of dilute hydrogen fluoride for exclusive use by Brush in the production of beryllium pebbles. The maximum permissible concentration of l

uranium in this aqueous hydrogen fluoride was set at 3 ppm with a maximum enrichment of 5% in U-235.

1 i

The extraction process for beryllium used by Brush Wellman is i

identical to that used in 1979. We do not foresee this process 1

changing in the future. The reduction process converts metal fluo-rides produced from the aqueous hydrogen fluoride to pebbles or metal. Uranium is co-reduced along with the beryllium in this process and ends up in the final metal product. The fluorine is converted to magnesium fluoride, an insoluble solid waste which is disposed in waste treatment lagoons. All lagoons are maintained at a pH of greater than 8 such that metals present in aqueous wastes I

are precipitated.

As beryllium is a toxic substance, all extraction processes are carefully controlled such that airborne contaminants from the peb-i ble making process are eliminated.

In addition, as long as the concentration of uranium in the aqueous hydrogen fluoride is kept below 3 ppm, 7 ppm based on HF, the uranium which ends up in our beryllium metal oroducts will not pose any problems.

i TELEX 810 490 2300 TELEFAX 862 4177 i

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Mr. Ed Reitler~ ' April 15, 1987-

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Additional
constraints 'are put upon' our acceptances...f aqueous i

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hydrogen fluoride by our acceptance specification. Don Faron islin

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charge. of testing batches of acid. here at' the Elmore plant. 71; understand you have sent.him' a sample' to test.

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The use of dil'ute (less' than 70%)- hydrogen fluoride in our beryllium-making operation causes us to. incur higher costs than'if l

we'were.to'use concentrated hydrogen fluoride,iThi g in turn,

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means we cannot' spend as much to get it to our plantsite. OurLptst

-1 acceptance of dilute hydrogen fluoride was encouraged by. tight

. supply.' :This is no longer a factor in_our acceptance uf dilute f

hydrogen'.f l uori d e..I question whether in the past we ever fully considered the added costs we incurred when we used dilute hydrogen.

fluoride in our process. How this material is priced will deter'-

mine.whether we use it or not. William Dairy is the. purchasing specialist'at our Elmore plant in charge.of HF purchases.

3 If you have any further questions that you need answered to assist!

you with your licensing, please feel free to contact me.

I have, l j

j assumed the duties 'of'Dr. Walsh who retired last year..Providing' l

terms can be agreed.upon, and that your dilute.hy& ogen fluoride

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<i meets our quality specification, I see no reason why we cannot use-it. Our process, coupled with our.. lagoon treatment system', is

. ]e identical to that found acceptable ~.to the NRC ind.979-1; g

' Sincerely, 1

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Dr. ' Donald' J. Kaczynski Supervisor, Chemical Metallurgy Beryllium / Mining Division

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1 l

l l

i 1

l L. -- _ _ _ _ _ _ _ _ _ _. _ _ _ -

-