ML051730285

E-Mail Dated 06/16/05 Regarding FSS Report 6 - FB-1700-01 Grid 179 Sample

ML051730285
Person / Time
Site:	Maine Yankee
Issue date:	06/16/2005
From:	Whitney M Maine Yankee Atomic Power Co
To:	Buckley J, Roberts M, Bruce Watson NRC/NMSS/DWM/DCB, Division of Nuclear Materials Safety I
References
Download: ML051730285 (9)

Text

1 John Buckley - FSS Report 6 - FB-1 700-01 Grid 179 Sample Page 1 John Buckley-FSS Report 6 - FB-1700-Oi Grid 179 Sample Page 1 I From:

"Mike Whitney" <whitney@ maineyankee.com>

To:

"mark roberts" <mcr~nrc.gov>, njohn buckley" <jtb~nrc.gov>, "Bruce Watson"

<BAW1 @nrc.gov>

Date:

6/16/05 11:31 AM

Subject:

FSS Report 6 - FB-1700-01 Grid 179 Sample Attached is the gamma spec for the concrete sample taken at Grid 179. This shows all the nuclides detected. None were plant derived.

Hopefully this gives you what you need.

Michael A. Whitney Maine Yankee Atomic Power Co.

321 Old Ferry Rd Wiscasset, ME 04578 (207) 721-9137 Brunswick office till 6/23 (207) 882-1349 Wiscasset office after 6/23 (207) 823-9646 Pager (207) 729-7871 Home office CC:

<Packer@myapc.com>, "George Pillsbury' <pillsbury@ maineyankee.com>

• • • • • GA MM A S PE C T RUM A NA LYS I S***

Report Generated On Sample Title Sample Description Sample Identification Sample Type Sample Geometry Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Sample Size

12/09/04 10:02:31 AM

250 mL concrete

XB1700-01-3-C179-VS

conctete

CON

250 mL concrete 3.00 1 -

4096 50 -

4095 1.000 keV 4.948E+002 Gm Sample Taken On Acquisition Started

12/09/04

12/09/04 8:15:00 AM 9:29:10 AM Live Time Real Time 2000.0 seconds 2000.5 seconds Energy Calibration Used Done On Efficiency Calibration Used Done On

11/29/04 4/30/02

Peak Analysis Report 12/09/04 10:02:32 AM Page 2

P E A K A N A L Y S I S R E P O R T Detector Name:

DET2 Sample

Title:

250 mL concrete Peak Analysis Performed on:

12/09/04 10:02:32 AM Peak Analysis From Channel:

50 Peak Analysis To Channel:

4095 Peak ROI ROI No. start end Peak centroid Energy Net Peak Net Area (keV)

Area Uncert.

Continuum Counts M

m 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 142-142-365-470-470-583-669-696-1013-1158-1211-1814-2232-2913-3519-156 156 374 487 487 593 680 707 1025 1170 1223 1827 2246 2927 3535 147.17 151.83 369.96 475.20 481.86 588.66 674.82 701.95 1019.70 1164.92 1217.02 1820.92 2239.19 2921.07 3527.95 74.68

77. 01 185. 98 238.56 241.89 295.24 338.28 351.84 510.58 583.13 609.16 910.86 1119.83 1460.49 1763.69 2.30E+002 2.80E+002 1.21E+002 3.51E+002 1.49E+002 2.25E+002 4.61E+001 3.34E+002 7.09E+001

1. 04E+002 2.41E+002 5.89E+001 5.78E+001

5. 82E+002

4. 69E+001 137.05 152. 91 47.61 203.04 86.48 42.18 34.38

46. 92 27.34 30.12 37.48

25. 93 25.59 48.20 15.16 3.38E+002 2.97E+002 2.08E+002 1.27E+002 9.73E+001

1. OOE+002

1. 04E+002 9.55E+001 4.71E+001

5. 02E+001 4.75E+001 4.21E+001 3.92E+001

7. 69E+000

4. 13E+000 M

n F

= First peak in a multiplet region

= Other peak in a multiplet region

= Fitted singlet Errors quoted at 1.960 sigma

Background Subtract Report 12/09/04 10:02:32 AM Page 3

B A C K G R O U N D S U B T R A C T R E P O R T Detector Name:

DET2 Sample

Title:

250 mL concrete Peak Analysis Performed on:

12/09/04 10:02:32 AM Peak Energy Original Orig. Area No. (keV)

Area Uncert.

Ambient

Background

Backgr.

Subtracted Uncert.

Area Subtracted Uncert.

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 74.68 77.01 185.98 238.56 241.89 295.24 338.28 351.84 510.58 583.13 609.16 910.86 1119.83 1460.49 1763.69 2.30E+002 2.80E+002 1.21E+002 3.51E+002 1.49E+002 2.25E+002

4. 61E+001

3. 34E+002 7.09E+001

1. 04E+002 2.41E+002 5.89E+001 5.78E+001 5.82E+002

4. 69E+001 137.05 152.91 47.61 203.04 86.48 42.18 34.38 46.92 27.34 30.12 37.48 25.93 25.59 48.20 15.16 2.20E+001 8.85E+000 3.08E+001 1.88E+000 1.23E+001 2.33E+000

1. 90E+000 1.63E+000 5.20E-001 9.33E-001 2.30E+002 2.80E+002 9.90E+001 3.42E+002 1.49E+002

2. 25E+002

4. 61E+001 3.34E+002

4. 01E+001

1. 04E+002 2.41E+002 5.70E+001 5.78E+001 5.70E+002 4.69E+001 1.37E+002

1. 53E+002 4.78E+001

2. 03E+002

8. 65E+001 4.22E+001 3.44E+001 4.69E+001 2.75E+001

3. 01E+001 3.75E+001 2.59E+001 2.56E+001 4.82E+001

1. 52E+001 M

m F

First peak in a multiplet region Other peak in a multiplet region Fitted singlet Errors quoted at 1.960 sigma

interference Corrected Activity Report 12/09/04 10:02:33 AM Page 4

N U C L I D E I D E N T I F I C A T I 0 N R E P O R T Sample

Title:

250 mL concrete Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\STDLIB.NLB

...IDENTIFIED NUCLIDES Nuclide Id Name Confidence Energy (keV)

Yield (M)

Activity (pci/Gm

)

Activity Uncertainty K-40 TL-208 PB-212 BI-214

0. 984

0. 733 0.779 0.456 1460.81*

277.35 510.84*

583.14*

763.13 860.37 74.81*

77.11*

87.30 238.63*

300.09 76.86*

79.29 89.80 273.70 387.00 389.10 405.74 454.77 469.69 474.38 609.31*

665.45 703.11 719.86 752.84 768.36 786.10 806.17 821.18 904.25 934.06 964.08 1051. 96 1069.96 1120.29*

1133.66 1155.19 1207.68 1238.11 1280.96 1303.76 10.67 6.80 21.60 84.20 1.64 12.46 10.70 18.00 8.00 44.60 3.41 0.36 0.60 0.27 0.18 0.37 0.41 0.17 0.32 0.13 0.12 46.30 1.57 0.47 0.41 0.13 5.04 0.32 1.23 0.15 0.11 3.21 0.38 0.32 0.29 15.10 0.26 1.70 0.46 5.94 1.48 0.12 1.86614E+001 2.41967E-001 1.82174E-001 1.65900E+000 1.13781E+000 5.12680E-001 5.68905E+001 8.03731E-001 1.05625E+000 1.91285E+000 1.67780E-001 5.42817E-002 1.00920E+000 6.34332E-001 3.07165E-001 3.16758E+001 1.39374E-001 4.75309E-001

Interference Corrected Activity Report 12/09/04 10:02:33 AM

-Page 5 Nuclide Id Energy Name Confidence (keV)

Yield Activity (0)

(pci/Gm )

Activity Uncertainty BI-214 PB-214 RA-226 U-235 0.456 1377.67 1385.31 1401.50 1407.98 1509.23 1538.50 1543.32 1583.22 1594.73 1599.31 1661.28 1683.99 1729.59 1764.49*

1838.36 1847.42 1873.16 1896.30 2118. 55 2204.21 2293.36 2447.86 0.886 53.23 74.82*

77.11*

87.30 241. 98*

295.21*

351. 92*

0.992 186.21*

0.667 89.95 143.76 185.71*

4.11 0.78 1.39 2.49 2.22 0.41 0.36 0.72 0.27 0.34 1.15 0.24 2.88 15.80 0.38 2.04 0.23 0.18 1.17 4.98 0.32 1.56 1.11 6.21 10.50 4.67 7.49 19.20 37.20 3.28 2.70 10.50 54.00 1.19894E+000 4.03638E-001 2.85849E+000 1.950532+000 1.34530E+000 9.28602E-001 8.31198E-001 1.71235E+000 1.04009E-001 1.73153E+000 1.08702E+000 7.88640E-001 1.91089E-001 1.34194E-001 8.35192E-001 5.06959E-002

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance :

1.000 keV Nuclide confidence index threshold =

0.10 Errors quoted at 1.960 sigma

Interference Corrected Activity Report 12/09/04 10:02:33 AM Page 6

INTERFERENCE CORR'ECTED REPORT Nuclide Name Nuclide Id Confidence Wt mean Activity (pci/Gm )

Wt mean Activity Uncertainty X

ANN K-40 TL-208 PB-212 BI-214 PB-214

?

RA-226

?

U-235 X

AM-243 0.972 0.984 0.733 0.779 0.456 0.886 0.992 0.667 1.000 1.866139E+001 1.878398E-001 5.753267E-001 8.581212E-001 8.746752E-001 1.712349E+000 1.040093E-001 1.912847E+000 5.164607E-002 2.658472E-001 1.219996E-001 1.018938E-001 8.351915E-00'1)

U 5.069586E-00

? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.960 sigma U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

P E A K S 12/09/04 10:02:32 AM 50 4095 Peak Energy No.

(keV) 7 338.28 12' 910.86 Peak Size in Counts per Second 2.3028E-002 2.8514E-002 Peak CPS i Uncertainty 74.647 45.50j 4

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.960 sigma

Nuclide MDA Report 12/09/04 10:02:33 AM Page 7

• • • • • • • • • • • t**************************************************************

N UCL I DE M DA RE P OR T***

Detector Name:

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name ANN BE-7

+

K-40 CR-51 MN-54 CO-57 CO-58 FE-59 CO-60 ZN-65 KR-85 Y-88 NB-94 NB-95 ZR-95 MO-99 RU-103 RH-106 CD-109 AG-llOM SN-113 SB-124 SB-125 SB-126 SN-126 CS-134 CS-137 CE-139 CE-144 EU-152 EU-154 EU-155 HG-203

+

TL-208 BI-212

+

PB-212

+

BI-214

+

PB-214

+

RA-226 AC-228 PA-234M TH-234 DET2 250 mL concrete 250 mL concrete C:\\GENIE2K\\CAMFILES\\STDLIB.NLB Nuclide MDA (pci/Gm )

5.72E-002 4.96E-001 7.33E-001 5.09E-001 8.80E-002 5.20E-002 7.97E-002 1.79E-001 9.37E-002/

2.79E-001 1.73E+001 6.63E-002 7.74E-002 8.88E-002 1.28E-001 5.49E-002 6.11E-002 3.70E-0O1 1.76E+000 6.37E-002 7.50E-002 6.19E-002 1.88E-001 6.OOE-002 1.82E-001 9.58E-002 7.77E-002&Z 5.22E-002 3.84E-001 1.54E-001 1.12E-O01 2.14E-001 6.21E-002 7.12E-002 7.40E-OOl 8.45E-002 1.31E-001 1.33E-001 1.32E+000 4.45E-001 1.80E+001 1.22E+000

Nuclide MDA Report 12/09/04 10:02:33 AM Page 8 Nuclide.

Name

+

U-235 AM-241 AM-243 CM-243 Nuclide MDA (pci/Gm )

7.99E-002 2.15E-001 1.03E-001 2.09E-001

+ = Nuclide identified during the nuclide identification

@ = Half-life too short to be able to perform the decay correction