ML20151W801

Calculation of Activity Ratio of Total U to U-235 in Residual U at Framatome Cogema Fuels Wet Weather Stream

ML20151W801
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Issue date:	09/04/1998
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References
C98-01, C98-1, NUDOCS 9809160102
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Calculation of Activity Ratio of Total Uranium to Uranium-235 in Residual Uranium at Framatome Cogema Fuels Wet Weather Stream

Background

A radiological survey was performed during March of 1998 in the area known as the Wet Weather Stream on the Framatome Cogema Fuels' (FCF) Lynchburg Manufacturing Facility site in Lynchburg, Virginia. The results of the survey, which are documented in a Survey Report (ABB 1998), identified residual low-enriched uranium contamination.

Twenty soil / sediment samples were collected as pan of the survey. These samples were split in the field and one set of splits was provided to a U.S. Nuclear Regulatory Commission (NRC) inspector for independent evaluation. The NRC submitted the samples to the Oak Ridge Institute for Science and Education (ORISE) for alpha spectroscopy and gamma spectroscopy analyses. On May 18,1998, ORISE submitted a report (ORISE 1998) to the NRC summarizing the results of the analyses. A copy of the report was also forwarded to FCF by the NRC and is included as Attachment I to this calculation.

Obiectives The objectives of this calculation are to: 1) determine the average ratio of total uranium activity to Uranium-235 activity in the residual low-enriched uranium present in the Wet Weather Stream; and 2) revise Table 6-2 of the March 1998 Survey Report (ABB 1998) to reflect the calculated ratio.

9809160102 980908 PDR ADOCK 07001201 C

PDR SiHB Sample alpha spectroscopy data is obtained from the ORISE report (ORISE 1998).

e The data used herein is limited to the reported Uranium-234, Uranium-235, and Uranium-238 activity concentrations.

The specific activity of Uranium-234 Uranium-235, and Uranium-238 are obtained e

from The Radiological Health Handbook (Shleien 1992). The specific activities are as follows:

4

-Uranium-234 1.602 x 10 pCi/ gram l

-Uranium-235 0.4624 pCi/ gram

-Uranium-238 2.984 pCi/ gram 45 Hartford Turnpike, Suite 10. Vernon, CT 06066. (860) 533 1334 e

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Solution Table I repons the activity concentrations of Uranium-234, Uranium-235, and Uranium-238 in each sample collected, as determined by ORISE alpha spectroscopy analyses (ORISE 1998). Total uranium activity concentrations reported in Table I are calculated by summing the reponed Uranium-234, Uranium-235, and Uranium-238 activity concentrations. As such, the total uranium concentrations reported in Table I may differ slightly from those reported by ORISE due to round-offerror. The propagated error associated with total uranium concentrations is calculated by the following formula:

It should be noted that all propagated errors reponed herein are bcsed only on counting statistics.

I

% = h(%,,)' + (%,,)' +(%,,)*

Where:

om a error in the total uranium activity concentration oAx a error in activity Concentration of the uranium x isotope Uranium-235 mass enrichments are also reponed for each sample. The Uranium-235

^

mass enrichments and associated errors are calculated using the following equations:

2" E% =

x100%

_M2x+M,+M u

u Mu=(A2y)(SA u) 2 2

M33 = (A33)(SA33)

M, =(A,)(SA,)

3 u

3 Where:

E% e percent Uranium-235 mass enrichment M, a mass of the uranium x isotope Ax e activity concentration ofuranium x isotope SA, e specific activity of the uranium x isotope l

45 Hanford Turnpike, Suite to, Vernon, CT 06066. (860) 533-1334 l

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t i

i

^

I

-2

- "2 1

(o,"')(SAus) *+

2n

_(M x + Mus + M,)2, M2u + M33 + M,

2 3

3, y

-2

- (o,,,,)(SA2x) '+

x100%

2" om=

_(M2u + M33 + M2n ),..

j

% )(SAus)

_(M2x + Mus + M,)2 3

i.

i.

Where:

. om a error in percent Uranium-235 mass enrichnient l

M = mass of the uranium x isotope.

l sax = specific activity of the uranium x isotope i

oAx E error in MClivity concentration of the uranium x isotope The ratio of total uranium to Uranium-235 activity concentration is also reported for each j

sample. Figure I is a plot of the ratio of total uranium to Uranium-235 activity concentration as a function of Uranium-235 mass enrichment. Review of the plot indicates that the activity ratio for samples with enrichments greater than 1% and less than 3% appear to decrease slightly with increasing enrichment, but are approximately

. equal. In addition,'at enrichments less than 1% the ratio mcreases rapidly with i

decreasing enrichment.-

1 Based on information presented in the ORISE report (ORISE 1998), the alpha spectroscopy results for sample "HS-B3-2 Inside" are suspect. The first two (i.e.,

I leftmost) data points on Figure I represent, values obtained from two duplicate alpha spectroscopy analyses that ORISE performed on sample "HS-B3-2 Inside", and did not

{

agree with each other. The Uranium-238 concentration determined by ORISE gamma F

spectroscopy analysis on the'same sample did not agree with either alpha spectroscopy result. In addition, the percent enrichments associated with the two alpha spectroscopy analyses, 0.27 +/- 0.08 % and 0.37 +/- 0.14 %, are indicative of depleted uranium which, according to FCF, was never discharged to the Wet Weather Stream. Considering these i

facts, alpha spectroscopy data for this sample are assumed to be invalid and, therefore are not used to determine the average ratio of total uranium to Uranium-235 activity

(-

' concentration.: All other alpha spectroscopy data is used in the calculation of the average

' ratio.

45 Hartford Turnpike, Suite 10, Vemon, CT 06066. (860) 533-1334 l

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Figure I 80

+-dets point excluded from everego 70 -

~

+-dels point suckaded from everage 2

=

5 h

50 -

o 2

E b 40 -

E s

A AA

~

Av.repe noio. m 1

Y W k"s

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l I

20 4

0.0 0.5 1.0 1.5 2.0 25 3.0 j

Uranium-235 Mass Enrichment (%)

1 Total uranium activity concentrations reported in Table 6-2 of the March 1998 Survey Report (ABB 1998) were inferred from Uranium-235 activity concentration measurements assuming a total uranium to Uranium-235 activity ratio of 25. This ratio is 1

based on data reported in ANSI Guide N13.22 for uranium enriched in the Uranium-235 '

i isotope to approximately 4% by mass (ANSI 1995). Based on the ratio calculated herem for the residual uranium in the Wet Weather Stream, the total uranium activity concentrations reported in Table 6-2 of the Survey Report (ABB 1998) are underestimated by a factor of approximately 1.3 (i.e.,33 + 25). Table 6-2 has been l

revised to reflect the calculated ratio of 33 and is included in this calculation.

l 45 Hartford Turnpike, Suite 10, Vernon, Cr 06066 (8(0)533-1334

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i Conclusions The average ratio of total uranium activity to Uranium 235 activity in the residual low-enriched uranium present in the Wet Weather Stream of the Framatome Cogema Fuels Lynchburg Virginia site is 33. This ratio is based on ORISE alpha spectroscopy analyses of samples collected in the Wet Weather Stream on March 25-26,1998. Table 6-2 of the March 1998 Survey Report (ABB 1998) has also been revised to reflect the calculated ratio.

45 Haitford Turnpike, Suite 10, Vernon, CT 06066 (8(o) 533-1334

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Tabie l l@

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p Wet Weather Stream Soil Sample Results (g)

NpS a

NRC (ORISE) Alpha Sp.Gv upy Data m

o U-234 U-236 u-238 U-Tatal U-236 Mass Activty Reno E

' a sen e 10 (pcuorem)

(pcueram)

(ocvgram)

(pCugram)

Enrictunert (%)

U4ctavU236 g

HS-832 Inside (firet)'4 289 +/- 0.33 n14 4 0.04 8.08 +/- 0.91 10.89 +/- 0.97 027 +/- 0.08 77.8

(*)

,,'PI -

g, HS-83-2 ineido (escond)'"

208 +/- 0.28 0.11 +/- 0.04 4.58 +/- 0.53 6.77 +/- 0.5 0.37 +/- 0.14 61.5 E"

HS-BN2 Odesde 13.9 +/- 1.7 G70 +/- 0.15 9.67 +/- 121 2427 +/- 2.N 1.1140.27 34.7

'm HS-83C31 Oweede 45.6 +/- 5.5 212 4 0.34 18.6 +/- 23 88.32 +/- 5.97 1.74 +/- 0.35 31.3 M

E,c HS-83C3-1 Inside 38.5 +/- 4.0 1.S3 +/- 0.21 14.6 +/- 1.6 -

52.63 +/- 4.31 1.80 +/- 02 34.4 2

1 HS-E3-1 Inside 25.6 +/- 28 1.03 +/- O.15 8.34 +/- 0.93 34.97 4 295 1.88 +/- O.34 34.0

'f P

HS-E3-1 Outside 19.0 +/- 21 0.79 +/- 0.12 5.83 +/- 0.88 25.62 +/- 220 208 +/- O.38 32.4 g

g T-9 40.644.5 1.SS +/- 0.22 10.7 +/- 12 5288 4 4.88 221 4 0.39 33.9 mi es l

V-12 23.2 +/- 25 0.98 +/- 0.14 5.95 +/- 0.67 30.11 +/- 250 144 +/- 0.44 31.4 d

d V-8 18.6 +/- 20 0.78 +/- O.12 5.32 +/- 0.61 24.7 4 209 222 4 0.42 31.7 p

L-3 1.54 +/- 0.21 0.08 +/- 0.03 1.00 +/- O.15 2640.28 0.92 4 0.48 43.3 Q-7 35.5 +/- 3.9 1.33 +/- 0.18 9.45 +/- 105 48.2B 4 4.04 213 +/- 0.37 34.8 HS-C3-2 Outside 20.2 +/- 22 031 +/- 0.14 8.10 +/- 0.91 29.21 +/- 238 1.71 +/- O.32 32.1 k.

sq HS-C3-2 inside 10.3 +/- 1.2 0.44 +/- 0.09 5.48 +/- 0 85 16.241.37 1.23 +/- 029 38.8 HS-R7-1 Inside 125 +/- O.16 0.0B +/- 0.03 1.13 +/- 0.15 246 +/- 0.22 1.09 +/- 0.43 30.8 A

HS-R7-1 OWeide 62.5 +/- 7.6 271 +/- 0.43 15.5 +/- 20 80.71 4 7.87 264 4 0.53 29.8 h

HS-TB-1 Outside 84.9 +/- 9.2 3.49 +/- 0.45 18.0420 106.39 4 9.43 292 +/- 0.48 30.5 HS-TB-1 Inside 222 +/- 25 0.8040.16 5.14 +/- 0.64 2B.14 4 2.2 235 4 0.54 35.2 v

O HS-V11-1 Inside 1.95 +/- 024 0.10 +/- 0.03 1.44 +/- O.19 3.4940.31 1.0840.35 34.9

[

HS-86-1 84.0 +/- 9.4 3.30 +/- 0.48 19.9 +/- 23 1072 4 92 251 4 0.45 32.5 I

N HS-R9-1 37.9 +/- 4.1 1.6340.22 9.42 +/- 105 48.95 +/- 424 261 4 0.45 30.0 6

Average 33 b

• Errore are beoed on counhng etsbetics and are reported at the 95% confidence level m Ratios not included m everage because semple reeute are suspect i

o g m

? %

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Revised Table 6-2 Affected Area Grid Center Measurements Average Total Grid Uranium-235 Total Uranium Uranium Identifier (pCi/ gram)

(pCi/ gram)

Concentration (pCi/ gram)

Concentration MDC Concentration MDC B1 0.19 +/- 0.04 0.21 6.1 +/- 1.2 6.9 6.1 B2 0.08 +/- 0.03 0.21 2.5 +/- 1.0 7.0 2.5 B3 1.28 +/- 0.20 0.26 42.2 +/- 6.6 8.6 43.2 C2 0.21 +/- 0.11 0.19 7.0 +/ 3.8 6.2 7.0 i

C3 0.95 +/- 0.17 0.24 31.3 +/- 5.7 8.1 31.7 i

D2 0.13 +/- 0.09

0. I 6 4.4 +/- 2.9 5.2 4.4 D3 0.54 +/- 0.15 0.22 17.7 +/- 4.8 7.4 17.7 E2 0.11 +/- 0.10 0.22 3.7 +/- 3.3 7.3 3.7 E3 0.27 +/- 0.14 0.24 8.9 +/- 4.8 7.8 9.2 F2 0.10 +/- 0.11 0.19 3.2 +/- 3.7 6.2 3.2 F3 0.13 +/- 0.14 0.24 4.4 +/- 4.7 7.8 4.4 G2 0.27 +/- 0.14 0.23 8.7 +/- 4.7 7.7 8.7 G3 0.11 +/- 0.14 0.24 3.5 +/- 4.6 7.8 3.5 H2 0.10 +/- 0.11 0.19 3.2 +/- 3.5 6.2 3.2 H3

0. I1 +/- 0.14 0.23 3.8 +/- 4.5 7.6 3.8 13 0.09 +/- 0.09 0.19 2.9 +/- 2.9 6.1 2.9 J3 0.86 +/- 0.16 0.22 28.4 +/- 5.1 7.3 28.4 K3 0.10 +/- 0.12 0.21 3.3 +/- 4.1 6.9 3.3 L3 0.08 +/ 0.08 0.13 2.7 +/- 2.6 4.4 2.7 L4 0.10 +/- 012 0.21 3.2 +/- 4.0 6,8 3.2 M3 0.18 +/- 0.14 0.23 5.8 +/- 4.5 7.5

5. 8 M4 0.48 +/- 0.15 0.23 15.9 +/- 4.8 7.7 15.9 N4 0.28 +/- 0.12 0.20 9.3 +/- 4.1

6. 6 9.3 N5 0.23 +/- 0.11

0. I 7 7.4 +/- 3.6 5.7 7.4 04 0.24 +/- 0.03 0.19 7.9 +/- 1. I 6.2 7.9 05 0.41 +/- 0.13 0.21 13.7 +/- 4.4 6.9 13.7 06 0.09 +/- 0.12 0.20 2.8 +/- 3.9 6.5 2.8 P4 0.13 +/- 0. I 1 0.20 4.3 +/- 3.6 6.7 4.3 P5 0.48 +/- 0.15 0.24 15.7 +/- 4.9 7.9 15.7 P6 1.17 +/- 0.16 0.21 38.6 +/- 5.2 6.9 38.6 i

P7 0.23 +/- 0.11 0.19 7.7 +/- 3.8 6.1 7.7 j

• Errors reported at the 95% confidence level 45 Hartford Turnpike, Suite 10, Vemon, CT 06066. (860) 533-1334

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Revised Table 6-2 continued Affected Area Grid Center Measurements Average Total Grid Uranium-235 Total Uranium Uranium Identifier (pCi/ gram)

(pCi/ gram)

Concentration i

Concentration MDC Concentration MDC Q4 0.34 +/- 0.04 0.22 11.2 +/- 1.5 7.4 11.2 QS

0. I6 +/- 0. I5 0.25 5.3 +/- 5.0 8.3 5.3 Q6 0.77 +/- O.17 0.25 25.3 +/- 5.4 8.2 25.3 Q7 1.78 +/- 0.19 0.22 58.7 +/- 6.3 7.1 58.7 R5 0.27 +/- 0.I1

0. I 8 9.0 +/- 3.7 5.9 9.0 R6 1.17 +/- 0.I7 0.22 38.6 +/- 5.6 7.2 38.6 R7 1.95 +/- 0.22 0.26 64.4 +/- 7.4 8.5 64.4 R8 2.03 +/- 0.19 0.19 67.0 +/- 6.4 6.3 67.0 R9 0.30 +/- 0.15 0.24 9.9 +/- 4.9 8.0 10.4 SS 0.27 +/- 0.12 0.20 8.7 +/- 4.0 6.5 8.7 S6 1.94 +/- 0.20 0.24 64.0 +/- 6.7 7.8 64.8 57 0.92 +/- 0. I6 0 22 30.4 +/- 5.2 7.4 30.4 S8 1.41 +/- 0.18 0.23 46.5 +/- 5.8 7.5 46.5 S9 1.17 +/- 0.15 0.20 38.6 +/- 5.0 6.6 38.6 S10 0.93 +/- 0.15 0.21 30.7 +/- 5.0 6.8 30.7 T5 0.40 +/- 0.15 0.23 13.1 +/- 4.8 7.6 13.1 T6 2.25 +/- 0.22 0.25 74.3 +/- 7.2 8.2 74.3 T7 0.91 +/- 0.14 0.22 29.9 +/- 4.5 7.4 29.9 T8 1.59 +/- 0.20 0.24 52.5 +/- 6.6 8.1 52.5 T9 0.94 +/- O.16 0.23 30.9 +/- 5.2 7.4 30.9 T10 1.56 +/- 0.19 0.25 51.5 +/- 6.3 8.3 51.5 Tl1 0.77 +/- 0.14 0.20 25.3 +/- 4.7 6.6 25.3 U5 0.11 +/- 0.11 0.20 3.5 +/- 3.8 6.5 3.5 U6 1.00 +/- 0.17 0.25 32.9 +/- 5.6 8.1 32.9 U7 1.52 +/- 0.18 0.22 50.2 +/- 5.8 7.3 50.2-US 1.14 +/- 0.17 0.24 37.6 +/- 5.6 7.9 37.6 U9 1.31 +/- 0.18 0.24 43.2 +/- 5.9 8.0 43.2 U10 1.26 +/- 0.17 0.24 41.6 +/- 5.7 7.8 41.6 U11 1.29 +/- 0.19 0.26 42.6 +/- 6.2 8.4 42.6 U12 0.65 +/- 0.14 0.21 21.5 +/- 4.6 6.8 21.5

• Errors reponed at the 95% confidence level 45 Hartford Turnpike, Suite 10, Vernon, CT 06066 e (860) 533-1334

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Date: '7A#97 9 of10 Checked B Page Number CABHEHA bERVICE:S, bC.

Revised Table 6-2 continued Affected Area Grid Center Measurements Average Total Grid Uranium-235 Total Uranium Uranium Identifier (pCi/ gram)

(pCi/ gram)

Concentration j

(pCi/ gram)

Concentration MDC Concentration MDC V6

0. 89 +/- 0. I 8 0.27 29.4 +/- 6.0 8.9 29.4 V7 0.93 +/- 0.17 0.24 30.5 +/- 5.6 7.9 30.5 i

V8 0.66 4/- 0.14 0.22 21.8 +/- 4.7 7.1 21.8 i

V9 0.43 +/- 0.15 0.23 14.0 +/- 4.9 7.7 14.0 VIO 0.48 4/- 0.13 0.19 16.0 +/- 4.1 6.3 16.0 Vil 0.82 +/- 0.17 0.25 27.1 +/- 5.6 8.2 27.5 V12 0.83 +/ 0.15 0.21 27.5 +/- 5.0 7.1 27.5 W6 0.35 +/- 0.16 0.26 11.6 +/- 5.3 8.6 11.6 W7 0.91 +/- 0.18 0.27 29.9 +/- 5.8 8.7 29.9 I

W8 0.80 +/- 0.17 0.26 26.2 +/- 5.6 8.5 26.2 W9 0.11 +/- 0.11 0.19 3.5 +/- 3.7 6.4 3.5 W10 0.14 +/- 0.11 0.19 4.5 +/- 3.7 6.4 4.5 X6 0.16 +/- 0.11 0.18 5.1 +/- 3.7 6.1 5.1 X7 0.16 +/- 0.10 0.16 5.1 +/- 3.2 5.2

5.1 Averages

0.66 +/- 1.11 0.22 21.8 +/- 36.7 7.2 21.8 +/- 36.8 l

• Errors reported at th: 95% confidence level l

f 45 Hartford Turnpike, Suite 10, Vernon, CT 06066 (860) 533-1334

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References:

ABB 1998 RadiologicalSurvey Report, Wet Weather Stream Survey, Lynchburg ManufacturingFacility, Lynchburg, Virginia, ABB Environmental Services of Michigan, Inc., dated April 1998.

ANSI 1995 Appendix C to BioassayProgramsfor Uranium, American National Standard, ANSI HPS N13.22-1995, Health Physics Society, dated October 1995.

ORISE 1998 Letter report from D. Condra (ORISE) to D. Seymour (NRC), Analytical Resultsfor SoilSamples Collectedfrom Framatome Cogema Fuels, Lynchburg, Virginia, March 25-26,1998 (RFTA No. 98-12), dated May 18,1998.

Shlelen 1992 The Health Physics and Radiological Health Handbook, Revised Edition, B. Shleien, dated 1992.

45 Hartford Turnpike, Suite 10, Vernon, Cr 06066 * (8(4)533-1334

i b BRERA ERVICES, INC.

45 Hartford Turnpike, Suite 10

• Vernon,CT 06066

• Phone:(860) 533-1334

• Fax:(860)5334151 l

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Attachment I ORISE Report h

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0848325167 DJOfP D12 PM M B7 '90 10:26 I.

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L OR-ISE oul46udA21550M2001

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. May 18,1998 I

1 Ms.Deborah Seymour U.S. Neelear Regulatory C-Region U.

suii 2900 101 Manetta Sweet, NW i

Atlassa, GA 30323-0199 SUIMECT: ANALYDCAL RESULTS FOR SOIL SAMPLES COLLECMD FROM FRAMA10hGt COGEMA FUELS, LYMCBBURG, VDtGDGAs MARCH 25-26,1998 (RFTA NO. 95-12).

DearMs.Seysaour:

The Envireemental Survey and Site Assesummt Pmeram (RSSAP) of the Oak Ridst lastitute for l

Science and haami (ORISE) aanlyzed 20 soil samples for muniam by alpha spectrometry and sunwas spamrometry. The results ase psesented in Tables I and 2 respectively. U-234 i

conecatrations as determined by aW spectametry ranged from 1.25 to 84.9 pCi/g. U-234 is desenmoed only by alpha spectresnery des to the lack of sigadicant samma -h U-235 cuaseentrations ranged Goso 0.08 to 3 49 pCi/g as determined by alpha wa y and <D 17 in 4.3 pCi/g as detennised by gamuna spacemenstry U 238 r===*ahans ranged from 1.13 to 19.9 pCilg and 1.7 to 24 0 pCi/g as dehwanned by alpha specacenetry and gamma wa, sospectively. The total manimo eaaer'* eases ranged from 2.46 to 107.2 pCi/g.

I All samples appear to contam emnched urannan cacept sample MS-B3-2/msade. Alpha and

. summa, ^ 7 results correlated well for all samples except HS-B3-2/uwide. Sample MS-B3-7/maide. was analyred oeos by semana spectmmetry and twice by alpha @wj. The U-238 cancentrahon for sampic HS-B3-2/sanid.. as detennmed by alpha :--- ^

" y was

'i twice the e=wwmatana as determined by namr=s spectrotnecy for one aliquot and appronnnately four times for a sesend ahquot. Appesently, sample HS-B3-2/mside is

' 7 - _: despite routme saanple procesmag ESSAF's QC procedmes were followed for these analyses. The daily QC and da** rear background for the comming insensmentamos used in the analyses were within acceptable limits.

Tha QC files are available for year soview upon request.

t D. tot tlF.0am amGE.1tNNEnsM D43001)F anomages med opensied h Dek RWye Anasce u=vwimmelm #e W 8 Depeanew aiInessy uhL m l (W Y Q

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-2 1319pg Plcese contact me at (423) 241-3242 or Mark Iwh at (423) 576-3561 with any questions or I

ans-Sinessely, D1 C J-Dale Condra TechakalResources Manager i

e isevey and Site Assessmem Program RDC:did Enclosure sc:

R.Uleck,NRC/NMSSmFFNf1F27 J.Halvorson, NRC/NMSStrWFN/8A23 M.Imnastra,NRC/NMS$mFFN/SDl4 T. Dscher, NRC/ Region II W. Beck, ORISE/ESSAP E. Abelgast, OIUSE/ESSAP T. Viskus, ORISE/ESSAP M. Lahaa, ORISE/ESSAP Filer 708 l

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l 0048325167 9) OFP 523 F77 A.UG.. 07 '98 10:Tl i

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ISOTOPIC UBAMIUM CONCENTRATIONS IN SOIL san 8FLES BY ALPHA SPECTROMETRY FRAMATOME COGEMA FUELS LYNCBBURG,VA

~

NBC U-234 U-235 U-23s TOTAL U wy, l

SS-33-2/IN 2.69

• 0.33' O.14 A 0.04 8.06

• 0.91 10.89

• 0.97 (first analysis)

EB3-2/IN 2.08 i 0.26 0.1120.04 434 r 0.53 6.77i059 (W analysis)

HS-33-2/ OUT 13.9

• 1.7 0.70

• 0.15 9.67

• 1.21 24g

[ 18.6

• 2M @W HS-33C3-Wuu t 45.6 m 3.5 2.12

• 0.34 18.612.2 HS-83C3-1/IN 36.544.0 133*0.21 14.6

• 1.6 M.3 HS-B 1 25.6

• 2.8 1.03

• 0.15 8.34

• 8.93 35.0 a 2.9 i

MS-D-14XTT 19.0

• 2.1 0.79

• 0.12 5.83

• 0.66 23;I

• n T-9 404 A 4.5 1.56

• 0.22 10.7

• 1.2 52.9 A 4.6 V-12 23.2

• 2.5 0.96

• 0.14 5.95

• 0.67 30.1

• 2.6 V6 18.6

• 2.0 0.78

• 0.12 532* 0.61 24.7

• 2.1 L-3 1.54*0.21 0.06

• 0.03 1.00

• 0.15 2.59 A 0.26 HS-C3-2)OUT 20.2

• 2.2 0.91

• 0.14 8.10

• 0.91 293

• 2.4 IIS-C3-2/IN 10.3

• 1.2 0.44

• 0.09 5.46

• 045 16.2

• 1,4 HS-R7-1/IN 1.25 A 0.16 0.08

• 0.03 1.13

• 0.15 2A6 e 0.23 MS-R7-1100T 62.5

• 7.6 2.71

• 0A3 15.5*2.0 80.7

• 7.9 kT8-1/OtTT) 84.9

• 9.2 3 49

• 0.45 180*2.0 (35.4A9.4 HS-NII1N 22.242.5 0 B0

• 0.1G 5.14

• 0.64 28 h l

, MS-V11-1 1.95 A 024 0.10

• 0.03 1.44 A 0.19 3 A8

• 0.31 i

Q-56-1) k.2

• 9[ p 84.0*9.4 3.30

• 0.48 19.9 a 23 l

HS-R9-1 J7.y

• 4.1 1.os = v.12 sat 4105 40.9 A 4.2 l

Q-7 35.5

• 3.9 1.33i0.18 9.45

• 1.05 46.3

• 4 4 "Ueceradaties represent the 955 conhdance lewt. based on tesal iancartalestes.

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,.. -tt 5.,98. doc

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0040325167 DJOFP 512 P28 AUG D7 '90 10:27 i

TABLE 2 CONCElfrRATION OF URANIUM BY GAhDdA SPECTROMETRY IN SOIL SAMPLES FROM FRAMATOME COCEMA FUELS LYNCRBURG,VA NRC Concentrasasa pC1/g

)

samspie no U-230 hans Tk 234 tL2Vi HS-B3-2/IN 2.41

• 0.23' O.1110.04 HS-B3-20UT 16.6

• 1.6 1.2*0.3 HS-B3C3-10UT 15.0

• 1.4 1.1

• 0 3 HS-BX'3-1/IN 14.4

• 1.1 1.6*0.2 RS-E31 6.9*1.2 1.2*03 HS-E3-1 0 VT 64*0.8 0.9*0.1 T-9 12.9

• 1.5 1.7*03 V-12 8.1*1.7 0.8*0.4 V-6 6.8

• 1.3 0.9*03 I-3 1.7i0.7

<0.20

• HS-C3-2017T 7.8*1.4 1.0*03 HS-C3-2/IN 4.8

• 0.9 0.5*0.2 ilC.R71/1N 7.010.6

<*ty HS-R7-1/OUT 20.7

• 1.9 3.4

• 0.5 HS-T8-tKET l

24.0

• 3 3 4340.7 HS-T8-1/IN 6.5e1.2 1.1* 03 HS-Vi1-1 1.8

• 0.9

<0.17 HS-S6-1 23.9 A 20 43*0.5 HS-R9-1 11.3

• 2.0 1.4+0.4 Q-7 11.8

• 1.3 1.9

• 0.3 l

ht. Lib rayseeeet the (d % remMnm r 1r..rJ hand es wiel==cenmat=5.

'MDCis based on 4.65 sigma.

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