ML20237L207

Forwards Addl Info Supporting 870723 Request for Offsite Drying of Calcium Fluoride,Including Changed Pages 4.8-1 & 4.8-2 Deleting Authorization to Ship Hydrofluoric Acid to Western Zirconium.Fee Paid

ML20237L207
Person / Time
Site:	Westinghouse
Issue date:	08/14/1987
From:	Nardi A WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
28504, NUDOCS 8709080283
Download: ML20237L207 (16)

Text

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<g LA 87-56 Westinghouse Water Reactor Rl315' u gh PennsyNania 15230 0355 Electric Corporation Divisions August 14, 1987 0'

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' U. S. Nuclear Regulatory Commission f

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NO10I387,k]Ii ATTN: Mr. Leland C. Rouse Fuel Cycle Safety Branch

,II Division of Fuel Cycle, Medical,

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, jut 0Rr Academic, and Commercial Use Safety Q

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Office of Nuclear Material Safety and Safeguards 4b u sema Washington, DC 20555 Mg -

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Gentlemen:

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USNRC

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REF: SNM-1107, Docket 70-1151 9

1 gg24 Jgg7 p 3' Calcium Fluoride NMSS Westinghouse Letter Dated April 24, 1987 g

ng acc[crio,y s

NRC Letter Dated May 12, 1987, Amendment 6

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Westinghouse Letter Dated July 23, 1987 Hydrofluoric Acid 4'/

y Guidelines For Decontamination Prior to Release Westinghouse hereby submits adoitional information to support our above referenced letter dated July 23, 1987 concerning our request for off-site drying of calcium fluoride: Attached are:

1.

Changed page 4.5-1, mooified to acd the off-site drying of calcium flooride by the briquettor.

2.

An information package describing additional facilities to be installed on the Columbia Site for the purpose of calcium fluoride dewatering, interim storage and truck loading.

3.

Changed pages 1.11-2, 1.11-4, 1.11-5 and 1.11-6 expanding the description of briquettes to include encapsulated materials.

The purpose is to permit the briquettor to bag calcium fluorice for use in the steel mills.

We also included changed pages 4.8-1 and 4.8-2, celeting the authorization to ship hydrofluoric acid to Western Zirconium.

Attached also is changed page 4.1-1, updating the document used for material and equipment releases.

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Received ty, /.,$,

8709000283 870814 PDR ADOCK 07001151 Ts, C

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LA 87-56 August 14, 1987 I

' Enclosed in a check for $150.00.

If you have any questions, please write or telephone me at (803) 776-2610, Extension 3247.

Very truly yours,

&& Q lr,.<

A. J. Nardi, Manager NES License Administration WP1637E:3p.2 Enclosures l

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ATTACHMENT TO WESTINGHOUSE LETTER DATED AUGUST 14, 1987 CALCIlN FLUORIDE DEWATERING, STORAGE FACILITIES PURPOSE-The purpose of this project is to provide facilites for dewatering,

' storage and truck loading of calcium fluoride.

DESCRIPTION The. facilities, described in the attached sketch, include 1.

a concrete pad approximately 80. feet X 50 feet X. 6 inches thick to accommodate dewatering presses.

.2.

a covered dewatered calcium fluoride storage pad approximately 50 feet X 40 feet X 6 inches thick.

3.

a graveled road approximately 15 feet wide connecting the two pads for transport of the dewatered calcium fluoride.

ENVIR0tNENTAL EVALUATION State of the art construction techniques will be used during the construction activities to minimize environmental effects.

Liquids generated during the dewatering process will be transferred to a lagoon for further processing.

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SCHEDULE OF REVISIONS L

Page-

. Revision Fbge-Revision Number Number Number Number i

12 1.'5-2 2

li' 10 1.5-3 2

111 14~

1.5-4 2

iv 3

l'.5-5 2-v 14 1.5-6 2

vi 10 1.6-1 2

1 vil 14 1.7 2 vili 12 1.7-2 2

ix 14 1.8-3 2

1.0-1 2

1.8-2 2

1.0-2 12 1.8-3 2

1.1-1 2

1.8-4 2

1.1-2.

2 1.8-5 2

1.2-1 2

1.8-6 2

1.3-1 2

1.8-7 2

1.3-2 11 1.8-8 2

1.3-3 2

1.8-9 2

1.3-4 2

1.8-10 2

1.3-5 2

1.8-11 2

1.3-6 2

1.8-12 2

1.3-7 2

1.8-13 2

1.4-1 2

1.8-14 2

1.4-2 2

1.8-15 2

1.4-3 2

1.8-16 2

1.4-4 2

1.8-17 2

1.4-5 2

1.8-18 2

J. 4-6.

2 1.8-19 2

1.4-7 2

1.8-20 2

1.4-8 2

1.8-21 2

1. 5-1 2

1.8-22 2

i Docket No. 70-1151 Initial Submittal Date:

4/30/83 Page No.

iii License No. SNM-1107 Revision Submittal Date: 8/14/87 Revision No.

14

[J SCHEDULE-OF REVISIONS Page Revision Page.

Revision Number Number Number Number 1.9-49 2

1.9-83 2

1.9-50 2'

1.9 2 1.9-51 2~

1.9-85 2

1.9-52 2

1.9-86 2

1.9-53

.2 1.9-87 2

'l.9-54 2'

1.9-88 2

'1.9-55 2'

1.9-89 2

q-

-1.9-56 2

1.9-90 2

1.9-57' 2

1.9-91 2

1.9-58

-2 1.9-92 2

1.9-59 2

1.9-93 2

1.9-60 2

1.9-94 2

1.9-61 2

1.9-95 2

1.9-62 2-1.9-96 2

1.9-63' 2

1.9-97 2

1.9-64~

2 1.9-98.

2 1.9-65' 2-1.9-99 2

1.9-66' 2-1.9-100 2

1.9-67 2

1.9-101-2 1:9-68 2

1.9-102 2

1.9-69 2

1.10-1 2

1.9-70 2

1.10-2 2

1.9-71 2

1.10-3 2

-1.9-72 2

1.11-1 10 1.9-73 2

1.11-2 14 1.9-74 2

1.11-3 10 1.9-75 2

1.11-4 14 1.9-76 2

1.11-5 14 1.9-77 2

1.11-6 14 1.9-78 2

1.11-7 13 l'.9-79 2--

1.11-8 13 1.9-80 2

1.12-1 11 1.9-81 2

1.12-2 11 1.9-82 2

1.12-3 11 1.13-1 12 1.13-2 12 1.13-3 12 Docket No. 70-1151 Initial Submittal Date:

4/30/83 Page No.

v License No. SNM-1107 Revision Submittal Date:

8/14/87 Revision No.

14

SCHEDULE OF REVISIONS

/

l Page-Revision Page' Revision

- Number Number Number Number l-3.1-10

'2 3.1-11 2

3.1-12 3

'3.2-1 2.

3.2-2 2

3.2-3 2

-3.2-4 3

3.2-5 2

3.2-6 2

3.2-7 2

3.2-8 3

3.2-9 3

3.2-10 2

3.2-11 3

3.2-12 3

3.3-1 2

3.3-2 2

3.3-3 2

4.0-1 3

4.1-1 14 4.2-1 3

4.3-1 2

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4.4-1 3

4.5-1 14

4. 6-1 2

4. 6-2 2

4.7-1 8

4.8-1 14 4.8-2 14 Docket No. 70-1151 Initial Submittal Date:

4/30/83 Page No, vil License No. SNM-1107 Revision Submittal Date:

8/14/87 Revision No. __14

r-l.l 4

l REVISION RECORD l-

'evision' Date of R

Number Revision Pages Revised Revision Reason 13' 7/23/87 New pages 1.11-6 Added authorization for through 1.11.-8.

off-site drying of calcium fluoride.

14 8/14/87 Revised page 4.5-1.

Added drying of calcium fluoride to scope of operations.

Revised pages 4.8-1 Delete Western Zironium and 4.8-2.

as an authorized recipient of HF.

Revised page 4.1-1.

Update document date.

Revised pages 1.11-2, Added encapsulated 1.11-4, 1.11-5, and materials to briquetting 1.11-6.

desciption.

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Docket 90. 70-1151

~ dit:.Al 5,;;bailttal Date:, 7/23/87 Page NO.

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License No. SNM-lld7 ' Revi ion Submitt Oate:

6/lb/S7 Revision No.. '14 e.

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Dewatered (greater than 60 w/o solids) calcium fluoride is transported to off-site briquettors (for encapsulation) in closed vehicles or containers to prepare the materjal for use as a fluxing agent.

The uranium concentration in - calcium fluoride generated at the Westinghouse Columbia Plant is in the same range as natural calcium fluoride (fluorspar) used as a fluxing agent in the manufacture of steel as shown below:

Source Uranium Level (ppm)

Seaforth Mineral and Ore (Natural) 14.0 - 14.2 Mercier (Natural) 2.53 - 2.78 Westinghouse Electric (Columnia, SC) 1.41 - 4.01 30 pC1/gm, 5 w/o U-235 12,6 Consequently, the environmental impact of calcium fluorioe generated at the Columbia Plant will not differ significantly from natural sources.

To demonstrate this, we have calculateo the cose to a worker involved in briquetting or encapsulation of this material using the following assumptions.

1.

250 days p r year, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per day exposure.

2.

30 pC1 per gram of total uranium in the calcium fluoride (12.6 ppm uranium based upon a specific activity of 2.36 uC1/gm).

3.

5 w/o U-2?5 enrichment (SA = 2.38 uCi per gram) 4 Dust loading during briquetting is a maximum for a nuisance (non-toxic) dust of 10 milligrams per cubic meter.

5.

Dose conversion factor (U-234) for inhalatien 6

1.3x10 rem /Ci from NUREG-0518.

Note:

The ocses from ingestion and immersion are significantly below that from inhalation.

The U-234 dose conversion factor is the highest of all the uranium isotopes.

Docket No. 70-1151 Initial Submittal Date:

4/24/87 Page No.

1.11-2 License No. SNM-1107 Revision Submittal Date: !1/14/87 Revision No.

14 i

I.

Note:

This dose. does not include the daughter products

[

'which are in equilibrium with natural calcium fluoride.

Consequently, the incremental dose due to our calcium fluoriae is:

0.94 - 0.094 = 0.85 mrem / year Once the material is briquetted or encapsulated, it is transported to a steel manufacturer for use as a fluxing agent.

A survey conducted for Westinghouse indicated that the annual usage of

" natural" fluorspar is approximately 170,000 tons per year.

Therefore, the Westinghouse Columbia Plant rate. of approximately 1,000 tons per year would not significantly impact the current supply system, and the uranium it contains would be diluted before use in the steel making process.

Uranium in the briquette or encapsulated material becomes part of the slag during the steel making process

( > 99%).

This is based upon a considerable amount of work performed by the National Lead Co. at the Feed Materials Plant in Fernald, Ohio and by Union Carbide at the Oak Ridge National Laboratory.1 Based upon this evaluation, the total uranium level in the slag will increase to approximately 2.66 ppm (for 15 ppm, 3% U-235 in the calcium fluoride, in an electric furnace) from approximately 1.98 ppm from calcium fluoride from

" natural sources."

The increase in activity is to approximately 2.52 pCi per gram of I.

H.

Cavendish, " Treatment of Metallic Wastes by Smelting,"

J NLCO-1157, September 25, 1978.

B.

Heshmatpour and G.

L.

Copeland, "The Effects of Slag Composition and Process Variables on Decontamination of Metallic Wastes by Melt Refining," ORNL/TM-7501, January 1981.

E. W. Mautz, et. al., " Uranium Decontamination of Common Meta 2s by Smelting - A Review," NLCO-1113, February 5, 1975.

Docket No. 70-1151 Initial Submittal Date:, 4/24/67 Page No.

1.11-4 License No. SNM-1107 Revision Submittal Date:

8/14/87 Revision No.

14

slag.from 1.29.pCi:per' gram of-slag.

This is the worst' N;,,.;,

case activit'y increase 'and is well below the present

~

licensed free release limit of 30 pCi per gram..

The-environmental' evaluation performed for the briquetting-operation will be conservative with respect to the steel making process for the following reasons:

i 1.

Westinghouse-generated calcium fluorice v:ill be mixed with natural calcium fluoride.

2.

The uranium in the calcium fluoride transported to a steel p

mills will be encapsulated.

3.

Uranium will be " encapsulated" in the slag at concentrations less than 30 pCi per gram.

Consequently, doses to' the public will-be well below 40CFR190 Jimits.

Docket No. 70-1151 Initial Submittal Date:

4/24/87 Page No.

1.13-5 License No. SNM-1107 Revision Submittal Date:

8/14/87 Revision No.

14

o EVALUATION OF CALCIUM FLUORIDE DRYING OPERATION INTRODUCTION' Mercier Corporation located in Gary, Indiana at the-Great Lakes Industrial Cent'er Site fabricates a variety of' briquette materials for end use in steel manufacturing ' and metallurgical foundry industries.

One product requires them to purchase fluorspar or calcium fluoride.

Westinghouse will supply ~this.need by shipping truckload quantities of dewatered calcium fluoride to Mercier for drying and fabricathn of calcium fluoride briquettes or encapsulated material.

This heavy industrial site is bounded by the U. S.~ Steel site to the north and the city of Gary to the south.

METEOROLOGY Assumptions:

1.

The emission rate of CaF2 equals 0.66 pounds per hour.

'2 The uranium contamination conservatively equals 12.6 ppm uranium at 5.0 w/o U-235.

3.

The specific activity is equal to 2.385 uC1/g.

4.

The ground level point-source release diffusion equation will be useo conservatively as a worst case.

l 5.

Class D stability category is assumed at a wind speed of 3 m/s.

6.

The nearest resident is approximately 610 meters south of the discharge point.

0.66#CaF2 454g CaF2 12.6 ugU 1 Hr.

, 1.049 ugU g

X X

X Hr Lb g CaF2 3,600 Sec Sec 1.049 gU X 10-6 X

=

2.385 uCi 2.50 X 10-6 uCi Sec gu Sec Docket No. 70-1151 Initial Submittal Date:

7/23/87 Page No.

1.11-6 License No. SNM-1107 Revision Submittal Date:

8/14/87 Revision No.

14

or.

Authorizations and Exemptions 4.1 Release for' Unrestricted Use Release of equipment and material from the plant to offsite for unrestricted use or.from contaminated to clean areas onsite shall be made in accordance with " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," August 1987.

i i

i Docket No. 70-1151 Initial Submittal Date:

4/30/83 Page No.

4.1-1 License No. SNM-1107 Revision Submittal Date: 6/14/87 Revision No.

14

-L

4.5 Nonradioactive Industrial Wastes Under the auspices of 10 CFR 20.302, industrial waste treatment products (primarily calcium fluoride) and other l

homogeneous mixtures in which the mean concentration of l

uranium constituents does not exceed 30 picocuries per gram shall be released for disposition in a chemical disposal

site, industrial

landfill, or to off-site drying vd briquette manufacturers (calcium fluiride only) without l

continuing USNRC licensing controls.

4.5.1 A sampling plan shall be implemented which will characterize the industrial wastes in accordance with NUREG/CH-2082 as follows:

4.5.1.1 The estimation of the population mean for the uranium concentration shall be representative of the industrial l

wastes located onsite and any subsequent shipment of this mate rial.

4.5.1.2 The sample size, used to calculate the mean value, shall be determined such that the 95 per cent confidence limit of the mean value shall be less than 25 per cent of this value (e.g., 1 ts/ {5<.25 li) where "t"

is from students t tables, "s" is the standard oeviation, "I" is the mean, and "n"

is the population size.

In addition to these requirements, the sampling plan shall provide a minimum confidence level of 95 per cent that the true mean value determined for these industrial waste products is less than the maximum allowable limit of 30 picocuries per gram of dry material.

Records pertaining to the release of these materials shall be maintaineo along with the names of the individuals receiving these materials.

Reasonable efforts shall be made to reduce the level of contamination in line with the ALARA concept.

4.5.2 Calcium fluoriae released to off-site briquette manufacturers shall contajn a minimum of 60% solids.

Docket Nc. 70-1151 Initial Submittal Date:

4/30/63 Page No.

4.5-1 License No. StN-1107 Revision Submittal Date:

8/14/87 Revision No.

14

F 4.8 Disposal of Aqueous Products t

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 facilities specified in 4.8.1.1 is granted provided the conditions in 4.8.1.4 are also met.

,- 4. 8.1.1 -

Receiver (s)

' BRUSH-WELLMAN,' INCORPORATED South River Road Elmore, Ohio. 43416 4.8.1.2 Conditiodsl The HF acid is transferred and used in such a manner that the minute quantity of uranium. oces not enter into any human ingestion chain.

Prior to such

transfer, each shipment will be representative 1y sampled and analyzed and the following maximum permissible concentrations shall not be exceedad:

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 ano 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 followir 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 Docket No. 70-1151

. Initial Submittal Date:

4/30/83 Page No.

4.8-1 License No. SNM-1107 Revision Submittal Date:

8/14/87 Revision No.

14

~

its use and since the solution is not to be used in manufacturing a product for human ingestion.

4.8.1.4 Brush-Wellman See attached letter dated April 15, 1987 from Dr. Donald 4

Kaczynski to Mr.

Edward Reitler and pIevious NRC

" Environmental Review" dated October 25, 1979.

'h

' I J

l 1

Docket No. 70-1151 Initial Submittal Date:

4/)D/83 Page No.

A.8-2 License No. SNM-1107 Revision Submittal Date: 8/14/87 Revision No.

14 L-.._..

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