ML20040D167

Application for Amend to License SNM-1067,to Detail Decontamination Plan

ML20040D167
Person / Time
Site:	07001100
Issue date:	12/10/1981
From:	Lichtenberger ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Page R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20040D168	List: ML20040D167 ML20040D170
References
20058, NUDOCS 8201300368
Download: ML20040D167 (12)

Text

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C-E Power Systems Tel. 203/688-1911

-/10(D Combustion Engineering. Inc.

Telex: 99297 1000 Prospect Hill Road Windsor. Connectut 06095 pgggjygg hgh

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License # SRI-1067 y=

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20555 c3 Attention: Mr. R.G. Page, Chief h,

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Reference:

(a) U.S.N.R.C. letter from R.G. Page to II.V. Lich nberger?

s' dated June 29, 1931, SNM-1067 - Amendment No. 30

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Gentlemen:

By reference (a) the NRC approved with conditions, Amendment 30 to the subject license which authorized the possession of certain uranium and thorium bearing waste material for repackaging and disposal. Condition 30 requires the submittal of a detailed plan for decontamination of the soil in the waste material staging area.

To comply with this condition it is requested that License SNM-1067 be amended to detail this decontamination plan. The criteria to be used for monitoring the area as well as the limits for its release as unrestricted are contained in Attachment A.

Information in support of the stated criteria is presented in Attachment B.

The amendment fee of $1400 required by 10CFR170.31.is being forvarded directly to the License Fee Management Branch under separate cover.

If you have any questions regarding this amendment application, please t

l contact Mr. P.R. Rosenthal of my staff on extension 3366.

Very trul yours, l

II.V. Lichtenberger, Vice President - Nuclear Fuel Nuclear Power Systems i

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DDil-31-204 4

Attachnent A - SRI License Amendment Criteria 1.

This amendment establishes the criteria to be used to survey the waste materials staging area and the tanporary waste material package storage l

area for the purpose of releasing the areas for unrestricted use.

2.

Based upon the analysis in Attachment B-1 a direct radiation survey will be performed and representative soil samples will be collected and analyzed to demonstrate that the waste materials staging area has been cleared of the material in question.

3.

The direct radiation survey will be perfonned in accordance with Attachnent B-2 using a calibrated instrunent (see Attachment B-3 and B-4) and the re-sults will be compared with the area background radiation levels as deter-mined in accordance with Attachment B-5.

The limit for release of the area for unrestricted use will be as follows:

The average radiation exposure rate (ganma dose rate measured one (1) meter above the ground) for any 30' x 30' section of the grid shall not exceed 10ur/hr (not including background) and no single measurement in a 30' x 30' section of the grid shall be greater than 20ur/hr (not including background).

Information in support of this limit can be found in Attachment B-6.

4.

Representative soil samples will be collected and ana7yzed by ganma or alpha spectrometery to determine the concentrations of the radionuclides in the soil. Using the approach outlined in Attachment B-7 the waste

-materials staging area will be considered acceptable for release as unrestricted when it is demonstrated that the dose to the lung will be less than 30 milliran per year.

5.

Release of the waste material package storage area will be based on a direct radiation survey of the area. This approach is sufficient since the weekly smear surveys of the area have demonstrated that no materials.

have been deposited in the area. This area will be released for unrestricted use if the radiation levels in the area are less than 20 above the instrument background radiation icvels.

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i DDII-81-204 6.

Region I of the U.S.N.R.C. will be notified upon successful catpletion of the survey.

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fW Attaciunent B List of Contents l;

B-1 I>emonstration of soil insoluability B-2 Direct Radiation Survey B-3 Instrument Description B-4 Instrument Calibration Procedure (DDil-81-206)

B-5 Background Radiation Level Determination B-6 Support Information B-7 Soil Sample Criteria B-8 Dose Conversion Factors.

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Attachnent B-1 l

This attachnent contains two tests that were perfomed on the material in gaestion. One being a waste oxide leach test and the other an analysis of stratification soil samplen. Both tests clearly demonstrate that the material that was removed from the waste materials staging area is insoluable.

Since the material has demonstrated that it does not leach down into the soil the primary exposure pathway to man is from direct radiation exposure and inhalation of particulates and not from the food ingestion pathway.

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l' ft. I:v,en thal Waste Oxide l.cach Test I:. A. llagelstein (791201) 11iDC.80-060

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cc: II. IL Graves J. 11. 1.imber t Hovember 6,1900 A water leech test h c. Leen conducted on six (E) vast e oxide samples The purpose collected f rom stora7c drums by lleal th physics personnel.o by rainstater f ro:a the oxide material.

The test was perforned by placing the san;>le materials in contact with At the end of simulated rainwater for a period of fifteen (15) days.

the leach peried, a portion of the liquid was removed, filtered and

!!csul ts analyzed for alpha and beta radioactivity and chemical uran per milliliter of leach solution.

A liquid presumed to be rainwater was found in :he bottom of drum 2-24.

This uater uns extracted from the drum and also analyzed for radioactivity These resuits are listed in Table 1 as Sample 0

and uranio:a content.

lio. 7 and are repor:ed per milliliter of liquid extract.

The test results shv.1 that no significant radioactive material was leached However, Saraple "o. 3 from drum 1-35 from samples 1, 2,1, 5 and 6.

l'o detectable indiEates leaching of some alpha and beta radioactivity.The liquid extracted from uranium was leached from any sample.

Saraple No. 7, contained no measurable radioactivity or uranium.

Simulated rainwater was The test procedure in detail is as follows.

prepared.by saturating domineralized water with carben dioxide and The resultant pH of this selution was 4.8.

A 50-gu atraospheric gases.

n a 3.25 in. diameter portion of each vias te oxide sample was placed iSimulated rainua ter (100 plastic centainer.

At the end of that container was cappcd and lef t undisturbed for 15 days.

period, a liquid simple was collected from the supernate of each container The liquid extracted from

'and filtered through 0.2 micron filter paper.

Alpha and beta radioactivity drum 2-?4 was also fil tered in t he same manner.

of the filtered liquids was determined by counting 10 ml. of evaporated ficasurements liquid for 1 hr. in a lou hacI: ground proportional counter.

for uranica content were performed with a uranium fluorimeter.

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Attachnent B-1 page 3 of,;

The hinim'im dntectabic activities lir.te'r! in Table 1 rer.nl L when they are i quallhe minit:um.on :i tivi ties r ej,0ried a, Ihr:

rfra*,ui cd r adioact.ivi ty concentra t ione li:.ted f or uranium concent ra tion, are ba,ed up m t.:in imum slotec r,':ler dcIlection and inretrument rer.pon ;c to uranium t,tandardJ.

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'Three. stratification ~ soil samples were obtained in the waste noterials

stanina area. Radioactivity variation with depth for each of the three samples :is shown on' page 6 of 6 of this attachnent. All three stratifi-cation samples were-in the fonn of resolidified scrap metal oxides which have " capped" the surface of. the soil, f

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w DDIl-81-204 Attachment B-2 Direct Radiation Survey For convenience and recording purposes the area in question will be divided up into a grid with sections of approximately 30' x 30' or smaller.

Each section of the grid will be surveyed three (3) times no less than seven (7) days apart. Erch survey will consist of several measurements in each of the grid sections taken at one (1) meter above the ground. Locations in the grid section will vary and be representative of the radiation level in the grid section. The surveys will be taken with a calibrated instrument suitable for measuring gamna radiation in the ur/hr range (see Attachments B-3 and B-4).

The surveys will be performed on a relatively clear day with air temperatures between 5.00C and 25.0% and windspeeds between calm and 10 mph (this weather information may be as reported at Bradley International Airport in Windsor Iocks, Connecticut). After all three surveys have been completed an average radiation level will be determined for each section of the grid. This average radiation level and the highest radiation level observed for each grid section will be used for comparison with the area background radiation levels to determine if the area can be released for unrestricted use.

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AttacJunent B -

- 'the. instrtw:nt that Ccuibustion Engineering, Inc. plans to' use to perfonn the

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radiation st1rveys is a LUDIMI Model 12S }!tCl:011 MEEl'nanufactured by LUDLUB1 liiMSUllDEifS I!!C., Sweetwater,' Texas.

She instrttnent utilizm an internally nounted 1" x 1" Na(TI) scintillator.

7he instrument is sel:'-contained using tsto "D" size batteries for power. It is very sensit>>c to yaimn energy and when exposed to low gannn energies it will, predaninantly, : cad high.

When the instrument in set in the slow response mo;1e 90% of full scale meter deficction takes 11 v:conds.

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