ML19295G795

Revised Final Status Survey (FSS) Report - Phase 2, RR 6100 Isocs Reports Part 2 of 2

ML19295G795
Person / Time
Site:	Zion  File:ZionSolutions icon.png (DPR-039, DPR-048)
Issue date:	08/10/2016
From:	ZionSolutions
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML19295G627	List: ML19295G587 ML19295G611 ML19295G612 ML19295G617 ML19295G621 ML19295G625 ML19295G670 ML19295G674 ML19295G699 ML19295G702 ML19295G705 ML19295G726 ML19295G728 ML19295G734 ML19295G738 ML19295G742 ML19295G747 ML19295G751 ML19295G758 ML19295G764 ML19295G768 ML19295G788 ML19295G791 ML19295G795 ML19295G816 ML19295G818 ML19295G820 ML19295G822 ML19295G826 ML19295G828 ML19295G831 ML19295G837 ML19295G841 ML19295G843 ML19295G846 ML19295G850 ML19295G853 ML19295G855 ML19295G857 ML19295G859 ML19295G863 ML19295G866 ML19295G870 ZS-2019-0090, Revised Final Status Survey (FSS) Report - Phase 2, Release Record - Waste Water Treatment Facility Survey Unit 09100
References
ZS-2019-0090
Download: ML19295G795 (150)

Text

[333]

GA MM A S P E C T R U M A N A L Y S I S

_lename: 5452 iport Generated On tmple Title tmple Description tmpl e Identification tmple Type tmple Geometry iak Locate Threshold iak Locate Range (in channels )

iak Area Range (in channels )

lentification Energ~ Tolerance tmple Size tmple Taken On

quisition Started

_ve Time ial Time iad Time 8/10/2016 4: 24:46 PM B306100BFRWC011GD ST SE. WALL NUMB 11 SHOT 11 3.00 85 -

8192 85 -

8192 10.000 keV 1.000E+OOO SQM 8/10/2016 4:14:44 PM 600.0 s econds 601. 3 seconds 0.21

~

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER DATA VALIDATED DATE!- K- !CJ TIME aoa Ci21t;4.

[334]

!ak Analysis Report tl/ lU /LU l b

'4: L '4:'4b.b'M Page L'.

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

5452 Sample

Title:

B3061 00BFRWC011GD Peak Analysis Performed on:

8/10/2 01 6 Peak Analysis From Channel:

Peak Analysis To Channel:

4 :2 4:46 PM 85 81 92 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) 1 2

3 4

5 6

7 8

9 10 11 12 288-950-1170-1400-1450-2326-2426-3865-4474-4944-5826-7050-305 962 1187 1413 1459 2339 2443 3879 4487 4 955 5853 7064 300.57 954.89 1180.88 1407.31 1454.84 2331. 93 2 436.00 3872. 03 4479.53 4949.93 5841. 54 7056.88 74.80 238.58 2 95.1 3 351.80 363.69 583.15 609.18 968.34 1120. 22 1237.8 2 1460.65 1764. 2 9

= First peak in a multiplet region Other peak in a multiplet region Fitted singlet

• rors quoted at 2.000 sigma (keV)

Area Uncert.

Counts 0.71 0.8 3 0.91

1. 03 0.70 1.18 1.17

1. 21 0.38 0.82

1. 2 7 0.73

1. 98E+00 2 8.51E+001

1. 08E+002 1.15E+002 9.19E+OOO 6.09E+001 1.68E+002

4. 28E+001 3.72E+001 2.46E+001 3.48E+00 2

4. 20E+001

98. 22 43.44 41.1 3 34.49 19.67 22.80

32. 18 18.04 17.04 13.14 39.11 12.96 6.81E+002 1.45E+00 2 9.66E+00 1 6.65E+001 3.88E+001 2.51E+001 2.83E+001 1.32E+001 1.28E+001 7.42E+OOO 7.39E+OOO 0.00E+OOO

[335]

' *************** **************************~*****************************

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

Title:

B306100BFRWC011GD Nuclide Librar:1 Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL. NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV)

( % )

(pCi/SQM )

Uncertainty K-40

1. 000 1460.82

• 10.66 1.8 1770E+007 2.58340E+006 Tl-208 1.000 583.19*

85.00 2.46560E+005 9.69643E+004 Pb-21 2 0.975 115.18 0.60 2 38.63*

43.60 3.99904E+005 2.14088E+005 300.09*

3.30 7.62818E+006 3.14687E+006 Bi-214 0.612 609. 32

• 45.49

1. 2 9840E+006 2.94014E+00 5 768. 3 6 4.89 806.18

1. 26 934.06

3. 11 1120.29*

14.92

1. 204 7 5E+OO 6 5.60876E+005 1155.21

1. 63 123 8.12*

5.83

2. 142 96E+006 1.15810E+006 1280.98

1. 43 1377.67 3.99 1385.31 0.79 1401. 52

1. 33 1407.99 2.39 1509. 2 1

2. 13 1661. 2 7

1. 05 172 9.59 2.88 1764.49*

15.30 1. 722 54E+006 5.49199E+005 1847.43

2. 03 2118.51 1.1 6 Pb-214 0.977 2 41. 99*

7. 2 5 2.40461E+006

1. 28616E+006 2 95.22*

18.42 1.36661E+006 5.62828E+005 351.93*

35.60 8.28383E+005 2.82564E+005 785.96

1. 06

• =Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2.000 sigma

[336]

1cerrerence ~orrecLeu ttCL.LVlLY ~epurL 0/.lU / L U.l O

':I ; L ':I ; ':I O 1:'lVJ 1:'age q

I N T E R F E R E N C E C O R R E C T E D R E P O R T

'****************************************************************** ~****

Nuclide Nuclide Id Name Confidence K-40 X

Ba-133 Tl-2 08 X

Bi-211 Pb-212 Bi-214 Pb-214

1. 000

0. 32 1

1. 000 0.999 0.975 0.612 0.977 Wt mean Activity (pCi/SQM) 1.817703E+007 2.465604E+005 2. 562 870E+005

1. 3 908 21E+006

9. 25 1154E+005 Wt mean Activity Uncertainty 2.58 33 96E+006 9.696428E+004 2.188645E+005 2.3058 38E+005 2.541274E+005

? = 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 2.000 sigma

[337]

• : ***'~****

U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

0/.l.U/ L U.l. O P E A K S 8/10/2016 85 81 92 Peak CPS

':I ; L ':I ; ':IO

.t:'lVJ 4: 2 4:46 PM Peak No.

Energy (keV)

Peak Size in Counts per Second

'6 Uncertainty Peak Type 1

74.80 3.2993E-001 49.61 Tol.

5 363.69

1. 5321E-002 213.97 Tol.

8 968.34 7.1391E-002 42.12 Sum M

First peak in a multiplet region m = Other peak in a multiplet region F

Fitted singlet Errors quoted at 2.000 sigma Tol.

Nuclide Pb214-XR Ba-133 Pb212-XR Pb212-XR Pb214-XR Zr-97 Ba-133 Eu-152

[338]

lC.llae MUA KeporL 0 /.l U/ L U.lO rage o

'***~ *************************1**** ***** ************* * *************************

N U C L I D E M DA R E P O R T

+

Detector Name:

5452 Sample Geometry:

Sample

Title:

B306100BFRWC0l1GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Name K-40 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-113 Cs - 134 Cs-137 Eu-1 52 Energy (keV) 1460.82

• 32 0.08 834.85 810.76 1173.23 1332.49 702.65 871. 09 255.1 3 391.70 475. 3 6 563. 2 5 569.33 604.72 795.86 801. 95 1038.61 1167.97 1365.19 661. 66 121. 7 8 244.70 295.94 344.28 367.79 411. 12 443.96 488.68 563.99 586.26 678.62 688.67 719.35 778.90 810.45 867.37 919. 33 964. 0 8 1 085.87 1089.74 1112.07 12 12.95 Yield

( ~)

10.66 9.91 99.98 99.45 99.85 99.98 99.81 99.89 2.1 1 64.97

1. 48 8.34 15.37 97. 62 85.46 8.69 0.99

1. 79 3.02 85.10 28.67 7.61 0.45 2 6.60 0.86 2. 2 4 2. 83 0.4 2 0.49 0.46 0.47 0.86

0. 2 8 12.96 0. 32

4. 26 0.43 14.65

10. 2 4

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/SQM )

(pCi/SQM )

Activity (pCi/SQM) 1.156E+006 1.558E+006 1.504E+005 1.799E+005

1. 62 9E+005 1.575E+005 1.695E+005

1. 670E+00 5 8.507E+006 2. 350E+005 1.007E+007

1. 773E+006 9.731E+005 2.589E+005

1. 849E+005 1.853E+006 1.562E+007 9.360E+006 4.692E+006 1.971E+005 7.025E+005 2.418E+006 4.414E+007 5.779E+005 1.912E+007 7.243E+006 5.460E+006 3.736E+007 2.958E+007

4. 2 44E+007 3. 2 66E+007 1.758E+007 5.615E+007 1.196E+006 5.606E+007 3.663E+006 3.703E+007 1.433E+006

1. 331E+006 8.655E+006 1.0 3 6E+006 1. 33 6E+007 1.16E+006 1.56E+006 1.50E+005 1.80E+005 1.58E+005

1. 67E+005 2.35E+005 1.85E+005 1. 97E+005 5.78E+005

1. 818E+007 4.352E+005

- 1. 061E+005 7.908E+004

-4.463E+004

1. 3 97E+005

-1.326E+003

-3.368E+004

-2.094E+006

-1. 212E+005

- 7.620E+006 1.706E+006

-2.089E+005

-5. 572E+004

1. 450E+005 1.167E+005

-7. 250E+006 5.107E+006

-4.016E+006 5.015E+004

- 6.385E+005 3.279E+005 6.471E+007

-2.528E+005

-5.671E+006 6.260E+006

-2.688E+005 1.373E+007 1.304E+007 2.606E+007

1. 462E+007

-3.777E+006

1. 556E+007 7.807E+005 4.075E+007

-5.740E+006

-1.972E+007

-1.404E+005

-1.182E+006

4. 2 31E+006

-3.184E+005

1. 412E+006 Dec. Level (pCi/SQM )

5.074E+00 5 7.457E+00 5 6.959E+004 8.440E+004 7.476E+004

7. 1 63E+004 7.960E+004 7.773E+004 4.1 17E+006 1.118E+005 4.756E+006 8.315E+005 4.567E+005

1. 24 6E+005 8.603E+004 8.634E+005 7.175E+006 4.307E+006 2.106E+006 9.272E+004 3.4 37E+005 1.172E+006 2.137E+007 2.760E+005 9.144E+006 3.451E+006 2. 5 89E+006

1. 7 68E+007 1.386E+007 2.020E+007

1. 52 6E+007 8.200E+006 2.621E+007 5.564E+005 2.631E+007 1.697E+006

1. 713E+007 6.751E+005 6.023E+005 3.954E+006 4.705E+005 6.201E+006

[339]

lC.llcte MlJA r<.eporc

'/j/ _LU /L U.L t>

4: L q:q /

l:'ivl

.!:"age Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

('.?;)

(pCi/SQM

) (pCi/SQM )

(pCi/SQM

)

(pCi/SQM

)

Eu-152 1249.94 0.19 9.450E+007 5.78E+005 7.487E+007

4. 359E+007 1299.14

1. 63 l.031E+007

-2.949E+006 4.719E+006 1408.01

21. 07 6.601E+005

-2.548E+005 2.950E+005 1457.64 0.50 1.012E+008 3.921E+0 08 4.913E+007 1528.1 0

0. 28

4. 214E+007 1. 281E+007 1.832E+007 Eu-154 123. 07 40.40 5.065E+005 4.48E+005

1. 785E+00 5 2.479E+005 247.93 6.89 2.545E+006

- 1. 989E+006

1. 232E+006 591.76 4.95 2.878E+006

-4.173E+005

1. 344E+006 692.42

1. 78 9.170E+006 2.520E+006

4. 2 98E+006 723.30 20.06 9.0 42 E+005

1. 327E+005

4. 2 61E+005 756.80 4.52 3. 218E+006

-7.111E+006 1.491E+006 873.18 12.08

1. 372E+006 2.922E+005 6.384E+005 996. 2 9 10.48

1. 686E+006 l.499E+006 7.840E+005 1004.76 18.01

9. 22 0E+005

-2.560E+005

4. 26 6E+005 1274.4 3 34.80 4.484E+005

-2.967E+005 2.042E+005 1596.48

1. 80 7.179E+006

-5.045E+006

3. 146E+006 Eu-155 45.30

1. 31 1.042E+007 7.75E+005

1. 869E+006

5. 043E+006

60. 01

1. 22

1. 4 66E+007

5. 007E+005 7.150E+006 86.55 30.70 7.754E+005 6.135E+005 3.806E+005 105.3 1 21.10 1.036E+006

-2.875E+005 5.079E+005

+

Tl-208 583.19*

85.00

1. 217E+005

l. 22E+005 2.466E+005 5.536E+004 Bi-211 351.07*

13.02

9. 337E+005 9.34E+005 2. 2 65E+006 4.401E+005 Pb-211 404.85 3.78

4. 2 35E+006 4.23E+006 -2. 322E+006 2.017E+006 427.09

1. 76 8.661E+006

-9.084E+006 4.109E+006 832.01 3. 52 4.377E+006

-8.538E+005 2.0 2 9E+006 Bi-212 39.86

1. 06

1. 267E+007 2.61E+006 l.271E+007

6. 132E+006 727.33 6. 67 2.612E+006 1.337E+006

1. 227E+006 785.37 1.10 1.391E+007 6.314E+006 6.461E+006 1620.50

1. 4 7 9.084E+006 1.518E+006 3.994E+006

+

Pb-~ 12 115.18 0.60 3.476E+007 3.17E+005 7.067E+006 1.701E+007 238.63*

43.60 3.167E+005 3.999E+005 1.520E+005 300.09*

3.30

4. 2 97E+006 7.628E+006 2.053E+006 Pb212-XR 74.82 10.28 2.514E+006 l.46E+006 5.886E+004

1. 23 6E+006

77. 11 17.10 1.458E+006

- 6.128E+005 7.161E+005 87.35 3.97 5.972E+006 2.084E+005 2.931E+006 89.78

1. 46 1.602E+007

-7.908E+006 7.863E+006

+

Bi-214 609. 32

• 45.49 2.643E+D05 1.11E+005

1. 2 98E+006

1. 217E+005 768. 3 6 4.89 3.577E+006 9.337E+005

1. 679E+006 806.18

1. 2 6

1. 2 87E+007 1.490E+006 5.997E+006 934.06 3.11 5.497E+006

1. 342E+006 2.556E+006 1120. 2 9*

14.92

7. 228E+005 1.205E+006 3.175E+005 1155. 21

1. 63 1.061E+007

- 6.506E+006 4.899E+006 1238.12*

5.83

1. 4 72E+006 2.143E+006 6.179E+005 1280.98

1. 43 1.224E+007 3.703E+006

5. 632 E+006 1377.67 3.99 3.863E+006

-5.815E+005

1. 749E+006 1385.31 0.79 1.602E+007

-2.698E+007 7.088E+006 1401.52

1. 33 1.081E+007

1. 640E+006 4.852E+006 1407.99 2.39 5.810E+006

-2. 243E+006 2.597E+006 1509. 2 1 2.1 3 6.552E+006 5.877E+006 2.915E+006 1 661. 2 7

1. 05 1.005E+007

8. 22 4E+005

4. 2 46E+006

[340]

iclide MDA Report tJ/l U/ LUl b 4: L4:4'/ PM

.Page tJ Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) nl (pCi/SQM ) (pCi/SQM )

(pCi/SQM )

(pCi/SQM )

+

Bi-214 1729.59 2.88 4.950E+006 l.11E+005 l.179E+006 2.184E+006 1764.49*

15.30 l.110E+005 l.723E+006 O.OOOE+OO O 1847.4 3 2.03 5.527E+006 3.173E+006 2.33 4E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 241. 99*

7.25

1. 904E+006 3.41E+005 2.405E+006 9.138E+005 2 95. 22

• 18.42 7.698E+005 l.367E+006 3.678E+005 351.93*

35.60 3.415E+005 8.284E+005 1.609E+005 785.96

1. 06 l.435E+007 l.072E+007 6.661E+006 Pb214-XR 74.82 5.80 4.456E+006 2.57E+0 06 l.043E+005 2.191E+006 77.11 9.70 2.570E+006

-1.080E+006

1. 2 62E+006 87.35 2. 2 4 l.058E+007 3.693E+005 5.195E+006 89.78 0.82 2.853E+007

- 1. 408E+007 l.400E+007 Ra-22 6 186. 21

3. 64

5. 2 08E+006

5. 21E+006 3.478E+006 2.537E+006 Ac-228 129.07 2.42 8.560E+006 8.68E+005

4. 1 95E+004 4.189E+006 209.25 3.89 4.590E+006

- 3.132E+006 2. 22 9E+006 270.24 3.46 5.098E+006

-3. 284E+005 2.463E+006 328.00 2.95 5.279E+006 l.1 97E+005 2.526E+006 338.32

11. 27 l.443E+006

-6.829E+005 6.912E+005 409.46

1. 92 8.184E+006 4.770E+005 3.893E+006 463.00 4.40 3.459E+006 2.334E+005

1. 637E+006 794.95 4.25 3.600E+006 9.653E+005

1. 671E+006 911. 20 25.80 8.685E+005

1. 340E+006 4.114E+005 964.77 4.99

4. 2 09E+006 5.181E+006

1. 983E+006 968.97 15.80

1. 2 7 5E+006 l.431E+006 5.991E+005 1588.20

3. 22 4.904E+006

-l.652E+006 2. 205E+006 Pa-23 1 27.36 10.30 7.118E+005 7.12E+005 3.043E+005 3. 348E+005 283.69

1. 70 9.529E+006 4.677E+005 4.584E+006 300.07 2.47 7.143E+006

-1. 463E+006 3.443E+006 302.65 2.2 0 7.816E+006 4.930E+006 3.763E+006 330.06

1. 40 l.087E+007

-4.720E+006 5.197E+006 Th-234 92.38 2.13 1.065E+007 l.06E+007 1.939E+005

5. 22 1E+006 92.80 2.10 1.087E+007 5.933E+006 5.332E+006 112.81

0. 21 9.746E+007

- 9.729E+007 4.770E+007 U-235 143.76 10.96 l.787E+006 3.33E+005 3.253E+004 8.729E+005 163.33 5.08 3.762E+006

-6.793E+005

1. 835E+006 185.71 57.20

3. 32 9E+005 2.601E+005

1. 622E+005 202.11

1. 08 l.676E+007

-2.778E+006 8.144E+006 205.31 5.01 3.510E+006

-3.525E+006 1.704E+006 Am-24 1 59.54 35.90 4.977E+005 4.98E+005

1. 353E+005

2. 428E+005

+

Nuclide identified during the nuclide identification Energy l ine found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been cal cula ted

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

[341]

GA MM A S P E C T R U M A N A L Y S I S

.lename: 54 52

port Generated On tmple Title tmpl e Description tmple Identification tmple Type tmple Geometry iak Locate Threshold

ak Locate Range (in channels )

iak Area Range (in channels )

ientification Energy Tolerance tmple Size tmple Taken On

quisition Started

.ve Time

al Time

ad Time 8/10/2 016 3 : 11: 42 PM B306100BFRWC012GD ST S. WALL NUMB 12 SHOT lMETERS 12 3.00 85 -

85 -

10.000 81 92 81 92 keV 1.000E+OOO SQM 8/10/2016 3 :01: 3 9 PM 600.0 seconds 601.3 seconds

0. 21 %

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER DATA VALIDATED DATEJ-8'-/2 TIME t>S"t~

a.4,,

[342]

'd/ 1.U /.::'. Ul. b

.:; : 1. l. : q L

.l:'M

.!:'age

'** ******* *******************************~************************ *******

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

54 52 Sample

Title:

B306100BFRWC012GD Peak Analysis Performed on:

8/10/2016 3:11:41 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

81 92 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

( keV)

Area Uncert.

Counts 1

113-120 116.42 28.70 0.91 4.05E+001 29.69 6.65E+001 2

2 96-

--306 300.77 74.84 0.75 6.74E+001 68.05 4.56E+002 3

346-358 350.09 87.19 0.88 5.02E+001 62.68 3.53E+002 4

369-376 372.1 3 92.71 0.55

1. 48E+001 43.79 2. 2 9E+002 5

949-960 955. 22 238.66

1. 2 0 5.67E+001 37.87 1.19E+002 6

1172-1188 1180.94 2 95.15

1. 31 8.55E+001 36.75 8.05E+001 7

1399-1416 1407. 2 8 351.79

1. 52

1. 2 9E+002 36.86 6.47E+001 8

2427-2443 2436. 23 609. 2 4

1. 61 1.27E+002

31. 42 3.83E+001 9

3173-3184 3178.02 794.78 0.37 6.23E+OOO 15.12

1. 98E+001 10 3634-3650 3641. 52 910.70

1. 40 5.62E+001 20.41

1. 48E+001 11 5831-5853 5841. 23 1460.57 2.13 3.00E+002 38.90 2.llE+OOl 12 7052-7066 7058.09 1764.60 0.49 3.49E+00 1

16. 2 4 1.0lE+OOl First peak in a multiplet region

= Other peak in a multiplet region

= Fitted singlet

• r ors quoted at 2.000 sigma

[343]

1terterence corrected Activity ~eport

'd/ lU / L Ulb j: 11 : '=IL PM Page j

'*********************~********* ****************************************

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

Title:

B306100BFRWC012GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL. NLB IDENTIFI ED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-4 0 Cs - 13 4 Eu-155 Pb-2 12 Bi-2 14 Pb-214 Ac228-XR

1. 000 0.699 0.3 04 0.975 0. 32 9 0.996 0.392 1460.82*

475.36 563.25 569.33 604.72*

795.86*

801.95 1038.61 1167.97 13 65. 1 9

45. 3 0

60. 01 86.55*

105.31 115.18 238.63*

300.09*

609. 32*

768. 36 806.18 934.06 112 0. 2 9 1155. 2 1 12 38.1 2 1280.98 1377.67 1385. 31 1401. 52 1407.99 1509.21 1661.27 172 9.59 1764.49*

1847.43 2118.51 241.99*

2 95. 22*

351.93*

785.96*

89.96 93.35*

Yield

(:)

10.66

1. 48

8. 3 4 15.37 97.6~

85.46 8.69 0.99

1. 79 3.02

1. 31

1. 22 30.70 21.10 0.60 43.60 3.30 45.49 4.89

1. 26 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79

1. 33 2. 39 2.13

1. 05 2. 88 15.30 2.03 1.16

7. 25 18.42 35.60

1. 06

1. 90 3.10 Activity (pCi/SQM )

1.56803E+007

4. 5 6940E+005 2.94797E+004 2. 62 788E+0 05 2.6653 2E+005 6.01574E+006 9.80578E+005 1.4 32 64E+006

1. 602 65E+00 6

1. 07774E+006 9.35520E+005 2.37673E+006 7.69530E+005 Activity Uncertainty 2.44782E+006

1. 25934E+005 7.15992E+004 3. 32421E+005

1. 83081E+005 2.76358E+006 2.70 33 0E+005 6.75947E+005 1.10027E+006 4.944 3 6E+005 3.05809E+005 5.77408E+006 2. 28474E+006

[344]

1terference Corrected Activity l:{e:i_:,ort

'd/lU/LUlb 3:11:4 L

.l::'JVJ Nuclide Id Energy Yield Activity Activity Name Confidence (keV}

( : }

(pCi/SQM )

Uncertainty Th-231 0.986 25.64

• 14.10 4.61577E+005 3.55760E+005

84. 21*

6.60

1. 2223 6E+006 l.55334E+006 89.95*

1. 00 2.38554E+006 7.06169E+006

• = Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2.000 sigma

.!::'age 4

[345]

1terrerence correctea Activity Keport

'd/.lU/ LUlb 3:1 1 :4L.PM

.Page

'**************** *********************** *******************~****** ******

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/SQM )

Uncertainty K-40

1. 000 l.568027E+007 2.447823E+00 6 X

Cd-109 0.999 X

Ba-133 0.321 Cs-134 0.699 7.714487E+003 7.0 12 483E+004 Eu-1 55 0.304 1.635563E+005 3.408704E+005 X

Bi-211 0.999 Pb-212 0.975 1.073067E+005 1.892603E+005 Bi-214

0. 32 9

1. 028607E+006 2.824881E+005 Pb-214 0.996 9.704163E+0 05 2.623441E+005 X

Th227-XR 0.389 Ac228-XR 0.392

6. 206344E+005 2. 278905E+006 X

Pa-231 0.574 Th-231 0.986 4.615765E+005 3.5084 63E+005

? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysi s Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma U N I D E N T I F I E D p E A K S Peak Locate Performed on:

8/ 10/2 01 6 3 :11:41 PM Peak Locate From Channel:

Peak Locate To Channel:

Peak Energy Peak Size in No.

(keV)

Counts per Second 2

74.84 1.1240E-001 10 910.70 9.3644E- 00 2 M

First peak in a multiplet region m

Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma 85 81 92 Peak CPS Peak

g.

C Uncertainty Type 100.90 Tol.

36. 32 Sum Tol.

Nuclide Pb214-XR Ba-133 Pb212-XR Pb212-XR Pb214-XR

[346]

1c.L1cte MUA r<.eporc

'd/.LU / LU.Lb j :.L.L : 4 L !:'M

!:'age b

N U C L I D E MD A R E P O R T

+

+

Detector Name:

5452 Sample Geometry :

Sample

Title:

B306100BFRWC012GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Name K-40 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-113 Cs-134 Cs-137 Eu-152 Energy (keV) 1460. 82

• 320.08 834.85 810.76 1173.23 1 332.49 702.65 871. 09 255.13 391.7 0 475.36 563.25 569.33 604.72*

795.86*

801.95 1038.61 1167.97 1365.19 661.66 121. 7 8 244.70 295.94 344. 28 367.79 411.12 44 3.96 488.68 563.99 586.26 678. 62 688.67 719.35 778.90 810.45 867.37 919. 33 964.08 1085.87 1089.74 1112.07 12 12.95 Yield

( % )

• 10. 66 9.91 99.98 99.45 99.85 99.98 99.81 99.89 2.11 64.97

1. 48

8. 34

15. 37 97.62 85.46 8.69 0.99

1. 79 3.02 85.10 28.67 7.61 0.45 26.60 0.86 2. 2 4 2.8 3 0.4 2 0.49 0.46 0.47 0.86

0. 2 8 12.96 0.32 4.26 0.43 14.65 10.24

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/SQM )

(pCi/SQM )

1. 665E+006 1.504E+006

1. 620E+005 1.516E+005 1.518E+005 1.371E+005 1.450E+005 1.525E+005 8.193E+006 2.2 71E+005 1.007E+007

1. 718E+006 1.056E+006

1. 399E+005

1. 239E+005

1. 783E+006 1.579E+007

8. 23 4E+006 3.886E+006 1.824E+005 6.742E+005 2.366E+006 3.960E+007 5.885E+005 1.878E+007 6.936E+006 5.108E+006 3.325E+007 2.920E+007 4.183E+007 3.438E+007 1.868E+007 5.375E+007 1.215E+006 4.735E+007 3.600E+006 3.703E+007 1.348E+006 1.528E+006 8.861E+006 1.144E+006

1. 2 91E+007

1. 67E+006 1.50E+006 1.62E+005 1.52E+005 1.37E+005

1. 45E+005 2. 27E+005

1. 2 4E+005

1. 82E+005 5.89E+005 Activity (pCi/SQM )

1. 568E+007

-2.176E+005 8.184E+004 8.664E+004

-1.050E+005 5.819E+004

- 8.046E+004 4.508E+004

1. 288E+006

- 8.357E+004

-2. 275E+006 3.604E+003

-2.698E+005 4.569E+005 2.948E+004

-5.395E+005

- 3. 2 93E+006

-5.032E+006

-2.391E+006 8.583E+004 3.736E+005 2. 25 4E+006 3.393E+007 4.287E+004 1.746E+006 2.956E+006

-4. 203E+006 5.937E+006

-1.728E+007 1.850E+007 1.661E+007

1. 239E+007

- 8.254E+006

-5. 0 62E+005

4. 2 65E+007

-8.392E+005

-2.678E+007

1. 3 78E+006

-8.409E+005

-8.348E+006

-2.469E+006

-5. 213E+006 Dec. Level (pCi/SQM

)

7. 62 0E+005 7.189E+005 7.537E+004 7.022E+004

6. 92 1E+004 6.142E+004 6.735E+004 7. 050E+004 3.960E+006 1.078E+005 4.756E+006 8.044E+005 4.981E+005 6.506E+004 5.553E+004

8. 284E+005 7.258E+006 3.743E+006 1.703E+006 8.533E+004

3. 2 95E+005 1.146E+006 1.910E+007 2.813E+005 8.975E+006 3.297E+006 2.413E+006 1.562E+007

1. 3 67E+007 1.990E+007 1.612E+007 8. 749E+006 2.501E+007 5.656E+005 2.195E+007

1. 666E+006 1.713E+007 6.325E+005 7.011E+005 4.057E+006

5. 24 4E+005 5.980E+006

[347]

1clide MDA Report tl/lU/ L'. Ulb j: ll :4L'. PM Page

"/

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( %)

(pCi/SQM)

(pCi/SQM)

(pCi/SQM )

(pCi/SQM

)

Eu-152 1249.94 0.19 6.897E+007

5. 89E+005

1. 420E+007 3.082E+007 1299.14

1. 63 1.054E+007 2.283E+006 4.836E+006 1408.01

21. 07 7.407E+005 4.466E+005 3.353E+005 1457.64 0.50 9.865E+007 3.661E+008 4.783E+007 1528.10

0. 28 3.542E+007 8.490E+006 1.496E+007 Eu-154 123.07 40.40 4.724E+005 4.60E+005 6.175E+004 2.308E+005 247.93 6.89 2.454E+006 3.626E+005 1.186E+006 591. 76 4.95 3.087E+006

-1.015E+006 l.449E+006 692.42

1. 78 8.823E+006 5.802E+006 4.125E+006 723.30 20.06 7.554E+005

-1.7 39E+005 3.517E+005 756.80 4.5 2 3.048E+006 2.617E+005 1.406E+006 873.18 12.08 l.251E+006 3.001E+005 5.780E+005 996. 2 9 10.48

1. 646E+006 1.559E+005 7.642E+005 1004.76 18.01 9.054E+005

-1.593E+005 4.183E+005 1274.4 3 34.80 4.599E+005

-2. 3 90E+005 2.099E+005 1596.48

1. 80 7.881E+006 2. 214E+006 3.497E+006

+

Eu-155 45.30

1. 31

1. 024E+007 5.40E+005

4. 234E+005 4.953E+006 60.01

1. 22 1.457E+007

-9.991E+005 7.104E+006 86.55*

30.70 5.402E+005 2. 62 8E+005 2.630E+005 105.31 21.10 9.811E+005 5.476E+003 4.802E+005 Tl-208 58 3.19 85.00 2.347E+005 2.35E+005 2.603E+005 1.118E+005 Bi-211 351.07*

13.02 9.973E+005 9.97E+005 2.558E+006 4.719E+005 Pb-211 404.85 3.78 3.944E+006 3.94E+006 6.811E+004

1. 872E+006 427.09

1. 76 9.008E+006 3.068E+006

4. 282E+006 832.01 3.52

4. 522E+006 l.358E+006 2.102E+006 Bi-212 39.86

1. 06 1.203E+007 2.31E+006 - 3.852E+006 5.809E+006 727.33 6.67 2.312E+006 4.488E+005

1. 078E+006 785.37 1.10

1. 538E+007 3.557E+006 7.199E+006 1620.50

1. 4 7 6.077E+006

-6.071E+006 2.491E+006

+

Pb-2 12 115.18 0.60 3.466E+007 2.81E+005 6.201E+006 1.697E+007 238.63*

43.60 2.813E+005 2.665E+005 1.343E+005 300.09*

3.30 3.867E+006 6.016E+006 1.838E+006 Pb212-XR 74.82

10. 28 2.437E+006

1. 40E+006 6.101E+006

1. 1 97E+006 77.11 17.10 1.403E+006 l.156E+005 6.889E+005 87.35 3.97 5.868E+006

4. 224E+006 2.879E+006 89.78

1. 46 1.542E+007

-3.561E+006 7.560E+006

+

Bi-2 14 609.32*

45.49 3.002E+005 3.00E+005 9.806E+005 1.396E+005 7 68. 3 6 4.89 3.535E+006 2.134E+006 1.657E+006 806.18

1. 2 6 1.199E+007

4. 381E+006 5.560E+006 934.06 3.11 5.411E+006 6.103E+005 2.513E+006 1120. 2 9 14.92 1.454E+006 1.189E+006 6.830E+005 1155. 2 1

1. 63

1. 081E+007 3.8 3 6E+006 4.998E+006 1238.12 5.83 3.507E+006 2.709E+006

1. 636E+006 1280.98

1. 43 1.173E+007 7.363E+006 5.376E+006 1377.67 3.99 3.919E+006 3.362E+006

1. 777E+006 1385.31 0.79 1.602E+007

-2.074E+007 7.088E+006 1401.52

1. 33 1.135E+007

-3.766E+006 5.124E+006 1407.99 2.39 6.519E+006 3.930E+006 2.951E+006 1509. 21 2.13

6. 2 81E+006

-2. 23 0E+006 2.779E+006 1661. 2 7

1. 05 1.161E+007 8.080E+006 5.024E+006

[348]

lC.llQe LVIUA r<.eporc

'd/.lU/ L'. Ulb

.,; : 11: 4L'.

.l:'M Page ti Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

(%)

(pCi/SQM )

(pCi/SQM )

(pCi/SQM )

(pCi/SQM

)

+

Bi-214 1729.59 2.88 4.833E+006 3.00E+005 -1. 418E+006 2.125E+006 1764.49*

15. 30 8.625E+005

1. 433E+006 3.757E+005 1847.43 2.03 6.764E+006 2.771E+006 2.953E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 241.99*

7. 25 1.691E+006 3.65E+005

1. 603E+006 8.074E+005 295. 22

• 18.4 2 6.929E+005

1. 078E+006

3. 2 94E+005 351. 93*

35.60 3.647E+005 9.355E+005 1.726E+005 785.96*

1. 06 9.986E+006 2.377E+006 4.477E+006 Pb214-XR 74.82 5.80 4.319E+006 2.47E+006 1.081E+007 2.122E+006 77.11 9.70 2.474E+006 2.039E+005 1.214E+006 87.35 2.24 1.040E+007 7.485E+006 5.103E+006 89.78 0.82 2.745E+007

- 6.340E+006

1. 346E+007 Ra-226 186.21 3.64 5.103E+006

5. 1 0E+006

1. 94 9E+006 2.485E+006 Ac-228 129.07 2.4 2 7.761E+006 8.65E+005 -2.777E+006 3.790E+006 209.25 3.89 4. 448E+006

-2.344E+006 2.157E+006 270.24

3. 4 6 4.765E+006

-1. 673E+005 2. 2 96E+006 328.00 2.95 5.157E+006 2. 223E+006 2.465E+006 338.32

11. 27 1.504E+006 3.583E+005

7. 218E+005 409.46

1. 92 7.909E+006

-2. 102E+00 5 3.756E+006 463.00 4.40 3.757E+006

1. 219E+006

1. 786E+006 794.95

4. 25 3.935E+006 3.211E+006 1.8 39E+006 911.20 25.80 8.647E+005 1.017E+006 4.095E+005 964.77 4.99 3.959E+006 3.1 2 9E+006 1.858E+006 968.97 15.80

1. 253E+006

1. 255E+006 5.881E+005 1588.20 3. 22 5. 22 0E+006 4.262E+006 2. 363E+006 Pa-23 1 27.36*

10.30 7.309E+005

7. 31E+005 6.319E+005 3.443E+005 283.69

1. 70 9.010E+006

-3.303E+006

4. 32 4E+006 300.07*

2.47 5.167E+006 8.037E+006 2.456E+006 302.65 2.20

7. 250E+006

1. 691E+006 3.480E+006 330.06

1. 40 1.135E+007 2.534E+006 5.437E+006 Th-234 92.38 2.13 1.029E+007 1.03E+007 -2.620E+006 5.041E+006 92.80 2.10 1.045E+007 2.101E+006 5.119E+006 112.81 0.21 9.905E+007 3.013E+007 4.849E+007 U-235 143.76 10.96 1.720E+006

3. 2 4E+005 - 1. 808E+005 8.398E+005 163.33 5.08 3.670E+006

7. 397E+005

1. 790E+006 185.71

57. 20

3. 236E+005

4. 252E+004 1.576E+005 202.11

1. 08 1.627E+007

-1.550E+006 7.900E+006 205.31 5.01 3.559E+006 1.728E+006

1. 72 9E+006 Am-24 1 59.54 35.90 4.877E+005 4.88E+005 -5.063E+004 2. 378E+005

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[349]

'***************WWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWW W WWWWWWWWWWWWWW GAMM A S P E C T R U M A N A L Y S I S

• • '\\'**

.lename: 54 52 iport Generated On 1mple Title 1mple Description tmple Identification tmple Type tmple Geometry iak Locate Threshold

!ak Locate Range (in channels )

!ak Area Range (in channels) lentification Energy Tolerance tmple Size tmple Taken On

quisition Started

.ve Time

al Time

• ad Time 9/13/2016 4:49:43 PM B306100BFRWC013GD Steam Tunnel Unit - 1 01 3 1 meter 3. 00 85 -

85 -

10.000 81 92 8192--

keV 1.000E+OOO S meters 9/ 13/20 1 6 4:39:4 0 PM 600.0 seconds 601.6 seconds 0. 27

~

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER DATA VALIDATED DATE/-8-/9 TIME tJ.Qfi" e2414

[350]

ia k Analysis Keport

':1/lj/L'. Ul b 4:4':1:4j PM Page L'.

'*************************** ****** ~***~******** **************************

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

• • • 'l**

Detector Name:

54 52 Sample

Title:

B306100BFRWC0l3GD Peak Analysis Performed on:

9/13/2016 Peak Analysis From Channel:

Peak Analysis To Channel:

4:49:42 PM 85 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Contiriuum No. start end centroid (keV) 1 2

3 4

5 6

7 8

9 10 11 12 13 14 113-286-332 -

949-1176-1401-2 426-2 637 -

3202-3635-3726-4473-5828-7046-118 306 345 960 1188 1415 2444 2 651 3213 3649 3737 4487 5852 7064 115.87 300.53 340.80 954.77 1180.68 1406.85 2435.42 2644.66 3207.66 3641.61 3731. 83 4479.56 5841.17 7055.46 28.56 74.78 84.87 23 8.54 295. 08 351. 68 609.03 661.37 802.19 910.7 2 933.28 1120.23 1460.5 6 1763.94 First peak in a multiplet region

= Other peak in a multiplet region

= Fitted singlet rors quoted at 2.000 sigma (keV )

Area Uncert.

Counts 0.44 0.95 0.62 0.7 2 1.15

1. 30

1. 50 0.37 0.4 2 0.41 0.59 0.5 2 2.06 0.75 1.42E+001 3.09E+002

1. 37E+002 7.86E+001 4.67E+001 1.62E+002 1.61E+002 5.39E+001

-2. 2 9E+OOO 5.17E+001 1.86E+001 6.56E+001 3.02E+002 5.70E+001 20.60 115.25 76.15 42.41 34.00 38.55 33.11 19.78 17.17 16.34 13.37 20.52 42.10 15.10 3.48E+001 8.31E+002 4.73E+00 2 1.48E+002 9.13E+001

7. 22E+001 3. 34E+001 1.51E+001 2.33E+001 5.32E+OOO 1.04E+001 1.34E+001 3.42E+001 O.OOE+OOO

[351]

1terference Corre cted Activity Report 9/13/2 016 4:49:43 PM Page 3

'************************************************* ~*********************

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

• • • '\\**

Sample

Title:

B306100BFRWC013GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Ba-133 Cs-137 Bi-211 Pb-212 Bi-2 14 Pa-2 31

1. 000 0.78 2 1.000 0.999 0.974 0.597 0.575 1460.82*

79.61*

81.00*

276.40 302.85*

356.01*

383.85 661.66*

351.07*

115.18 238.63*

300.09*

609. 32

• 768.36 806.18*

934.06*

1120. 2 9*

1155. 21 1238.12 1280. 98 1377.67 1385.31 1401.52 1407.99 1509. 21 1661. 2 7 17 29.59 1764.49*

1847.43 2118.51 27.36*

283.69 300.07*

30 2.65 330.06 Yield

( % )

10.66 2.65 32.90 7.16 18.34 62.05 8.94 85.10 13.02 0.60 43.60 3.30 45.49 4.89

1. 2 6 3.11 14.92

1. 63 5.83

1. 4 3 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 10.30

1. 70 2.47 2.20

1. 40 Activity (pCi/S me) 1.57806E+007 1.87747E+007 6.68720E+005 5.91566E+005 6.71464E+005 2. 32 932E+005 3.2 0003E+006 3.69098E+005

3. 2 8767E+006

1. 243 03E+006

-7.34680E+005 2.63312E+006 2.12684E+006 2.33743E+006 2. 22 347E+005

4. 392 44E+006 Activity Uncertainty 2.59316E+006 7.96799E+006 3.95590E+005 4.40840E+005 1.92712E+005 8.99372E+004 9.20309E+005 2.07990E+005 2.45085E+006 2.96645E+005 5.51840E+006

1. 90733E+006 6.86610E+005 6.46886E+005 3. 26024E+005 3. 32179E+006

[352]

1terference Corrected Activity Report 9/13/2 016 4 :49:4 3 PM

• = Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2.000 sigma Page 4

[353]

1terference Corrected Activity Report 9/13/2016 4:49:4 3 PM Page 5

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Nuclide Id Name Confidence K-40 X

Co-58 X

Cd-1 0 9 Ba-133 Cs-137 X

Eu-155 Bi-211 Pb-212 Bi-214 X

Pb-214 Pa-2 31 X

Th-231

1. 000 0.889 0.984 0.78 2

1. 000 0.30 2 0.999 0.974 0.597 0.97 6 0.57 5 0.917 Wt mean Activity (pCi/S me )

1.578057E+007 6.17 232 0E+005 2. 32 9318E+005 2.584558E+005 3.64 2 986E+005

1. 5447 21E+00 6 2.135815E+00 5 Wt mean Activity Uncertainty 2.593158E+006 2.952262E+005 8.9937 21E+004 1.680197E+006 2.074 062E+005 2.488393E+005 3. 23 7412E+005

? = 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 2.000 sigma u N I D E N T I F I E D p E A K s Peak Locate PPrf()rmed on:

9/13/2 016 4:49:4 2 PM Pea k No.

10 Peak Peak Energy (keV) 910.7 2 Locate From Channel:

Locate To Channel:

Peak Size in Counts per Second 8.6140E-00 2 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 s igma 85 81 92 Peak CPS

% Uncertainty

31. 62 Peak Type Sum Tol.

Nuclide

[354]

iclide MDA Report 9/13/2016 4: 4 9: 43 PM Page 6

'************** ~*** *****~**************************************************** +*

N U C L I D E M D A R E P O R T

+

+

Detector Name:

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name K-40 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-113 Cs-134 Cs-137 Eu-15 2 Energy (keV) 1 460.8 2

• 32 0.08 834.85 810.76*

1173.23 1332.49 702.65 871. 0 9 255.13 391. 70 475.36 563. 2 5 569.33 604.72 795.86 801. 95 1038.61 1167.97 1365.19 661.66*

121. 78 244.70 295.94 344. 2 8 367.79 411. 12 443.96 488.68 563.99 586. 2 6 678. 62 688.67 719. 35 778.90 810.45 867.37 919. 33 964.08 1085.87 1089.74 1112.07 1212.95 5452 1 meter B306100BFRWC013GD C:\\GENIE2K\\CAMFILES \\ Zion Lib-BNL.NLB Yield

('<;)

10.66 9.91 99.98 99.45 99.85 99.98 99.81 99.89 2.11 64.97

1. 48 8.34 15.37 97.62 85.46 8.69 0.99

1. 79 3.02 85.10 28.67 7.61 0.45 26.60 0.86 2.24 2.83 0.4 2 0.49

0. 46 0.47 0.86

0. 2 8 12.96 0.32 4.26 0.43 14.65

10. 2 4

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/S me ) (pCi/S me )

Activity (pCi/S me )

2.187E+006

1. 700E+006

1. 739E+005

1. 2 82E+005 1.518E+005

1. 489E+005 1.753E+005 1.682E+005 8.507E+006 2.452E+005 1.032E+007

1. 916E+006 9.846E+005 2.622E+005 1.945E+005 2.011E+006 1.529E+007 8.765E+006 4.081E+006

1. 059E+005 7.673E+005 2.466E+006 4.183E+007 6.470E+005 1.923E+007 7.391E+006 5.938E+006 3.736E+007 3.154E+007 4.214E+007 3.221E+007 1.707E+007 5.334E+007 1.099E+006 5.006E+007 3.600E+006 3.534E+007 1.463E+006

1. 656E+006 9.727E+006 1.169E+006

1. 2 45E+007 2.19E+006 1.70E+006 1.74E+005

1. 2 8E+005 l.49E+005 1.68E+005 2.45E+005 1.94E+005 1.06E+005 6.47E+005

1. 578E+007

-4.769E+005 2.160E+004

-9.338E+00 3

-6.935E+004

- 8.158E+004 3. 136E+004 1.804E+004

-3.315E+004

-6.653E+004

-1. 067E+006

-7.382E+005 7.178E+004

-4.672E+004 4.380E+004

-7.450E+004

-1.627E+007 2.047E+006

-6.134E+006 2.329E+005

-9.606E+004

-1.353E+006 1.675E+007

- 1. 619E+005 5.618E+006 6.461E+006 2.112E+006 4.772E+006

- 3.151E+007 6.058E+007 3.978E+005

-7.597E+005

-5.309E+007

-5.403E+005

-2.980E+007

-6.448E+006 2.591E+006 7.884E+005

-3. 232E+005

-6.542E+005

-2.228E+006

-1.111E+007 Dec. Level (pCi/S me )

1. 023E+006 8.168E+005 8.132E+004 5.857E+004 6.921E+004 6.7 2 8E+004

8. 2 49E+004 7.8 3 6E+004 4.117E+006 1.169E+005 4.877E+006 9.031E+005

4. 62 4E+005

1. 2 62E+005 9.083E+004 9.420E+005 7.007E+006 4.009E+006

1. 800E+006 4.7 10E+004 3.761E+005 1.1 96E+006 2.021E+007 3.106E+005

9. 200E+006 3.525E+006

2. 828E+006 1.768E+007 1.484E+007 2.005E+007 1.504E+007 7.944E+006 2.481E+007 5.079E+005 2. 331E+007

1. 666E+006

1. 62 9E+007 6.900E+005 7.650E+005 4.491E+006

5. 370E+005 5.750E+00 6

[355]

1clide MDA Report 9/13/ 2016 4:49:43 PM Page 7

Nuclide Energy Yield Line I1DA Nuclide MDA Activity Dec. Level Name (keV)

(% )

(pCi/S me)

(pCi/S me)

(pCi/S me)

(pCi/S me)

Eu-1 52 1249.94 0.19

7. 27 1E+007 6.47E+005 - 9.732E+007 3.269E+007 1299.14

1. 63 9.697E+006

-2.092E+006 4.415E+006 1408.01

21. 07 8.690E+005 l.622E+005 3.995E+005 1457.64 0.50

1. 006E+008 3.604E+008 4.879E+007 1528.10

0. 2 8

4. 214E+007 3.050E+007 l.832E+007 Eu-154 123.07 40.40 5.485E+005 4.71E+005 - 3. 244E+003 2.688E+005 247.93 6. 89 2. 479E+006

-1. 741E+006 l.199E+006 591.76 4. 95 2.897E+006

-7.565E+004

1. 354E+006 692.4 2

1. 78 8.275E+006

-8.530E+006 3.851E+006 723.3 0 20.06 8.659E+005

-1. 7 l 6E+005 4.069E+005 756.8 0 4.5 2 2.866E+006

-1. 802E+006

1. 315E+006 873.18 12.08

l. 382E+006

- l. 2 98E+005 6.436E+005 996. 2 9 10.48 l.591E+006

- l.418E+006 7.369E+005 1004.76 18.01 l.030E+006 5.386E+005 4.806E+005 1274.4 3 34.80 4.711E+005

-1. 482E+0 05 2.1 55E+005 1596.48

1. 80 7.712E+006

-5.740E+004 3.412E+006 Eu-155 45.30

1. 31 l.210E+007 6.38E+00 5

3. 279E+006 5.886E+006

60. 01

1. 22 l.665E+007

6. 304E+006 8.146E+006 86.55*

30.70 6.384E+005 7.166E+005 3.121E+005 105.31 21.10 l.138E+006 4.089E+005 5.586E+005 Tl-208 583. 1 9 85.00 2.274E+005 2.27E+005 2.862E+005

1. 082E+005

+

Bi-211 351. 07

• 13.02 9.959E+005 9.96E+005 3.200E+006 4.712E+005 Pb-211 404.85 3.78 4.190E+006

4. 19E+006 2.259E+006

1. 995E+006 427.09

1. 76

9. 276E+006

-3. 329E+005 4.416E+006 832.0 1 3. 52 4.730E+006

-1. 628E+004 2.206E+006 Bi-2 12 39.86

1. 06 l.342E+007 2.66E+006 - l.851E+006 6.506E+006 727.33 6.67 2. 655E+00 6 l.376E+006

1. 249E+006 785.37 1.10

1. 380E+007

-7.610E+006 6.405E+006 1620.50

1. 4 7 7.884E+006 2.483E+006 3.395E+006

+

Pb-212 115.18 0.60 3.711E+007 3.10E+005 -2.547E+007

1. 81 9E+007 238.63*

43.60 3.105E+005 3.691E+005 l.489E+005 300.0 9*

3. 30 3.794E+006

3. 2 88E+006

1. 802E+006 Pb2 12-XR 74.8 2 10.28 2.692E+006

l. 51E+006 6.160E+005

1. 325E+006 77.11 17. 10 l.509E+006

- 6.725E+005 7.417E+00 5

87. 35 3.97 6.648E+006

-l.130E+006 3. 2 69E+006 89.78

1. 46

1. 751E+007

-7.614E+005 8.608E+006

+

Bi -2 14 609.32*

45.49 2.922E+005 1.11E+005 l.243E+006

1. 356E+005 768.36 4.89 3.380E+006 2.215E+006

1. 580E+006 806.18*

1. 26 l.009E+007

-7.347E+005 4.608E+006 934.06*

3.11

2. 767E+006 2.633E+006

l. 192E+006 1120. 2 9*

14. 92 7.592E+005 2.127E+006 3.357E+005 1155.21

1. 63 l.061E+007

-4.190E+005 4.899E+006 1238.12 5.83 3.819E+006

1. 025E+006

1. 792E+006 1280.98

1. 43 l.091E+007

l. 521E+005 4.967E+006 1377.67 3.99 3.974E+006

-2.209E+005

1. 804E+006 1385.31 0. 79 l.637E+007

-2.069E+007

7. 263E+006 1401.52

1. 33 l.387E+007 3.395E+006 6.383E+006 1407.99 2.39 7.648E+006 l.428E+006 3.516E+006 1509. 21 2.1 3 5.847E+006

1. 053E+006 2.562E+006 1661. 27

1. 05 1.086E+007

6. 92 6E+006 4.651E+006

[356]

1clide MDA Report 9/13/20 1 6 4:49:43 PM Page 8

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( ~ )

(pCi/S me)

(pCi/S me )

(pCi/S me)

(pCi/S me)

+

Bi - 214 1729. 5 9 2.88 4.714E+006 1. 11E+005 2. 223E+006 2.065E+006 1764.49*

15.3 0 1.110E+005 2. 337E+006 O.OOOE+OOO 1847.43 2.03 6.576E+006 2. 22 6E+006 2.859E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO Pb-214 24 1. 99*

7.25

1. 8 67E+006 3.64E+005 2.219E+006 8.952E+005 295. 22

• 18.42 6.797E+005 5.890E+005 3. 22 8E+005 351. 93*

35.60 3.642E+005 1.170E+006

1. 72 3E+005 785.96

1. 06 1.447E+007 3.793E+006 6.719E+006 Pb21 4-XR

74. 82 5.80 4.771E+006 2.66E+006 1.092E+006 2.348E+006

77. 11 9.70 2.660E+006

-1.186E+006 1.308E+006

87. 35 2. 24

1. 178E+007

-2.003E+006 5.794E+006 89.78 0.82 3.118E+007

-1.3 56E+006

1. 533E+007 Ra-226 186. 2 1 3.64 5.446E+006 5.45E+006 -2.883E+006 2.656E+006 Ac-228 12 9. 07 2.4 2 9.176E+006 7.77E+005 7.370E+006 4.497E+006 209. 25 3.89 4.751E+006

- 3. 239E+006 2. 309E+006 270. 2 4 3. 46 4.971E+006

- 2.500E+006 2. 399E+006 328.00 2.95 5.808E+006 2. 204E+006 2.790E+006 338. 32

11. 27

1. 555E+006 9.017E+005 7.475E+005 409.46

1. 92 8.184E+006

-1. 301E+005 3.893E+006 463.00 4.40

3. 2 99E+006

-2.881E+006 1.557E+006 794.95 4.25 3.908E+006 3.739E+005 1.825E+006 911. 2 0 25.80 7.774E+005 6.687E+003 3.659E+005 964.77 4.99 4.318E+00 6 2.411E+006 2.037E+006 968.97 15.80

1. 311E+00 6 9.347E+005 6.171E+005 1588. 2 0 3. 22 5.065E+00 6

-1.313E+006 2.286E+006

+

Pa-23 1 27.36*

10.30 5.344E+005

5. 3 4E+00 5 2. 22 3E+005 2.461E+005 283.69

1. 70 9.737E+006

-9.843E+006 4.688E+006 300.07*

2.47 5.069E+006 4.392E+006 2.407E+006 302. 65 2.20 7.513E+006 8.469E+004 3.612E+006 330.0 6

1. 40 1.175E+007

-3.443E+006 5.637E+006 Th-23 4 92.38 2.1 3 1.166E+007 1.17E+007

8. 62 1E+005 5.7 2 8E+006 92.80 2.10 1.177E+007 2.063E+006 5.780E+006 112.81

0. 21 1.080E+008

-3.024E+007 5.299E+007 U-23 5 143.76 10.96

1. 856E+006 3.51E+005 7.744E+005 9.074E+005 163.33 5.08 3.897E+006 4.424E+006

1. 903E+006 185.71

57. 2 0 3.510E+005 5.028E+004 1. 713E+005 202. 11

1. 08

1. 7 52E+007 8.001E+006 8.525E+006 2 05. 31

5. 01 3.763E+006 1.492E+006

1. 830E+006 Am-241 59.54 35.90 5.547E+005 5.55E+005 2.006E+005 2.713E+005

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[357]

G A M M A S P E C T R U M A N A L Y S I S

_lename: 5 4 52 iport Generated On tmple Title tmple Description tmple Identification tmple Type tmple Geometry iak Locate Threshold iak Locate Range (in channels )

iak Area Range (in channels) ientification Energy Tolerance tmple Size tmple Taken On

quisition Started

_ve Time ial Time 9/13/2016 4:12:09 PM B306100BFRWC014GD Steam Tunnel Unit-1 014 1 meter 3.00 85 -

85 -

10.000 8192 8192 keV 1.000E+OOO S meters 9/13 /2 016 4:02:07 PM 600.0 seconds 601.4 seconds

0. 2 4 %

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER DATA VALIDATED DATE /-f-/~

Tl ME a,51,t; Q,,t;"

[358]

'::J/1...:J/ L. U.l..O

~ ; 1.. L. ; u ::;

t'l'l rctye L.

'**********************************~*************************************

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

5452 Sample

Title:

B306100BFRWC014GD Peak Analysis Performed on:

9/13/2016 Peak Analysis From Channel:

Peak Analysis To Channel:

4:12:09 PM 85 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV )

1 2

3 4

5 6

7 8

9 10 11 12 288-346-574-950-1176-1399-2037-2326-2429-3636-4472-5828-307 353 58 2 963 1187 1414 2 048 2337 2 444 3650 4485 5852 300.78 349.11 578.31 954.85 1180.77 1407.53 2042.3 3 23 30.88 2435.99 3641. 78 4478.62 5841.18 74.85 86.95 144.32 238.57 295.11 351. 85 51 0.69 582.88 609.18 910.76 1120.00 1460.56 First peak in a multiplet region

= Other peak in a multiplet region

= Fitted singlet rors quoted at

2. 000 sigma (keV)

Area Uncert.

Counts 0.7 3 0.74 0.66

1. 09 0.68

1. 22 0.84 0.79

1. 45 0.28 0.59

1. 95 2.85E+002 2.40E+001 2.22E+001 7.08E+001 2.59E+001 l.30E+002 4.60E+001 4.26E+001

1. 37E+002 3.55E+001 3.62E+001 3.15E+002 107.80 48.25 40.93 45.75

31. 74 35.90 24.02 20.67 28.40 17.41 16.48 39.67 7.48E+002 2.78E+002 1.82E+002 1.60E+002 8.91E+001 6.40E+001 3.90E+001 2.54E+001 2. 1 9E+001

1. 35E+001 1.08E+001 1.87E+001

[359]

.J /..L..J/

£.. V

..L. V

~

• ..L L.

• V.J

.1..

.1.-.J.

'*** *********~**************************** ***************** ************'

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

'***************************************** ~*****************************

Sample

Title:

B306100BFRWC0l4GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Sr-85 Tc-99m Ba-133 Tl-2 08 Bi-2 11 Pb-212 Bi-214 Pb-214

1. 000 0.98 3 0.977 0.775

1. 000 0.999 0.975

0. 350 0.977 1460.82 1<

514.01*

140.51*

79.61*

81. 00*

276.40 302.85*

356.01*

383.85 583.19*

351.07*

115.18 23 8.63*

300.09*

609.32*

768.36 806.18 934.06 112 0. 2 9*

1155.21 1238.12 1280.98 1377.67 1385.31 1401.52 1407.99 1509. 2 1 1661. 2 7 172 9.59 1764.49 1847.43 2118.51 2 41. 99*

2 95. 22

• 351.93*

785.96 Yield

( ~)

10.66 96.00 89.00 2.65 32.90 7.16 18.34 62.05 8.94 85.00 13.02 0.60 43.60 3.30 45.49 4.89

1. 2 6 3.11 14.92 1'.63 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 7.25 18.42 35.60

1. 06 Activity (pCi/S me )

1. 64862E+007

1. 52 995E+005 4.17001E+004

1. 73001E+007 1.1 72 80E+005 3. 28340E+005

5. 3 9507E+005

1. 72563E+005 2.57115E+006 3. 32 685E+005

1. 82 478E+006 1.06150E+006 1.17219E+006 2.00042E+006 3.26914E+005 9.40 348E+005 Activity Uncertainty 2.52047E+006

8. 252 70E+004 7.73662E+004 7.42759E+006 2. 3 6956E+005 4. 052 85E+005

1. 7223 2E+005

8. 62 093E+004

8. 22179E+005 2.21570E+005 2. 252 69E+006 2.54 22 6E+005 5.42482E+005

1. 33153E+00 6 4.03501E+005 3.00219E+005

[360]

lLeLLeLe!u.;t:::: "ULLt::::L,;Lt::::U rl.L,; L..l. V..l.LY

£\\.t::::.l:,)ULL

J /L..)/

L V L U

':i

• LL

• V ::J r l"l

• = Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2.000 sigma

[361]

J/.l.J/ L V.l.O

':I ;.l. L ; V ::I

.t:'lvl

'*************************** **** ******* ~********************************

I N T E R F E R E N C E C O R R E C T E D R E P O R T

'***********************************************~***********************

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/S me )

Uncertainty K-40

1. 000

1. 648619E+007 2.520475E+006 Sr-85 0.983 1.529954E+005

8. 252695E+004 Tc-99m 0.977 4.170014E+004 7.736623E+004 X

Cd-109 0.998 Ba-1 33 0.775 1.348844E+005 2.368250E+005 X

Eu-155

0. 3 04 Tl-208

1. 000

1. 725627E+005 8.62092 8E+004 Bi-211 0.999 1.553463E+006

1. 481467E+006 Pb-21 2 0.975 3.098843E+005 2.4 18893E+005 Bi-214 0.350 1.081429E+006 2.302012E+005 Pb-2 14 0.977

l. 370990E+005 4.834288E+005

?

Nuclide is part of an undetermined solution X

Nuclide rejected by the interference analysis Nuclide contains energy l ines not used in Weighted Mean Activity Errors quoted at 2.000 s igma U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Peak Energy Peak Si ze in P E A K S 9/13/2016 85 81 92 Peak CPS 4:12 :09 PM No.

(keV)

Counts per Second

% Uncertainty Peak Type 10 910.76 5.922 6E-002 49.00 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma Tol.

Nuclide

[362]

!C.L.LUe 1v1u1-1.

.t'i.t;_fJUL L

J/ 1..

:)f LU.LO rctye o

N U C L I D E MD A R E P O R T

+

Detector Name:

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name K-40 Cr-5 1 Mn-54 Co-58 Co-60 Nb-94 Sn-11 3 Cs-134 Cs-137 Eu-152 Energy (keV) 1460.82*

320.08 834.85 810.76 1173. 23 1332.49 70 2.65 871. 09 255.13 391. 70 475.36 563. 2 5 569.33 604.72 795.86 801. 95 1038.61 1167.97 1365.19 661.66 121. 7 8 2 44.70 2 95.94 344. 2 8 3 67.79 411.12 443.96 488.68 563.99 586.26 678. 62 688.67 719.35 778.90 810.45 867.37 919. 33 964.08 1085.87 1089.74 1112.07 1212.95 5452 1 meter B306100BFRWC014GD C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL. NLB Yield

( ';;)

10.66 9.91 99.98 99.45 99.85 99.98 99.81 99.89 2.11 64.97

1. 48 8.34 15.37 97.62 85.46 8.69 0.99

1. 79 3.02

85. 10 28.67 7.61 0.45 26.60 0.86 2.24 2.83 0.4 2 0.49 0.46 0.47 0.86 0.28 12.96

0. 32 4.26 0.43 14.65 10.24

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/S me ) (pCi/S me)

Activity (pCi/S me)

1. 663E+006

1. 430E+006 1.449E+005 1.489E+005 1.556E+005 1.321E+005 1.583E+005 1.364E+005 8.372E+006 2.262E+005 9.926E+006 1.696E+006 9.317E+005 2.378E+005 1.638E+005

1. 649E+006 l.562E+007 8.557E+006 4.081E+00 6

1. 800E+005 7.439E+005 2.319E+006 4.154E+007 5.670E+005

1. 621E+007 7.218E+006 5.108E+006 4.104E+007 2.920E+007 4.074E+007

3. 288E+007

1. 771E+007 5.375E+007 9.807E+005 4.613E+007 3.116E+006 3.206E+007

1. 299E+006

1. 625E+006 9.909E+006 1.092E+006 1.185E+007 1.66E+006 1.43E+006 1.45E+005 l.49E+005 1.32E+005

1. 3 6E+005 2. 2 6E+005 1.64E+005 1.80E+005 5.67E+005

1. 649E+007

-1.178E+005 4.157E+004

-5.607E+004 1.608E+005 2.135E+004

-7.603E+004

-3.416E+004

-1.056E+006 2.408E+004 9.827E+004 5.196E+005

-2.526E+005

-1.473E+005

-1. 392E+005

- 1.382E+006 1.120E+007 1.350E+006 9.320E+00 5

1. 784.E+005

- 4.138E+005

-1.169E+006 2.815E+007

-2.420E+005

-4.054E+006 5.621E+006 1.120E+006 2.699E+007 4.593E+005 4.614E+007

-7.496E+006

-1.113E+007

-2.043E+007

-1. 381E+006

-2.630E+007

-3. 22 7E+006

-4.414E+006

-1. 178E+005

-1.022E+006

5. 227E+006

-1. 636E+006

7. 214E+006 Dec. Level (pCi/S me) 7.606E+005 6.815E+005 6.686E+004 6.891E+004 7.111E+004 5.891E+004 7.400E+004

6. 2 44E+004 4.049E+006 1.074E+005 4.682E+006 7.933E+005 4.360E+005 1.140E+005 7.551E+004 7.614E+005

7. 175E+006 3.905E+006 1.800E+006 8.4 14E+004 3.643E+005 l.123E+006 2.007E+007 2.706E+005 7.690E+006 3.438E+006 2.413E+006 1.952E+007

1. 367E+007 1.936E+007 1.537E+007

8. 2 63E+006 2.501E+007 4.486E+005 2.134E+007 1.424E+006

1. 465E+007 6.080E+005 7.495E+005 4.581E+006 4.982E+005 5.448E+006

[363]

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Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV )

( *)

(pCi/S me)

(pCi/S me)

(pCi/S me )

(pCi/S me)

Eu-1 52 1249.94 0.19

7. 62 4E+007 5.67E+005 - 9.804E+006 3.446E+007 1299. 1 4

1. 63 9.570E+006 2.085E+006

4. 351E+006 1408.01

21. 07

7. 62 0E+005 6.866E+005 3.460E+005 1457.64 0.50 9.865E+007 3.604E+008 4.783E+007 1528.10

0. 2 8 3.8 28E+007

-6.482E+006 1.639E+007 Eu-154 12 3.07 40.40 5. 276E+005 4.43E+00 5 -2.721E+005 2.584E+005 247.93 6.89 2.459E+006

-2.360E+006 1.188E+006 591. 76 4.95 2.818E+006

-1. 945E+006 1.314E+006 692.4 2

1. 78 7.615E+006

- 1. 068E+007 3.521E+006 723.30 20.06 7.832E+005 3. 22 0E+005 3.656E+005 756.80

4. 52 3.191E+006

- 1.667E+006 1.477E+006 873.18 12.08 1.192E+006

1. 2 77E+005 5.483E+005 996.29 10.48

1. 398E+006 3.342E+005 6.402E+005 1004.76 18.01 7.885E+005

-5.843E+005 3.598E+005 1274.43 34.80 4.426E+005

-4.967E+005 2.012E+005 1596.48

1. 80 7.539E+006 2.814E+006 3. 32 6E+006 Eu-155 45.30

1. 31 1. 058E+007

4. 2 1E+005 - 2.484E+006 5.123E+006 60.01

1. 22

1. 624E+007

-6. 22 5E+006 7.941E+006 86.55*

30.70

4. 212E+005

1. 2 57E+005 2.035E+005 105.31 21.10 1.090E+006 4.878E+005 5.347E+005

+

Tl-208 583.19*

85.00 1.177E+005 1.18E+005

1. 72 6E+005 5.335E+004

+

Bi-211 351. 07*

13.02 9.561E+005 9.56E+005 2.571E+006 4.513E+005 Pb-211 404.85 3.78 4.190E+006 4.19E+006 4.7 2 9E+005

1. 995E+006 427.09

1. 76

8. 33 6E+006

-1. 837E+006 3.946E+006 832.01

3. 52 4.377E+006

-1. 732E+005 2.029E+006 Bi-212 39.86

1. 06 1.232E+007 2.36E+006 -7.706E+005 5.957E+006 727. 33 6.67 2.362E+006

1. 2 09E+006 1.103E+006 785.37 1.10 1.346E+007 8.950E+006

6. 23 4E+006 1620.50

1. 4 7 6.744E+006

-2.900E+006 2.825E+006

+

Pb-212 115.18 0.60 3. 728E+007 3.42E+005 1.021E+007 1.827E+007 238.63*

43.60 3.415E+005 3.32 7E+005 1.644E+005 300.09*

3.30 3.670E+006

1. 82 5E+006 1.740E+006 Pb212-XR 74.82 10.28 2.597E+006

1. 50E+00 6 2.948E+005 1.278E+006 77.11 17.10 1.499E+006 8.884E+004 7.365E+005 87.35 3.97

6. 362E+006 4.970E+006 3.126E+006 89.78

1. 46 1.672E+007

-5.535E+006 8.210E+006

+

Bi-2 14 609.32

• 45.49 2.256E+005 2. 2 6E+00 5 1.061E+006

1. 023E+005 768.36 4.89 3.447E+006 3.187E+006

1. 614E+006 806.18

1. 2 6 1.199E+007 6.512E+006 5.560E+006 934.06 3.11 5.454E+006 3.850E+006 2.535E+006 1120.29*

14.92 6.887E+005 1.172E+006 3.005E+005 1155.21

1. 63 l.091E+007 5.085E+006 5.047E+006 1238.12 5.83 3. 352E+006 2.834E+006 1.558E+006 1280.98

1. 43 1.062E+007

4. 62 9E+006 4.823E+006 1377.67 3.99 3.919E+006

-l. 33 8E+006

1. 777E+006 1385.31 0.79

1. 7 37E+007 1.540E+006 7.764E+006 1401.52

1. 33 1. 2 04E+007 5.379E+006 5.466E+006 1407.99 2.39 6.706E+006 6.043E+006 3.045E+006 1509. 21 2.13 6.552E+006 2.999E+006 2.915E+006 1661. 2 7

1. 05 1. 12 4E+007 7.503E+006 4.841E+006

[364]

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Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( z, )

(pCi/S me ) (pCi/S me )

(pCi/S me )

(pCi/S me )

+

Bi-214 1729.59 2.88

4. 331E+006 2. 2 6E+005 1.415E+006 l.874E+006 1764.49 15.30 1.4 33E+006

1. 969E+006 6.611E+005 1847.43 2.03 6.764E+006 3.322E+006 2.953E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO 0.000E+OOO

+

Pb-2 14 24 1. 99*

7. 25 2.053E+006 3.50E+005 2.000E+006 9.885E+005 295. 22

• 18.42 6.575E+005

3. 2 69E+005 3.117E+005 351.93*

35.60 3.497E+005 9.403E+005

1. 650E+005 785.96

1. 06 1.387E+007 6.821E+006 6.423E+006 Pb214-XR 74.82 5.80 4.604E+006 2.64E+006 5.225E+005 2.264E+006 77.11 9.70 2.642E+006 1.566E+005

1. 298E+006 87.35 2. 2 4 1.127E+007 8.808E+006 5.540E+006 89.78 0.82 2.976E+007

-9.855E+006 1.462E+007 Ra-226 186.21 3.64 5.082E+006 5.08E+006 2.911E+006 2.474E+006 Ac-228 129.07 2.42 8.749E+006

7. 34E+005 -3.175E+006

4. 284E+006 209. 2 5 3.89 4.717E+006 3.138E+005 2. 2 92E+006 270. 2 4 3.46 4.999E+006 4.331E+006 2.413E+006 328.00 2.95 4.985E+006 5.660E+005 2.379E+006 338.32

11. 27

1. 44 7E+006 8.789E+004 6.932E+005 409.46

1. 92 8.390E+006 3.638E+006 3.997E+006 463.00 4.40 3.412E+006 5.526E+005

1. 613E+006 794.95

4. 25 3.356E+006 l.034E+005 1.549£+006 911. 2 0 25.80 7.341E+005

-2. 32 3E+005 3.442E+005 964.77 4.99 3.766E+006 l.171E+004 1.761E+006 968.97 15.80

1. 200E+006

1. 203E+006 5.614E+005 1588.20

3. 22 4.652E+006 3.286E+006 2.079E+006 Pa-231 27.36 10.30 6.918£+005

6. 92E+005 2.048E+005 3.248E+005 283.69

1. 70 1.002E+007 3.754E+006 4.830E+006 300.07 2.47 7.000E+006

1. 047E+006 3.371£+006 302.65 2. 20 7.513£+006

-4.687E+006 3.612E+006 330.06

1. 40 1.094E+007 5.329E+006

5. 230E+006 Th-234 92.38 2.13

1. 132E+007 1. 13E+007 2.612E+006 5.556E+006 92.80 2.10 l.144E+007 2.122E+006 5.616E+006 112.81

0. 21

1. 061E+008

-2. 210E+007 5.199E+007 U-235 143.76 10.96 1.834E+006 3. 22E+005 1.937E+005 8.965E+005 163.33 5.08 3.708£+006

1. 843E+006 1.808E+006 185.71 57.20 3.216E+005

-1. 82 8E+005

1. 566E+005 202.11

1. 08 1.668E+007

- 2.101E+007 8.104E+006 2 05.31 5.01 3.708E+006

1. 893E+006 1.803E+006 Am-241 59.54 35.90 5.515E+005 5.51E+005 -1.534E+005 2.697E+005

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[365]

GAMM A S P E C T R U M A N A L Y S I S

'*******************************~***************************************

.lename: 54 52 iport Generated On tmple Title tmple Description tmple Identification tmple Type tmple Geometry iak Locate Threshold iak Locate Range (in channels )

iak Area Range (in channels) ientification Energy Tolerance tmple Size tmple Taken On

quisition Started

.ve Time

al Time 9/13 /2 016 3:55:54 PM B306100BFRWC015GD Steam Tunnel Unit-1 015 1 meter 3.00 85 -

85 -

10.000 8192 8192 keV 1.000E+OOO S meters 9/13/2016 3 : 45: 52 PM 600.0 seconds 601.3 seconds

0. 22

~

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER OATA,VALIDATED DATE /.. 8-/'f T1ME 0St5 Ql,d,~

[366]

JI.J. J/ <'..V.J. U P E A K A N A L Y S I S R E P O R T Detector Name:

5452 Sample

Title:

B306l00BFRWC0 l 5GD Peak Analysis Performed on:

9/13/2016 Peak Analysis From Channel:

Peak Analysis To Channel:

3:55:54 PM 85 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV )

1 2

3 4

5 6

7 8

9 10 1 1 12 113-2 96-333-944 -

1402 -

2326-2 429-3635-38 70-4472-5830-7052-119 306 346 960 1413 2338 2444 3649 3881 4486 5853 7065 116. 26 300.60 340.56 954.45 1407.31 233 1.26 2436.04 3641. 87 3875.01 4478.75 5841.94 7058.49 28.66 74.80 84.81 238.47 351. 80 582.98 609.19 910.78 969.08 1120.03 1460.75 1764.70 First peak in a multiplet region

= Other peak in a multiplet region

= Fitted singlet

• rors quoted at 2.000 sigma (keV)

Area Uncert.

Counts 0.50 0.90 0.69 0.55

1. 28 0.80

1. 64 0.31 0.34 0.32

1. 31 0.45 2.69E+001

7. 22 E+001 l.12E+002 l.02E+002 l.09E+002 2.92E+001

l. 3 6E+002 2.87E+001 l.80E+001 3.72E+001 3.10E+002 3.60E+001 23.75 73.93 75.77 47.80 33.08

21. 27 29.60 20.46 15.95 18.49 38.36 15.75 4.41E+001 5.42E+002-4.81E+002 l.49E+002 6.51E+001 3.18E+001 2.75E+001 2.63E+001 1.80E+001 l.68E+001 l.46E+001 8.97E+OOO

[367]

J /

.J.. J/ L. V.J..U J

• J J

• J ':I r 1*1

'*****'~*****************************************************************

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

Title:

B306100BFRWC015GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Ba-133 Tl-20.8 Pb-212 Bi-214 Pa-23 1

1. 000 0.581

1. 000 0.873 0.534

0. 384 1460.82*

79. 61*

81. 00

• 276.4 0 302.85 356. 01

• 383.85 583.19*

115.1 8 238.63*

300.09 609. 32

• 768.36 806.18 934. 0 6 1120. 2 9*

1155. 2 1 1238.12 128 0.98 1377.67 1385.31 1401.52 1407.99 1509. 2 1 1661. 2 7 1729.59 1764.49*

1847.43 2118.51 2 7.36*

283.69 300.07 302.65 330.06 Yield

( % )

10.66 2.65 32.9 0 7.16 18.34 62.05 8.94 85.00 0.60 43.60 3. 30 45.49 4.89

1. 26 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79

1. 33 2. 39 2.1 3

1. 05 2.88 15. 30 2.0 3 1.1 6 10.30

1. 70 2.47 2. 2 0

1. 40 Activity (pCi/S me)

1. 623 19E+007

4. 38191E+006 5.47104E+005 4.5 2099E+005 1.18190E+005 4.77 2 89E+005

1. 05650E+006

1. 2 066 6E+006 l.47803E+006 4.19680E+005

• =Energy line found in the spectrum.

Activity Uncertainty 2.45185E+006 4.57293E+006 3.86199E+005 l.55184E+005 8.72746E+004 2.37412E+005 2.61992E+005 6.07050E+005 6. 56816E+005 3.84 289E+005

@ = Energy line not used fo r Weighted Mean Activity Energy Tolerance :

10.000 keV Nuclide confidence index threshold

0. 3 0 Errors quoted at 2.0 00 sigma

[368]

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.t' lVJ I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/S me )

Uncertainty K-40

1. 000 1.623194E+007 2.451851E+006 X

Cd-109 0.983 Ba-133

0. 581 4.691855E+005 1.43922 6E+005 V,.

Eu-155

0. 3 01 Tl-208

1. 000 l.181903E+005 8.727463E+004 X

Bi-211 0.999 Pb-21 2 0.873 4.772893E+005 2.37412 1E+005 Bi-214 0.534 1.127140E+006 2.258742E+005 X

Pb-214 0.491 Pa-23 1 0.384 4.196804E+005 3.842889E+005 X

Th-231 0.917

?

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 2.000 s igma U N I D E N T I F I E D P E A K S 9/13/2 01 6 85 81 92 Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Peak Energy No.

(keV) 8 910.78 9

969.08 Peak Size in Counts per Second 4.7848E-002 3.0000E-002 M

First peak in a multiplet region m

Other peak in a multiplet region F

Fitted singlet Errors quoted at 2.000 sigma 3:55:54 PM Peak CPS

% Uncertainty 71.27 88.63 Peak Type Tol.

Sum Tol.

Nuclide Eu-152 Ac-22 8

[369]

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'********** ****** ******* ********* ***************************** ************** ~**

N U C L I D E M D A R E P O R T

+

Detector Name:

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name K-40 Cr-5 1 Mn-54 Co-58 Co-6 0 Nb-94 Sn-113 Cs-134 Cs-137 Eu-15 2 Energy (keV) 1460. 82*

32 0.08 834.85 810.76 117 3. 23 1332.49 702.65 871.09 255.13 391. 70 475.36 563.25 569.33 604.72 795.86 801.95 1038.61 1167.97 1365. 1 9 661. 66 121.78 244.70 295.94 344. 2 8 367.79 411. 12 443.96 488.68 563.99 586. 2 6 678. 62 688.67 719.35 778.90 810.45 867. 37 919. 33 964.08 1085.87 1089.74 1112.07 1212.95 54 52 1 meter B306100BFRWC015GD C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL. NLB Yield

(% )

10.66

9. 91-

99. 98 99.45 99.85 99.98 99.81 99.89 2.11 64.97

1. 48 8.34 15.37

97. 62 85.46 8.69 0.99

1. 79 3.02 85.10 28.67 7.61 0.45 26.60 0.86 2. 2 4 2.83 0.4 2 0.49 0.46 0.47 0.86

0. 2 8 12.96

0. 32

4. 26 0.43 14.65

10. 2 4

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/S me ) (pCi/S me) 1.447E+006

1. 571E+006

1. 784E+005

1. 62 8E+005 1.845E+005

1. 321E+005 1.518E+005 1.511E+005

8. 1 37E+006 2.418E+005 1.027E+007

1. 955E+006 1.040E+006 2.432E+005 1.890E+005 1.894E+006 1.403E+007 1.053E+007 3.886E+006

1. 84 7E+005 7.763E+005 2.359E+006 4.311E+007 5.761E+005

1. 803E+007

7. 243E+006 5.7 2 6E+006 3.668E+007 3.386E+007 3.979E+00 7 2.963E+007 1.681E+007 5.456E+007

1. 036E+006 4.968E+007 3.726E+006 3.768E+007 1.4 2 6E+006 1.494E+006 8.550E+006

1. 2 65E+006

1. 2 91E+007

1. 45E+006

1. 57E+006 1.78E+005 1.63E+005

1. 32E+005

1. 51E+005 2.42E+005 1.89E+005

1. 85E+005 5.76E+005 Activity (pCi/S me )

1. 623E+007

1. 023E+005 8.061E+004

1. 098E+005 l.172E+005

- 9. 2 86E+004

5. 2 61E+004

-1.082E+005

-1.768E+006 4.597E+004

-1.426E+006 1.618E+006

- 5.861E+005

- 1.565E+005 5.267E+004

-6.656E+005

-1.010E+007 2.745E+006 3.237E+005

-6.686E+004

- 9.626E+004 1.214E+006 4.616E+007

- 1. 318E+005

- 6.137E+006 7.489E+005

-7.818E+004

-4.996E+006 4.061E+007 7.951E+006

-9.807E+006

- 1.618E+007 2. 3 63E+007

-1. 326E+005 8.609E+006

-9. 215E+005

-4.494E+007 1.156E+005 9.455E+00 5

-2. 24 9E+006

-4.576E+005 9.861E+006 Dec. Level (pCi/S me )

6.526E+005 7.522E+005 8.357E+004 7.585E+004 8.555E+004 5.891E+004 7.075E+004 6.98 1E+004 3.932E+006 1.152E+005 4.853E+006

9. 225E+005 4.901E+005 1. 167E+005 8.812E+004 8.837E+005 6.380E+006 4.889E+006 1.703E+006 8.651E+004 3.806E+005 1.142E+00 6 2.085E+007 2.751E+005 8.598E+006 3.451E+006 2.722E+006 1.734E+007 1.600E+007

1. 888E+007

1. 375E+007 7.812E+006 2.542E+007 4.765E+005 2.312E+007

1. 72 9E+006

1. 746E+007 6.714E+005 6.842E+005 3.902E+006 5.849E+005 5.980E+006

[370]

l~.L.LUe 1*JLJl"i rl.efJV.L I..

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V Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

(: )

(pCi/S me ) (pCi/S me)

(pCi/S me )

(pCi/S me)

Eu-1 52 12 49.94 0.19 8.984E+007 5.76E+005 4.463E+007 4.126E+007 1299.14

1. 63 1.065E+007 5.548E+006 4.893E+006 1408.01

21. 07 6.601E+005

-2.920E+005 2.950E+005 1457.64 0.50 9.753E+007 3.683E+008

4. 727E+007 1528.10

0. 2 8 3.053E+007

-8.431E+007

1. 252E+007 Eu-154 123.07 40.40 5.507E+005 4.98E+005 1.715E+005 2.700E+005 247.93 6.89 2.521E+006

-l.303E+006

1. 219E+006 591. 76 4.95 3.105E+006

- 1. 22 4E+006 1.458E+006 692.42

1. 78 8.462E+006 3.7 92E+005 3.944E+006 723.30 20.06

8. 308E+005 2.077E+005

3. 894E+005 756.80 4.52 3.353E+006

-3.235E+006 1.559E+006 873.18 12.08 1.263E+006

-4. 258E+005 5.837E+005 996. 2 9 10.48 1.414E+006

-1. 016E+006 6.481E+005 1004.76 18.01 9.542E+005 4.514E+005 4.427E+005 1274.4 3 34.80 4.979E+005 2.662E+005 2.289E+005 1596.48

1. 80 6.597E+006 6.091E+005 2.855E+006 Eu-155

45. 30

1. 31 1.126E+007 6.41E+005 -2.611E+006 5.462E+006 60.01

1. 22 1.639E+007 6.373E+006 8.018E+006 86.55*

30.70 6.409E+005 5.863E+005 3.134E+005 105.31 21.10 1.081E+006

- 6.8 21E+005

5. 303E+005

+

Tl-2 08 583.19*

85.00

1. 330E+005 1.33E+005 1.182E+005 6.100E+004 Bi-2 11 351.07*

13.0~

8.885E+005 8.88E+005 2.155E+006 4. 175E+005 Pb-2 11 404.85 3.78 4.408E+006 4.41E+006

1. 7 52E+005 2.1 04E+006 427.09

1. 76 8.940E+006 2.876E+006 4.248E+006 832.01 3.52 4.994E+006 5.822E+006 2.338E+006 Bi-212 39.86

1. 06 1.311E+007 2.52E+006 l.333E+005 6.351E+006 727.33 6.67 2.521E+006

-8.066E+004 1.182E+006 785.37 1.10 1.357E+007

-3.554E+006 6.292E+006 1 620.50

1. 4 7 9.303E+006 4.409E+006 4.104E+006

+

Pb-2 12 115.18 0.60 3.786E+007 3.48E+005 2.110E+007

1. 856E+007 238.63*

43.60 3.476E+005 4.773E+005 1.674E+005 300.09 3.30 5.585E+006

-5.748E+006 2.696E+006 Pb212-XR 74.82 10.28 2.654E+006 1.52E+006

7. 2 97E+006

1. 306E+006 77.11 17.10 1.519E+006

-1. 716E+005 7.465E+005 87.35 3.97 6.463E+006

-1.125E+006 3.177E+006 89.78

1. 46 1.696E+007 2.381E+006

8. 333E+006

+

Bi-214 609.32*

45.49 2.524E+005 2.52E+005

1. 056E+006 1.157E+005 768.36 4.89 3.703E+006 7.396E+005

1. 741E+006 806. 18

1. 2 6

1. 324E+007 6.767E+006

6. 182E+006 934. 0 6 3. 11 5.004E+006

1. 738E+006 2. 310E+006 1120. 2 9*

14.92

8. 283E+005

1. 2 07E+006 3.703E+005 1155. 21

1. 63 1.061E+007 l.407E+006 4.899E+006 1238.12 5.83 3.456E+006 2.02 7E+006

1. 61 0E+006 1280.98

1. 43 1.160E+007

-1. 038E+007 5.310E+006 1377.67 3.99 4.028E+006

-7.545E+004

1. 832E+006 1385.31 0.79 1.8 62 E+007

-1.066E+007 8.386E+006 1 401.52

1. 33 1.081E+007

-3. 319E+006 4.8 52E+006 1407.99 2. 3 9 5.810E+006

-2.570E+006 2.597E+006 1509. 21 2. 1 3 6.937E+006

1. 020E+006 3.107E+006 1661. 27

1. 05 9.618E+006

-3.607E+006 4.028E+006

[371]

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

(% )

(pCi/S me ) (pCi/S me )

(pCi/S me )

(pCi/S me)

+

Bi-214 1729.59 2.88 3.588E+006 2.52E+005 l.938E+006 l.503E+006 1764.49*

15.3 0 7.989E+005

1. 478E+006 3.440E+005 1847.43 2.03

6. 382E+006

-3. 966E+005 2.762E+006 2 118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO Pb-214 241.99*

7.25 2.090E+006 3.25E+005 2.870E+006 1.007E+006 2 95. 22 18.42 1.052E+006

1. 314E+006 5.089E+005 351. 93*

35.60 3.249E+005 7.880E+005

1. 52 7E+005 785.96

1. 06 1.399E+007

- 8.551E+006 6.484E+006 Pb214-XR 74.8 2 5.80 4.704E+006 2.68E+006 1.2 93E+007 2.314E+006 77.11 9. 70 2.677E+006

-3.025E+005

1. 316E+006 87.35 2.24 1.145E+007

- 1. 995E+006 5.630E+006 89.78 0.82 3.020E+007

4. 239E+006 1.484E+007 Ra-226 186. 21 3.64 5.182E+006 5.18E+006 1.461E+006 2.524E+006 Ac-228 129.07 2.4 2 8.761E+006 8.42E+005 3.094E+006 4.290E+006 209.25 3.89 4.677E+006

1. 762E+006 2. 272E+006 270. 2 4

3. 46 4.934E+006

-3.587E+006 2.381E+006 328.00 2.95 5.642E+006 2.481E+005 2.708E+006 338. 32

11. 27

1. 466E+006

-1.056E+004 7.028E+005 409.46

1. 92 8.478E+006

-7.092E+006 4.040E+006 463.00 4.40 3.800E+006 3.507E+006 1.807E+006 794.95

4. 2 5 3.8 54E+006 6.898E+005 1.798E+006 911. 20 25.8 0 8.419E+005 7.054E+005 3.981E+005 964.77 4.99 4.120E+006

-1.090E+006

1. 938E+006 968.97 15.80 1.304E+006

1. 052E+006 6.136E+005 1588.2 0

3. 22 4.652E+006 1.779E+006 2.079E+006

+

Pa-23 1 27.36*

10.30 5.907E+005 5.91E+005 4.197E+005 2.742E+005 283.69

1. 70 9.8 39E+006 5.358E+006 4.739E+006 300.07 2.47 7.461E+006

-7.680E+006 3.602E+006 302.65 2. 20 7.882E+006

-3.007E+006 3.796E+006 330.06

1. 40 1.169E+007

-2.823E+006 5.606E+006 Th-234 92.38 2.13 1.150E+007 1.15E+007

1. 340E+006 5.650E+006 92.80 2.10 1.174E+007 1.013E+007 5.766E+006 112.81

0. 21 1.063E+008

-2.236E+007

5. 211E+007 U-235 143.76 10.96 1.816E+006 3. 30E+005 -2.181E+005 8.876E+005 163.33 5.08 3.815E+006 3.310E+006

1. 862E+006 185.71

57. 2 0 3.296E+005 6.043E+004

1. 606E+005 202. 11

1. 08 1.713E+007

- 4.815E+006 8.332E+006 205.31 5.01 3.699E+006 2.383E+006

1. 798E+006 Am-241 59.54 35.90 5.421E+005 5.42E+005 -1.505E+005 2.650E+005

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[372]

GA MM A S P E C T R U M A N A L Y S I S

_lename: 54 52 iport Generated On tmple Title tmple Description tmple Identification tmple Type tmple Geometry

~ak Locate Threshold iak Locate Range (in channels )

iak Area Range (in channels )

lentification Energy Tolerance tmple Size tmple Taken On

quisition Started

_ve Time ial Time iad Time 9/13/2016 3 :40:03 PM B306100BFRWC016GD Steam Tunnel Unit-1 016 1 meter 3. 0 0 85 -

85 -

10.000 8192 8192 keV 1.000E+OOO S meters 9/13 /2 016 3 :30:00 PM 600.0 seconds 601. 4 seconds 0. 23:

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2 01 5 8/9/2016 UNNELSTS 1 METER DATA VALIDATED DATE t-1-t<}

TIME as:,.~

Q_~,,

[373]

..J *

-::I V* V..J J.. L *.l

• • • • • • • • • • • • • • • ** **************~******************************* **********

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

5452 Sample

Title:

B306100BFRWC016GD Pea k Analysis Performed on:

9/13/2016 Peak Analysis From Channel:

Pea k Analysis To Channel:

3 : 40: 02 PM 85 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) 1 2

3 4

5 6

7 8

9 10 11 12 113-297-949-1173-1400-2327-2425-3290-3637-3868-5830-7053-120 306 959 1186 1418 2339 2445 3301 3650 3880 5854 7066 115.81 301.23 954.64 1181. 25 1407.59 2331.88 2436.8 0 3295.57 3643.17 3873.76 5842.68 7059.16 28.54 74.96 238.51 295.23 351. 87 583. 13 609. 38 824.18 911.11 968.77 1460.94 1764.8 6 First peak in a multiplet region Other peak in a multiplet region

= Fitted singlet

• rors quoted at 2. 000 sigma (keV)

Area Uncert.

Counts 0.49 0.68 0.50 0.74 1.11

0. 32 1.18 0.48

1. 25 0.50 2.41 0.85 2.47E+001 1.51E+002 7.62E+001 6.98E+001

1. 18E+002 5.13E+001 l.40E+002 8.57E+OOO 4.46E+001 3.73E+001 3.08E+002 2.88E+001 24.30 66.47 36.37 33.54

41. 24 20.8 3 33.08

11. 79 17.81 15.89 39.91 15.09 4.43E+001

4. 21E+002 1.03E+002 7.62E+001 9.08E+001 2.17E+001 3.68E+001 1.04E+001 1. 2 4E+001 9.75E+OOO 2.18E+001 1.02E+001

[374]

-::J/ 1..:)f L Ul.O J ; '+/- U ; U J t' lvl N U C L I D E I D E N T I F I C A T I O N R E P O R T Sample

Title:

B306100BFRWC016GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Ba-133 Tl-208 Pb-2 12 Bi-214 Pb-2 14 Th-231

1. 000

0. 322 1.000 0.975 0.3 2 9 0.977 0.877 1460.8 2*

79.61*

81. 00 276.40 30 2.85*

356.01*

383.85 583.19*

115.18 238.63*

300.09*

609.32*

768.36 806.18 934.06 112 0. 2 9 1155. 2 1 1238.12 1280.98 1377.67 1385.31 1401.52 1407.99 1509. 2 1 1661. 2 7 1729.59 1764.49*

1847.4 3 2118.51 241. 99*

295. 22

• 351.93*

785.96 25.64*

84.21*

89.95 Yield

( ~)

10.66 2.65 32.90 7.16 18.34 62.05 8.94 85.00 0.60 43.60 3.30 45.49 4.89

1. 26 3.11 14.92

1. 63 5.8 3

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88

15. 30 2.03 1.16 7.25 18.42 35.60

1. 06 14.10 6.60

1. 00 Activity (pCi/S me) 1.61160E+007 9.15743E+006 8.8 42 47E+005 4.90737E+005 2.07633E+005 3.580 27E+005 4.91427E+006 1.08597E+006 1.18014E+006 2.15280E+006 8.80407E+005 8.55343E+005 2.81255E+005 3.67685E+006 Activity Uncertainty 2.51285E+006 4.44275E+006 4.47915E+005 1.88 337E+005 8.7 932 6E+004 1.80403E+005 2.4912 0E+006 2.87462E+005

6. 2632 4E+005 1.08367E+006 4.45812E+005 3. 28284E+005

2. 84977E+005 1.83342E+006

[375]

J / J.....J/ LV J...V

• = Energy l ine found in the spectrum.

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

10.000 keV Nuclide confidence index threshold

0. 30 Errors quoted at 2.000 sigma

[376]

! Lt::L.l..t::Lt::lll-t::

l...,ULL t::l-Lt::U L":1.1...,L.LV.LL:f nC::.1:-'VLL

I /..l..J/ LU..l..U

'*****************************~*****************************************

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Nuclide Id Name Confidence K-40 Ba-133 Tl-208 X

Bi-21 1 Pb-212 Bi-214 Pb-214 X

Pa-231 Th-231

1. 000

0. 322

1. 000 0.999 0.975

0. 32 9 0.977 0.575 0.877 Wt mean Activity (pCi/S me )

1.611600E+007 2.729845E+005 2.076330E+005 2.881380E+005 1.102356E+006 4.407087E+005 3. 622 435E+005 Wt mean Activity Uncertainty 2.512852E+006 7.772911E+005 8.793259E+004 2.7 722 91E+005 2.612588E+005 1.197414E+006 2.793064E+005

? = 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 2.000 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:

Peak Energy Peak Size in P E A K S 9/13/2016 85 8192 Peak CPS 3 :40:02 PM Pea l-:

No.

(keV)

Counts per Second

% Uncertainty Type 8

824.18 1.4276E-002 9

911.11 7.4313E-00 2 10 968.77 6.2083E-002 M

First peak in a multiplet region m

Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma 137.60 Sum 39.93 Sum 42.66 Sum Tol.

Nuclide

[377]

J

/

..J.......J /

L. U.l.U

.J. "-:t: V

• V.J J:l"J

'*****************************************************************************~

N U C L I D E M D A R E P O R T

+

Detector Name:

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name K-40 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-113 Cs-134 Cs-137 Eu-15 2 Energy (keV) 1460.8 2*

320.08 834.85 810.76 1173. 23 1332.49 702.65 871. 0 9 255.13 391.7 0 475.36 563.25 569.33 604.72 795.86 801.95 1038.61 1167.97 1365.19 661. 66 12 1. 7 8 244.70 2 95.94 344. 2 8 3 67.79 411.12 44 3.96 488.68 563.99 586.26 678.62 688.67 719.35 778.9 0 810.45 867.37 919.33 964.08 1085.87 1089.74 1112.07 12 12.95 5452 1 meter B306100BFRWC0 1 6GD C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Yield

(%)

10.66 9.91 99.98 99.45 99.85 99.98 99.81 99.89 2.11 64.97

1. 48 8.34 15.37 97.62 85.46 8.69 0.99

1. 79 3.02 85.10 28.67 7.61 0.45 2 6.60 0.86 2.24 2.83 0.42 0.49 0.46 0.47 0.86

0. 2 8 12.96

0. 32

4. 26 0.43 14.65 10.24

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/S me)

(pCi/S me)

Activity (pCi/S me )

1. 774E+006 1.614E+006 1.739E+005 1.529E+005

1. 682E+005 1. 321E+005 1.438E+005 1.552E+005

8. 2 62E+006 2.533E+005

1. 101E+007 1.825E+006 9.903E+005 2.371E+005

1. 849E+005 l.894E+006 1.529E+007

1. 001E+007 4.92 8E+006

1. 83 5E+005 7.410E+005 2.473E+006 4.117E+007 6.041E+005

1. 660E+007 7.117E+006 5.204E+006 3.400E+007 2.994E+007 4.090E+007 3. 374E+007

1. 7 96E+007 5.576E+007

1. 036E+006 4.695E+007 3.469E+006 3.392E+007 1.520E+006

1. 686E+006 9.542E+006

1. 230E+006

1. 2 69E+007 1.77E+006 1.61E+006 1.74E+005 1.53E+005 1.32E+005 1.44E+005 2.53E+005 1.85E+005 l.84E+005 6.04E+005 1.612E+007 1.080E+005

-2.452E+004

-1.378E+004 1.319E+005

-2.068E+005 5.002E+002 7.532E+004 5.757E+006 1.755E+005 2.029E+006 1.051E+005 5.494E+005

-5. 2 86E+004 1.162E+004

-5.028E+005 2.874E+006

-1. 215E+006 2.707E+006

-1.036E+002

-1.895E+005 1.270E+006

1. 945E+007

-8. 2 05E+005 4.815E+006 8.492E+005

-3.492E+006 1.630E+007

-2.460E+007 4.886E+007 1.8 04E+007 3.499E+006

-8.760E+005

-1. 215E+006

-3.566E+007

-2. 1 47E+006

-2. 2 93E+007

-3.653E+005

-2.202E+005

-1.165E+007

-1.533E+005

- 9.917E+005 Dec. Level (pCi/S me) 8.162E+005 7.737E+005 8.132E+004 7.087E+004 7.738E+004 5.891E+004 6.677E+004 7.187E+004 3.994E+006

1. 2 09E+005

5. 22 4E+006 8.578E+005 4.652E+005 1.137E+005 8.603E+004 8.837E+005 7.007E+006 4.630E+006 2. 22 4E+006 8.593E+004 3.629E+005 1.199E+006

1. 988E+007 2.891E+005 7.887E+006 3.3 88E+006 2.461E+006 1.600E+007 1.404E+007 1.944E+007

1. 580E+007 8.387E+006 2.602E+007 4.765E+005 2.175E+007

1. 600E+006

1. 558E+007 7.187E+005 7.801E+005 4.398E+006 5.674E+005 5.866E+006

[378]

!l_;.L.LU<::::

1*1u.t-1 L'\\Cf:-iV.I..L.

J/.l......J/ L..V..LU

...J,

""::t V

• V-J

.L" J.*J.

i:a~c:;

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV}

( % )

(pCi/S me)

(pCi/S me)

(pCi/S me)

(pCi/S me)

Eu-152 1 249.94 0.19 7.738E+007 6.04E+005 -5.950E+007 3.503E+007 1299.14

1. 63 7.200E+006 5.774E+006 3.166E+006 1408.01

21. 07 6.959E+005

- 3.689E+005 3.129E+005 1457.64 0.50 9.823E+007 3.312E+008 4.762E+007 1528.10 0.28 4.214E+007 l.739E+007

1. 832E+007 Eu-154 123.07 40.40 5.182E+005 4.37E+005 -3.386E+005 2.537E+005 247.93 6.89 2.492E+006

-l.636E+006 1.205E+006 591.76 4.95 2.994E+006 2. 282E+006 1.402E+006 692.42

1. 78 8.083E+006

-5.571E+006 3.755E+006 723. 30 20.06 7.994E+005

1. 597E+005 3.737E+005 756.80 4.52 3.380E+006 8.523E+005 1.572E+006 873.18 12.08

1. 251E+006 4.993E+005 5.780E+005 996. 29 10.48 1.563E+006

- 4.818E+005

7. 22 8E+005 1004.76 18.01 9.852E+005 7.382E+005 4.582E+005 1274.43 34.80

4. 366E+005

-6.166E+005

1. 982E+005 1596.48

1. 80 6.174E+006

-5.248E+006 2.643E+006 Eu-155 45.30

1. 31 1.101E+007 8.40E+005 -4.751E+005 5.34 1E+006 60.0 1

1. 22

1. 590E+007

-3.916E+006 7.774E+006 86.55 30.70 8.401E+005 1.016E+006 4.130E+005 105.31 21.10

1. 063E+006 4.563E+005

5. 210E+005

+

Tl-208 583.19*

85.00 1.116E+005

1. 12E+005

2. 076E+005 5.034E+004 Bi-211 351.07*

13.02 1.194E+006 1.19E+006 2.339E+006 5.702E+005 Pb-211 404.85 3.78

4. 23 5E+006 4.23E+006 3.915E+005 2.017E+006 427.09

1. 76

9. 2 09E+006

-2.220E+006 4.383E+006 83 2.01 3.52 4.764E+006 2.943E+006 2.223E+006 Bi-2 12 39.86

1. 06

1. 2 63E+007 2.46E+006 -9.649E+006 6.111E+006 727.33 6.67 2.459E+006 1.308E+006 1.151E+006 785.37 1.10

1. 391E+007 4.046E+006 6.461E+006 1620.50

1. 47 7.050E+006 l.437E+006 2.977E+006

+

Pb-212 115.18 0.60 3.762E+007 2.59E+005 -2.204E+007

1. 845E+007 238.63*

43.60 2.593E+005 3.580E+005 1.233E+005 300.09*

3.30 3.558E+006 4.914E+006 1.684E+006 Pb212-XR

74. 82 10.28 2.552E+006 1.47E+006 6.010E+006

1. 255E+006

77. 11 17.10 1.473E+006

-9.849E+005 7.238E+005 87.35 3.97 6.429E+006 7.633E+006 3.160E+006 89.78

1. 46 1.660E+007

-1. 939E+007 8.153E+006

+

Bi-214 609. 32

• 45.49 3.150E+005 3.15E+005

1. 086E+006 1.470E+005 768.36 4.89 3.882E+006 3.866E+006

1. 831E+006 806.18

1. 2 6

1. 258E+007

-3.551E+006 5.855E+006 934.06 3.11 5.664E+006 1.196E+006 2.640E+006 1120. 2 9 14.92

1. 626E+006

1. 940E+006 7.692E+005 1155. 21

1. 63 1.147E+007

-1. 730E+006 5.330E+006 1238.12 5.83 3.630E+006 4.919E+006

1. 697E+006 1280.98

1. 43 1.077E+007

-2.617E+006 4.896E+006 1377.67 3.99 3.806E+006

1. 278E+006

1. 720E+006 1385.31 0.79 1.977E+007

-1. 58 4E+007 8.965E+006 1401.5'.2

1. 33 9.827E+006

-1.072E+007 4.360E+006 1407.99 2.39 6.125E+006

-3. 247E+006 2.754E+006 1509.21 2.13 7.060E+006 4.880E+006

3. 1 69E+006 1661. 27

1. 05 1.086E+007 2.765E+006 4.651E+006

[379]

...........L....L........ _

... "'~"'.I,.

..1.,-....J::-""'-'-.....

Jf.J...._./ f L-V

.J.. V

....J *-:IV

• V..J

.L l.".1

,::. o.~ c; u

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( ~' )

(pCi/S me ) (pCi/S me)

(pCi/S me)

(pCi/S me)

+

Bi-214 1729.59 2.88 5.691E+006 3.15E+005 2.315E+006 2.554E+006 1764.49*

15.30

8. 275E+005 l.180E+006 3.582E+005 1847.43 2.03 6.1 81E+006 4.125E+006 2.661E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 241.99*

7.25 l.559E+006

4. 37E+005 2.153E+006 7.413E+005 295.22*

18.42 6.374E+005 8.804E+005 3.016E+005 351.93*

35.60 4.366E+005 8.553E+005 2.085E+005 785.96

1. 06 l.458E+007 4.551E+006 6.777E+006 Pb214-XR 74.82 5.80 4.524E+006 2.60E+006

1. 065E+007 2. 22 5E+006 77.11 9.70 2.597E+006

- 1. 736E+006

l. 27 6E+006 87.35 2. 2 4

1. 139E+007 l.353E+007 5.600E+006 89.78 0.82 2.956E+007

-3.452E+007

1. 452E+007 Ra-226 186. 21 3.64 5.151E+006 5.15E+006 -1. 542E+006 2.509E+006 Ac-228 129.07 2.42 8.595E+006 7.94E+005

1. 593E+006

4. 207E+006 209.25 3.89 4.666E+006

-2.940E+006 2. 2 66E+006 27 0. 2 4 3.46 4.707E+006

-3.501E+006 2. 2 68E+006 328.00 2.95 5.339E+006

1. 284E+006 2.556E+006 338. 32

11. 27

1. 523E+006

1. 410E+006 7.311E+005 409.46

1. 92 8.390E+006

-5.461E+005 3.997E+006 463.00 4.40 3.670E+006 l.426E+006

1. 742E+006 794.95 4.25 3.658E+006

-5.620E+005

1. 700E+006 911.20 25.80 7.940E+005 8.010E+005 3.742E+005 964.77 4.99 4.4 23E+006 4.128E+006 2.090E+006 968.97 15.80

1. 318E+006 6.014E+005 6.207E+005 1588. 2 0 3. 22 4.475E+006 2. 82 4E+006

1. 991E+006 Pa-231 27.36*

10.30 6.116E+005 6.12E+005 3.850E+005 2.847E+005 283.69

1. 70 1.037E+007 2.848E+006 5.006E+006 300.07*

2.47 4.753E+006 6.566E+006 2. 249E+006 302.65 2. 2 0 7.717E+006 4.168E+006 3.713E+006 330.06

1. 40 1.116E+007

-2.446E+006 5.343E+006 Th-23 4 92.38 2.13 1.105E+007 l.10E+007 -8.905E+006 5.4 21E+006 92.80 2.10 1.115E+007

-4.747E+005 5.473E+006 112.81

0. 21 1.070E+008

-2.661E+006

5. 248E+007 U-235 143.76 10.96

1. 774E+006 3. 34E+005 -l.327E+006 8.665E+005 163.33 5.08 3.759E+006

-l.806E+006 l.8 3 4E+006 185.71

57. 2 0 3.339E+005 2.401E+005

1. 62 7E+005 202.11

1. 08 l.782E+007

2. 281E+007 8.677E+006 205.31 5.01 3.699E+006

-5.933E+005

1. 7 98E+00 6 Am-2 41 59.54 35.90

5. 284E+005

5. 28E+005 -5. 214E+005 2.582E+005

+

Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[380]

GA MM A S P E C T R U M A N A L Y S I S

_lename: 5452 iport Generated On tmple Title tmple Description tmple Identification tmple Type tmple Geometry ia k Locate Threshold iak Locate Range (in channels )

iak Area Range (in channels) lentification Energy Tolerance tmple Size tmple Taken On

quisition Started

.ve Time ial Time 9/13/2 016 4: 2 9:19 PM B306100BFRWC017GD Steam Tunnel Unit - 1 017 1 meter 3.00 85 -

85 -

10.000 81 92 8192 keV 1.000E+OOO S meters 9/13/2 01 6 4:1 9 :17 PM 600.0 seconds 601. 6 seconds 0.26 %

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2 01 6 UNNELSTS 1 METER DATA.VALIDATED DATE L-r~ L2 TIME OS"J.f:

e24,.

[381]

Cl,J'\\.

I"l.l!Cl...L:fU..LU l"\\.~~V.L '-

J f

..J.....Jf £.. VJ...V P E A K A N A L Y S I S R E P O R T Detector Name:

5452 Sample

Title:

B306100BFRWC017GD Peak Analysi s Performed on:

9/13/2016 4: 2 9: 1 9 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV )

(keV)

Area Uncert.

Counts 1

138 -

146 142.17 35.14 0.4 2 -3. 2 1E-001

31. 7 5 1. 17E+002 2

289-323 300.71 74.83

1. 34 4.44E+002 173.58

1. 31E+003 3

947-963 954.70 238.53 0.90 9.86E+001 54.24 2.03E+002 4

1174-1188 1181.03 2 95.17

1. 44 7.66E+001 36.41 8.84E+001 5

1399-1413 1406.67 351. 64

1. 45

1. 21E+00 2 38.39 8.62E+001 6

2325-2338 2331. 2 9 582.98 1.14 3.80E+001 23. 74 3.70E+001 7

2429-2447 2435.78 609.1 2

1. 37 1.60E+002 33.83 3.75E+001 8

3634 -

3650 3641.51 910.69 2.19 7.85E+001 20.11 7.48E+OOO 9

4469-4486 4478.86 1120.06 0.58

4. 31E+001 19.53 1.59E+001 10 5828-5852 5840.98 1460.51 2.00 3.2 5E+002 40.75

2. 17E+001 11 7049-7063 7056.51 1764.20

1. 08 3.63E+001 14.66 5.71E+OOO

= First peak in a multiplet region

= Other peak in a multiplet region

= Fitted singlet

• rors quoted at 2. 000 sigma

[382]

l L.c:;;:.L..L o;.::;..Lo;.::;J.J.VV VV..L..L'--' '-'-'\\,,,A.

L.i.........._..L V..L'-J

.L'\\.'-'.t""'-"..L.. '-

J I

...L....J /

L.. V...L. v N U C L I D E I D E N T I F I C A T I O N R E P O R T Sample

Title:

B306100BFRWC0l7GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Tl-208 Bi-211 Pb-212 Bi-2 14 Pa-231 Th-231

1. 000

1. 000 0.999 0.975 0.534 0.523 0.798 1460.82*

58 3.19*

351.07*

115.18 238.63*

300.09*

609.32*

768.36 80 6.18 934.06 112 0. 2 9*

1155.21 12 38.12 1280.98 1377.67 1385.31 14 01. 52 1407.99 1509.21 1661.27 172 9.. 59 1764.49*

1847.4 3 2118.51 27.36*

283.69 300.07*

30 2.65 33 0.06 25.64*

84.21*

89.95 Yield

( *%)

10.66 85.00 13.02 0.60 43.60 3. 3 0 45.49 4.89

1. 2 6 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88

15. 30 2.03 1.16

10. 30

1. 70 2.47 2.20

1. 40 14.10 6.60

1. 00 Activity (pCi/S me)

1. 70092E+007 1.54030E+005 2. 38994E+006 4.63257E+005 5.39287E+006

l. 23477E+006

1. 39755E+006 1.4881 3E+0 06

- 5.00281E+003

7. 20505E+006

-3.65453E+00 3 1.08235E+007

• = Energy line found in the spectrum.

Activity Uncertainty 2.59241E+006 9.78747E+004 8.51306E+005 2.65574E+005 2.707 21E+006 3.01002E+005 6.42800E+00 5

6. 12 841E+00 5 4.95596E+005 3.73135E+006 3.62031E+005 4.92795E+006

@ = Energy l ine not used for Weighted Mean Activity Energy Tolerance :

10.000 keV Nuclide confidence index threshold 0.30 Errors quoted at 2.000 s igma

[383]

lL..,;;:;..L.LV.L\\,.,llV......

'-,V..1-.L........_1._\\,...,\\..A.

L.l.\\....o!._..LV..L.._:J

.L'\\.......,t,-'\\J..1-1._

-' /

.J.......J/

£... V..LV

"":I

£... J

• L. V J.. l.-.J.

'** ~:

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Nuclide Id Name Confidence K-40 X

Ba-133 Tl-208 Bi-211 Pb-21 2 Bi-214 X

Pb-214 Pa-231 Th-231

1. 000

0. 320

1. 000 0.999 0.975 0.534 0.976

0. 523 0.798 Wt mean Activity (pCi/S me)

1. 700 92 3E+007 1.5402 98E+005 2.389938E+006 4.632574E+005 1.301059E+006 6.586127E+006 1.0823 48E+007 Wt mean Activity Uncertainty 2. 592 415E+006 9.787468E+004 8.513058E+005 2.653610E+005 2.490672E+005 3.630060E+006 4.7501 05E+006

? = 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 2. 000 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 9/13/2016 85 8192 Pea k CPS 4 : 2 9 :1 9 PM Peak No.

Energy (keV)

Peak Size in Counts per Second

% Uncertainty Peav.

Type 8

910.69

1. 3087E-001 M

First peak in a multiplet region m

Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 s igma

25. 62 Sum Tol.

Nuclide

[384]

-I /

.l......J/ £.. V J.. U N U C L I D E MD A R E P O R T

'** ~***************************************************************************

+

Detector Name :

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name K-40 Cr-5 1 Mn-54 Co-58 Co-60 Nb-94 Sn-11 3 Cs-134 Cs-137 Eu-152 Energy (keV) 1460. 82

• 320.08 834.85 810.76 117 3. 23 1 332.49 702.65 871. 09 255. 1 3 391. 70 475.36 563.25 569.33 604.7 2 795.86 801. 95 1038.61 1167.97 1365.19 661. 66 121. 78 2 44.70 2 95.94 344. 2 8 367.79 411.12 44 3.96 488.68 563.99 586.26 67 8. 62 688.67 719. 35 778.90 810.45 867.37 919.33 964.08 1085.87 1089.74 111:.07 1212.95 54 52 1 meter B306100BFRWC017GD C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL. NLB Yield

( % )

10.66 9.91 99.98 99.45 99.85 99.98 99.81 99.89

2. 11

64. 97

1. 48 8.34 15.37

97. 62 85.46 8.69 0.99

1. 79 3.02

85. 10 28.67 7.61 0.45 26.60 0.86 2. 2 4 2.83 0.42 0.49 0.46 0.47 0.86

0. 28 12.96

0. 32

4. 2 6

0. 43 14.65

10. 2 4

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/S me ) (pCi/S me )

1. 771E+006 1.575E+006 l.449E+005

1. 640E+005 l.7 33E+005

1. 845E+005

1. 496E+005

1. 644E+005 8.547E+006 2. 359E+005

1. 041E+007 l.856E+00 6 9.846E+005 2.583E+005 2.135E+005 l.853E+006 l.690E+007

1. 009E+007 4.081E+006

1. 949E+005 7.776E+005 2. 3 94E+006

4. 338E+007 6.193E+005

1. 844E+007 7.367E+006 5.228E+006 3.616E+007 3.188E+007

4. 259E+007 3.060E+007 l.694E+007 5.456E+007

l. 119E+006 4.968E+007 3.993E+006 3.464E+007 l.455E+006 1.561E+006 9.159E+006 l.131E+006

l. 325E+007 l.77E+006

1. 58E+006 l.45E+005

1. 64E+005 l.73E+005 l.50E+005 2. 3 6E+005 2.14E+005 l.95E+005 6.19E+005 Activity (pCi/S me )

1. 701E+007

-l. 272E+003 5.289E+004

-4.621E+004 5.857E+004

-3.300E+002

-1. 876E+004

7. 2 58E+004 7.819E+005

1. 375E+005

- 8.099E+005 2.870E+005 2. 232E+005

-2.995E+005

1. 319E+005

-7.036E+005

9. 278E+006

- l.168E+006 3. 373E+006

-1.024E+005

-2.352E+005

-8.373E+005 2.656E+007

-2. 38 4E+005

- 4.090E+006 2.616E+006

-1. 973E+006 5.013E+006 2.907E+007 4.836E+007

-6.014E+006

-6.394E+005

-2.542E+007

-9.961E+005

- 5.694E+007 6.206E+005 7.711E+006

l. 1 97E+006

-1.485E+00 6

1. 3 95E+00 6

-1. 275E+00 6 l.075E+007 Dec. Level (pCi/S me) 8.149E+00 5 7.544E+00 5 6.686E+004 7.645E+004 7.992E+004 8.511E+004 6.964E+004 7.647E+004 4.137E+006 1.122E+005 4.925E+006 8.731E+005

4. 62 4E+005

1. 2 43E+005 l.003E+005 8.634E+005 7.814E+006 4.674E+006

1. 800E+006 9.162E+004 3.812E+005 l.160E+006 2.099E+007 2.967E+005 8.803E+006 3.513E+006 2.473E+006

1. 708E+007 1.501E+007 2.02 8E+007 l.423E+007 7.878E+006 2.542E+007 5.180E+005 2.312E+007

1. 862E+006 1.594E+007 6.863E+00 5

7. 1 76E+005

4. 2 07E+006 5.180E+005 6.147E+00 6

[385]

! V..L..L\\..A G L'.1.Ll.l'J.

.1.'\\.C:t-'V.L L..

J f

J......1 /

L.. VJ.. V

"'2

• L.. J

• L..V

.LJ.".1

.L U '::1 '-

V Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( ~)

(pCi/S me ) (pCi/S me )

(pCi/S me)

(pCi/S me)

Eu-15 2 1249.94 0.19

8. 2 82E+007 6.19E+005 -1.083E+008 3.775E+007 12 99.14

1. 63 1.077E+007 7.363E+005 4.950E+006 1408.01

21. 07 7.187E+005 3.948E+005 3.243E+005 1457.64 0.50 1.014E+008 3.934E+008 4.919E+007 1528.10 0.28 4.886E+007 2.694E+007 2.168E+007 Eu-1 54 123.07 40.40 5.472E+005 4.82E+005 -2.350E+005 2.682E+005 247.93 6.89 2.566E+006

-7.616E+005

1. 2 42E+006 591. 76 4.95 3.087E+006

1. 237E+006 1.449E+006 692.42

1. 78 8.584E+006

-2.702E+006 4.005E+006 723.30 20.06 8.756E+00 5 9.840E+005 4.116E+005 756.80 4.52 3. 218E+006

-7.075E+005

1. 491E+006 873.18 12.08

1. 382E+006 7.434E+005 6.436E+005 996. 2 9 10.48 1.535E+006

-3.742E+006 7.085E+005 1 00 4.76 18.01 9.301E+005 3.002E+005

4. 307E+005 1274.43 34.80 4.821E+005

- 3.368E+005 2. 210E+005 1596.48

1. 80 6.390E+006

-2.050E+006 2.751E+006 Eu-155

45. 30

1. 31 1.177E+007 8.67E+005 3.442E+006 5.717E+006 60.01

1. 22 1.649E+007

-1. 7 54E+O 07 8.065E+006 86.55 30.70 8.670E+005 9.441E+005

4. 2 64E+005 105.31 21.10 1.136E+006 1.886E+005 5.574E+005

+

Tl-2 08 583.19*

85.00 1.460E+005 1.46E+005 1.540E+005 6.754E+004

+

Bi-211 351.07*

13.02 1.078E+006 1.08E+006 2.390E+006 5.120E+005 Pb-211 404.85 3.78

4. 3 08E+006 4.26E+006 -6.896E+005 2.054E+006 427.09

1. 76 9.042E+006

1. 638E+006

4. 2 99E+006 832.01 3.52 4.264E+006

1. 936E+006

1. 973E+006 Bi-21 2 39.86

1. 06 1.365E+007 2.38E+006 9.464E+006 6. 62 0E+006 727.33 6.67 2.379E+006 2. 314E+006 1.111E+006 785.37 1.10 1.456E+007

-2. 370E+006 6.787E+006 1620.50

1. 47 7.618E+006 2.083E+006 3.261E+006

+

Pb-212 11 5.18 0.60 3.880E+007 4.03E+005 7.954E+006 1.903E+0 07 238.63*

43.60 4.027E+005 4.633E+005 1.950E+005 300.09*

3.30 3.887E+006 5.393E+006 1.848E+006 Pb212-XR 74.82 10.28 2.716E+006

1. 59E+006 6.554E+006

1. 337E+006 77.11 17.10

1. 566E+006

2. 082E+006 7.804E+005 87.35 3.97 6.677E+006 5.826E+006 3.284E+006 89.78

1. 46

1. 739E+007

-1.863E+007 8.546E+006

+

Bi-2 14 609. 32

• 45.49 3.075E+005 3.07E+005

1. 235E+006 1.433E+005 768.36 4.89 3.843E+006

1. 913E+006 1.812E+006 806.18

1. 2 6

1. 2 58E+007

4. 383E+006 5.855E+006 934.06 3.11 5.906E+006 3.466E+005 2.761E+006 1120. 2 9*

14.92 8.583E+005

1. 398E+006 3.853E+005 1 155. 21

1. 63 1.119E+007 3.078E+006 5.190E+006 1238.12 5.83 3.507E+006 1.643E+006

1. 636E+006 1280.98

1. 43

1. 2 85E+007 2.544E+006 5. 937 E+006 1377.67 3.99 4.485E+006 2.948E+006 2.060E+006 1385.31 0.79 1.602E+007

-1. 046E+007 7.088E+006 1401.52

1. 33 1.135E+007

-1. 87 6E+OO 6 5.1 2 4E+006 1407.99 2.39 6.325E+006 3.474E+006 2.854E+006 1509. 21 2.13

6. 2 81E+006 3.145E+006 2.779E+006 1 661. 27

1. 05

1. 2 30E+007

4. 32 9E+005 5. 371E+006

[386]

,LV..L..L\\.A.C.

l.".ll...l.rl.

J.'\\.C.t:,JV..L. '-

_,, I

.J......JI £.. u..1. \\.J

""'1

• L..J * £.. V

..C J.*l I:Cl':::jC Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( ~)

(pCi/S me)

(pCi/S me)

(pCi/S me)

(pCi/S me)

+

Bi-2 14 1729.59 2.88 4.590E+006 3.07E+005 1.918E+006 2.004E+006 1764.49*

15.30 6.742E+005 1.488E+006 2.816E+005 1847.4 3 2.03 6.181E+006

1. 904E+006 2.661E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO Pb-214 241. 99*

7. 25 2.422E+006 3.94E+005 2.786E+006 1.173E+006 295.22*

18.42 6.963E+005 9.661E+005

3. 311E+005 351. 93*

35.60 3.941E+005 8.741E+005 1.873E+005 785.96

1. 06 1.514E+007

-3.926E+005 7.058E+006 Pb214-XR 74.82 5.80 4.814E+006 2.80E+006 1.162E+007 2.369E+006 77.11 9.70 2.796E+006 3.671E+006 1.376E+006 87.35 2.24 1.183E+007 1.033E+007 5.820E+006 89.78 0.82 3.096E+007. 317E+007 1.522E+007 Ra-226 186.21 3.64 5.549E+006 5.55E+006 6.154E+006 2.708E+006 Ac-228 129.07 2.4 2 8.868E+006 8.94E+005 -5.517E+006 4.343E+006 209. 2 5 3.89 4.625E+006

-4.325E+006 2.246E+006 270. 2 4 3.46 4.989E+006

-1.961E+005 2.408E+006 328.00 2.95 5.656E+006 1.427E+006 2.715E+006 338.32

11. 27 1.570E+006 7.916E+005 7.547E+005 409.46

1. 92 8.478E+006

1. 986E+006 4.040E+006 463.00 4.40 3.581E+006 9.82 6E+005 1.698E+006 794.95

4. 25

4. 2 42E+006

1. 063E+006

1. 992E+006 911. 20 25.80 8.942E+005

1. 257E+006

4. 2 43E+005 964.77 4.99 4.253E+006 3. 213E+006 2.005E+006 968.97 15.80 1.311E+006 1.139E+006 6.171E+005 1588. 2 0 3. 22 4.985E+006

1. 262E+006 2.246E+006

+

Pa-231 27.36*

10.30 8.580E+005 8.58E+005 -5.003E+003 4.079E+005 28 3.69

1. 70 9.859E+006

-1.087E+007 4.749E+006 300.07*

2.47 5.193E+006

7. 205E+006 2.469E+006 302.65 2. 2 0 7.833E+006

-1.951E+005 3.772E+006 330.06

1. 40

1. 205E+007 9.114E+006 5.785E+006 Th-234 92.38 2.13 1.188E+007 1.19E+007 3.259E+006 5.840E+006 92.80 2.10

1. 201E+007

1. 401E+006 5.902E+006 112.81

0. 21 1.104E+008

-8.241E+007 5.417E+007 U-235 143.76 10.96

1. 969E+006 3.54E+005

1. 274E+006 9.640E+005 163.33 5.08 3.942E+006 2.183E+006

1. 92 5E+006 185.71

57. 2 0 3.535E+005

4. 22 3E+005 1.72 5E+00 5 202.11

1. 08 1.723E+007

1. 301E+007 8.381E+006 205.31 5.01 3.665E+006

-3. 210E+006

1. 781E+006 Am-241 59.54 35.90 5.622E+005 5.62E+005 -4. 62 1E+004 2.750E+005

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[387]

GAMM A S P E C T R U M A N A L Y S I S

_lename: 5452 iport Generated On 1mple Title 1mple Description 1mple Identification 1mple Type 1mple Geometry iak Locate Threshold iak Locate Range (in channels) iak Area Range (in channels) lentification Energy Tolerance 1mple Size 1mple Taken On

quisition Started

.ve Time

al Time

,act Time 9/13/2 016 2 :58: 22 PM B306100BFRWC0l8GD Steam Tunnel Unit-1 018 1 meter

3. 00 85 -

85 -

10.000 81 92 81 92 keV 1.000E+OOO S meters 9/13/2016 2 :48:20 PM 600.0 seconds 601. 3 seconds

0. 22 %

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER DATA VALIDATED DATE J.. 1?.. L'l TIME 0,5:/S:

C2c~'ct

[388]

..L....,,

c...1..J _J.._ 1..J

'********************* *~" * **** ************ ******************* *************

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

545 2 Sample

Title:

B3 061 00BFRWC01 8GD Pea k Analysis Performed on:

9/13/2 01 6 2 :58: 22 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV)

Area Uncert.

Counts 1

286-306 300.7 1 74.83

1. 24 2.81E+00 2 119.3 0 9.03E+002 2

948 -

963 954.83 238.56 0.95 8.20E+001

51. 61 1.93E+002 3

1175-1188 1181. 32 2 95. 2 4

1. 05 7.48E+001 36.59 9.42E+001 4

1401-1416 1407.4 3 351.83

1. 71

1. 2 9E+002 37.12 7.15E+001 5

2326-2338 2331. 32 582.99 0.96 4.33E+001 24.09 3.87E+001 6

2428-2445 2436.39 609. 28 0.72 1.43E+002 33.58

4. 2 6E+001 7

4474-4486 4479.63 1120.25 0.57 3.34E+001 16.06 l.16E+001 8

5830- 5853 584 1. 97 1460.76

1. 96 3.11E+002 38.50 1.49E+001 First peak in a mult i p l et regi on Other peak in a multiplet region

= Fitted singlet

-rors quoted at 2. 000 sigma

[389]

../ /

.J......J/ £.. V.J..V

£..*..JU"&..,.£..

.1..1. *.i

'*** ******* f ***************************************** *******************

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

Title:

B306100BFRWC018GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES \\ Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Ba-133 Tl-208 Pb-2 12 Bi-2 14 Pb-214

1. 000 0. 321 1.000 0.975 0.35 0 0.977 1460.82*

79.61*

81. 00 276.40 302.85*

356.01*

383.85 583.19*

115.18 238.63*

300.09*

609.32*

768.36 806.18 934.06 1120.29*

1155.21 1238.12 1280.98 1377. 67 1385.31 1401.52 1407.99 1509.21 1661.27 1729.59 1764.49 1847.43 2118.51 2 41. 99*

295.22*

351. 93*

785.96 Yield

( % )

10.66 2.65 32.90 7.16 18.34 62.05 8.94 85.00 0.60 43.60 3.30

45. 49 4.89

1. 2 6 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 7. 25 18.42 35.60

1. 06 Activity (pCi/S me) 1.62673E+007

1. 70565E+007 9.47530E+005 5.33480E+005 1.75304E+005 3.85124E+0 05

5. 2 6597E+006 1.11028E+006

1. 08376E+006 2.31574E+006 9.43415E+005

9. 2 9844E+005

• =Energy line found in the spectrum.

Activity Uncertainty 2.45947E+006 8.02703E+006 4.87763E+005

1. 76145E+005 9.97835E+004 2.50325E+005 2.71275E+006 2. 922 75E+005 5.27869E+005 l.50429E+006 4.85477E+005 3.07038E+005

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2. 000 sigma

[390]

J.'-'--'-.L. '-"'.LVJ. J. '--

VV..L..L '-'--....... "-"'-

.L '"l.Vl,...J.. "..L'-::f

.l.'-'-.t:,--'V.l.. l,..

J

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r l"l

'*********** ****************** ** ******* ********************~************

I N T E R F E R E N C E C O R R E C T E D REPORT Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/S me)

Uncertainty K-40

1. 000

1. 62 6730E+007 2.459474E+006 Ba-133 0.321 2.174098E+005 8.172846E+005 Tl-208

1. 000

1. 753037E+005 9.978350E+004 X

Bi-211 0.999 Pb-212 0.975 2.91 9931E+005 3.435379E+005 Bi-214 0.350 1.104055E+006 2.556966E+005 Pb-214 0.977 5.854948E+005 1.292116E+006

? = 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 2.000 s igma Peak No.

U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Energy (keV)

Pea k Size in Counts per Second Al l peaks were identified.

P E A K S 9/13/2 01 6 85 81 92 Peak CPS 2 :58: 21 PM t Uncertainty Peak Type Tol.

Nuclide

[391]

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L..ll.J~

l.'\\.,;:;;j:J'\\J.L '-

J f

.J.....J/ L-V.L V

£..

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£...£...

.L L *.l

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N U C L I D E MD A R E P O R T Detector Name:

54 52 Sample Geometry:

1 meter Sample

Title:

B306100BFRWC018GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name

( keV)

('J)

(pCi/S me ) (pCi/S me)

(pCi/S me )

(pCi/S me)

+

K-40 1460.82*

10.66

1. 469E+006 1.47E+006

1. 627E+007 6.636E+005 Cr-51 320.08 9.91 1.605E+006

1. 61E+006 3.562E+004 7.694E+005 Mn-54 834.85 99.98

1. 656E+005 1.66E+005 4.489E+004 7.720E+004 Co-58 810.76 99.45 1.503E+005 1.50E+005

9. 202E+004 6.957E+004 Co-6 0 1173. 23 99.85 1.537E+005

1. 4 7E+005 -4.781E+004 7.016E+004 1332.49 99.98 1.466E+005 7.920E+00 3 6.615E+004 Nb-94 702.65 99.8 1 1.518E+005 1.41E+005 -5.720E+004 7.075E+004 871.09 99.89

1. 410E+005

-8.167E+004 6.474E+004 Sn-113 255.13 2.11

8. 358E+006 2.49E+005 2.510E+006 4.043E+006 391.70 64.97 2.493E+005

-1.234E+005 1.189E+005 Cs-134 475.36

1. 48 1.140E+007 1.76E+005 -4.943E+005 5.421E+006 563. 25 8.34 1.804E+006 4.161E+005 8.474E+005 569.33 15.37 9.788E+005

- 8.724E+004 4.595E+005 604.72 97.62 2.438E+005

- 1.579E+005 1.170E+005 795.86 85.46 1.762E+005 9.351E+004 8.169E+004 801. 95 8.69

1. 783E+006

-5.965E+005 8.284E+005 1038.61 0.99 l.595E+007 5.814E+006 7.340E+006 1167.97

1. 79 8.765E+006 2.070E+005 4.009E+006 1365.19 3.02 4.441E+006

-3.240E+006 1.981E+006 Cs-13 7 661.66

85. 10 2.025E+005 2.03E+005 1.218E+005 9.541E+004 Eu-152 121. 7 8 28.67 7.727E+005 6.09E+005 -2.067E+005 3.788E+005 244.70 7.61 2.519E+006

- 7.33 6E+005 1.223£+006 295.94 0.45 4.468E+007 2.105E+007 2.164E+007 344. 2 8 26.60 6.092E+005

-1. 691E+005 2.917E+005 367.79

0. 86 l.923E+007 1.546E+007 9.200E+006 411.12 2.24 7.489E+006 3. 810E+006 3.573E+006 443.96 2.83

5. 2 99E+006 1.5 23E+006 2.508E+006 488.68 0.4 2 3.736E+007 3.988E+006

1. 768E+007 563.99 0.49 2.976E+007

-7.034E+006 1. 3 95E+007 586. 2 6 0.46 4.244E+007 5.781E+006 2.020E+007 678.62 0.47 3.130E+007

- 3.076E+007 l.458E+007 688.67

0. 8 6 1.808E+007

- 8.587E+006 8.448E+006 719.35

0. 2 8 5.615E+007

- 8.319E+007 2.621E+007 778.90 12.96 1.187E+006 8.491E+004 5.517E+005 810.45 0.32 4.654E+007 1.460E+007 2.155E+007 867.37 4.26 3.469E+006 1.818E+006

1. 600E+006 919.33 0.4 3 3.534E+007

-1.146E+007

1. 62 9E+007 964. 08 14.65

1. 372E+006

-2.458E+005 6.444E+005 1085.87

10. 2 4 1.716E+006

-1.468E+005 7.950E+005 1089.74

1. 73 1.017E+007 2.157E+006 4.714E+006 1112.07 13.69

1. 288E+006 7.453E+005 5.962E+005 1212.95

1. 43 1.173E+007 5.986E+006 5.386E+006

[392]

,I...........L..LUC:.

.1*.J.J.J.C"l.

.L'-C:::t""V.L '-

J

/

.J.....J/ £..V --L V

£.. *...JU* £..£..

.L rl

.L. 01=:f C u

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

(% )

(pCi/S me)

(pCi/S me)

(pCi/S me)

(pCi/S me )

Eu-152 1249.94 0.19 9.173E+007

6. 09E+005 9.586E+006 4.221E+007 1299.14

1. 63 8.905E+006

- 3.929E+006 4.018E+006 140R.Ol

21. 07 7.620E+005

1. 77 9E+005 3.460E+005 1457.64 0.50 9.837E+007 3.687E+008 4.769E+007 1528.10

0. 28 4.564E+007 3.660E+007 2.007E+007 Eu-154 123.07 40.40 5.523E+005 4.87E+005 l.820E+004 2.707E+005 247.93 6.89 2. 60.6E+006

-7.170E+005

1. 2 62E+006 591.76 4.95 3.105E+006 2.2 77E+005 1.458E+006 692.4 2

1. 78 8.705E+006

1. 201E+006 4.066E+006 723. 30 20.06 9. 042E+005 8.947E+005 4.261E+005 756.80 4.52 3.300E+006 2.028E+006

1. 532E+006 873.18 12.08 1.103E+006

- l.655E+006 5.039E+005 996. 2 9 10.48 1.445E+006 7.614E+005 6.637E+005 1004.76 18. 01 8.536E+005 3.245E+005 3.924E+005 1274.43 34.80 4.874E+005 l.136E+005 2.236E+005 1596.48

1. 80 6.390E+006

-8.830E+004 2.751E+006 Eu-155 45.30

1. 31 1.170E+007 8.83E+005 5.922E+006 5.682E+006 60.01

1. 22 1.722E+007

5. 251E+006 8.429E+006 86.55 30.70 8.828E+005 8.011E+005 4.343E+005 105.31 21. 10 1.129E+006 3.879E+005 5.541E+005

+

Tl-2 08 583.19*

85.00 l.453E+005 1.45E+005 l.753E+005 6.719E+004 Bi-211 351.07*

13.02 1.010E+006

1. 01E+006 2.542E+006 4.782E+005 Pb-2 11 404.85 3.78 4.351E+006 4.35E+006 2.813E+006 2.075E+006 427.09

1. 76 9.076E+006 9.813E+005 4.316E+006 832.01 3.5 2 4.592E+006

-l. ll 7E+006 2.137E+006 Bi-2 12 39.86

1. 0 6 1.346E+007 2.74E+006

4. 245E+006 6.525E+006 72 7.33 6.67 2.741E+006 2.052E+006

1. 2 92E+006 785.37 1.10 1.477E+007 3.202E+006 6.892E+006 1620.50

1. 4 7 8.627E+006 4.053E+006 3.766E+006

+

Pb-212 115.18 0.60 3.900E+007 3.86E+005 2.318E+007 l.914E+007 238.63*

43.60 3.862E+005 3.851E+005 l.86'7E+005 300.09*

3.30 3.924E+006 5.266E+006 l.867E+006 Pb212-XR 74.82

10. 28 2.768E+006 1.59E+006 5.039E+005 l.363E+006

77. 11 17.1 0 1.587E+006 2.401E+005 7.807E+005 87.35 3.97 6.766E+006 2.044E+006 3.328E+006 89.78

1. 46 1.788E+007

-1.082E+007 8.789E+006

+

Bi-2 14 609. 32

• 45.49 3.208E+005

3. 21E+005 1.110E+006 l.499E+005 768.36 4.89 3.556E+006 2. 2 42E+006

1. 668E+006 806.18

1. 26 1.287E+007 1.322E+007 5.997E+006 934. 0 6 3.11 5.367E+006

1. 978E+006 2.492E+006 1120. 2 9*

14.92 6.821E+005

1. 084E+006 2.972E+005 1155. 21

1. 63 1.041E+007

- 5.261E+006 4.798E+006 1238.12 5.83 3.379E+006 6.104E+005 l.571E+006 128 0.9'8

1. 43 l.146E+007 9.189E+006 5.243E+006 1377.67 3.99 4.626E+006

5. 272E+006 2.130E+006 1385.31 0.79 1.737E+007

-4.198E+007 7.764E+006 1 401.5 2

1. 33

1. 236E+007

-5.060E+006 5. 62 9E+006 1407.99 2.39 6.706E+006 l.566E+006 3.045E+006 1509.21 2.13 5.996E+006

-2.805E+006 2.636E+006 1 661. 2 7

1. 05 9.157E+006 4.617E+006 3.798E+006

[393]

,L V

.L.LUC L".1LJI"'l.

l.'\\c:;.t-'V.L '-

J/..J......,I/L-V.J.. V

'-. v v

• L..L..

~ 4,

.L """" ';:1......

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV}

( !I: }

(pCi/S me}

(pCi/S me)

(pCi/S me)

(pCi/S me)

+

Bi-214 1729.59 2.88 5.174E+006 3. 21E+005

1. 23 8E+006 2.296E+006 1764.49 15.30

1. 650E+006 2.666E+006 7.693E+005 1847.43

2. 03 7.293E+006 3.578E+006 3.2 17E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 24 1. 99*

7.25 2.322E+006 3.69E+005 2.316E+006 1.123E+006 295. 22

• 18.42 7.029E+005 9.434E+005 3.344E+005 351.93*

35.60 3.694E+005 9.298E+005 1.749E+005 785.96

1. 06 1.536E+007 9.635E+006 7.168E+006 Pb2 14-XR 74.8 2 5.80 4.906E+006 2.80E+006 8.932E+005 2.415E+006 77.11 9.70 2.797E+006 4.232E+005 1.376E+006 87.35

2. 2 4 1.199E+007 3.623E+006 5.899E+006 89.78 0.8 2 3.183E+007

- 1. 926E+007 1.565E+007 Ra-22 6 186. 21 3.64

5. 744E+006 5.74E+006 5.360E+006 2.805E+006 Ac-22 8 129.07 2.42 9.348E+006 8.57E+005 6.911E+006 4.583E+006 209.25 3.89 5.025E+006 1.568E+006 2.446E+006 270.24 3. 46 5.142E+006 1.4 39E+006 2.485E+006 328.00 2.95 5.969E+006 4.985E+006 2.871E+006 338.32

11. 27 1.508E+006 4. 781E+005

7. 237E+005 409.46

1. 92 8.478E+006

-3.62 7E+006 4.040E+006 463.00 4.40 3.626E+006

-2.716E+006

1. 720E+006 794.95

4. 25 3.450E+006

-2.867E+006

1. 596E+006 911. 20 25.80 8.572E+005 4.636E+005 4.058E+005 964.77 4.99 4.074E+006 5.492E+005

1. 916E+006 968.97 15.80 1.339E+006 1.194E+006 6.312E+005 1588.20

3. 22 4.384E+006 2.769E+006

1. 945E+006 Pa-2 31 27.36 10.30 7.900E+005 7.90E+005 6.777E+005 3.739E+005 283.69

1. 70 9.880E+006 2.492E+005 4.759E+006 300.07 2.47 7.407E+006 3.292E+005 3.575E+006 302.65 2.20 7.899E+006 3.705E+006 3.804E+006 330.06

1. 40

1. 23 7E+007

4. 208E+006 5.945E+006 Th-23 4 92.38 2.13 l.194E+007 1.19E+007 2.797E+006 5.867E+006 92.80 2.10 1.204E+007 3.320E+006 5.918E+006 112.81

0. 21 1.110E+0 08

-8.544E+006 5.447E+007 U-235 143.76 10.96 2.015E+006 3.62E+0 05

1. 885E+006 9.873E+005 163.33 5.08

3. 989E+006 5.152E+005

1. 949E+006 185.71 57.20 3.617E+005 2. 31 7E+004

1. 766E+005 202.11

1. 08 1.777E+007

-8. 300E+006 8.649E+006 205.3 1 5.01 3.887E+006

-4.083E+005

1. 892 E+006 Arn-241 59.54 35.90 5.7ZOE+005 5.72E+005 -2.630E+005 2.799E+005

+ = Nuclide identified during the nuclide identification Energy line found in the spectrum Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[394]

GA MM A S P E C T R U M A N A L Y S I S

'*************************************************************i:*********

.lename: 54 52 iport Generated On 1mple Title tmple Description tmple Identification 1mple Type tmple Geometry iak Locate Threshold iak Locate Range (in channels )

iak Area Range (in channels) ientification Energy Tolerance 1mple Size tmple Taken On

quisition Started

.ve Time ial Time

!ad Time 9/ 13/201 6 3 :09: 35 PM B306100BFRWC0l9GD Steam Tunnel Unit-1 019 1 meter 3.00 85 -

85 -

10.000 8192 8192 keV 1.000E+OOO S meters 9/1 3/ 2 016 2 :59: 33 PM 600.0 seconds 601.3 seconds

0. 22 %

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER DATA-VALIDATED DATE l-i-\\l:\\

TIME 051s Q. sl'r:-,

[395]

P E A K A N A L Y S I S RE.PORT Detector Name:

5452 Sample

Title:

B306100BFRWC019GD Peak Analysis Performed on:

9/13/2016 3:09:35 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

81 92 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. s tart end centroid (keV )

(keV )

Area Uncert.

Counts 1

113-118 115.90 28.57 0.34 2.05E+001

21. 59 3.75E+001 2

2 88-306 300.67 74.8 2

1. 04 3.12E+002 106.81 7.49E+002 3

724-732 727.97 181. 78 0.43 1.76E+000

35. 33 l.43E+00 2 4

949-962 955.11 238.63 0.74 8.49E+001 45.58 1.57E+002 5

1172-1188 1181.27 2 95.23

1. 21 7.80E+001 42.74

1. 21E+002 6

1399-1417 1407.35 351. 81 1.11 1.69E+002 42.86 8.60E+001 7

2428-2444 2436.32 609.26

1. 37 1.51E+002 34.85 4.88E+001 8

3635-3651 3643.65 911.23 0.39 4.93E+001 17.57 8.67E+OOO 9

3729-3740 3734.67 933.99 0.66 8.00E+OOO 16.55 2.40E+001 10 447 2-4486 4479.94 112 0.33 0.41 4.44E+001 2 0.37 2.06E+001 11 5831-5853 5842.27 1460.84 2.01 3.11E+002 38.75

1. 68E+001 12 7052-7065 7058.37 1764.67

0. 4 6 3.62E+001 15.94 9.78E+OOO

= First peak in a multiplet region

= Other peak in a multiplet region Fitted singlet

• rors quoted at 2.000 sigma

[396]

.J(..J......J (

L.. V

..J...V

'************** *~ *******************************************************

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

Title:

B306100BFRWC019GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES \\ Zion Lib-BNL.NLB I DENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-4 0 Ba-133 Pb - 212 Bi-21 4 Pb-214 Ra-2 2 6 Th-2 31 U-235

1. 000 0.32 1 0.975 0.579 0.977 0.96 9 0.87 6 0.5 3 0 1460.82*

79.61*

81. 00 2 76.40 302.85*

356.01*

383.85 115.18 23 8.63*

300.09*

609. 32

• 768.36 806.18 934.06*

1120. 2 9*

1155. 2 1 1238.12 128 0.98 1377.67 1385.31 1401.52 1407. 99 1509. 2 1 1661. 2 7 172 9.59 1764.49*

1847.43 2118.51 2 41. 99*

2 95. 22

• 351.93*

785.96 186. 21*

25.64*

84.21*

89.95 143.76 1 63.33 185.71*

2 02.11 2 05. 3 1 Yield

(%)

10.66 2.65 32.90

7. 1 6

18. 34 62.05 8.94 0.6 0 43.60 3.30 45.49 4.89

1. 26 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.3 0 2.03 1.16

7. 2 5 18. 42 35.60

1. 06 3.64 14.10 6.60

1. 00 10.96 5.08

57. 20

1. 08 5.01 Activity (pCi/S me) 1.62752E+007 1.89156E+007 9.87523E+005 7.01482E+00 5 3.98743E+005 5.488 23E+006 1.17082E+006 1.13487E+006 1.43891E+006 1.48557E+006 2. 39763E+006 9.8 32 34E+005 1. 222 67E+006 8.58586E+004 2.34237E+005 7.59488E+006 5.4 63 73E+00 3 Activity Uncertainty 2.47071E+006 7. 53761E+006 5.63981E+005 2.10355E+005 2. 23654E+005 3.13623E+006 3.04 34 3E+005 2. 35 023E+006 6.70 350£+005 6.64561£+005 1.34 374£+006 5.61375E+005 3.66675E+005

1. 72 469E+006 2.52 418E+005 3.15037£+006 1.09753£+005

[397]

,1.,.__..._ __.&....._..1..1. _. _

.A.J.'-'"'- --'-Y...L. "'-_J

"-"'-.t"-"..._,._

Nuclide Id Energy Name Confidence (keV)

Yield

( ~ )

Activity (pCi/S me )

• = Energy line found in the spectrum.

..J

• V

../ *.J.J L l.-.l Activity Uncertainty

@=Energy line not used for Weighted Mean Activity Energy Tole rance :

10.000 keV Nuclide confidence index threshold =

0. 30 Errors quoted at 2.000 sigma

[398]

l LC:.L.L C::.L ClJ.\\......C::::

VV.J...L'C\\...,L. 'C \\..A I"l.\\.., L..J.. V.J..L.:f l.\\.Vt-'V.Ll..-

.J /

.J....J/ £..V..L V

'******************************** '~ **************************************

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Nuclide Id Name Confidence K-40 Ba-133

}(

Bi-211 Pb-212 Bi-214 Pb-214

?

Ra-226 X

Pa-231 Th-231

?

U-235 1.000 0.321 0.999 0.975 0.579 0.977 0.969 0.575 0.876 0.530 Wt mean Activity (pCi/S me )

1. 62 7518E+007 6.800565E+00 5 3.868268E+005 1.255050E+006 9.573848E+004 8.585859E+004 2.8 29502E+005 5.463728E+00 3 Wt mean Activity Uncertainty 2.470706E+006 9.497725E+005 3.449495E+005 2.542717E+005 1.493611E+006

1. 724686E+006 2.497917E+005 1.097527E+005

? = 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 quot ed at 2.000 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:

Peak Energy Peak Size in P E A K S 9/13/2016 85 8192 Peak CPS 3:09:35 PM No.

(keV )

Counts per Second t Uncertainty Peak Type 8

911. 23 8.2213E-002

35. 62 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at

2. 000 sigma Tol.

Nucl ide

[399]

J

/

..J......J/ £.. VJ..U

...J *V J*...J...J

.1.1*.l

.L a.~,;::;:

V N U C L I D E M D A R E P O R T

+

Detector Name:

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name K-40 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-113 Cs-134 Cs-137 Eu-152 Energy (keV) 1460.82*

32 0.08 834.85 810.76 1173. 23 1332.49 702.65 871.09 255.13 391. 70 475.36 563.25 569.33 604.72 795.86 801. 95 1038.61 1167.97 1365. 19 661. 66 121. 78 244.70 295.94 344. 2 8 367.79 411. 12 443.96 488.68 563.99 586. 2 6 678. 62 688.67 719.35 778.90 810.45 867.37 919.33 964.08 1085.87 1089.74 1112.07 1212.95 5452 1 meter B306100BFRWC01 9GD C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Yield

( 'o )

10.66 9.91 99.98 99.45 99.85 99.98 99.81 99.89 2.11 64.97

1. 48 8.34 15.37 97.62 85.46 8.69 0.99

1. 79 3.02 85.10 28.67 7.61 0.45 26.60 0.86 2. 2 4 2.8 3 0.4 2 0.49 0.46 0.47 0.86

0. 28 12.96 0.32 4.26 0.43 14.65

10. 2 4

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/S me)

(pCi/S me )

1.520E+006 1.571E+006 1.491E+005

1. 449E+005 1.682E+005

1. 321E+005 1.635E+005 1.592E+005 8.165E+006 2. 2 97E+005 9.926E+006

1. 773E+006 1.171E+006 2.566E+005 2.061E+005 1.934E+006 1.705E+007

9. 2 64E+006 4.772E+006 1.982E+005 7.852E+005 2.526E+006 4.489E+007 6.502E+005 1.803E+007 7.168E+006

5. 2 99E+006 3.819E+007

3. 256E+007

4. 259E+007 3. 500E+007

1. 771E+007 5.497E+007

1. 303E+006 4.488E+007 3.787E+006 3.392E+007 1.548E+006 1.494E+006 8.861E+006 1. 2 99E+006

1. 210E+007

1. 52E+006

1. 57E+006

1. 4 9E+005 1.45E+005

1. 32E+005 1.59E+005 2.30E+005 2.06E+005 l. 98E+005 6.50E+005 Activity (pCitS me )

1.628E+007

-8.416E+004 9.761E+002

-6.598E+004

1. 375E+005

-2.376E+004

-1.186E+005 6.144E+004 2.156E+005

-8.826E+004

-9.816E+006

-5.130E+006 6.613E+00 5

-7.846E+004 3.353E+004 2.643E+005

6. 32 7E+006

-8.182E+006 1.118E+006 2.853E+004

4. 7 92E+0 05 2.089E+006 5.505E+007

-3. 2 95E+005

-1.088E+007

-2. 387E+005

-5.102E+006 1.286E+007

-1.352E+007 4.247E+007

-3.627E+006

-5.895E+006

-6.531E+007

-7.520E+005

-1.241E+007

-2.354E+005

-2.483E+007

1. 82 8E+006

-5.903E+005 2. 22 5E+006

1. 203E+005 4.882E+006 Dec. Level (pCi/S me) 6.894E+005 7.522E+005 6.892E+004 6.689E+004 7.738E+004 5.891E+004 7.659E+004 7.388E+004 3.946E+006

1. 091E+005 4.682E+006 8.315E+005 5.557E+005 1.234E+005 9.665E+004 9.035E+005 7.891E+006 4.259E+006 2.146E+006

9. 32 6E+004 3.850E+005

1. 22 6E+006 2.174E+007 3.122E+005 8.598E+006 3.413E+006 2.508E+006

1. 809E+007

1. 535E+007 2.028E+007 1.643E+007

8. 2 63E+006 2.562E+007 6.095E+005 2.072E+007

1. 7 59E+006 1.558E+007 7.327E+005 6.842E+005 4.057E+006 6.018E+005 5.571E+006

[400]

,&.L,.L.l. \\..A.C l.".l.LJ.£"'1 l.'\\.Cf,JV.L 1,....

.J /.J.....J/

L V.LU

...J *VJ* J..J J:" l ' l l:"0':::JC::

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( :; )

(pCi/S me ) (pCi/S me )

(pCi/S me )

(pCi/S me )

Eu-15 2 1249.94 0.19 8.282E+007 6.50E+005 -2.864E+007 3.775E+007 12 99.14

1. 63 9.310E+006

-8.059E+006 4.221E+006 1408.01

21. 07 7.826E+005 4.384E+005 3.563E+005 1457.64 0.5 0 9.879E+007 3.562E+008 4.790E+007 1 52 8.10

0. 2 8 3.688E+007

-6.609E+006 1.569E+007 Eu-154 123.07 40. 40 5.427E+005 4.54E+005 -2.150E+005 2.659E+005 247.93 6.89 2.578E+006

-1.262E+006 l.248E+006 591.76 4.95 3.160E+006 5.468E+005

1. 485E+006 692.4 2

1. 78 8.882E+006

-3.028E+006 4.154E+006 723. 3 0 20.06 8.804E+005 4.164E+005 4.142E+005 756.80 4.52 3.191E+006

-3.749E+006

1. 4 77E+006 873. 18 12. 08

1. 3 07E+006 6.939E+005 6.062E+00 5 996. 2 9 10.48

1. 619E+006

- 1. 435E+006 7.506E+005 1004.76 18. 01 9.929E+005

-1. 869E+005 4.620E+005 1274.43 34.80 4.542E+005

-5.201E+005 2.070E+005 1596.48

1. 80 7.881E+006

-4. 217E+005 3.497E+006 Eu-155 45.30

1. 31 1.161E+007 8. 56E+005 5.385E+006 5.638E+006 60.01

1. 22 1.623E+007

-7.168E+006 7.935E+006 86.55 30.70 8.565E+005

1. 092E+006

4. 211E+005 105.31 21.10 1.106E+006 6.098E+005 5.426E+005 Tl-208 583.19 85.00 2. 2 82E+005 2. 28E+005 1.183E+005

1. 086E+005 Bi-21 1 351.07*

13.02 1.162E+006 1.16E+006 3.343E+006 5.544E+005 Pb-211 404.85 3.78 4.279E+006 4.07E+006 -1.799E+005 2.039E+006 427.09

1. 76 8.767E+006

-4.468E+006 4.161E+006 832.01 3.52 4.070E+006

9. 321E+004 1.876E+006 Bi-212 39.86

1. 06 1. 356E+007 2.77E+006 -l.612E+006 6.573E+006 727.33 6. 67 2.769E+006 1.554E+006

1. 306E+006 785.37 1.10 1.558E+007 3.167E+006 7.298E+006 1620.50

1. 4 7 8.141E+006

-2.508E+006 3.523E+006

+

Pb-212 115.18 0.60 3.851E+007 3.35E+005 -9.145E+006 1.889E+007 238.63*

43.60 3.350E+005 3.987E+005 1.611E+005 300.09*

3.30 4.696E+006 5.488E+006 2.253E+006 Pb212-XR 74.82 10.28 2.700E+006 1.54E+006 1.980E+005

1. 32 9E+006 77.11 17.10 1.541E+006

- 3.923E+005 7.580E+005 87.35 3.97 6.661E+006 1.185E+007 3.276E+006 89.78

1. 46

1. 7 53E+007

-9.766E+006 8.615E+006

+

Bi-214 609. 32*

45.49 3.355E+005 3.35E+005

1. l 71E+006 l.573E+005 768. 3 6 4.89 3.921E+006 3.597E+006

1. 851E+006 806.18

1. 2 6

1. 2 87E+007 1.208E+006 5.997E+006 934.06*

3.11 4.015E+006 1.135E+006

1. 815E+006 112 0. 2 9*

14.92 9.094E+005

1. 439E+006 4.108E+005 1155.21

1. 63 1.110E+007 9.025E+005 5.143E+006 1238.12 5.83 3.507E+006 2.723E+006

1. 636E+006 1280.98

1. 43

1. 343E+007 3.020E+006 6.227E+006 1377.67 3.99

4. 238E+006 3.301E+006

1. 936E+006 1385.31 0.79

l. 92 0E+007

-2.253E+007 8.680E+006 1401.52

1. 33 1.081E+007

-2.009E+007 4.852E+006 1407.99 2.39 6.888E+006 3.859E+006 3.136E+006 1509.21 2.13 7.643E+006 1.071E+006 3.460E+006 1661.27

1. 05 9.618E+006

8. 336E+005 4.02 8E+006

[401]

lL..L.LUC:

l'lLJrl r..c: 1-1v-'- L-

.;//

.L.J /

L. V.LU

...J *V J*..J.J

.C l'"'l

.C-0'::J C:

u Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( ~)

(pCi/S me)

(pCi/S me)

(pCi/S me)

(pCi/S me)

+

Bi-21 4 1729.59 2.88

4. 590E+006 3.35E+00 5

1. 615E+005 2.004E+006 1764.49*

15.30 8.161E+005 1.486E+006 3.526E+005 1847.43 2.03

7. 122E+006 3.741E+006 3.132E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 241.99*

7.25 2.014E+006

4. 25E+005 2.398E+006 9. 688E+005 2 95. 22

• 18.42 8.413E+005 9.832E+005 4.036E+005 351.93*

35.60

4. 251E+005

1. 22 3E+006 2.028E+005 785.96

1. 06 1.610E+007 6.949E+005 7.538E+006 Pb214-XR 74.8 2 5.80 4.786E+006

~.72E+006 3.509E+005 2.355E+006 77.11 9.70 2.717E+006

-6.917E+005 1.336E+006 87.35 2. 2 4 1.181E+007 2.100E+007 5.806E+006 89.78 0.82 3.121E+007

-1. 739E+007 1.534E+007

+

Ra-22 6 186. ~1*

3.64 2.961E+006 2.96E+006 8.586E+004

1. 415E+006 Ac-22 8 129.07 2.42 8.857E+006 7.77E+005 -2.646E+006

4. 338E+006 209. 25 3.89 4.907E+006 2.721E+006 2. 387E+006 270. 2 4 3.46 4.999E+006

-1.065E+006 2.413E+006 328.00 2.95 5.543E+006

1. 637E+006 2.658E+006 338.32

11. 27 1.581E+006

1. 979E+006 7.600E+005 409.46

1. 92

8. 243E+006

-6.847E+006 3.923E+006 463.00 4.40 3.699E+006

1. 613E+006

1. 7 57E+006 794.95 4.25 4.167E+006 7.136E+005

1. 955E+006 911. 2 0 25.80 7.774E+005 2. 276E+005 3.659E+005 964.77 4.99 4.567E+006 5.859E+006 2.162E+006 968.97 15.80 1.433E+006

1. 941E+006 6.780E+005 1588.20 3.22 4.652E+006 4.379E+006 2.079E+006 Pa-231 27.36*

10.30 5.455E+005 5.45E+005 3.207E+005 2.516E+005 283.69

1. 70 9.550E+006

-9.460E+005 4.594E+006 300.07*

2.47 6.274E+006

7. 332E+006 3.010E+006 302. 65 2. 2 0 7.633E+006

4. 233E+005 3.671E+006

.3.30.06

1. 40 1.160E+007 1.901E+005 5.561E+006 Th-23 4 92.38 2.13 1.172E+007 l.1 7E+007 - 1. 396E+005 5.758E+006 92.80 2.10 1.188E+007 5.3 09E+006 5.837E+006 112.81 0.21 1.087E+008 6.404E+007 5.332E+007

+

U-235 143.76 10.96 1.879E+006

1. 88E+00 5 3. 52 7E+005 9.189E+005 163.33 5.08 3.861E+00 6

-9.8 51E+004

1. 885E+006 185.71*

57. 2 0 1.884E+005 5.4 64E+003 9.001E+004 202.1 1

1. 08 1.696E+007

- 6.453E+006

8. 243E+006 2 05.31 5.01 3.712E+00 6

- 1. 074E+006

1. 805E+006 Am-241 59.54 35.90 5.466E+005 5.47E+005 - 1. 786E+005 2.672E+005

+

Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[402]

GA MM A S P E C T R U M A N A L Y S I S

.lename: 54 52

~ort Generated On tmple Title tmple Description tmple Identificat ion tmple Type tmple Geometry iak Locate Threshold iak Locate Range (in channels )

iak Area Range (in channels) ientification Energy Tolerance tmple Size tmple Taken On

quisition Started

.ve Time ial Time iad Time 8/10/20 1 6 2 :41:40 PM B306100BFRFC020GD ST FLOOR NUMB20 SHOT 3METERS 2 0 3.00 85 -

85 -

10.000 8192 8192 keV 1.000E+OOO SQM 8/1 0 / 2 01 6 2 :31:38 PM 600.0 seconds 600.9 seconds 0. 15 %

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency I D 1/13/2 015 8/2 /2016 STEAMTUNNELSTS DATA VALIDATED DATE I- ~-LCZ TIME CJ,~0 G)b~~~

[403]

.,(..,L,J'!rt.

LJ.J.J.~-'-.:t LJ..LLJ J."'--',t-"..._,, -'- '-

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

54 52 Sample

Title:

B306100BFRFC0~0GD Peak Analysis Performed on:

8/10/2016 2 :41:4 0 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV)

Area Uncert.

Counts 1

113-1~0 115.89 2 8.56 0.51 2.96E+001 25.0 3 4.64E+001 2

2 95-319 300.58 74.80 0.82 9.75E+001 79.07 3.49E+002 3

948-959 95 3.77 238. 2 9 0.47 5.69E+001 25.14 4.0lE+OOl 4

2327-2339 2332.06 583.18 0.91 3.04E+001 17.57 1.76E+001 5

2 429-2 442 2436.05 609.19

0. 53 5.79E+001

21. 21 1.91E+001 6

4474-4485 4479.46 1120. 2 1 0.57 2.lOE+OOl 10.68 3.00E+OOO 7

5829-5852 5841.56 1460.66

1. 45

1. 58E+00 2 2 9.51 1.49E+001 8

7049-7062 7055.99 1764.07 0.37 1.61E+001

11. 09 4.93E+OOO

= First peak in a multiplet region

= Other peak in a multiplet region Fitted singlet

-rors quoted at 2.000 sigma

[404]

.1...1...

.I......

.&..1-.J

'***~***********************************~**************** ~**************

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

Title:

B306100BFRFC020GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV)

( % )

(pCi/SQM )

Uncertainty K-40

1. 000 1460.82*

10.66 1.07779E+006 2.21910E+005 Tl-208

1. 000 583.19*

85. 00 1.66104E+004 9.79553E+003 Pb-2 12 0.87 2 115.18 0.60 238.63*

43.60 3.85771E+004 1.81532E+004 300.09 3. 30 Bi-214 0.531 609.32*

45.49 6.02931E+004 2. 32 600E+004 768.36 4.89 806.18

1. 2 6 934.06 3.11 112 0. 2 9*

14.92

8. 91566E+004 4.58954E+004 1155. 21

1. 63 1238. 12 5.83 1280.98

1. 43 1377.67 3.99 1385.31 0.79 1401. 52

1. 33 1407.99 2.39 1509.21 2.13 1661. 27

1. 05 1729.59 2.88 1764.49*

15.30 8.5 6334E+004 5.95134E+004 1847.43 2.0 3 2118.51 1.16 Th-2 31 0.876 25.64*

14.10 4.92955E+004 4.33171E+004

84. 21*

6.60 3.47 252E+005 2.93015E+005 89.95

1. 00

• = Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2.000 sigma

[405]

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Nuclide Id Name Confidence K-40 Tl-208 Pb-212 Bi-214 X

Pa-231 Th-231

1. 000

1. 000 0.872 0.531 0.378 0.876 Wt mean Activity (pCi/SQM )

1.077787E+006 l.6610 37E+004 3.857709E+004 6.82 9853E+004 5.566791E+004 Wt mean Activity Uncertainty 2. 219100E+005 9.795534E+003

1. 8153 20E+004

1. 9591 20E+004 4.285134E+004

? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysi s

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma Peak No.

U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Energy (keV)

Peak Size in Counts per Second All peaks were identified.

P E A K S 8/10/2 01 6 85 81 92 Peak CPS

• • • • • • • • +*

2 :41:40 PM

~' Uncertainty Peak Type Tol.

Nuclide

[406]

.&.\\._t' _ _._.....

'*** *********** *********************************************************~******

N U C L I D E M DA R E P O R T

+

Detector Name:

5452 Sample Geometry:

Sample

Title:

B306100BFRFC020GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL. NLB Nuclide Name K-4 0 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-113 Cs-134 Cs-137 Eu-1 52 Energy (keV) 1460.8 2*

320.08 834.85 810.76 117 3. 23 1332.49 702.65 871. 09 255.13 391. 70 475.36 563.25 569.33 604.72 795.86 801. 95 1038.61 1167.97 1365.19 661. 66 121.78 244.70 295.94 344. 2 8 367.79 411.12 443.96 488.68 563.99 586.26 678.62 688.67 719.35 778.90 810.45 867.37 919.33 964.08 1085.87 1089.74 1112.07 1212.95 Yield

( >; )

10.66 9.91 99.98 99.45 99.85 99.98 99.8 1 99.89 2.11 64.97

1. 48 8.34 15.37 97.62 85.46 8.69 0.99

1. 79 3.02 85.10 28.67 7.61 0.45 2 6.60 0.86 2. 2 4 2.83 0.42 0.49 0.46 0.47 0.86 0.28 12.96 0.32

4. 2 6 0.43 14.65 10.24

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/SQM

)

(pCi/SQM)

Activity (pCi/SQM) 1.917E+005

1. 587E+005

1. 61 7E+004 1.559E+004 1.685E+004 1.4 2 9E+004 1.92E+005 1.59E+005 1.62E+004 1.56E+004 1.43E+004 1.724E+004

1. 51E+004

1. 507E+004

8. 318E+005 2. 42E+004 2.419E+004 1.010E+006 1.95E+004 1.797E+005 1.032E+005 2. 348E+004 -

1. 950E+004

1. 723E+005

1. 544E+006 9.706E+005 3.861E+005

2. 1 03E+004 2.10E+004 6.350E+004 6.06E+004 2.171E+005 4.133E+006 6.065E+004 1.914E+006 6.532E+005 5.792E+005 3.856E+006 3.11 9E+006 4.402E+006

3. 2 81E+006 2.025E+006 6.172E+006 1. 1 40E+005 4.900E+006 3.809E+005 4.015E+006

1. 2 16E+005

1. 464E+005 8.682E+005

1. 219E+005 1.177E+00 6 1.078E+006 2.509E+004

- 1.12 8E+004

1. 049E+004

- 3. 2 43E+002 9.191E+001 8.702E+003 7.425E+003 5.083E+005

-1.057E+004 3.567E+005

- 1. 301E+005

-7.502E+00 3

-4.979E+00 3

-6.794E+003

-1. 2 60E+005

6. 32 4E+005 5.650E+005 5.792E+00 3 1. 059E+004

- 1.196E+004

- 5.910E+004 1.036E+006

-3.547E+004

-4.571E+005

-6.384E+005 2.287E+005 3.898E+006

-1.126E+006 4.645E+006

-2.674E+005 1.085E+006

-1.224E+006

-3.362E+004 3.418E+006 2. 2 45E+004 4.462E+005 2.442E+004

-7.073E+004

5. 381E+005 9.523E+004

-7. 271E+005 Dec. Level (pCi/SQM )

8.661E+004 7.466E+004

7. 343E+003 7.059E+003 7.545E+003

6. 211E+003 7.9 34E+00 3 6.778E+00 3 3.963E+005 1.131E+004 4.664E+005

8. 2 44E+004 4.756E+004 1.108E+004 8.898E+00 3 7.776E+004 6.883E+005 4.365E+005 1.617E+005 9.731E+003 3.063E+004 l. 032E+005

1. 967E+006 2.851E+004 8.992E+00 5 3.031E+005 2.703E+005

1. 791E+006

1. 434E+006 2.064E+006

1. 497E+006

9. 33 5E+005 2.837E+006 5.143E+004 2. 22 2E+006

1. 727E+005

1. 825E+006 5.536E+004 6.497E+004 3.852E+005 5.469E+004

5. 2 61E+005

[407]

... _...1.....L--

~...,_,......

~"'-"t""'_..........

V/..1..V /

'-oV..l..l>J L.,. ".I... -;a.

..L.

~.,

.L.. (,..l.':1 '-

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( %)

(pCi/SQM )

(pCi/SQM )

(pCi/SQM )

(pCi/SQM )

Eu-152 1249.94 0.19 6.157E+006 6.06E+004 -1.720E+007 2.600E+006 1299.14

1. 63 l.048E+006 7.112E+005 4.674E+005 1408.01

21. 07 7.199E+004

- 1. 773E+004 3.143E+004 1457.64 0.50 9.475E+006 2.436E+007 4.542E+006 1528.10

0. 2 8

4. 2 03E+006

4. 22 2E+005

1. 743E+006 Eu-154 123.07 40.40 4.681E+004 3. 78E+004

1. 406E+004 2. 261E+004 247.93 6.89 2. 3 68E+005 1.699E+005 1.125E+005 591.76 4.95 2. 927E+005

-3. 280E+005

1. 33 6E+005 692.42

1. 78 9.422E+005

-3. 384E+005

4. 32 7E+005 723.30 20.06

8. 331E+004

-2.553E+004 3.819E+004 756.80 4.52 3.690E+005

1. 917E+005

1. 688E+005 873.18 12.08 1.227E+005 4.160E+004 5.507E+004 996. 2 9 10.48 1.634E+005

-7.440E+004 7.399E+004 1004.76 18.01 8.822E+004

-2.4 2 9E+004 3.959E+004 1274.43 34.80 3.775E+004

-7.379E+00 3 1.625E+004 1596.48

1. 80 8.588E+005 3.034E+005 3.716E+005 Eu-155 45.30

1. 31 1.121E+006

7. 31E+004 4.855E+005 5.360E+005 60.01

1. 22

1. 332E+006

-4. 206E+00 5 6.400E+005 86.55 30.70

7. 312E+004 1.003E+00 5 3.552E+004 105.31

21. 10

9. 594E+004 1.079E+004 4.645E+004

+

Tl-208 583.19*

85.00

1. 375E+004

1. 38E+004 1.661E+004 6.139E+00 3 Bi-211 351. 07 13.02 1.631E+005 1.63E+005 2.099E+005 7.783E+004 Pb-211 404.85 3.78 4.341E+005 4.34E+005 -4.324E+004 2.032E+005 427.09

1. 76 8.249E+005 9.585E+004 3.819E+005 832.01 3. 52 4.523E+005

-1. 250E+005 2.050E+005 Bi-212 39.86

1. 06

1. 340E+006 2.54E+005 9.674E+004 6.400E+005 727. 33 6.67 2.540E+005 3.037E+004 1.165E+005 785.37 1.10

1. 3 46E+006

-6.447E+005 6.072E+005 1620.SO 1.47 8.356E+005

4. 213E+005 3.466E+005

+

Pb-212 115.18 0.60 3.101E+006 2.43E+004 - 2.582E+005 J.497E+006 238.63*

43.60 2. 427E+004 3.858E+004 l.122E+004 300.09 3.30 5. 248E+005

-5.121E+005 2.488E+005 Pb212-XR 74.82 10.28 2.411E+005 1.38E+005 3.498E+004

1. l 75E+005 77.11 17.10

1. 37 5E+005 6.527E+003 6.691E+004 87.35 3.97 5.557E+005 3.124E+005 2.698E+00 5 89.78

1. 46 1.469E+006

-2.842E+005 7.128E+00 5

+

Bi-2 14 609.32*

45.49 2.815E+004

2. 82E+004 6.029E+004

1. 2 67E+004 768.36 4.89 3.811E+005

-2.128E+004

1. 759E+005 806.18

1. 2 6 1.150E+00 6

1. 497E+005 5.170E+005 934.06 3.11 5.573E+00 5 4.129E+005 2.534E+005 112 0. 2 9*

14.92 4.976E+004 8. 916E+004 1.914E+004 1155. 2 1

1. 63

l. 175E+006 1.068E+006

5. 3 40E+005 1238.12 5.83 3.446E+005 9.745E+004 1.569E+005 1280.98

1. 43 9.185E+005 2. 257E+005 3.954E+005 1 377.67 3.99 3.955E+005

-1.889E+005

1. 7 3 9E+005 1385.31 0.79

1. 788E+006

-1. 746E+005 7.737E+005 1401.52

1. 33

1. 039E+006

-4.453E+005 4.476E+005 1407.99 2.39 6.336E+005

-1. 560E+005 2.766E+005 1509. 21 2.13 7.421E+005 3.149E+005

3. 2 39E+005 1661. 27

1. 05 9.017E+005 3.003E+005 3.493E+005

[408]

.. ------ **-** **-£" __ _

.l..1..

~.,

.,_ \\..,,I,'='......

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV )

( z )

(pCi/SQM )

(pCi/SQM )

(pCi/SQM )

(pCi/SQM )

+

Bi-214 1729.59 2.88 4.441E+005 2.82E+004 2. 239E+005 1.842E+005 1764.49*

15.30 8.164E+004 8.563E+004 3. 361E+004 1847.43 2.03 6.188E+005 2.885E+005 2.53 6E+00 5 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO Pb-2 14 241. 99

7. 25 2.704E+005 5.91E+004 -6.667E+004 l.297E+005 295. 22 18.42 1.008E+005

1. 885E+004 4.796E+004 351. 93 35.60 5.915E+004 7.172E+004 2.821E+004 785.96

1. 06 1.442E+006

7. 239E+005 6.529E+005 Pb214-XR 74.82 5.80

4. 274E+005 2.4 2E+005 6. 2 00E+004 2.082E+005 77.11 9.70 2.425E+005 1. 151E+004 1.179E+005 87.35 2.24 9.849E+005 5.537E+005 4.782E+005 89. 78 0.82 2.616E+006

-5.059E+00 5 1.2 69E+006 Ra-22 6 186. 21 3.64 4.569E+005 4.57E+00 5

5. 22 8E+004 2.187E+005 Ac-22 8 129.07 2.42 7.375E+005 7.99E+004 - 3.032E+005 3.553E+005 209.25 3.89 4.165E+005

- 6.574E+005 1.986E+005 27 0.24 3.46 4.866E+005 3.664E+005 2. 310E+005 328.00 2.95

5. 3 67E+005 3.198E+004 2. 52 4E+005 338.32

11. 27

1. 562E+00 5 2.033E+004

7. 38 7E+004 409.46

1. 92 7.903E+00 5

-1. 682E+005 3.678E+005 463.00 4.40

3. 345E+005 5. 814E+004 1.545E+005 794.95 4.25 3.919E+005

9. 239E+004

1. 788E+005 911. 2 0 25.80 7.986E+004 1.914E+004

3. 693E+004 964.77 4.99 3.663E+005 l.817E+005

l. 672E+00 5 968.97 15.80

1. 229E+005

-2.470E+003 5.637E+004 1588. 2 0 3. 22

4. 92 3E+005 3.563E+005 2.140E+005 Pa-23 1 27.36*

10. 30 9.076E+004 9.08E+004 6.748E+004 4.22 9E+004 283.69

1. 70 9.346E+005

-9.619E+005 4.416E+005 300.07 2.47 7.0llE+OOS

- 6.842E+005 3.324E+005 302.65 2.20 7.670E+005 4.130E+005 3.630E+005 330.06

1. 40

l. 141E+006 7.022E+004 5.367E+005 Th-23 4 92.38 2.13 9.596E+005 9. 60E+005 -3.051E+004 4.648E+005 92.80 2.10 9.734E+005

-5. 29 4E+004 4.715E+005 112.81

0. 21

9. 254E+006

-9.7 27E+005 4.475E+006 U-235 143.76 10.96

1. 583E+005 2.94E+004 -7.1 36E+004 7.615E+004 163.33 5.08 3. 312E+005

-9.164E+004 1.589E+005 185.71 57.20 2.937E+004

1. 395E+004

1. 406E+004 2 02.11

1. 08

1. 642E+006

1. 2 83E+006 7.869E+005 205.31 5.01 3.490E+005

-4. 23 9E+004

1. 671E+005 Am-241 59.54 35.90 4.527E+004 4.53E+004 -1. 63 6E+003 2. 175E+004

+

Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calcula t ed

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

[409]

GA MM A S P E C T R U M A N A L Y S I S

'************************************************************ ~**********

.lename: 5452 iport Generated On tmpl e Title tmple Description tmple Identification 1mple Type 1mple Geometry iak Locate Threshold iak Locate Range (in channel s )

iak Area Range (in channels) lentification Energy Tolerance tmple Si ze tmple Taken On

quisition Started

.ve Time ial Time

!ad Time 8/10/2016 4: 37: 2 6 PM B306100BFQWC0l1GD ST SE. WALL NUMB 11 SHOT Q-:--11

3. 00 85 -

85 -

10.000 8192 8192 keV

1. OOOE+OOO SQM 8/10/2 016 4:27:24 PM 600. 0 seconds 601.0 seconds 0.16 %

Energy Calibration Us ed Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER DATA VALIDATED DATE/-f.,./2 TIME 5,20 Q.~~

[410]

U/.l.V/ L. V.l.U

<:t *..J I

• L U

r 1'1 P E A K A N A L Y S I S R E P O R T Detector Name:

54 52 Sample

Title:

B306100BFQWC0 11GD Peak Analysi s Performed on:

8/10/2 016 Peak Analysi s From Channel:

Peak Analysi s To Channel:

4:37: 2 5 PM 85 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV )

1 2

3 4

5 6

7 8

9 10 11 12 114 -

2 97-946-1175-1401-2037-2325-2427-2903-3637-4475-5831-127 308 963 11 88 1 414 2052 2337 2441 2914 3651 4487 5854 122. 11 300.83 954.60 1180.47 1407.16 2043.90 2331. 09 2435.38 2908.15 3643.27 448 0. 2 1 5841. 71 30.12 74.86 238.50 2 95.03 351.76 511. 08 582.93 609.02 727.28 911. 13 1120.40 14 60.70

= First peak in a multiplet region

= Other peak in a multiplet region Fitted singlet

• rors quoted at 2.000 sigma (keV)

Area Uncert.

Counts 0.54 1.11

1. 36 1.12 0.77 0.59 1.12 1.11 0.48

1. 06 0.80

1. 59 1.10E+002 1.53E+002 1.09E+00 2 6.77E+001

1. 34E+00 2 6.60E+00 1 3.72E+001

1. 42E+002

1. 55E+001 4.76E+001 2.94E+001 3.46E+002 39.82

71. 21 49.56 33.97 35.09 28.8 0

19. 02 30.19 16.40 19.84 16.17 40.70 8.78E+001 4.40E+002 1.55E+002 7.93E+001

6. 21E+001 4.70E+001 1.98E+001 3.03E+001 2.05E+001 1.74E+001 1.36E+001 1.74E+001

[411]

U/..J..V/ £.. V..LU

""J:

...I J

• L.. U L l.-.l

'***************** ~************* ****************************************

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

• * * -~

• Sample

Title:

B306100BFQWC0l1GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Sr-85 Ba-133 Tl-208 Bi-21 2 Pb-212 Bi-2 14 Pb-214 Th-23 1

1. 000 0.986

0. 32 0

1. 000 0.64 2 0.974 0.35 0 0.97 6 0.865 1460.82*

514. 01

• 79.61*

81. 00 276.40 302.85*

356.01*

383.85 583. 19*

39.86*

727.33*

785.37 1 62 0.50 115.18 238.63*

300.09*

609.32*

768.36 806.18 934. 0 6 112 0. 2 9*

1155. 21 1238.12 1280.98 1377.67 1385.31 1401. 52 1407.99 1509. 21 1661. 2 7 172 9.59 1764.49 1847.43 2 118.51 241.99*

2 95. 22

• 351.93*

785.96 25.64*

84. 21*

89.95 Yield

( ';;)

10.66 96.00 2.65 32.90 7.16 18.34 62. 05 8.94 85.00

1. 06 6.67 1.10

1. 47 0.60 43.60 3.30

45. 49 4.89

1. 2 6

3. 11 14.92

1. 63 5.83

1. 43 3. 99 0. 79

1. 33 2.39

2. 1 3

1. 05 2.88 15.30 2.03 1.16 7.25 18.42 35.60

1. 06 14.10 6.60

1. 00 Activity (pCi/SQM )

1.80715E+007 2.19522E+005

9. 30853E+006 8.57092E+005 5.55692E+005 1.50766E+005 1.67213E+007 8.95994E+005 5.14122E+005 4.76335E+006 1.09702E+006 9.54217E+005 3.09140E+006 8.53370E+005 9.68558E+005

1. 25 7 07E+006 3.7 3752E+006 Activity Uncertainty 2.644 23E+006 1.00303E+005 4.7 1743E+006 4.51526E+005 1.70621E+005 7.91145E+004 7.46497E+006 9.55596E+005 2.47 208E+005 2.51114E+006 2.68337E+005

5. 2 9837E+005 1.48483E+006 4.49417E+005 2.97413E+005 5.43256E+005 1.942 43E+006

[412]

l LC.L.LC.LC::1!1 *..-C::

1....-U.L.L C::l....- l-C::U

!"1v l-.J.V.J.l- _y nc::l-'u.L l-Nuclide Id Energy Name Confidence (keV)

Yield

( ~)

U/.J-V/ L. U..LU Activity (pCi/SQM)

• = Energy line found in the spectrum.

Activity Uncertainty

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2.000 sigma

[413]

U/..J... V/ L...V..J...

V

'* 1****+************************* ******* +********************************

I N T E R F E R E N C E C O R R E C T E D R E P O R T

'********************* ~*************************************************

Nuclide Nuclide Id Name Confidence K-40 Sr-85 Ba-133 Tl-208 X

Bi-211 Bi-212 Pb-212 Bi-214 Pb-214 X

Pa-231 Th-231

1. 000 0.986

0. 32 0

1. 000 0.999 0.642 0.974 0.350 0.976 0.569 0.865 Wt mean Activity (pCi/SQM )

1.807154E+007 2.195222E+005 4.046267E+005 1.507664E+005 8.534032E+005 4.691 333E+005 1.067871E+006 2.940598E+005 1.360139E+006 Wt mean Activity Uncertainty 2.644231E+006 1.003031E+005 7.611938E+005 7.911445E+004 9.546639E+005 3.307281E+005 2.393869E+005 1.195151E+006 5.053652E+005

? = 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 2.000 sigma U N I D E N T I F I E D Peak Locate Performed on:

Pea k Locate From Channel:

Pea k Locate To Channel:

Peak Energy Peak Size in P E A K S 8/10 /2 016 85 8192 Peak CPS 4:37: 2 5 PM No.

(keV)

Counts per Second

% Uncertainty Peak Type 10 911. 13 7.9256E-002

41. 73 Sum M

First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma Tol.

Nuclide

[414]

V/..J..V/ L..V..J..V

""'3:

• -' I L.. V

.L..1.-.l

.L U.'::::tV V

N U C L I D E MD A R E P O R T

+

Detector Name:

5452 Sample Geometry:

Sample

Title:

B306100BFQWC011GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Name K-40 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-11 3 Cs - 134 Cs - 137 Eu-152 Energy (keV) 1460.8 2

• 32 0.08 834.85 810.76 1173. 23 1332.49 702.65 871. 09 255.1 3 391. 70 475. 3 6 563. 2 5 569.33 604.72 795.86 801.95 1038.61 1167.97 1365.19 661.66 121.78 244.70 295.94 344. 2 8 367.79 411. 12 443.96 488.68 563.99 586. 2 6 678.62 688.67 719.35 778.90 810.45 867.37 919.33 964.08 1085.87 1 089.74 1112.07 1212.95 Yield

( ~)

10.66 9.91 99.98 99.45 99.85 99.98 99.81 99.89 2.11 64.97

1. 48 8.34 15.37 97.62 85.46 8.69 0.99

1. 79 3.02 85.10 28.67 7.61 0.45 2 6.60 0.86 2. 2 4 2.8 3 0.4 2 0.49 0.46 0.47 0.86

0. 2 8 12.96 0.32 4.26 0.43 14.65 10.24

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/SQM) (pCi/SQM)

Activity (pCi/SQM )

l.566E+006

1. 622E+006

1. 569E+005

1. 733E+005

1. 716E+005 l.511E+005 1.551E+005

l. 3 94E+005 8.081E+006 2.635E+005

1. 046E+007

1. 804E+006 9.903E+005 2.497E+005 l.747E+005

1. 798E+006 1.690E+007 l.018E+007 4.441E+006 l.713E+005

7. 2 40E+005 2. 23 9E+006 4.146E+007 5.885E+005 1.730E+007

7. 218E+006 5.483E+006 3.803E+007 3.066E+007 3.881E+007 3.479E+007

1. 613E+007 5. 251E+007

1. 2 59E+006

5. 2 97E+007 3.002E+006 3.568E+007

1. 380E+006

1. 460E+006

9. 2 57E+006

1. 218E+006

1. 2 69E+007 1.57E+006 1.62E+006 1.57E+005 1.73E+005 1.51E+005

1. 3 9E+005 2.64E+005

1. 75E+005 1.71E+005 5.89E+005 1.807E+007 5.782E+005

-3.495E+004 2.920E+004

5. 2 48E+004 5.923E+004

-2.063E+004

-6.669E+003

1. 438E+00 6 6.8 3 8E+004

-1.016E+007 5.741E+005 9.082E+005

-6.432E+004 3.314E+004

-1. 036E+006 O.OOOE+OOO 8.534E+005 5.557E+005

-1.049E+005 6.858E+004

- 3.372E+005 2.232E+007

-3.869E+004

-9.566E+006

-1.803E+006

-4.831E+006 2.341E+007

- l.471E+007 5.373E+007 2.311E+007

-8.592E+006 8.497E+006

-1.847E+005

-9.461E+006

-2.930E+006

-2.429E+007 6.654E+005

-1. 496E+006

1. 930E+006

- 1. 2 78E+006

6. 007E+006 Dec. Level (pCi/SQM )

7.120E+005 7.779E+005

7. 286E+004 8.109E+004 7.908E+004 6.839E+004

7. 2 39E+004

6. 3 98E+004 3.904E+006

1. 2 60E+005 4.949E+006 8.474E+005 4.65 2E+005

l. 2 00E+005 8.094E+004 8.355E+005 7.814E+006 4.718E+006

1. 981E+006 7.982E+004 3.544E+005

1. 082 E+006 2.003E+007 2.813E+005

8. 2 35E+006 3.4 38E+006 2.600E+006

1. 801E+007 1.440E+007

1. 83 9E+007

1. 633E+007 7.474E+006 2.439E+007 5.880E+00 5 2.477E+007

1. 367E+006

1. 646E+007 6.484E+005 6.669E+005

4. 255E+006 5.615E+005 5.866E+006

[415]

'-'-'..L..L'-"-~

.L.lJ-JJ..1.

"' ' '-.t:-'..._,.J.,.

V/..J..V/ L.. V..LV

-:I *

..J,

L.. \\J

..L..L."J.

J.. t,..L";:j-

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Lev e l Name (keV)

( i)

(pCi/SQM ) (pCi/SQM )

(pCi/SQM )

(pCi/SQM

)

Eu-1 52 1249.94 0.19 9.541E+007 5.89E+005 1.118E+007 4.404E+007 1299.14

1. 63 1.031E+007

1. 736E+006 4.719E+006 1408.01

21. 07

7. 62 0E+005 3.434E+005 3.460E+005 1457.64 0.50 1.036E+008 3.803E+008 5.033E+007 1528.10

0. 28 4.674E+007

-1.932E+007 2.062E+007 Eu-154 12 3.07 40.40 5.107E+005 5.11E+005 - 6. 140E+004 2.500E+005 247.93 6.89 2.492E+006

- 6. 254E+005

1. 2 05E+006 591. 76 4.95 2.956E+006

-1.103E+006

1. 383E+006 692.4 2

1. 78

8. 338E+006

-2.501E+006 3.882E+006 723. 30 20.06 8.852E+005

-5. 22 5E+005 4.166E+005 756.80 4.52 3.558E+006

1. 380E+005 1.661E+006 873. 18 12.08

1. 23 9E+006 l.530E+006 5.7 22E+005 996. 2 9 10.48

1. 686E+006 6.588E+005 7.840E+005 1004.76 18.01 9.137E+005

-5.172E+005

4. 225E+005 127 4.43 34.80

5. 233E+005 3.189E+005 2.416E+005 1596.48

1. 80

6. 174E+006

-7.380E+005 2.643E+006 Eu-155 45.30

1. 31 1.027E+007 7.77E+005 -2.058E+006 4.970E+006 60.01

1. 22 1.478E+007

-4.214E+006

7. 2 09E+006 86.55 30.70 7.773E+005 4.545E+005 3.816E+005 105. 31 21.10 1.009E+006

-4.563E+005 4.944E+005

+

Tl-208 583.19*

85.00 1.081E+005 1.08E+005

1. 508E+005 4.858E+004 Bi-211 351.07*

13.02 9.116E+005

9. 12E+005 2.648E+006

4. 2 91E+005 Pb-211 404.85 3.78

4. 3 65E+006 4.11E+006 6.812E+005 2.082E+006 427.09

1. 76

8. 373E+006

9. 1 90E+005 3.964E+006 832.01 3.52 4.109E+006

-6. 82 8E+006

1. 896E+006

+

Bi-212 39.86*

1. 06 8.852E+006

l. 53E+00 6

1. 672E+007

4. 221E+006 727.33*

6.67

1. 52 8E+006 8.960E+005 6.855E+005 785.37 1.10 1.508E+007

-2.562E+006 7.047E+006 1620.50

1. 4 7 9.303E+006

-6.976E+005 4.104E+006

+

Pb-212 115.18 0.60 3.485E+007 3.60E+005 -1.047E+007 1.706E+007 238.63*

43.60 3.599E+005

5. 1 41E+005

1. 73 6E+005 300. 09 :~

3.30 3.630E+006 4.763E+006

1. 72 0E+006 Pb212-XR 74.8 2

10. 28 2.441E+006 1.42E+006 5.166E+006

1. 200E+006 77.11 17.10 l. 417E+006 2. 82 0E+005 6.958E+005 87.35 3.97 6.053E+006 8.196E+006

2. 972E+006 89.78

1. 46

1. 598E+007

-2. 93 0E+006 7.842E+006

+

Bi-214 609. 32

• 45. 49 2.573E+005 2.57E+005 1.097E+006 1. 182E+005 768.36 4.89 3.599E+00 6

- 7.805E+00 5

1. 689E+006 806.18

1. 2 6

1. 258E+007

7. 251E+00 5 5.855E+006 934.06 3.11

5. 323E+006 3. 103E+004 2.470E+006 11;20. 2 9*

14.92

7. 272E+005 9.542E+005 3.198E+005 1155. 21

1. 63 9.555E+006

-5. 42 3E+006

4. 371E+006 1238.12 5.83 3.865E+006 2. 22 0E+006 l.814E+006 1280.98

1. 43 1.199E+007

-3.443E+006 5. 506E+006 1377.67 3.99 4.1 35E+006 2.110E+006 1.885E+006 1385.31 0.79

1. 8 62E+007

-2.138E+007 8.386E+006 1401.52

1. 33

1. 236E+007 4.730E+006 5.629E+006 1407.99 2. 39 6.706E+006 3.022E+006 3.045E+006 1 509. 21 2.13 5.996E+006

- 1. 692E+006 2.636E+006 1 661. 27

1. 05 1.047E+007

- 6.991E+006 4.453E+006

[416]

~... ~

,4.L

.t.\\._.t"'_...... -

\\.JI

..J.. \\JI '-' \\J..J.. \\.J

~ * -' I

• L-V

.L.L'.I

.L u.':::' '-

V Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( ~;)

(pCi/SQM

) (pCi/SQM )

(pCi/SQM )

(pCi/SQM)

+

Bi-2 14 1729.59 2.88 4.463E+006 2.57E+0 05 1.712E+006

1. 940E+006 1764.49 15.30

1. 474E+006 2. 092E+006 6.814E+005 1847.4 3 2.03 5.527E+006

1. 356E+006 2.334E+006 2118. 51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 2 41. 99*

7. 2 5 2.164E+006 3.33E+005 3.091E+006 1.044E+006 2 95. 22

• 18.42 6.503E+005 8.534E+005 3.081E+005 351.93*

35.60 3.334E+005 9.686E+005 1.569E+005 785.96

1. 06 1.568E+007

1. 789E+006

7. 32 9E+006 Pb214-XR 74.8 2 5.80

4. 32 7E+006 2.50E+006 9.156E+006 2. 12 6E+006 77.11 9. 70 2.4 98E+006 4.972E+005 1.227E+006 87.35 2.24 1.073E+007

1. 453E+007 5.267E+006 89.78 0.8 2 2.845E+007

-5. 217E+006

1. 39 6E+007 Ra-226 186. 21 3.64 4.991E+006 4.99E+006 1.885E+006 2.4 2 9E+006 Ac-228 129.07 2.42

8. 282E+006 8.61E+005 -2. 32 6E+006 4.050E+006 2 09.25 3.89 4.712E+006 2.156E+006 2. 289E+006 270. 2 4 3.46 5.142E+006

1. 706E+006 2.485E+006 328.00 2.95 5.398E+006

-2.417E+006 2.586E+006 338. 32

11. 27 1.515E+006 1.084E+006 7.274E+005 409.46

1. 92 8.592E+006 3.951E+006 4.097E+006 463.00 4.40 3.459E+006 1.171E+006

1. 637E+006 794.95

4. 25 3.600E+006

1. 380E+006

1. 671E+006 911. 2 0 25.80 8.610E+005 4.354E+005 4.077E+005 964.77 4.99 4.097E+006 2.851E+006 1.927E+006 968.97 15.80 1.332E+006 1.333E+006 6.277E+005 1588. 2 0 3. 22 3.994E+006

1. 430E+006

1. 750E+006 Pa-231 2 7.36*

10.30 9.110E+005 9.11E+005

1. 721E+006 4.344E+005 283.69

1. 70 9.675E+006 1.260E+006 4.657E+006 300.07*

2.47 4.849E+006 6.364E+006 2. 2 97E+006 302.65 2.2 0

7. 250E+006

-1. 566E+004 3.480E+006 330.06

1. 40 1.116E+0 07

-3.004E+006 5.343E+006 Th-234 92.38 2.13 1.073E+007 1.07E+007 -1. 678E+006

5. 2 62E+006 92.8 0 2.10

1. 088E+007 7.468E+005 5. 33 8E+006 112.8 1 0.21 1.006E+008 1.308E+007 4.927E+007 U-235 14 3.76 10.96

1. 734E+006 3.17E+005 1.414E+005 8.464E+005 163.33 5.08 3.619E+006

9. 2 91E+005 1.764E+006 185.71

57. 20 3.168E+005 9.156E+004 1.542E+005 202.11

1. 08

1. 5 98E+007

-6.844E+00 6 7.754E+006 205.31 5.01 3.496E+006

-2.160E+005 1.697E+006 Am-241 59.54 35.90

4. 91'4E+005 4.91E+005 -2. 52 4E+00 5 2. 396E+005

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[417]

GAMM A S P E C T R U M A N A L Y S I S Filename: C:\\Users\\kevin\\Desktop\\Zion D&D\\GENIE2K 545 2 \\CAMFILES\\ARCHIVE 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 Sample Taken On Acquisition Started Live Time Real Time Dead Time 1/7/2019 4:17:09 PM B3U1STEAMTUNNEL B306100BFJWC001GD NORTHWALL 3.00 85 -

85 -

10.000 8192 81 92 keV 1.000E+OOO SQ METER 4/11/2016 4/11/2016 2 :43:33 PM 2 :43:33 PM 600.0 seconds 601.0 seconds 0.17 ':,

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 4/5/2016 DTWALL DATA VALIDATED DATE /- t.. J'f TIME ()5',3~

(2.~4-

[418]

Peak Analysis Report 1/ 7 /2019 4:17:09 PM Page 2

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

5452 Sample

Title:

B3U1STEAMTUNNEL B306100BFJWC001GD Peak Analysis Performed on:

1/7/2019 4:17:09 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV)

Area Uncert.

Counts 1

113-118 116.00 28.59 0.54 1.08E+001

14. 33

l. 62E+001 2

296-306 300.31 74.73 0.56

4. 99E+00 1 46.19 2.00E+002 3

332-345 340.54 84.80 0.70 5.16E+001 49.00 1.99E+002 4

1176-11 86 11 80. 38 2 95. 01 0.49 2.88E+001 21.49 3. 62E+001 5

2326-2337 2331. 23 58 2. 97

0. 92 2.80E+001 16.43 1.50E+001 6

2427-2443 2435. 2 0 608.98 0.56 6.19E+001 22. 62 2.llE+OOl 7

2636-2653 2644.50 661.34 0.71 9.74E+001 25.34

1. 96E+001 8

3866-3877 387 1.28 968.15 0.49 l.07E+001 12.10 1.03E+001 9

58 29-5850 5838.94 1460.00 0.69 1.88E+002 28.02 2.49E+OOO 10 7049-7062 7055.36 1763. 92 0.81 1.78E+001 12.80 8.1 7E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[419]

Interference Corrected Activity Report 1/7/2019 4:17:09 PM Page 3

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

Title:

B3U1STEAMTUNNEL B306100BFJWC001GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV)

( !", )

(pCi/SQ M)

Uncertainty K-40 0.999 1460.82*

10.66 1.27825E+006 2. 20900E+005 Cs-137

1. 000 661.66*

85.10 5.65024E+004 1.61846E+004 Eu-155 0.345 86.55*

30.70 4.01445E+004 3.89389E+004 105.31 21.10 Tl-208 1.000 583.19*

85.00 l.53055E+004 9.15481E+00 3 Bi-214 0.705 609.32*

45.49 6.44791E+004 2.48030E+004 1120.29

14. 92 1764.49*

15.30 9.49820E+004 6.86151E+004

• =Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2.000 sigma

[420]

Interference Corrected Activity Report 1/7/2019 4:17:09 PM Page 4

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Name K-40 Cs-137 Eu-155 Tl-208 Bi-214 Nuclide Id Confidence 0.999 1.000 0.345 1.000 0.705 Wt mean Activity (pCi/SQ M) 1.278252E+006 5.650243E+004 4.014447E+004 1.530546E+004 6.800421E+004 Wt mean Activity Uncertainty 2.208997E+005

1. 618461E+004 3.893885E+004 9.154807E+003 2.332578E+004

? = 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 2.000 sigma

[421]

Interference Corrected Activity Report U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Peak Energy 1/7/2019 P E A K S 1/7/2019 85 8192 Peak CPS 4:17 : 0 9 PM 4:17:09 PM No.

(keV)

Peak Size in Counts per Second o Uncertainty Peak Type 1

28.59 2

74.73 4

295.01 8

968.15 1.7963E-002 8.3217E-002 4.8077E-002 l.7758E-002 M

First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma 132.93 92.51 74.51 113.57 Tol.

Tol.

Page 5

Tol.

Nuclide Pb-~1 4 Ac-228

[422]

Nuclide MDA Report 1/7/2 019 4: 1 7:09 PM Page 6

N U C L I D E MD A R E P O R T

+

+

+

+

+

Detector Name:

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name K-40 Co-60 Nb-94 Ag-108m Cs-134 Cs-137 Eu-152 Eu-154 Eu-155 Tl-208 Bi-212 Pb-2 12 Bi-214 Pb-214 Ra-2 2 6 Ac-2 2 8 Arn-2 41 Energy (keV) 1460.82*

1173. 23 1332.49 702.65 871. 09 433.9 0 614.3 0 722.90 604.72 795.86 661.66*

121.78 344. 2 8 1 408.0 1 12 3.07 723.30 1274.4 3 86.55*

105. 31 583.1 9*

727. 33 238.63 609.32*

1 120. 2 9 1764.49*

2 95. 22 351. 93 186.21 338.3~

911. 20 968.97 59.54 545 2 B3U1STEAMTUNNEL B306100BFJWC001GD C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Yield

0) 10.66 99.85 99.98 99.81 99.89 90.50 89.80 90.80 97.62

85. 46 85.10 28.67 2 6.60

21. 07 40.40 20.06 34.80 30.70 21.10 8.S.00 6. 67 43.60 45.49 14.92 15.30 18.42 35.60 3.64

11. 27 25.80 15.80 35.90 Line MDA Nuclide MDA (pCi/SQ M)

(pCi/SQ M)

Activity (pCi/SQ M) 8.469E+004 1.744E+004 1.621E+004 1.496E+004 1.628E+004 1.765E+004 2.560E+004 1.712E+004 2.313E+004 1.799E+004 1.672E+004 6.575E+004 5.493E+004 8.114E+004 4.469E+004 7.851E+004

4. 350E+004

6. 2 03E+004 9.753E+004 l.2 76E+004 2.275E+005 4.855E+004 3. 066E+004 1. 3 64E+005 9.871E+004 9.8 1 9E+004

5. 2 71E+004 4.758E+005 l.481E+00 5 8.130E+004

1. 2 42E+005 5.477E+004 8.47E+004 1.62E+004 1.50E+004 1.71E+004 1.80E+004 l.67E+004 5.49E+004 4.35E+004

6. 2 0E+004 1.28E+004 2. 2 8E+005 4.86E+004 3.07E+004

5. 2 7E+004 4.76E+005 8.13E+004 5.48E+004

l. 278E+00 6

-7. 2 98E+00 3

-1.120E+00 3

-3.813E+002 4.723E+003 2.335E+003

-5.019E+00 3 1.399E+004

-5.331E+00 2

-1.006E+004 5.650E+004 2.929E+004

- 9.593E+00 3 5.415E+004

-7.360E+003 4.994E+004

-3. 095E+003 4.014E+004 3.260E+00 4

1. 531E+004

- 8.081E+003 5.954E+004 6.448E+004 7.971E+004 9.498E+004 5.243E+004 1.825E+004

- 6.483E+004 5. 632E+004 7.912E+004 l.608E+005

-3.763E+003

+=Nucl i de identified during the nuclide identification

• = Energy line found in the spectrum

>= Calculated MDA is zero due to zero counts in the region, or Dec. Le'!el (pCi/SQ M) 3.312E+004 7.841E+00 3

7. 1 71E+00 3 6.794E+00 3

7. 379E+003

8. 22 7E+003 1.208E+004 7.793E+003 l.091E+004 8.145E+00 3 7.575E+003 3.176E+004 2.566E+004 3.600E+004 2.155E+004 3.578E+004 1.913E+004 2.996E+004 4. 72 5E+004 5.640E+003 l.033E+005 2. 33 6E+004 1.392E+004 6.247E+004 4.215E+004 4.668E+004 2.499E+004 2.282E+005 6.982E+004 3.764E+004 5.703E+004 2.632E+004 the region is outside the spectrum, or MDA has not been calculated

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

[423]

GAMM A S P E C T R U M A N A L Y S I S Filename: C:\\Users\\kevin\\Desktop\\Zion D&D\\GENIE2K 5452\\CAMFILES\\ARCHIVE 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 Sample Taken On Acquisition Started Live Time Real Time Dead Time 1/7/2019 4:15:14 PM B3U1STEAMTUNNEL B306100BFJWC002GD SOUTHWALL 3.00 85 -

85 -

10.000 81 92 8192 keV 1.000E+OOO SQ METER 4/11/2016 4/1 1 /2016 2:30:40 PM 2 :30:40 PM 600.0 seconds 601.0 seconds

0. 16 ',

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1 /13/2015 4/5/2016 DTWALL DATA VALIDATED DATE 1-1.. /9 TIME OStJ~

Q.~~

[424]

Peak Analysis Report 1/7/2019 4:15:14 PM Page 2

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

5452 Sample

Title:

B3U1STEAMTUNNEL B306l00BFJWC002GD Peak Analysis Performed on:

1/7/2019 4:15: 1 4 Pf-1 Peak Analysis From Channel:

85 Peak Analysis To Channel:

81 92 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start e nd centroid (keV)

(keV)

Area Uncert.

Counts 1

287-3 06 300.53 74.78 0.79 1.30E+002 72.19 3.35E+002 2

1175-1185 1180.64 295.07

1. 34 4.50E+001

21. 58 3.00E+OOl 3

1375-1384 1379.54 344.85 0.46 8.33E+OOO 12.83

1. 2 7E+001 4

1401-1416 1406.93 351.70

0. 3 1 8.14E+001 26.19 2.96E+001 5

2429-2442 2434.43 608.79

1. 62 8.05E+001 22.21 1.55E+001 6

3635-3646 3640.53 910.45 0.59 l.50E+001 9.49 3.00E+OOO 7

3867-3878 3872.44 968.44 0.8 2 1.63E+001 10.86 4.68E+OOO 8

5831-5849 5838.98 1460.01

1. 41 1.25E+002 27.59 1.97E+001 9

7049-7062 7055.42 1763.93 0.75 3.20E+001

11. 31 O.OOE+OOO M

First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[425]

Interference Corrected Activity Report 1 /7/2019 4:15:15 PM Page 3

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

Title:

B3U1STEAMTUNNEL B306l00BFJWC002GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Name K-40 Bi-21 4 Pb-2 14 Ac-228 Id Confidence 0.999 0.705 1.000 0.985 IDENTIFIED NUCLIDES Energj' (keV) 1 460.8 ~*

609.3 2*

1120.29 17 64.49*

295. 22

• 35 1.93*

338.32*

911.20*

968.97*

Yield

( ~ )

10.66 45.49 14.92

15. 30 18.42 35.60 11.27 25.8 0 15.8 0 Activity (pCi/SQ M) 8.53933E+005 8.38579E+004 l.70497E+005 8.04048E+004

8. 21710E+004 2.63260E+004 3.33205E+004 6.10041E+004

• = Energy l ine found in the spectrum.

Activity Uncertainty 2.02 173E+005 2. 523 40E+004 6.18074E+004 4.06496E+004 2.95445E+004 4.07665E+004 2.12918E+004 4.09633E+004

@ = Energy line not used for Weighted Mean Activitj' Energy Tolerance :

10.000 keV Nuclide confidence index threshold =

0. 3 0 Errors quoted at 2.000 sigma

[426]

I nterference Corrected Activity Report 1 /7/2019 4:15:15 PM Page 4

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Name K-40 Bi-214 Pb-214 Ac-228 Nuclide Id Confidence 0.999 0.705 1.000 0.985 Wt mean Activity (pCi/SQ M) 8.539332E+005 9.623603E+004 8.156054E+004 3.693133E+004 Wt mean Activity Uncertainty 2.021728E+005 2.336201E+004 2.389899E+004 1.714102E+004

?

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 2.000 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 1/7/2019 85 8192 Peak CPS 4:15:14 PM Peak No.

Energy (keV)

Peak Si z e in Counts per Second

~ Uncertainty Peak Type 1

M =

m =

F =

74.78 2.1722E-001 First peak in a multiplet region Other peak in a multiplet region Fitted singlet Errors quoted at 2.000 sigma 55.39 Tol.

Nuclide

[427]

Nucl ide MDA Report 1 /7/20 1 9 4: 15: 15 PM Page 5

N U C L I D E M DA R E P O R T Detector Name:

5452 Sample Geometry:

Sample

Title:

B3U1STEAMTUNNEL B306100BFJWC002GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

(~ )

(pCi/SQ M)

(pCi/SQ M)

(pCi/SQ M)

(pCi/SQ M)

+

K-40 1460.82*

10.66 1.993E+005

1. 99E+005 8.539E+005 9.044E+004 Co-60 1173. 23 99.85 1.559E+004 1.34E+004 - 1.055E+004 6.915E+003 1332.49 99.98 l.343E+004 5.037E+003 5.782E+003 Nb-94 702.65 99.81 1.496E+004 l.50E+004 -3.081E+003 6.794E+00 3 871. 09 99.89

1. 62 8E+004

1. 976E+003 7.379E+003 Ag-1 08m 433.90 90.50 1.659E+004

1. 66E+004 8.555E+003 7.696E+003 614. 30 89. 80 2.547E+004

- 1.291E+004 1.202E+004 722. 90 90.80 1.689E+004 6.512E+003 7.681E+003 Cs-134 604. 72

97. 62 2.658E+004 2.18E+004 -2.484E+004 1.263E+004 795.86 85.46 2.176E+004 1.037E+004 1.003E+004 Cs-137 661. 66 85.10 1.799E+004 1.80E+004 2.493E+003 8.208E+003 Eu-1 52 121.78 28.67 6.894E+004 5.18E+004 -4.883E+004 3.335E+004 344. 2 8 26.60 5.182E+004

- 2.062E+004 2.410E+004 1408.01

21. 07 7.199E+004 1.477E+004 3.143E+004 Eu-154 123.07 40.40 5.040E+004

4. 24E+004 2.501E+00 4 2.440E+004 723.30 20.06 7.441E+004 8.692E+003 3.374E+004 1274. 43 34.80

4. 242E+004 6.298E+003 1.859E+004 Eu-155 86.55 30.70 7.8 3 4E+004 7.8 3E+004 1.172E+005 3.813E+004 105.31 21.10 9.402E+004

- 6.439E+004 4.549E+004 Tl-208 583.19 85.00 2.163E+004 2.16E+004 2. 320E+004 1.008E+004 Bi-2 12 727.33 6.67 2.337E+005 2.34E+005 1.883E+005 l.064E+005 Pb-2 12 238.63 43.60 4.569E+004 4.57E+004 6.793E+003 2.193E+004

+

Bi-214 609.32*

45.49 2.524E+004 1.44E+004 8.386E+004

1. 121E+004 1120.29 14.92 1.498E+005 2.080E+005 6.914E+004 1764.49*

15.30 1.442E+004 1.705E+005 O.OOOE+OOO

+

Pb-2 14 295.22*

18.42 5.451E+004 3.4 3E+004 8.040E+004 2.484E+004 351.93*

35.60 3.429E+004

8. 217E+004 l.578E+004 Ra-226 186. 21 3.64 4.856E+005 4.86E+005 3.554E+005 2.330E+005

+

Ac-228 338.32*

11. 27 6.810E+004 2.61E+004 2.633E+004 2.978E+004 911. 20*

25.80 2.608E+004 3.332E+004

1. 003E+004 968.97*

15.80 5.476E+004 6.100E+004 2. 233E+004 Arn-241 59.54 35.90 5.739E+004 5.74E+004 -4.142E+003 2.763E+004

+ = Nuclide identified during the nuclide identif ication

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[428]

GAMM A S P E C T R U M ANALYSIS Filename: 5452 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 Sample Taken On Acquisition Started Live Time Real Time Dead Time 4/ 11 /2 016 3 : 12 :06 PM

~ig~~TEAMTUNNEL - ~-a-o<o,oaa~-..)fc-CC1'3- ~1) 3.00 85 -

85 -

10.000 81 92 8192 keV 1.000E+OOO SQ METER 4/11/2016 3: 02:03 PM 600.0 seconds 601.5 seconds

0. 25 %

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 4/11/2016 DTMUDDFLOOR DATA--VALIDATED DATE 1-4i-t1 TIMEos;;n Ci:2+

[429]

Peak Analysis Report 4/ 11/2 016 3: 12 : 06 PM Page 2

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

5452 Sample

Title:

B3U1STEAMTUNNEL Peak Analysis Performed on:

4/11/2016 3: 12: 06 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV)

Area Uncert.

Counts 1

113-123 115.95 28.58 0.76 9.79E+001 43.08 l.23E+002 2

283-306 300.55 74.79 1.11 2.95E+002 124. 2 7 8.90E+002 3

948-960 954.74 238.54 0.36 7.56E+001

43. 26 1.49E+002 4

1172-1188 1181.12 295. 19 0.97 9.79E+001 41.14 1.04E+002 5

1347-1358 1353.16 338.25 0.86 4.40E+001 26.79 5.40E+001 6

1397-1415 1407.28 351.79

1. 69 1.88E+002 42.18 7.60E+001 7

2323-2338 2330.79 582.86

1. 70 6.lOE+OOl 25.08 3.20E+001 8

2428-2444 2434.32 608.76 1.11 l.95E+002 35.16 3.57E+001 9

3635-3648 3641.17 910.61 0.42 4.49E+001 19.18 1.71E+001 10 3865-3877 3870.96 968.07 0.55 2.79E+001 15.53 1.21E+001 11 4469-4485 4476.90 1119.57

1. 21 5.90E+001

21. 76 1.90E+001 12 58 28-5850 5839.60 1460.17

1. 63 3.14E+002 40.91 2.73E+001 13 7044-7063 7053.83 1763.53 0.87 6.15E+001 19.54 9.54E+OOO M

First peak in a multiplet region m

Other peak in a multiplet region F

Fitted singlet Errors quoted at

2. 000 sigma

[430]

Interference Corrected Activity Report 4/11 /2 016 3:12:06 Pl-1 Page 3

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

Title:

B3U1STEAMTUNNEL Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Ba-133 Tl-2 08 Pb-2 12 Bi-214 Pb-214 Ac-22 8 0.999 0.32 1

1. 000 0.975 0.53 4 0.977

0. 3 50 1460.82*

79.61*

81. 00 276.40 302.85*

356.01*

383.85 583.19*

115.18 238.63*

300.09*

609.32*

768.36 806.18 934.06 112 0.29*

1155.21 1238.1 2 1280.98 1377.67 1385.31 1401.52 1407.99 1509.21 1661. 2 7 17 29.59 1764.49*

1847.43 2118.51 241.99*

295.22*

3 51.93*

785.96 129.07 209.25 270.24 328.00 338.32*

409.46 463.00 794.95 Yield

(%)

10.66 2.65 32.9 0 7.16 18.34 62.05 8.94 85.00 0.60 43.60 3.30 45.49 4.89

1. 26 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79 1.33 2.39 2.13

1. 05 2.88

15. 3 0 2.03 1.16

7. 25 18.42 35.60

1. 06 2.42 3.89 3.46 2.95

11. 2 7

1. 92 4.40 4.25 Activity (pCi/SQ M) 5.80083E+005

6. 32162E+005 4.38579E+004 2.75949E+004 8.73246E+003

1. 25634E+004 2.43744E+005

5. 3 4554E+004 6.76210E+004 8.91325E+004 7.55431E+004 4.36674E+004 4.80973E+004 3.47418E+004 Activity Uncertainty 9.08749E+004 2.96073E+005

1. 97281E+004 7.60475E+003 3.74039E+003 7.46919E+003 l.09745E+005 l.15717E+004 2.55215E+004 2.9 2165E+004 4.48798E+004 l.96336E+004 1.32563E+004 2.19093E+004

[431]

Interference Corrected Activity Report 4/11/2016 3 :12:06 PM Nuclide Id Energy Yield Acti"\\-i ty Activity Name Confidence (keV)

( % )

(pCi/SQ M)

Uncertainty Ac-228 0.350 911.20*

25.80 2.67379E+004 l.16683E+004 964.77 4.99 968.97*

15.80 2.79997E+004 1.58044E+004 1588. 20 3. 22 Th-23 1 0.875 25.64*

14.10 3.94658E+004 1.97364E+004

84. 21*

6.60 2.538 23E+005

1. 22 420E+005 89.95

1. 00

• = Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold

0. 3 0 Errors quoted at 2.000 sigma Page 4

[432]

Interference Corrected Activity Report 4/11/2 016 3 :12:06 PM Page 5

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Nuclide Id Name Confidence K-40 Ba-133 Tl-208 X

Bi-211 Pb-21 2 Bi-214 Pb-214 Ac-22 8 X

Pa-23 1 Th-231 0.999 0.321 1.000 0.999 0.975

0. 53 4 0.977 0.350 0.674 0.875 Wt mean Activity (pCi/SQ M) 5.800831E+005 l.419294E+004 8.732458E+003 8.524911E+00 3 5.970065E+004 2.478500E+004 2.835538E+004 4.474073E+004 Wt mea n Activity Uncertainty 9.087493E+004 3.3590 87E+004 3.7403 93E+003 l.184255E+004 9.913724E+003

5. 252816E+004 8.6 28476E+003 1.884284E+004

? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysi s

@ = Nuclide contains energy lines not used in Weighted Mean Activit~*

Errors quoted at 2.000 sigma Peak No.

U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Energy (keV)

Peak Size in Counts per Second All peaks were identif i ed.

P E A K S 4/11/2016 85 8192 Peak CPS 3:12:06 PM

% Uncertainty Peak Type Tol.

Nuclide

[433]

Nuclide MDA Report 4/11/ 2016 3:12:06 PM Page 6

N U C L I D E M D A R E P O R T

• • • • • • • • • • • • • ****** ~******* *****************************************************

Detector Name:

5452 Sample Geometry :

Sample

Title:

B3U1STEAMTUNNEL Nuclide Library Used: C:\\GENIE2K\\CAMFI1ES \\ Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV )

( % )

(pCi/SQ M)

(pCi/SQ M)

(pCi/SQ M)

(pCi/SQ M)

+

K-40 1460.82*

1 0.66 6.722E+004 6.72E+004 5.801E+005 3.111E+004 Cr-5 1 320.08 9.91 5.648E+004 5.65E+004 -4.730E+003 2.706E+004 Mn-54 834.85 99.98 5.772E+003 5.77E+003 3.701E+003 2.687E+003 Co-58 810.76 99.45 6.208E+003 6.21E+003 -4.613E+003

2. 907E+003 Co-6 0 1173. 23 99.85

6. 128E+003 4.67E+003 2.934E+003 2.826E+003 1332.49 99.98 4.673E+003

-2.125E+003 2.084E+003 Nb-94 70 2.65 99.81 5.745E+003 5.39E+003 -5.928E+003 2.691E+003 871.09 99.89 5.393E+003 1.438E+003 2.494E+003 Sn-113 255.13 2.11 3.079E+005 9.77E+003 1.283E+005 l.491E+005 391.70 64.97 9.770E+003 3.056E+003 4.683E+003 Cs-134 475.36

1. 48 3.987E+005 6.69E+003 -2.215E+004 1.894E+005 563. 25 8.34 7.047E+004 4.044E+004 3.330E+004 569.33

15. 3 7 3.522E+004

-2. 110E+003 1.655E+004 604.7 2 97.62 9.824E+003

-l.173E+004

4. 740E+003 795.86 85.46 6.686E+003

-8.059E+00 2 3.116E+003 801.95 8.69 7.541E+004 9.109E+004 3.547E+004 1038.61 0.99 5.466E+005 2. 202E+005 2.508E+005 1167.97

1. 79 3.693E+005

1. 280E+005 1.714E+005 1365.19 3.02 1.409E+005

-1.129E+005 6.197E+004 Cs-137 661.66 85.10 7.237E+003 7.24E+003 3.058E+002 3.412E+003 Eu-15 2 121.78 28.67 2.651E+004 2.28E+004 -1.572E+004 l. 298E+004 244.70 7.61 8. 625E+004

-l.862E+004 4.182E+004 295.94 0.45 1.539E+006 2.077E+006 7.448E+005 344. 2 8 26.60 2.277E+004

- 1. 260E+003 1.093E+004 367.79 0.86 6.622E+005

-2.604E+005 3.164E+005 411.12 2. 24 2.798E+005 1.113E+005 l.339E+005 443.96 2.83 l.891E+005

-l. 376E+005 8.954E+004 488.68 0.42 l. 254E+006

-9.054E+005 5.915E+005 563.99 0.49

1. 209E+006 7.359E+005 5.715E+005 586.26 0.46 l.574E+006 2.957E+005 7.510E+005 678.6 2 0.4 7 l.074E+006

-l.024E+006 4.991E+005 688.67 0.86 6.263E+005

-4.942E+005 2.922E+005 719. 3 5

0. 28 2.000E+006

- l.106E+006 9.340E+005 778.90 12.96 4.637E+004 4.525E+002 2.171E+004 810.45

0. 32 l.935E+006

- 4.665E+004 9.066E+005 867.37 4.26

l. 250E+005

-3.073E+004 5.777E+004 919.33 0.43 l.333E+006

-2.100E+005 6.175E+005 964.08 14.65 4.851E+004 5.690E+004 2.279E+004 1085.87 10.24 6.273E+004

-5. 140E+004 2.914E+004 1089.74

1. 73 3.837E+005 l.693E+005 l.786E+005 1112.07 13.69 4.474E+004

-7.114E+003 2.069E+004 1212.95

1. 43 4.838E+005

-l.464E+005

2. 250E+005

[434]

Nuclide MDA Report 4/11/ 2016 3 :1 2 :06 PM Page 7

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( % )

(pCi/SQ M)

(pCi/ SQ M)

(pCi/SQ M)

(pCi/SQ M)

Eu-15 2 1249.94 0.19 3.529E+006 2.28E+004 -2.303E+004 1.635E+006 1299.14

1. 63 3.768E+005 1.758E+005 1.731E+005 1408. 01

21. 07 3.009E+004 9.810E+003 l.380E+004 1457.64 0.50 3.609E+006

1. 31 7E+007 l.752E+006 1528.10

0. 28 l.447E+006 4.521E+005 6.260E+005 Eu-154 123.07 40.40 1.880E+004 1.82E+004 -5.390E+003 9.210E+003 247.93 6.89 9.031E+004

-6.022E+002 4.370E+004 591.76 4.95 1.098E+005 6.590E+003 5.156E+004 692.42

1. 78

3. 263E+005

1. 6 7 5E+005 1.530E+005 723.30 2 0.06 3.062E+004 2.724E+004 l.439E+004 756.80 4. 52 l. 167E+005

-1. 34 7E+005 5.418E+004 873.18 12.08

4. 258E+004

-1.657E+004 l.961E+004 996. 2 9 10.48 4.945E+004

-2.070E+004 2. 264E+004 1004.76 18.01 2.789E+004

-2. 97 8E+004

l. 273E+004 1274.43 34.80 l.815E+004 l.419E+004 8.367E+003 1596.48

1. 80 2. 728E+005

-9.860E+004 l.207E+005 Eu-155 45.30 1.3 1

4. 25 6E+005 2.96E+004 -9. 285E+004 2.069E+005 60.01

1. 22 5.578E+005 2.904E+004 2.726E+005 86.55 30.70 2.956E+004 2. 287E+004 l.453E+004 105. 3 1 21.10 3.769E+004 5.659E+003 1.848E+004

+

Tl-2 08 583.19*

85.00 5.007E+003 5.01E+003 8.732E+003 2. 310E+003 Bi-21 1 351.07*

13.02 3.878E+004 3.88E+004 l.315E+005 l.844E+004 Pb-2 11 404.85 3.78 1.534E+005 l.52E+005 -7.441E+004 7.314E+004 427.09

1. 76 3.234E+005 2.167E+005 l.538E+005 832.01 3.52 1.522E+005

-2.392E+004 7.045E+004 Bi-212 39.86

1. 06 5.093E+005 8.86E+004 -2.933E+004 2.474E+005 727.33 6.67 8.862E+004 5.280E+004 4.154E+004 785.37 1.10 5.150E+005 3.708E+005 2.400E+005 1620.50

1. 47 3.133E +005

-6.673E+004 l.373E+005

+

Pb-2 12 115.18 0.60 l.281E+006 l.13E+004 -1.015E+006 6.274E+005 238.6 3

• 43.60 1.128E+004

1. 256E+004 5.413E+003 300.09*

3.30 1.544E+005 2.437E+005

7. 3 85E+004 Pb212-XR 74.8 2 1 0. 2 8

9. 3 79E+004 5.27E+004 3.290E+004 4.615E+004 77.11 17.10

5. 2 72E+004 l.562E+003 2.591E+004

87. 3 5 3.97 2. 281E+005 l.944E+005 1.121E+005

89. 78

1. 46 5. 910E+005

-l.515E+005 2.902E+005

+

Bi-214 6 09. 32*

45.49 l.035E+004 l.03E+004

5. 3 46E+004 4.802E+003 768.36 4.89

1. 26 5E+005

-8.306E+004 5.938E+004 806.18

1. 26 5.022E+005 1.829E+005 2.357E+005 934.06 3.11 2.003E+005

1. 367E+005 9.338E+004 1120.29*

14.92 3.216E+004 6.762E+004 l.453E+004 1155. 21

1. 63 4.058E+005

-6.402E+004 1.885E+005 1238.1 2 5.83

l. 222E+005 2.681E+004 5.695E+004 1280.98

1. 43

4. 285E+005 1. 207E+005 1.970E+005 1377.67 3.99 1. 499E+005

1. 122E+005 6.848E+004 1385.31 0.79

6. 257E+005

-5.496E+005 2.803E+005 1401.52

1. 33 4.701E+005 2. 28 2E+005 2.155E+005 1407.99 2.39 2.648E+005 8. 63 4E+004

1. 215E+005 1509. 21 2.13 2.317E+005 1.336E+005 l.031E+005 1661. 2 7

1. 05 4.468E+005 1.903E+005 1.958E+005

[435]

Nuclide MDA Report 4/ 11 / 2 016 3 :1 2 :06 PM Page 8

Nucl ide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( % )

(pCi / SQ M)

(pCi/SQ M)

(pCi/SQ M)

(pCi/SQ M)

+

Bi-214 1729.59 2.88 l.868E+005 l.03E+004 6.300E+004 8.310E+004 1764.49*

15.30 3.172E+004 8.913E+004 l.390E+004 1847.43 2.03 2.639E+005

5. 330E+004 l.168E+005 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 2 41.99*

7. 25 6.780E+004 l.42E+004 7.554E+004 3. 25 5E+004 295. 22

• 18.42 2.767E+004 4.367E+004 l.323E+004 351.93*

35.60 l.418E+004 4.810E+004 6.745E+003 785.96

1. 06 5.157E+005

-2.694E+004 2.397E+005 Pb21 4-XR 74.82 5.80 l.662E+OOS

9. 29E+004 5.832E+004 8.179E+004 77.11 9.70 9. 295E+004 2.753E+003 4.568E+004

87. 3 5 2.24 4.042E+005 3.445E+005 l.987E+005 89.78 0.82 l.052E+006

-2.697E+005 5.167E+005 Ra-226 186. 21 3.64 l.898E+005 l.90E+005

1. 065E+005 9.253E+004

+

Ac-228 129.07 2.42 3. 124E+005 l.51E+004 -l.699E+004 l.530E+005 209.25 3.89 l.770E+005

-2.133E+004 8.614E+004 270.24 3.46 l.765E+005

-l. 26 3E+004 8.518E+004 328.00 2.95 l.935E+005 l.870E+004 9.274E+004 338.32*

11. 27 3.238E+004 3.474E+004 l. 512E+004 409.46

1. 92 3.280E+005 3.0 90E+004 l.570E+005 463.00 4.40 l.251E+005 7.6 18E+004 5.924E+004 794.95

4. 25 l.324E+005 2.841E+004 6.164E+004 911.20*

25.80 l.507E+004 2.674E+004 6.731E+003 964.77 4.99 l.41 7E+005 l.457E+005 6.653E+004 968.97*

15.80 2.155E+004 2.800E+004 9.415E+003 1588.20

3. 22 l.705E+005 l.181E+005 7.654E+004 Pa-231 27.36*

10.30 3.625E+004 3.62E+004 5.403E+004 l.7 38E+004 283.69

1. 70 3.523E+005 l.383E+005 l.698E+005 300.07*

2.47 2.063E+005 3.256E+005 9.866E+004 302.65 2. 20 2.681E+OOS 3.203E+004 l.289E+OOS 330. 06*

1. 40 2.607E+005 2.797E+005 l.217E+005 Th-234 92.38 2.13 3.933E+OOS 3.93E+005 -l.430E+005 l.930E+005 92.80 2.10 3.973E+OOS

-6.115E+004 1.950E+OOS 112.81 0.21 3.659E+006

-8.075E+005 1.793E+006 U-235 143.76 10.96 6.476E+004

1. 22E+ 004 -7.952E+003 3.166E+004 163.33 5.08 l.342E+005 2.887E+004 6.550E+004 185.71 57.20

l. 218E+004 9.625E+003 5.942E+003 2 02.11

1. 08 6.163E+005

-4.821E+004 2.998E+005 205.3 1 5.01 1.388E+005 8.743E+004 6.757E+004 Am-241 59.54 35.90 l.860E+004 l.86E+004 -6.735E+003 9.086E+003

+ = Nuclide identified during the nuclide identification Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated Half-life too short to be able to perform the decay correction

[436]

GAMM A S P E C T R U M A N A L Y S I S Filename: E:\\Steam Tunnel\\B306100BFRWC004GD.CNF 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 Sample Taken On Acquisition Started Live Time Real Time Dead Time 1/7/2019 2 :11: 3 9 PM U2 STM TUNNEL SE WALL TB 570 B3-06100B-FJWC-004GD 3.00 85 -

85 -

10.000 81 92 81 92 keV 1.000E+OOO SQM 4/19/2016 4/19/2016 10:1 6 : 2 6 AM 10:1 6 : 2 6 AM 600.0 seconds 600.6 seconds 0. 11 t Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 4/14/2016 TBWALL DATA-VALIDATED DATEJ-8-fJ TIME osa10 (i), l&jd

[437]

Peak Analysis Report 1 /7 /2 01 9 2 :11:39 PM Page 2

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

5452 Sample

Title:

U2 STM TUNNEL SE WALL Peak Anal ysis Performed on:

1/7/2019 2:11:39 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

81 92 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV)

Area Uncert.

Counts 1

298-305 3 01. 2 4 74.96 0.66 6.51E+001 36.35 l.31E+002 2

949-961 955.19 238.65 0.37 3.94E+001

26. 70

5. 2 6E+001 3

1400- 1413 1407.23 351.78 0.98 7.03E+001 19.42 8.73E+OOO 4

2 428-2443 2436.13 60 9.21 1.16 7.41E+001 19.80 7.94E+OOO 5

3867-3878 3872.70 968. 50 0.54 l.45E+001 10.18 4.51E+OOO 6

5829-5850 5839. 1 9 1 460. 06

1. 52 l.48E+ 002 26.34

7. 32E+OOO 7

7048-7061 7054.88 1763. 79 0.46 l.64E+001 9.09 l.56E+OOO M

First peak in a multiplet region m

Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[438]

Interference Corrected Activity Report 1/7/2019 2 :11:39 PM Page 3

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

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • '~******************

Sample

Title:

U2 STM TUNNEL SE WALL Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV)

( ~)

(pCi/SQM)

Uncertainty K-40 0.999 1460.82*

10.66 1.00673E+00 6 1.99713E+005 Pb-212 1.000 238.63*

43.60 2.67015E+004

1. 86245E+004 Bi-2 14 0.705 609.32*

45.49 7.71718E+004 2. 2 6189E+004 1120.29

14. 92 1764.49*

15.30 8.76125E+004 4.89351E+004 Pb-2 14 0.438 295. 22 18.42 351.93*

35.60 7.09826E+004 2. 2 6701E+004

• = Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold 0.30 Errors quoted at 2.000 sigma

[439]

Interference Corrected Activity Report 1/7/2 01 9 2 : 11: 3 9 PM Page 4

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Name K-40 Pb-21 2 Bi-214 Pb-214 Nuclide Id Confidence 0.999 1.000 0.705 0.4 38 Wt mean Activity (pCi/SQM )

1.006733E+006 2.67 01 52E+004 7.900979E+004 7.098255E+004 Wt mean Activity Uncertainty 1.997129E+005 1.862 449E+004 2.05 3169E+004 2.267 014E+004

?

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 2. 000 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 1/7 /2 019 85 8192 Peak CPS 2 : 11: 3 9 PM Peak No.

Energy (keV)

Peak Size in Counts per Second

's Uncertainty Peak Type 1

5 74.96 968.50 1.0844E-001 2.4145E-002 M = First peak in a multiplet region m = Other peak in a multiplet region F

Fitted singlet Errors quoted at 2.000 sigma 55.87 70.30 Sum Tol.

Nuclide

[440]

Nuclide MDA Report 1/7/201 9 2 :11: 39 PM Page 5

N U C L I D E MD A REPORT

+

+

+

+

Detector Name:

5452 Sample Geometry:

Sample

Title:

U2 STM TUNNEL SE WALL Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Name K-40 Co-60 Nb-94 Ag-108m Cs-134 Cs -137 Eu-152 Eu-1 54 Eu-15 5 Tl-208 Bi-212 Pb-212 Bi-214 Pb-214 Ra-226 Ac-228 Am-2 41 Energy (keV) 1460.82*

1173. 23 1332.49 702.65 871.09 433.90 614.30 722.90 604.7 2 795. 86 661.66 121.78 344.28 1408.01 123.07 723.30 1274.4 3 86.55 105.31 583.19 727.33 238.63*

609.32*

1120.29 1764.49*

295.22 351.93*

186. 21 338.3 2 911.20 968.97 59.54 Yield

( !: )

10.66 99.85 99.98 99. 81 99.89 90.50 89.80 90.80

97. 62 85.46 85.10 28.67 26.60 21.07 40.40 20.06 34.80 30.70 21.10 85.00 6.67 43.60 45.49 14.92 15.30 18.42 35.60 3.64

11. 27 25.80 15.80 35.90 Line MDA Nuclide MDA (pCi/SQM ) (pCi/SQM)

Acti,.7i ty (pCi/SQM )

1. 32 3E+005 1.744E+004

l. 42 9E+004 1.576E+004 1.507E+004 1.559E+004 2.390E+004 l.978E+004 2. 2 66E+004 1.799E+004 1.842E+004 6.446E+004 5.605E+004 9.079E+004 4.673E+004 8.958E+004 4.016E+004 7.321E+004 9.190E+004 2. 2 72E+004 2.595E+005 2.814E+004 1.959E+004 1.580E+005 5.039E+004 9.480E+004 1.902E+004 4.582E+005

1. 337E+005

8. 3 40E+004 1.173E+005 4.705E+004 1.32E+005 1.43E+004 1.51E+004

1. 5 6E+004 1.80E+004 1.84E+004 5.60E+004 4.02E+004

7. 32E+004 2.27E+004 2.59E+005 2.81E+004 1.96E+004 1.90E+004 4.58E+005

8. 34E+004 4.70E+004 1.007E+006 5.105E+003

-3.504E+003

-6.699E+003 2.492E+002 5. 3 68E+002

- l. 32 6E+004 5.149E+003

-7.378E+003 3.971E+003 1.049E+004

-8. 060E+004 5.784E+004 2.098E+004 8.492E+003

- 9.814E+003

1. 311E+004

1. 319E+004

-.5.818E+004 1.246E+004 1.662E+005 2.670E+004 7. 717E+004 6.685E+004 8.761E+004 2.189E+004 7.098E+004 3.064E+005

1. 123E+005

6. 83 8E+004 2.575E+004 3.168E+003

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> =Calculated MDA is zero due to zero counts in the region, or Dec. Level (pCi/SQM )

5.693E+004 7.841E+00 3

6. 211E+003 7.194E+00 3 6.778E+00 3

7. 1 99E+003 1.123E+004 9.126E+003 l.068E+004 8.145E+003 8.427E+003 3.111E+004 2.622E+004 4.082E+004 2. 257E+004 4.132E+004 l.746E+004 3.557E+004 4.444E+004 1. 062E+004 1.193E+005 1.315E+004 8.384E+003 7.325E+004 1.799E+004 4.498E+004 8.145E+00 3 2.194E+005

6. 2 62E+004 3.869E+004

5. 3 62E+004 2. 2 64E+004 the region is outside the spectrum, or MDA has not been calculated

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

[441]

GAMM A S P E C T R U M A N A L Y S I S Filename: E :\\Steam Tunnel\\B306100BFRWC005GD.CNF 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 Sample Taken On Acquisition Started Live Time Real Time Dead Time 1/7/2 01 9 2 :08:05 PM U2 STM TUNNEL NE WALL TB 570 B3-06100B-FJWC-005GD

3. 00 85 -

85 -

10.000 81 92 8192 keV 1.000E+OOO SQM 4/19/2016 4/19/2016 10:02 :48 AM 10:02 :48 AM 600.0 seconds 600.6 seconds 0.10 t Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 4/14/2016 TBWALL DATA-VALIDATED DATE 1-8-Jj TIME 05x>

au;A,

[442]

Pea k Analysis Report 1 /7/20 19 2 :08:06 PM Page 2

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

5452 Sample

Title:

U2 STM TUNNEL NE WALL Peak Analysis Performed on:

1/7/201 9 2:08:05 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV)

Area Uncert.

Counts 1

287-307 300.86 74.87 0.53 1.34E+002

71. 51 3.1 4E+002 2

345-353 348.84 86.88 0.27 9.49E+OOO 32.93

1. 2 3E+002 3

43 1-438 43 4.02 108. 2 0 0.40 1.87E+001 26.23 7.63E+001 4

1175-1187 1 181.18 2 95. 21 0.53 2.12E+001 20.24 3.08E+001 5

1402-1414 1406.58 351. 62

1. 32 5.87E+001 22.93 2.73E+001 6

2037-2 048 2 04 2.1 2 510.64

1. 22 3.44E+001 17.44 1.66E+001 7

2427-2442 2435.44 609.04

1. 37 6.58E+001 20.91 l.42E+001 8

5829-5849 5838.54 1459.90

1. 06 1.25E+002 26.71 1.49E+001 M

First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma

[443]

Interference Corrected Activity heport 1/7/2019 2 :08:06 PM Page 3

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

Title:

02 STM TUNNEL NE WALL Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide I d Energy Yield Activity Activity Name Confidence (keV)

( '<;)

(pCi/SQM }

Uncertainty K-40 0.999 1460.82*

10.66 8.52513E+005 l.96525E+005 Eu-155 0.994 86.55*

30.70

7. 2 6289E+00 3 2. 52 485E+004 105.31*

21.10 2.10094E+004 2.97138E+004 Bi-214 0.439 609.32*

45.49 6.85478E+004 2. 32938E+004 1120. 2 9

14. 92 1764.49

15. 3 0 Pb-2 14 1.000 2 95. 22 *

18. 42 3.79146E+004 3.66838E+004 351.93*

35.60

5. 92 477E+004 2.50225E+004

• =Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2.000 s i gma

[444]

Interference Corrected Activity Report 1/7/2019 2 :08:06 PM Page 4

I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Name K-40 Eu-155 Bi-214 Pb-214 Nuclide Id Confidence 0.999 0.994 0.439 1.000 Wt mean Activity (pCi/SQM )

8. 52 5127E+005 1.302 667E+004 6.854776E+004

5. 24 7370E+004 Wt mean Activity Uncertainty 1.965252E+005 1.924046E+004 2.329380E+004 2.067141E+00 4

?

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 2. 000 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 1/7/2019 85 8192 Peak CPS 2 :08:05 PM Peak No.

Energy (keV)

Peak Size in Counts per Second

':, Uncertainty Peak Type 1

6 74.87 510.64 2. 2314E-001 5.7394E-002 M

First peak in a multiplet region m

Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma 53.41 SO.ES Tol.

Nuclide

[445]

Nuclide MDA Report 1/7/2019 2 :08:06 PM Page 5

N U C L I D E M DA R E P O R T

+

+

+

+

Detector Name:

545 2 Sample Geometry:

Sample

Title:

U2 STM TUNNEL NE WALL Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Name K-40 Co-60 Nb-94 Ag-1 08m Cs - 13 4 Cs-137 Eu-152 Eu-154 Eu-155 Tl-2 08 Bi-2 12 Pb-212 Bi-214 Pb-214 Ra-226 Ac-228 Am-241 Energy (keV )

1 460. 82*

1173.23 1332.49 702.65 87 1. 09 433.90 614.30 72 2.90 604.72 795.86 661.66 121.78 344. 28 1408.01 123.07 723. 30 1274.4 3 86.55*

105.31*

583.19 727.33 238.63 609.32*

1120.29 1764.49 295.22*

351.93*

186.21 338.32 911.20 968.97 59.54 Yield

(!is) 10.66 99.85 99.98 99.8 1 99.89 90.50 89.80 90.80

97. 62

85. 46 85.10 28.67 26.60

21. 07 40.40 20.06 34.80 30.70 21.10 85.00 6.67 43.60 45.49 14.92 15.30 18.42 35.60 3.64 11.27 25.80 15.80 35.90 Line MDA Nuclide MDA (pCi/SQM ) (pCi/SQM)

Activity (pCi/SQM )

l.821E+005 1.909E+004 1.343E+004 1.742E+004 1.403E+004 1.673E+004 2.522E+004 l.620E+004 2.415E+004 2.089E+004 2.084E+004

6. 62 2E+004 4.977E+004 7.941E+004 4.690E+004 7.441E+004 3.898E+004 4.280E+004 4. 868E+004 2.362E+004 2. 3 67E+005 4..512E+004 2.544E+004 1.567E+005 1.409E+005 5.783E+004 3.108E+004 4.684E+005 1.504E+005

8. 130E+004

l. 187E+005 4.484E+004 1.82E+005 1.34E+004 l.40E+004 1.62E+004 2.09E+004 2.08E+004 4.98E+004 3.90E+004 4.28E+004 2.36E+004 2.37E+005 4. 51E+004 2.54E+004 3.11E+004 4.68E+005 8.13E+004 4.48E+004 8.525E+005 8.698E+003

-5.992E+003 9.875E+003

-1. 22 0E+004

-1.606E+004 3.097E+003 5.932E+00 3 1.012E+004 1.327E+003 4.006E+003

-2.144E+004

-8.118E+004 2.111E+004

-2.857E+003 2.435E+004 1.315£+003 7.263E+00 3 2.101E+004 2.613E+004 5.765E+00 4 4. 725E+004 6.855E+004

1. 210E+005 1.065E+005 3.791E+004 5.925E+004

-2. 386E+00 5

-7. 3 61E+003 6.334E+004 3.679E+004

-1.791£+004

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

>= Calculated MDA is zero due to zero counts in the region, or Dec. Level (pCi/SQM )

8.183E+004 8.669E+003 5.782E+003 8.022E+003

6. 256E+003 7.764E+003 1.1 89E+004 7.334E+003 l.142E+004 9.592E+003 9.637E+003 3.199E+004 2.307E+004 3.514E+004 2.265E+004 3.374E+004 1.687E+004 2.037E+004 2.282E+004 1.107E+004 1.079E+005 2.164E+004

1. 131E+004

7. 258E+004 6.321E+004 2.650E+004 1.417E+004 2.244E+005 7.095E+004 3.764E+004 5.432E+004 2.154E+004 the region is outside the spectrum, or MDA has not been calculated Half-life too short to be able to perform the decay correction

[446]

~****************

GAMM A S 1-' E C T R U M A N A L Y S I S

.lename: 5452 iport Generated On unple Title unple Description tmple Identification tmple Type unple Geometry

!ak Locate Threshold

!ak Locate Range (in channels)

!ak Area Range (in channels) lentification Energy Tolerance 1mple Si ze 1mple Taken On

quisition Started

.ve Time

!al Time

!ad Time 4/ 19/2 016 10:40:00 AM U2 STM TUNNEL E FLOOR - B3 - fo\\OOP->

• F.rF C. - 00'1 C:.0 TB 570 3.00 85 -

85 -

10.000 8192 8192 keV 1.000E+OOO SQM 4/19/2016 10: 29:58 AM 600.0 seconds 601.0 seconds 0.17 %

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID

1/13/2015 4/14/2016 TB FLOOR 1M

[447]

iak Anaiysis Report 4 / 1 9/2 016 10:40:00 AI Page 2

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

5452 Sample

Title:

U2 STM TUNNEL E FLOOR Peak Analysis Performed on:

4/19/2016 10:40:00 AM Peak Analysis From Channel:

85 Peak Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV)

Area Uncert.

Counts 1

298-305 301.21 74.96 0.57 1.22E+002

53. 85 2.98E+002 2

555-562 558.56 139.38 0.87

1. 46E+001

36. 50

1. 57E+002 3

946-962 954.37 238.44

1. 13 1.13E+002

51. 35

1. 73E+00 2 4

1170-1187 1179.94 294.90

1. 22 7.40E+001 41.23

1. 08E+002 5

1401-1415 1407.03 351. 73 0.85 1.58E+002 34.90

5. 1 0E+001 6

2326-2339 2331.30 582.99 0.88

4. 2 4E+001 23.12 3.26E+001 7

2427-2444 2434.89 608.90 0.97 l.51E+002 34.59 4.53E+001 8

3635-365 0 364 2.45 910.93 1.12 5.10E+001 2 1. 3 8 2.10E+001 9

4472-4485 4477.46 1119.71 0.44 4.10E+001 18.57 1.60E+001 10 5827-5852 5839.73 1460.20

1. 90 3.31E+002

40. 5 8 1.92E+001 11 7045-7061 7052.83 1763.28 0.36 5.79E+001 16.07 2.11E+OOO

= First peak in a multiplet region

= Other peak in a multiplet region

= Fitted singlet

rors quoted at 2.000 s igma

[448]

1terference Corrected Acti ty Report 4/19/2016 1

10:00 AM Page 3

NUCLIDE I D E N T I F I C A T I O N R E P O R T Sample

Title:

U2 STM TUNNEL E FLOOR Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES I

e e

e e

e Nuclide Id Energy Yield Activity Activity Name Confidence (keV)

(%)

(pCi/SQM)

Uncertainty K-40 0.999 1460.82*

10.66 6.11668E+005 9.19345E+004 Tc-99m 0.998 140.51*

89.00 9.60791E+002 2.41731E+003 Ba-133 0.320 79.61*

2.65 2.62498E+005

1. 27 307E+005

81. 00 32.90 276.40 7.16 302.85*

18.34 3.31234E+004 l.92077E+004 356.01*

62.05 2.31925E+004

6. 32 602E+003 383.85 8.94 Tl-2 08

1. 000 583.19*

85.00 6.07051E+003 3.39017E+003 Pb-21 2 0.974 115.18 0.60 238.63*

43.60 l.87442E+004 9.05234E+003 300.09*

3.30 1.84086E+005

1. 06810E+005 Bi-214 0.534 609.32*

45.49 4.12571E+004 l.06883E+004 768.36 4.89 806.18 1.26 934.06 3.11 1120.29*

14.92 4.69813E+004 2.16198E+004 1155.21

1. 63 1238.12 5.83 1280.98

1. 43 1377.67 3.99 1385.31 0.79 1401.52 1.33 1407.99 2.39 1509.21 2.13 1661.27

1. 05 1729.59 2.88 1764.49*

15.30 8.394 3 6E+004 2.42465E+004 1847.43 2.03 2118.51 1.16

• = Energy line found in the spectrum.

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

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at 2.000 sigma

[449]

1terference Corrected Acti ty Report 4/19/2 01 6 1

10:00 AM Page 4

"*********************************************~*************************

I N T E R F E R E N C E CORRE C. TE D R E P O R T Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/SQM )

Uncertainty K-40 0.999 6.116681E+005 9.193449E+004 Tc-99m 0.998 9.607908E+002 2.417311E+003 Ba-133 0.320 2.436447E+004 6.003729E+003 Tl-208

1. 000 6.070511E+003 3.390166E+003 X

Bi-211 0.999 Pb-212 0.974 1.895760E+004 9.012 976E+003 Bi-214 0.534 4.799490E+004 8.910857E+003 X

Pb-214 0.976

? = Nuclide is part of an undetermined solution A = Nuclide rejected by the interference analysis

@ = Nuclide contains energy lines not used in Weighted Mean Acti vity Errors quoted at 2.000 sigma

• ~* ********

Peak No.

8 U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Energy (keV) 910.93 Peak Size in Counts per Second 8.5041E-002 P E A K S 4/19/2 01 6 10:40:00 AM 85 8192 Peak CPS

% Uncertainty

41. 90 Peak Type Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma Tol.

Nuclide

[450]

lClide MDA Report 4/19/201 10:40:00 AM Page 5

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • ~***

N U C L I D E M D A R E P O R T

+

Detector Name:

54 52 Sample Geometry:

Sample

Title:

U2 STM TUNNEL E FLOOR Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level

(%)

(pCi/SQM J (pCi/SQM )

(pCi/SQM )

{pCi/SQM )

Name (keV)

K-40 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-113 Cs-13 4 Cs-137 Eu-152 1460.82*

320.08 834.85 810.76 1173. 23 1332. 4 9 70 2.65 871. 09 255.13 391. 7 0 475.36 563.25 569.33 604.72 795.86 801.95 1038.61 1167.97 1365.19 661. 66 121. 78 244.70 295.94 344.28 367.79 411.12 443.96 488. 68 563. 99 586.26 678.62 688.67 719.35 778.90 810. 45 867.37 919.33 964.08 1085.87 1089.74 1112.07 1212.95

10. 66 9.91 99.98 99.45

99. 85 99.98 99.81 99.89 2.11 64.97

1. 48 8.34 15.37 97.62 85.46 8.69 0.99

1. 79 3.02

85. 10 28.67 7.61 0.45 26.60 0.86 2. 2 4 2.83 0.4 2 0. 49 0.46 0.47 0.86 0.28 12.96 0.32 4.26 0.43 14.65 10.24

1. 73 13.69

1. 43 5.973E+004 5.572E+004 5.413E+003 5.716E+00 3 5.948E+003 4.581E+003 6.165E+003 5.442E+003 2.922E+005 8.700E+003 3.894E+005 6.307E+004 3.864E+004 9.254E+003 6.017E+003 5.888E+004 6.345E+005 3.276E+005 l. 509E+005 7.909E+003 2.621E+004 8.637E+004

1. 4 u6E+006 2.131E+004 5.895E+005 2.562E+005 1.955E+005 1.235E+006

1. 078E+006

1. 533E+006 1. 139E+006 6.438E+005

1. 781E+006 4.577E+OD4 1.77DE+006

1. 262E+005

1. 378E+OD6

5. 251E+004 6.120E+004 3.504E+005 4.433E+OD4 5.1 2 9E+005 5.97E+004 5.57E+004 5.41E+00 3 5.72E+003 4.58E+003 5.44E+D03 8.70E+003 6.02E+00 3 7.91£+003 2. 13E+004 6.117E+005

-7.593E+003 2.989E+001 4.675£+002 5.656E+003

-3.595E+003 2.487E+003 6.494E+002

-7.797E+004

-6.090E+002 2.570E+005

-4.607E+003 1.632E+004

-6.570E+001

-2.253£+003

-1.447E+004 2.325E+005 4.913E+004

-1. 204E+005 6.523E+D03

-2.074£+003

7. 621E+004 1.083E+006

-2.014E+004

-3.877E+005

-1.372E+D04

-1.224E+005

- 1.263E+D05

-1.677E+005

1. 933E+006 1.384E+005 3.733E+004

-7.315E+OOS

-2.308E+004 1.557E+005

-1. 055E+005

-9.746E+004 3.366E+004 6.078E+003

- 1.988£+005

-9.052E+D04 l.359E+004 2.736E+004 2.668E+004 2.508E+003 2.661E+003 2.737E+003 2.038E+003 2.901E+003 2.518E+003 l.413E+005

4. 1 48E+003 l.847E+005 2.960£+004

1. 826E+004 4.455E+00 3 2.782E+003 2.720E+004 2.947E+005 l.506E+005 6.693E+004 3.747E+003 1.284E+D04 4.188E+004 7.084E+005

1. 020E+004 2.801E+005 1.220E+005 9. 277E+004 5.820E+005 5.062E+005 7.304E+005 5.318E+005 3.010E+005

8. 2 46E+005 2.141E+004 8.243E+OD5 5.834E+OD4 6.4DOE+005 2.479E+004 2.838E+D04

1. 620E+OD5 2.048E+D04 2.396E+005

[451]

1clide MDA Report 4/19/201 10:40:00 AM Page 6

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( % )

(pCi/SQM)

(pCi/SQM )

(pCi/SQM )

(pCi/SQM)

Eu-152 1249.94 0.19 3.244E+006 2. 1 3E+004 2.648E+006

1. 4 93E+006 1299.14

1. 63 3.339E+005

-2. 2 00E+004

1. 516E+005 1408.01

21. 07 2.246E+004

-7.491E+002 9.990E+003 1457.64 0.50 3.614E+006

1. 379E+007

1. 754E+006 1528.1 0 0.28

1. 354E+006 4.510E+005 5.796E+00 5 Eu-154 123.07 40.40 l.859E+004 1.61E+004 1. 648E+004 9.104E+00 3 247.93 6.89 8. 945E+004

- 5.987E+004 4.327E+004 591. 7 6 4.95 1.130E+005 9.468E+004 5.315E+004 692.4 2

1. 78 3.036E+005 7.308E+004

1. 417E+OD5 723.30 20.06 2.808E+004 1. 728E+004

1. 312E+004 756.80 4.52 l.258E+005

- 8, 021E+004 5.875E+004 873.18 12.08 4.383E+004 7.519E+003 2.024E+004 996. 2 9 10.48 5.325E+OD4 6.120E+004 2.454E+004 1004.76 18.01 3.261E+004 l.804E+004 1.509E+004 1274.43 34.80 1.607E+004

-2.236E+004 7.323E+003 1596.48

1. 80 2.539E+005

-7.352E+004 l.113E+005 Eu-155 45.30 1.31 3.497E+005 2.70E+004 3.523E+004 1.690E+005 60.01

1. 22 4.975E+005 4.686E+004 2.425E+005 86.55 30.70 2.699E+004 8.867E+003

1. 325E+004 105.31 21.10 3.655E+004

-3.832E+OD3

1. 791E+004

+

Tl-208 583.19*

85.00 4.888E+003 4.89E+003 6.071E+003 2. 250E+003 Bi-211 351.07*

13.02 2.976E+004 2.98E+004 1. 105E+005

1. 3 93E+OD4 Pb-211 404.85 3.78 1.559E+005

1. 38E+005 7.101E+004 7.440E+004 427.Q9

1. 76 3.088E+005 8.503E+003 1.466E+OD5 832.0 1 3.52 1.382E+005

-2. 380E+005

6. 3 46E+004 Bi-212 39.86

1. 06 3.771E+005 8.30E+004 -l.286E+005 1.813E+005 727.33 6.67 8.296E+004 1.997E+004 3.871E+004 785.37 1.10 5.334E+005

-5.355E+004 2.492E+005 1 620.50

1. 47 2.694E+005

-3.426E+005 l. 154E+005

+

Pb-212 115.18

0. 60 1.210E+006

1. 32E+0 04 - 4. 561E+005 5.922E+005 238.63*

43.60 1.322E+004

1. 87 4E+OO 4 6.388E+003 300.09*

3.30

1. 601E+005

1. 841E+005 7.667E+004 Pb212-XR 74.82

10. 28 8.533E+004 4. 86E+004 2.013E+005 4.191E+004 77.11 17.10

4. 864E+004 5.192E+004 2.387E+004 87.35 3.97 2.097E+005 2.597E+005 1.029E+005 89.78

1. 4 6 5.563E+005

-1.981E+005 2. 72 9E+005

+

Bi-214 609.32*

45.49

1. l 71E+004

1. 1 7E+004 4.126E+004 5.485E+003 768.36 4.89 1. 338E+005 7.489E+004 6.302E+004 806.18

1. 26 4.416E+005 7.835E+004 2.054E+005 934.06 3.11 1.959E+005 2.926E+004 9.116E+004 1120. 2 9*

14.92 2.847E+004 4.698E+004

1. 268E+004 1155.21

1. 63 3.926E+005 3.700E+005 1.819E+005 1238.12 5.83

1. 240E+00 5

-1.434E+005 5.784E+004 1280.98

1. 43 4.240E+005 l.151E+005 1.947E+005 1377. 67 3.99 1.305E+005 1.021E+005 5.878E+004 1385.31 0.79 4.535E+005

-5.060E+005 l.942E+005 1 401. 52

1. 33 4.078E+005 3.616E+004 1.843E+005 1407.99 2.39 1.977E+005

-6.593E+003 8.793E+004 1509.21 2.13 2.453E+005 l.618E+005 1.099E+005 1661.27 1.05

4. 231E+005 1.551E+005 1.839E+005

[452]

lC.i.ide MDA Report 4/19/ 201 10:40:00 AM Page 7

Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

(~)

(pCi/SQM } (pCi/SQM )

(pCi/SQM )

(pCi/SQM }

+

Bi-214 1729.59 2.88 1.667E+005

1. l 7E+004 9.061E+004 7.305E+004 1764.49*

15.30 l.621E+004 8.394E+004 6.145E+003 1847.43 2.03 1.685E+005

-3.687E+004 6.907E+004 2118.51

1. 16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO Pb-214 241. 99*

7.25 7.952E+004

1. 09E+004 1.127E+005 3.841Et004 295. 22

• 18.42 2.868E+004 3.298E+004

1. 374E+004 351. 93*

35. 60 1.088E+004 4.042E+004 5. 095E+003 785.96

1. 06 5.433E+005

-2.185E+005 2.535E+005 Pb214-XR 74. 82 5.80

1. 512E+005 8.57E+004 3.568E+005 7.429E+004 77.11 9.70 8.574E+004 9.153E+004

4. 208E+004 87.35 2.24 3.717E+005 4.603E+005

1. 824E+005 89.78 0.82 9.904E+00 5

-3.527E+005 4.858E+005 Ra-226 186.21 3.64 l.796E+005

1. 80E+005 5.099E+004 8.742E+004 Ac-228 12 9. 07 2.4 2 2.933E+005 3.08E+004 -2.204E+005 1.435E+005 209.25 3.89 1.700E+005

-2.828E+004 8.266E+004 270.24 3.46 1.692E+005

-7.990E+003 8.156E+004 32 8.00 2.95 1.846E+005

-1.062E+004 8.827E+004 33 8.32

11. 27 5.590E+004

-7.736E+003 2.688Et004 409.46

1. 92 3.049E+005

-6.489E+003

1. 454E+005 463.00 4.40

1. 277E+005 5.104E+004 6.058E+004 794.95 4.25

1. 209E+005

-6.600E+004 5.591E+004 911. 20 25.80 3.085E+004 2.590E+004 1.462E+004 964.77 4.99 1.550E+005 8.415E+004

7. 318E+004 968.97 15.80 4.905E+004 3.556E+004 2.317E+004 1 588. 20 3. 22 1.705E+005 8.153E+004 7.654E+004 Pa-231

27. 3 6

10. 30 2.573E+004 2.57E+004 2.693E+004 l.212E+004 283.69

1. 70 3.621E+005

1. 947E+005

1. 747E+005 300.07 2.47 2.349E+005 3.772E+004 1.129E+005 302. 65 2.20 2.602E+005

1. 921E+005

1. 250E+005 330.06

1. 40 3.982E+005

...,1.061E+005 1.906E+005 Th-234 92.38 2.1 3 3.743E+005 3.74E+005 8.064E+004 1.835E+005 92.80 2.10 3.785E+005 1.647E+005 1.856E+005 112.81 0.21 3.489E+006

-1.073E+006 1.708E+006 U-235 143. 76 10.96 5.996E+004 l.14E+004 -2.720E+004 2. 92 6E+004 163.33 5.08 1.32 6E+005

-9.059E+004 6.468E+004 185.71

57. 2 0 1. 141E+004 9.928E+002 5.555E+003 202.11

1. 08 6.128E+005 4.971E+005 2.981E+005 205.31 5.01

1. 317E+005

- 9.754E+004 6.406E+004 Am-2 41 59.54 35.90 1.666E+004 1.67E+004 -4.600E+002 8. 115E+003

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[453]

GA MM A S P E C T R U M A N A L Y S I S

'********************** ******************* ** ** **** *************~********

.lename: 54 52

!port Generated On tmple Title tmple Description tmple Identification unple Type tmple Geometry

,ak Locate Threshold

,ak Locate Range {in channels )

,ak Area Range (in channels )

lentification Energy Tolerance tmple Size tmpl e Taken On

quisition Started

_ve Time

,al Time

,ad Time 8/10 /2 016 4:52:06 PM B306100BFJWC021GD ST SW. WALL NUMB 2 1 SHOT 2 1

3. 00 85 -

81 92 85 -

81 92 10.000 keV

1. OOOE+OOO SQM 8/10/20 16 4:42:05 PM 600.0 seconds 600.7 seconds 0. 12 !;;

Energy Calibration Used Done On Bfficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/20 1 6 UNNELSTS 1 METER DATA,VAUDATED DATE l-l--11 TIME OS:t!<2

~~A

[454]

tj/.LU/ L U.l tl

'I: :JL : U tl J:'lVJ

.!:'age

'******************* ***~************************** ************* **********

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

545 2 Sample

Title:

B306100BFJWC02 1GD Peak Analysis Performed on:

8/10/2016 4:52:06 PM Peak Analysis From Channel:

85 Pea k Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV )

Area Uncert.

Counts 1

113-120 116.02 28.60 0.63 2. 55E+001

30. 2 6 7. 15E+001 2

346-354 349. 23 86.98 0.39 3.0lE+OOl 48. 59 2.57E+002 3

797 -

810 805.96 2 01. 30 0.86 1.13E+001 45.67 1.84E+002 4

95 0-961 954.59 238.50 0.60

4. 92 E+001

41. 09 1.46E+002 5

1175-1187 1181. 68 2 95. 33

0. 37 4.67E+001 34.0 2

9. 2 3E+001 6

1401-1415 1407.19 351. 77

1. 31 8.98E+001 34.40 7.13E+001 7

2325-2338 23 31.82 58 3.12

1. 2 6 6.llE+OOl 24.54 3.19E+001 8

2430- 2445 2435.84 609.14

1. 57 l.63E+002 32.92 3.61E+001 9

3638-3652 3643.55 911. 20 0.68 2.46E+001 20.74 2.84E+001 10 3868-3883 3874.85 969.04 0.56 3. 2 8E+001

19. 2 4 1.92E+001 11 4472 -

4484 4477.76 1119.78 0.38 2.78E+001 17.76 1.92E+001 12 5831-5855 5841. 65 1460.68

1. 74 3.02E+00 2 37.05 1.09E+001

= First peak in a multiplet region

= Other peak in a multiplet region Fitted singlet

rors quoted at 2. 000 sigma

[455]

1terrerence correcLea ACLlVlLY KeporL 0/.l U / L U.l O

.t'age

.)

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

=* ******************* ***************************** ************** ********

Sample

Title:

B306100BFJWC021GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES \\ Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Ba-1 33 Tl-2 08 Bi-2 11 Pb-212 Bi-2 1 4 Pb-214 Pa-23 1

1. 000 0. 739

1. 000 0.999 0.975

0. 350 0.976 0.575 1460.82*

79.61 81.00*

276.40 302.85*

356.01*

383.85 583. 1 9*

351. 07*

115.18 238.63*

300.09*

609.32*

768.36 806.18 934.06 112 0. 2 9*

1155. 2 1 1238.12 12 80.98 1377.67 1385.31 1401.52 1407.99 1509.21 1661. 27 172 9.59 17 64.49 1847.4 3 2118.51 2 41. 99*

2 95.22*

351.93*

785.96 27.36*

283.69 300.07*

302.65 330.06 Yield

( ':; )

10.66 2.65 32.90 7.16 18.34 62.05 8.94 85.00 13.02 0.60 43.60 3.30 45.49 4.89

1. 2 6 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.3 0 2.03 1.16 7. 2 5 18.42 35.60

1. 06 10.30

1. 70 2.47 2. 2 0

1. 40 Activity (pCi/SQM

)

1.57987E+007 1.47 25 5E+005 5.91158E+005 3.7 2 517E+005 2.4 72 05E+005 1.77532E+006 2.31236E+005 3. 285 41E+006

1. 2 6077E+006 9.0 2 077E+005

1. 39041E+00 6 5.88591E+005 6.49288E+005 3.98549E+005 4.38941E+006 Activity Uncertainty 2.37407E+006 2. 392 65E+005 4.4 12 61E+005

1. 54 736E+005

1. 03706E+005 7.38156E+005

1. 96618E+00 5 2.45319E+006 2.96524E+005 5.8012 1E+005 1.18184E+006 4.39273E+005 2.69713E+005 4.81995E+005 3.32481E+006

[456]

1terterence Correctect Activity Keport

~/ ~U / L U~b

~age

~

• = Energy l ine found in the spectrum.

@=Energy l ine not used fo r Weighted Mean Activity Energy Tolerance :

10.000 keV Nuclide confidence index threshold

0. 30 Errors quoted at 2.000 s igma

[457]

0/1-U/ L U.LO

'i ; ;J L ; U O r1vJ

'**************************~********************************************

I N T E R F E R E N C E C O R R E C T E D R E P O R T

• • ~**

'******************+***************************************** ~**~*******

Nuclide Nuclide Id Name Confidence K-40 X

Cd-109 Ba-133 X

Eu-155 Tl-208 Bi-211 Pb-212 Bi-214 Pb-214 X

Th227-XR Pa-231 X

Th-231 1.000 0.998

0. 739 0.304

1. 000 0.999 0.975

0. 350 0.976 0.389 0.575 0.914 Wt mean Activity (pCi/SQM

)

l.579868E+007

1. 4 72555E+005 2.472050E+005 9.531774E+004 l.717 3 66E+005 1.1864 72E+006 3.577649E+005 3.985489E+005 Wt mean Activity Uncertainty 2.374075E+006 2.392500E+005 1.037059E+005 l.529302E+006 2.202 22 0E+005 2.640317E+005

5. 2 05469E+005 4.789416E+005

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma U N I D E N T I F I E D Pea k Locate Performed on:

Pea k Locate From Channel:

Peak Locate To Channel:

Peak Energy P E A K S 8/10/2016 85 8192 Peak CPS 4:52: 0 6 PM No.

(keV)

Peak Size in Counts per Second

% Uncertainty Peak Type 3

2 01.30 9

10 911. 2 0 969.04

1. 8895E-002 4.1022E-002 5.4712E-0 02 M = First peak in a multiplet region m = Other peak in a multiplet region F

Fitted singlet Errors quot ed at 2.000 sigma 402.85

84. 27 58.60 Tol.

Sum Sum Tol.

Nuclide Th-22 7 Ac-22 8 U-235 U-23 5

[458]

lC.Llae 1v1u1-1..KepoL L 0/J.U/ L U.LO

'**************' ******** ***************~********** ************* ~**** ~**********

N U C L I D E M D A R E P O R T

'******'~***********************************************************************

+

Detector Name:

5452 Sample Geometry:

Sample

Title:

B306100BFJWC021GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Name K-40 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-113 Cs-134 Cs-13 7 Eu-1 52 Energy (keV) 1460.82

• 32 0.08 834.85 810.76 117 3. 2 3 1332.49 70 2.65 871. 09 255.13 391.70 475.36 563.25 569.33 604.72 795.86 801.95 1038.61 1167.97 1365.19 661.66 121. 7 8 2 44.70 295.94 344. 2 8 367.79 411. 12 44 3.96 488.68 563.99 586.26 678. 62 688.67 719.35 778.90 810.45 867.37 919.33 964.08 1085.87 1089.74 1112.07 1212.95 Yield

( Z; )

10.66 9.91 99.98 99.45 99.-85 99.9R 99.81 99.89 2.11 64.97

1. 48

8. 34 15.37 97.62 85.46 8.69 0.99

1. 79 3.02

85. 10 28.67 7.61 0.45 2 6.60 0.86 2.24 2.8 3 0.4 2 0.49 0.46 0.47 0.86

0. 28 12.96 0.32 4.26 0.43 14.65 10.24

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/SQM

) (pCi/SQM)

Activity (pCi/SQM)

1. 2 45E+006

1. 778E+006 1.582E+005 1.529E+005 1.936E+005 1.489E+005 1.655E+005 1.592E+005 8.386E+006 2. 2 97E+005 1.110E+007 1.916E+006 9.903E+005 2.577E+005 1.918E+005 1.812E+006 1.822E+007 1.086E+007 3.886E+006 1.870E+005 7.000E+005 2.425E+006 4.380E+007 6.058E+005 1.820E+007 7.464E+006 5.204E+006 3.736E+007 3.338E+007 4.507E+007 3.036E+007 1.771E+007 5.416E+007

1. 206E+006 4.853E+007 3.756E+006 3.428E+007 1.520E+006 1.656E+006 9.542E+006

1. 288E+006 1.325E+007

1. 2 4E+006

1. 78E+006 1.58E+005 1.53E+005 1.49E+005 1.59E+005 2. 30E+005 1.92E+005 1.87E+005 6.06E+005 1.580E+007 5.907E+005

7. 3 67E+004 9.026E+004 8.561E+004

- 2.064E+004

-2.794E+004 6.407E+004 2.735E+006 6.541E+004

-3. 357E+006 3. 2 42E+005 4.444E+004

- 1.817E+005 2.045E+005

-1.032E+006 1.584E+007 8.924E+005

-2.973E+006

-6.052E+004

-3.925E+004 3.070E+005 5.027E+007 7.000E+004

- 6.197E+006 3.160E+006 5.670E+005

-1.494E+006 1.607E+007 3.564E+007

-2.495E+007

-6.256E+006

-2.475E+007 4.655E+005 5.885E+007 2.160E+006 2.569E+007 8.118E+004

-7.115E+004

-2.699E+006 1.8 37E+005 5.737E+006 Dec. Level (pCi/SQM

)

5.515E+005

8. 5 60E+005 7.349E+004 7.087E+004 9.009E+004 6.728E+004 7.761E+004

7. 383E+004 4.056E+006 1.091E+005

5. 2 68E+006 9.031E+005 4.652E+005

1. 2 40E+005 8.948E+004 8.425E+005 8.476E+006 5.055E+006 1.703E+006 8.767E+004 3.4 2 4E+005 1.175E+006 2.12 0E+007 2.900E+005 8.686E+006 3.561E+006 2.461E+006 1.768E+007 1.576E+007 2.152E+007 1.411E+007

8. 2 63E+006 2.522E+007 5.610E+005 2. 2 54E+007

1. 744E+006 1. 576E+007 7.187E+005 7.650E+005 4.398E+006 5.962E+005 6.147E+006

[459]

1c.11ae l".IUA Keporc 0/.lU / L: U.lO

'I ; ::> L ; U O

.t'!VJ r cty e Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( ~)

(pCi/SQM ) (pCi/SQM )

(pCi/SQM)

(pCi/SQM)

Eu-152 1249.94 0.19 8.591E+007 6.06E+005 - 9.066E+007 3.929E+007 1299.14

1. 63 9.310E+006 5.854E+006

4. 22 1E+006 1408.01

21. 07 6.842E+005 3.027E+005 3.071E+005 1457.64 0.50 9.725E+007 3.599E+008 4.713E+007 1528.1 0

0. 28 4.335E+007 5.084E+005 1.892E+007 Eu-154 123.07 40.40 4.978E+005 4.77E+005 2.663E+005 2.435E+005 247.93 6.89 2.416E+006

-2.875E+006 1.167E+006 591.76 4.95 3.248E+006

-6.121E+005

1. 529E+006 692.42

1. 78 8.462E+006

-1. 893E+006 3.944E+006 723.30 20.06 9.498E+005 5.157E+005 4.489E+005 756.80 4.52 3.300E+006

- 3.535E+005 1.532E+006 873.18 12.08 1. 274E+006 3.738E+005

5. 894E+005 996. 2 9 10.48 1.578E+006 5.882E+005

7. 2 99E+005 1004.76 18.01 9.137E+005 O.OOOE+OOO 4.225E+005 1274.4 3 34.80 4.766E+005 2.873E+005 2.182E+005 1596.48

1. 80

6. 3 90E+006

-8.073E+006 2.751E+00 6 Eu-155 45.30

1. 31 1.112E+007

4. 22E+005 9.867E+006 5.395E+00 6 60.01

1. 22 l.466E+007 5.678E+006 7.150E+00 6 86.55*

30.70

4. 219E+005 1.578E+005 2.039E+005 105.31 21.10 1.023E+006

-1.971E+005 5.010E+005

+

Tl-2 08 583.19*

85.00

1. 370E+005 1.37E+005 2.472E+005 6.301E+004

+

Bi-2 11 351.07*

13.02 9.879E+005 9.88E+005 1.775E+006 4.672E+005 Pb-2 11 404.85 3.78 4.308E+006 4.31E+006 9.507E+004 2.054E+006 427. 09

1. 76 8.518E+006

-8.525E+006 4.037E+006 83 2.01 3.52 4.450E+006

-3.082E+006 2.066E+006 Bi-212 39.86

1. 06

1. 2 63E+007 2.88E+006 -6.346E+006

6. 111E+006 727.33 6.67 2.878E+006 1.070E+005

1. 361E+006 785.37 1.10 1.538E+007 2.691E+006 7.199E+006 1620.50

1. 4 7 8.141E+006

-3.440E+006 3.523E+006

+

Pb-212 115.18 0.60 3.540E+007 3.11E+005 1.520E+007 1.733E+007 238.63*

43.60 3.112E+005 2.312E+00 5 1.492E+005 300.09*

3.30 3.798E+006 3.285E+006 1.804E+006 Pb212-XR 74.82

10. 2 8 2. 2 54E+006

1. 28E+006 2.891E+005 1.106E+006 77.11

17. 10

1. 277E+006

-1. 999E+005

6. 2 59E+005 87.35 3.97 5.724E+006

-8.113E+005 2.807E+006 89.78

1. 46 1.503E+007

-4.459E+006

7. 367E+006

+

Bi-214 609. 32*

45.49 2.858E+005 2.86E+005 1.261E+006

1. 32 4E+005 768.36 4.89 3.513E+006

-5.414E+005 1.647E+006 806.18

1. 26 1.258E+007 1.389E+007 5.855E+006 934.06 3.11 5.454E+006 2. 32 5E+006 2.535E+006 1120. 2 9*

14.92 8.493E+005 9.021E+005 3.808E+005 1155. 21

1. 63 1.020E+007

- 1. 750E+006 4.695E+006 1238.12 5.83 3.773E+006 4.009E+006 1.769E+006 1280.98

1. 43 1.091E+007

-7. 218E+006 4.967E+006 1377.67 3.99 4.028E+006

1. 789E+006 1.832E+006 1385. 31 0.79 1.891E+007

- 1.264E+007 8.535E+006 1401. 52

1. 33 1.081E+007

-1.395E+007 4.852E+006 1407.99 2.39 6.022E+006 2.664E+006 2.703E+006 1509. 21 2.13 7.060E+006

1. 387E+006 3.169E+006 1 661. 27

1. 05 9.618E+006

-3.607E+006 4.028E+006

[460]

lC.l lde MU.A Keporc.

'd/.L U / L U.lo q : :J L : U b r'J.Vl

.!:'age

'd Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( %)

(pCi/SQM ) (pCi/SQM)

(pCi/SQM )

(pCi/SQM)

+

Bi-2 1 4 1729.59 2.88 4.833E+006 2.86E+005 2. 2 61E+006 2.125E+006 1764.49

15. 30 l.391E+006 l.846E+006 6.401E+005 1847.43 2.03 6.945E+006 5.553E+005 3.043E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 241. 99° 1

7. 2 5 1.871E+006 3.61E+005

l. 390E+006 8.973E+005 295. 22*

18.42 6.805E+005 5.886E+005 3.232E+005 351.93*

35.60 3.613E+005 6.493E+005 1.709E+005 785.96

1. 06 1.590E+007 2.516E+006 7.434E+006 Pb214-XR 74.82 5.80 3.995E+006 2. 25E+006 5.125E+005 1.960E+006

77. 11 9.70 2.252E+006

-3. 52 3E+005 1.103E+006 87.35 2. 2 4 1.015E+007

-1.438E+006 4.976E+006 89.78 0.82 2.676E+007

-7.938E+006 1.312E+007 Ra-226 186. 2 1 3.64

5. 213E+006

5. 21E+006 3.190E+006 2.540E+006 Ac-2 28 129.07 2.42 8.149E+006 8.34E+005 - 4.845E+006 3.984E+006 209.25 3.89 4.751E+006 7.961E+005 2. 309E+006 27 0.24 3.46 4.756E+006

1. 555E+006 2. 2 92E+006 32 8.00 2.95 5.485E+006 4.085E+005 2. 62 9E+006 33 8. 32

11. 27 1.478E+006 2.503E+005 7.086E+005 409.46

1. 92 8.420E+006

-4.985E+006 4. 011E+006 463. 00 4.40 3.814E+006 8.598E+005 1.814E+006 794.95

4. 25 3.799E+006

-6. 02 9E+005 1.771E+006 911. 20 25.80

8. 341E+005 6.794E+005 3.942E+005 964.77 4.99 4.4 23E+006

- 6.482E+005 2.090E+006 968.97 15.80 1.4 2 6E+006 2.485E+006 6.747E+005 1588. 2 0 3. 22 4.822E+006 2.144E+006 2.164E+006

+

Pa-23 1 27.36*

10.30 7.745E+005 7.74E+005 3.985E+005 3.661E+005 283.69

1. 70 1.006E+007 2.286E+006 4.850E+006 300.07*

2.47 5.075E+006 4.389E+006 2.410E+006 302.65 2. 20 7.461E+006

-1.421E+006 3.586E+006 330.06

1. 40 1.169E+007 2.815E+006 5.606E+006 Th-234 92.38 2.13 1.006E+007 1.01E+007 4.977E+006 4.927E+006 92.80 2.10 1.018E+007 5.078E+006 4.987E+006 112.81

0. 2 1 1.031E+008 3. 383E+007 5.054E+007 U-235 143.76 10.96 1.764E+006 3.33E+005 1.468E+005 8.615E+005 163.33 5.08 3.705E+006

1. 967E+006

1. 807E+006 185.71 57.20 3.326E+005

1. 759E+005 1.621E+005 202.11

1. 08 1.739E+007 1.185E+007 8.458E+006 2 05. 31 5.01 3.825E+006 7.092E+005 1.8 62E+006 Am-2 41 59.54 35.90 4.945E+005 4.95E+ 00 5 8.410E+004 2.412E+005

+

Nuclide identified during the nuclide identification Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[461]

GA MM A S P E C T R U M A N ALYSIS

'******************************** ~**** *************** ~* ******************

_lename: 5452 iport Generated On tmple Title tmple Description tmple Identification tmpl e Type tmpl e Geometry iak Locate Threshold iak Locate Range (in channels )

iak Area Range (in channels) ientification Energy Tolerance tmple Size tmpl e Taken On

quisition Started

_ve Time ial Time iad Time 9/13 /2 016 3: 21: 23 PM B306100BFJWC022GD Steam Tunnel Unit-1 022 1 meter

3. 00 85 -

85 -

10.000 81 92 81 92 keV 1.000E+OOO S met e rs 9/13 /2 01 6 3: 11: 2 0 PM 600.0 seconds 601.5 seconds 0. 2 4 %

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency I D 1/13/2015 8/9/2016 UNNELSTS 1 METER DATA-VALIDATED DAarrE L* K~ 11 TIME 235:

a?..!4&

[462]

___,,_..,._............ J.

..... _£ -- -

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

Title:

B306100BFJWC022GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 Cs-137 Tl-2 08 Pb-212 Bi-2 14 Pb-214

1. 000

1. 000

1. 000 0.974 0.612 0.977 1460.8 2

• 661. 66 1*

58 3.19*

115.18 23 8.63*

300.09*

609. 32

• 768.36 806.18 934. 06 1120.29*

1155.2 1 123 8.12*

1280.98 1377.67 1385.31 1401.52 1407.99 1509. 21 1661. 27 1729.59 1764.49*

1847.43 2118.51 241. 99*

295. 22

• 351.93*

785.96 Yield

( %)

10.66 85.10 85.00 0.60 43.60 3.30 45.49 4.89

1. 2 6 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.3 0 2.03

1. 16 7.25 18.42 35.60

1. 06 Activity (pCi/S me) l.64591E+007 2.03835E+005 1.56012E+005 3.73348E+005 7.36950E+006 1.37754E+006 1.33 094E+006 2.50602E+006

1. 7769 0E+00 6 2. 2 4493E+006

1. 32 027E+006 1.10037E+006

• = Energy line found in the spectrum.

Activity Uncertainty 2.46935E+006 8.79736E+004 1.02487E+005 2.08460E+005 3.06896E+006 3.11651E+005 6.60711E+005 1.27 063E+0 0 6 6.94747E+005 1. 25244E+006 5.48911E+005 3.39462E+005

@=Energy line not used fo r Weighted Mean Activity Energy Tolerance :

10.000 keV Nuclide confidence index threshold =

0.30 Errors quot ed at 2.000 s igma

[463]

lLC::.L.L C::.LCll\\....,c:;:

\\..,V.L.LC\\..;l..C~

.C'l.\\...,\\.-..LV..L L.,;f l.'\\.CtJV.L L..

.J /

.L._J/ £. V.LU

...J * £....l.

• L....J L l."l

'******************************************************** ~*** *"**********

I N T E R F E R E N C E C O R R E C T E D R E PORT Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/S me )

Uncertainty K-40

1. 000

1. 645913E+007 2.469353E+006 X

Ba-1 33

0. 3~ 1 Cs-137

1. 000 2.0 38351E+005 8.797364E+004 Tl-208

1. 000 1.560117E+005 1.024872E+005 X

Bi-211 0.999 Pb-21 2 0.974

1. 854582E+005 2.151379E+005 Bi-2 14 0.612

1. 470458E+006 2.558410E+005 Pb-214 0.977 1.150892E+006 2.9124 21E+005

?

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 2.000 sigma

[464]

! Lt::.L.L t::..Lt:ll\\,..,C::

\\..,U.L J..-c:;;:\\..... l..t::'U

.C'l.\\.....~..LV..L~:f J.'\\.'C.J::-IV.1. ~

• • • • • +-****

U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Peak Energy J

/..L.J/ £.. U..l..U P E A K S 9/13/2 016 85 8192 Peak CPS

...J * £...L * £...J

.L J."J

'~******'~'J'*

3: 21: 23 PM No.

(keV)

Peak Si ze in Counts per Second

~- Uncertainty Peak Type 1

74.79

1. 6347E-001 5

543.90 2.4271E-002 M = First peak in a multiplet region m

Other peak in a multiplet region F

Fitted singlet Errors quoted at 2.000 sigma 75.08 Tol.

106.50 Tol.

J Tol.

Nuclide Pb214-XR Ba-133 Pb212-XR Pb212-XR Pb214-XR Cs-138

[465]

J I.l..J / L V_l_U

.J

• L.l.

• L.J r l *1

'****************************************************************~*************

N U C L I D E MD A R E P O R T

'*************************************************************************~****

+

+

Detector Name:

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name K-40 Cr-51 Mn-54 Co-58 Co-6 0 Nb-94 Sn-113 Cs-134 Cs-137 Eu-15 2 Energy (keV) 1460.82 "-*

32 0.08 834.85 810.76 1173. 23 1332.49 702.65 871.09 255.13 391. 70 475. 3 6 563. 25 569.33 604.72 795.86 801.95 1038.61 1167.97 1365.19 661.66*

121. 7 8 2 44.70 2 95.94 344. 2 8 367.79 411. 12 44 3.96 488.68 563.99 586.26 678.62 688.67 719. 35 778.90 810.45 867.37 919.33 964.08 1085.87 1089.74 1112.07 1212.95 5452 1 meter B306100BFJWC022GD C:\\GENIE2K\\CAMFILES\\ Zion Lib-BNL.NLB Yield

(,., )

10.66 9.91 99.98 99.45 99.85 99.98 99.81 99.89 2.11 64.97

1. 48

8. 3 4

15. 37

97. 62 85.46 8.69 0.99

1. 79

3. 02 85.10 28.67 7.61 0.45 26.60 0.86 2. 2 4 2.83 0.4 2 0.49 0.46 0.47 0.86

0. 28 12.96 0.3 2

4. 2 6 0.43 14.65

10. 2 4

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/S me)

(pCi/S me)

Activity (pCi/S me )

1. 428E+006 l.643E+006

1. 692E+005 1.676E+005 1.733E+005

1. 489E+00 5

1. 583E+00 5

1. 52 5E+005 8.745E+006 2.517E+005 1.078E+007

1. 783E+006

1. 002E+006 2.560E+005

1. 849E+005 1.867E+006 1.750E+007 9.264E+006 3.679E+006 1.106E+005 7.619E+005 2.575E+006 4.562E+007 6.581E+005 1.901E+007 7.656E+006 5.438E+006 3.685E+007 3.030E+007 4.591E+007 3.459E+007

1. 832E+007 5.654E+007 1.139E+006 5.190E+007 3.726E+006 3.895E+007

1. 5 06E+006 1.730E+006

1. 026E+007

1. 2 88E+006

1. 2 69E+007 1.43E+006

1. 64E+006 1.69E+005 1.68E+005 1.49E+005

1. 52E+005 2. 52E+005 1.85E+005 1.11E+005 6.58E+005 1.646E+007

-6.560E+004

8. ~96E+004 2.8 2 9E+004 1.800E+004 1.144E+004 9.504E+00 3

-6.546E+004 2.085E+006

-1.598E+005

-5.561E+006

-1.756E+006

-7.486E+004

-1.174E+005 3.396E+003

-8.800E+005 3.312E+00 6

-7. 2 99E+006

-2.219E+006 2.038E+005

-1.244E+005 5.951E+005 5.983E+007

-2.796E+005 2.394E+006

3. 33 6E+006

-1.856E+006 1.916E+007

-2.299E+007

-4.314E+007 1.327E+007 1.137E+007

-1.844E+007

-6.072E+005 8.954E+006

-2.954E+006

-8. 25 4E+006 4.314E+005 5.158E+005

-2.947E+006 9.017E+004

-3. 1 71E+00 6 Dec. Level (pCi/S me) 6.4 34E+005 7.883E+005 7.899E+004 7.822E+004 7.992E+004 6. 72 8E+004 7.400E+004 7.050E+004

4. 236E+006

1. 2 01E+005 5.111E+006

8. 3 69E+005 4.709E+005

1. 232E+005 8.603E+004 8.702E+005 8.115E+006

4. 25 9E+006

1. 59 9E+006 4.946E+004 3.733E+005

1. 250E+006 2. 211E+007 3.161E+005 9.088E+006 3.657E+006 2.578E+006

1. 742E+007 1.422E+007 2.194E+007 1.622E+007 8.570E+006 2.641E+007

5. 2 78E+005 2.4 2 3E+007

1. 72 9E+00 6

1. 809E+007 7.117E+005 8.023E+005 4.757E+006 5.962E+00 5 5.866E+006

[466]

tL;.L.LUC:

1*JU.M.

f'.C: _E.JU.L L

/f.J..

J/ L. V.J. U

.:J. L.J.. L...J r:1*1 ra~c:

Nuclide Energy Yield Line MDA Nuclide MD.A Activity Dec. Level Name (keV)

( % )

(pCi/S me ) (pCi/S me)

(pCi/S me)

(pCi/S me)

Eu-1 52 1249.94 0.19 9.173E+007

6. 58E+00 5 5.137E+007

4. 22 1E+007 1299.14

1. 63 1.019E+007 3.333E+006 4.660E+006 1408.01

21. 07 8.125E+005 7.862E+005 3.712E+005 1457.64 0.50 9.906E+007 3.408E+008 4.803E+007 1528.10

0. 28 4.214E+007 1.423E+006 1.832E+007 Eu-154 123.07 40.40 5.381E+005 5. 33E+005 -9.638E+00 3 2.637E+005 247.9 3 6.89 2.680E+006

-1.587E+006 1. 2 99E+006 591. 76 4.95 3.433E+006 l.501E+006

1. 62 2E+006 692.42

1. 78 9.665E+006

-4.420E+006 4.546E+006 723.30 20.06 8.560E+005 2.791E+005 4.020E+005 756.80

4. 52 3. 273E+006

-2.519E+006 1.519E+006 87 3.18 12.08

1. 285E+006

-8.287E+002 5.951E+005 996. 2 9 10.48 1.476E+006 2. 36 4E+005 6.790E+005 1004.76 18.01 9.054E+005

l. 397E+005 4.183E+005 1274.43 34.80 5.330E+005 4.590E+005 2.464E+005 1596.48

1. 80 7.179E+00 6 5.576E+006 3.146E+006 Eu-155 45.30

1. 31 1.042E+007 8.44E+005 -3.441E+006 5.043E+006 60.01

1. 22

1. 576E+007

- 1. 304E+006 7.701E+006 86.55 30.70 8.440E+005 1.013E+006 4.149E+00 5 105.31 21.10 1.073E+006

-5. 92 6E+005 5.264E+005

+

Tl-208 583.19*

85.00 1.546E+005 1.55E+005 1.560E+005 7.182E+004 Bi-211 351.07*

13.02

1. 083E+006

1. 08E+006 3.009E+006 5.146E+005 Pb-211 404.85 3.78

4. 2 93E+006

4. 2 9E+006 -1. 463E+006 2.046E+006 427.09

1. 76 9.276E+006

-6.533E+006 4.416E+006 832.01 3. 52 4.592E+006

-2.192E+006 2.137E+006 Bi-212 39.86

1. 06

1. 177E+007 2.60E+006 -8.572E+006 5.678E+006 727.33 6.67 2.597E+006 2.451E+006

1. 22 0E+006 785.37 1.10 1.413E+007 4.716E+006 6.571E+006 1620.5 0

1. 47 7.884E+006

-1. 2 45E+006 3.395E+006

+

Pb-212 115.18 0.60 3.674E+007 3.11E+005 -1. 763E+007

1. 800E+007 238.63*

43.60 3.106E+005 3.733E+005

1. 4 90E+005 300.09*

3.30 4.194E+006

7. 3 69E+006 2.002E+006 Pb212-XR 74.82

10. 2 8 2. 62 2E+006 1.48E+006 7.659E+006

1. 2 90E+006 77.11 17.10 1.478E+006

-3.570E+005

7. 2 64E+005 87.35 3.97 6.455E+006

1. 641E+006 3.173E+006 89.78

1. 46 1.696E+007 2.687E+006 8.333E+006

+

Bi-214 609.32*

45.49 2.915E+005

.91E+005

1. 378E+006 1.353E+005 768.36 4.89 3.921E+006 1.130E+006 1.851E+U06 806.18

1. 2 6 1.268E+007

-3.488E+006 5.903E+006 934.06 3.11 6.023E+006 5.143E+006 2.8 2 0E+006 1120. 2 9*

14.92 9.144E+005

1. 331E+006 4.134E+005 1155. 21

1. 63 1.277E+007 8.693E+006 5.979E+006 1238. 12

• 5.83 1.612E+006 2.506E+006 6.881E+005 1280.98

1. 43

1. 2 73E+007 2.797E+006 5.877E+00 6 1377.67 3.99 4.187E+006

-3.035E+006

1. 911E+00 6 1385.31 0.79 2.005E+007

-7.968E+006 9.104E+00 6 1401.52

1. 33 1.135E+007

-3.381E+006 5.124E+006 1407.99 2.39 7.151E+006 6.919E+006 3.267E+00 6 1509. 21

2. 1 3 7.060E+006

1. 25 6E+006 3.169E+00 6 1 661. 27

1. 05

1. 230E+007 5.077E+006

5. 371E+00 6

[467]

H.,.L.LUC:

1*1ur1 1'C:_l:.)U.L L.

J /

.L..J /

L U.LU

..J

• L.L. L..J r1*1 ra~c:

0 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

(~)

(pCi/S me)

(pCi/S me)

(pCi/S me)

(pCi/S me)

+

Bi-214 1729.59 2.88 3.588E+006 2.91E+005 1.196E+005 1.503E+006 1764.49*

15.30 7.910E+005 1.777E+006 3.400E+005 1847.43 2.03

7. 122E+006

-1. 375E+006 3.132E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 241. 99*

7. 2 5

1. 868E+006 3.96E+005 2. 245E+006 8.957E+005 295.2 2*

18.42 7.513E+005

1. 32 0E+006 3.586E+005 351.93*

35.60 3.960E+005 1.100E+006

1. 882E+005 785.96

1. 06 1.469E+007 5.278E+005 6.834E+006 Pb214-XR 74.82 5.80 4.648E+006 2.61E+006 1.358E+007 2.286E+006 77.11 9.70 2.606E+006

- 6.294E+005

1. 281E+006

87. 35 2. 2 4 1.144E+007 2.909E+006 5.623E+006 89.78 0.8 2 3.020E+007 4.784E+00 6

1. 484E+007 Ra-226 186. 2 1 3.64 5.510E+006 5.51E+006

1. 444E+004 2.688E+006 Ac-228 129.07 2.42 8.687E+006 7.77E+005 -3.838E+006

4. 253E+006 209. 25 3.89 4.993E+006 2.643E+006 2.430E+006 270. 2 4 3. 46

5. 107E+006

-1.831E+006 2.467E+006 32 8.00 2.95 5.571E+006

-1.843E+006 2.672E+006 33 8. 32

11. 27 1.612E+006 6.514E+005 7.759E+005 409.46

1. 92 8.733E+006

-9.7 2 0E+005 4.168E+006 463.00 4.40 3.743E+006

-5.467E+005

1. 779E+006 794.95

4. 2 5 3.771E+006

-1. 759E+005

1. 757E+006 911.20 25.80 7.774E+005

-4.059E+005 3.659E+005 964.77 4.99 4.506E+006 4.551E+006 2.132E+006 968.97 15.80

1. 426E+006 1.578E+006 6.747E+005 1588. 2 0

3. 22 4.565E+006 4.462E+005 2.035E+006 Pa-2 31 27.36 10.30 7.900E+005 7.90E+005 7.585E+005 3.7 39E+005 28 3.69

1. 70

1. 049E+007 8.048E+006 5.063E+006 300.07 2.47 7.199E+006

-4. 63 8E+006 3.471E+006 302.65 2. 2 0 7.650E+006

-3. 34 8E+006 3.680E+006 330.06

1. 40 1.187E+007

-1. 912E+006 5.697E+006 Th-23 4 92.38 2.13 1.119E+007 1.12E+007 -2.478E+006 5.495E+006 92.80 2.10 l.119E+007

-6.375E+006 5.493E+006 112.81 0.21 1.055E+008

-1.143E+008 5.172E+007 U-235 143.76 10.96 1.854E+006 3.55E+005 -5.706E+005 9.068E+005 163.33 5.08 3.967E+006

-1.542E+006

1. 938E+006 185.71

57. 20 3.554E+005 2.393E+005

1. 734E+005 202.11

1. 08 l.715E+007

-6.146E+006

8. 342E+006 205.3 1 5.01 3.767E+006

-2.043E+006

1. 832E+006 Am-241 59.54 35.90

5. 2 67E+005

5. 2 7E+005 -9.529E+00 3 2.573E+005

+

Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[468]

GA MM A S P E C T R U M A N A L Y S I S

'** ************ ********************* ****** ********************* ****~**~

• _lename: 54 52 iport Generated On 1mple Title tmple Description 1mple Identification trnple Type tmple Geometry iak Locate Threshold iak Locate Range (in channels )

iak Area Range (in channels) lentification Energy Tolerance 1mple Size tmple Taken On

quisition Started

_ve Time ial Time iad Time 8/10 /2 016 4: 52 :06 PM B306100BFJWC0 2 1GD ST SW. WALL NUMB 21 SHOT 2 1 3.00 85 -

85 -

10.000 81 92 81 92 keV 1.000E+OOO SQM 8/1 0/2 01 6 4:4 2 :0 5 PM 600. 0 seconds 600.7 seconds 0.12 ~-

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER DATA,VALIDATED DATE t-l-11 TIME OSAS-

~~:,

[469]

--~- ----- -J ---

..... -r - -

'*************** *******************************************************~*

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

'*****************************~'******************************************

Detector Name:

5452 Sample

Title:

B306100BFJWC021GD Peak Analysis Performed on:

8/10 /2 016 4:52:06 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV)

Area Uncert.

Counts 1

113-120 116.02 28.60 0.63 2.5 5E+001

30. 2 6 7.15E+001 2

346-354 349. 23 8 6. 98

0. 39 3.0lE+OOl 48.59 2.57E+002 3

797 -

810 805.96 201. 30 0.86 1.13E+001 45.67 1.84E+002 4

950-961 954.59 238.50 0.60 4.92E+001

41. 09

1. 46E+002 5

1175-1187 1181.68 295.33 0.37 4.67E+001 34.0 2 9.23E+001 6

1401-1415 1407.19 351. 77

1. 31

8. 98E+001 34.40 7.13E+001 7

2325-2338 2331. 82 583.12

1. 2 6 6.11E+001 2 4.54 3.19E+001 8

2430 -

2445 2435.84 609.14

1. 57 1.63E+002 32. 92 3.61E+001 9

3638 -

3652 3643.55 911.20 0.68 2.46E+001 20. 74 2.84E+001 10 3868-3883 3874.85 969.04 0.56 3.28E+001

19. 2 4

1. 92E+001 11 4472-4484 4477.76 1119.78 0.38 2.78E+001 17.76 1.92E+001 12 5831-5855 5841. 65 1460.68

1. 74 3.02E+00 2 37.05 1.09E+001

= First peak in a multiplet region

= Other peak in a multiplet region Fitted singlet

-rors quoted at 2.000 sigma

[470]

V/..J... V/ £- V

..J...V

'*************** **************~**** *********** ****************** ' *******

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

• • • ~,.*

Sample

Title:

B306100BFJWC021GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES \\ Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-4 0 Ba-133 Tl-2 08 Bi-2 11 Pb-212 Bi-2 14 Pb - 214 Pa-2 31

1. 000 0.739

1. 000 0.999 0.975 0.35 0 0.976 0.575 1460.82*

79.61 81.00*

276.4 0 302.85*

356.01*

383.85 583.19*

351.07*

115.18 2 38.63*

300.09*

609.32*

768.36 806.18 934.06 1120. 2 9*

1155.21 12 38.12 1280.98 1377.67 1385.31 1401.52 1407.99 1509.21 1661.27 1729.59 1764.49 1847.43 2 118.51 2 41. 99*

2 95. 2 2*

351.93*

785.96 2 7. 3 6*

283.69 300.07*

302.65 330.06 Yield

( 't )

10.66 2.65 32.90

7. 1 6 18.34 62.05 8.94 85.00 13.02 0.60 43.60 3.30 45.49 4.89 1.26 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03

1. 16

7. 25 18.42 35.60

1. 06 10.30

1. 70 2.47 2. 2 0

1. 40 Activity (pCi/SQM )

1. 57987E+007 1.47255E+005 5.91158E+005 3.72517E+005 2.47 2 05E+005

1. 77532E+006 2.31236E+005 3.28541E+006

1. 2 6077E+006 9.02 077E+005

1. 3 9041E+006 5.88591E+005 6.4 92 88E+005 3.98549E+005 4.38941E+006 Activity Uncertainty 2. 37407E+006 2. 39265E+005 4.41261E+005

1. 547 3 6E+005

1. 037 06E+005

7. 38156E+005

1. 96618E+005 2.45319E+006 2.965 2 4E+005 5.80121E+005 1.18184E+006 4.39273E+005 2.69713E+005 4.81995E+005

3. 32 481E+006

[471]

.....__...._.L... _

........... y

...L '-..1

.&.'-_.t"'_-'-

• = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tole rance :

10.000 keV Nuclide confidence index threshold =

0.30 Errors quoted at

~.000 sigma

[472]

v..._._...J

"'~-,e- ---

'***** ***************** ************************************************~

I N T E R F E R E N C E C O R R E C T E D R E P O R T

'*********************~'*************************************************

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/SQM )

Uncertainty K-40

1. 000 1.579868E+007 2. 3 74075E+006 X

Cd-1 0 9 0.998 Ba-1 33 0.739

1. 4 72555E+0 05 2.392500E+005 X

Eu-1 55 0.304 Tl-2 08

1. 000 2.472050E+00 5 1.037059E+005 Bi-211 0.999 9.531774E+004 1.529302E+006 Pb-212 0.975 l.717366E+005 2.20222 0E+005 Bi-214

0. 350 l.186472E+006 2.640317E+005 Pb-214 0.976 3.577649E+005

5. 2 05469E+005 X

Th227-XR 0.389 Pa-2 31 0.575 3.985489E+005 4.789416E+005 X

Th-231 0.914

?

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 2.000 sigma U N I D E N T I F I E D P E A K S 8/10/201 6 85 8192 Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Peak Energy No.

(keV) 3 201. 30 9

10 911. 2 0 969.04 Peak Size in Counts per Second 1.8895E-0 02 4.1022E-002 5.4712E-002 M = First pea k in a multiplet region m

Other peak in a multiplet region F

Fitted singlet Errors quoted at

2. 000 sigma 4:52:06 PM Peak CPS

% Uncertainty 402.85

84. 2 7 58.60 Peak Type Tol.

Sum Sum Tol.

Nuclide Th-2 27 Ac-228 U-235 U-235

[473]

~. -.JL..

v v

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'* *** *********t************************+****************** *+** *****************

N U C L I D E MD A R E P O R T

=************************************************************************** ****

+

Detector Name:

5 452 Sample Geometry :

Sample

Title:

B306100BFJWC021GD Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\Zion Lib-BNL.NLB Nuclide Name K-40 Cr-51 Mn-54 Co-58 Co-60 Nb-94 Sn-113 Cs-1 34 Cs-13 7 Eu-1 52 Energy (keV) 1460.82*

32 0.08 834.85 810.76 1173. 2 3 1332.49 70 2.65 871. 09 255.13 391.70 475.36 563.25 569.33 604.72 795.86 801. 95 1038.61 1167.97 1365.19 661.66 121.78 244.70 295.94 344.28 367.79 411. 12 443.96 488.68 563.99 586. 2 6 678. 62 688.67 719.35 778.90 810.45 867. 37 919. 33 964.08 1085.87 1089.74 1112.07 1212.95 Yield

( % )

10.66 9.91 99.98 99.45 99.*85 99.98 99.81 99.89 2.11 64.97

1. 48

8. 34

15. 37

97. 62 85.46 8.69 0.99

1. 79 3. 02

85. 10 28.67 7.61 0.45 2 6.60 0.86 2. 2 4 2.83 0.42 0.49 0.46 0.47 0.86

0. 2 8 12.96 0.32 4.26 0.43 14.65

10. 2 4

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/SQM )

(pCi/SQM )

1.245E+006 1.778E+006 1.582E+005

1. 529E+00 5 1.936E+005

1. 489E+005

1. 655E+005 1.592E+005

8. 3 86E+006 2. 2 97E+005 1.110E+007 1.916E+006 9.903E+005 2.577E+005 1.918E+005 1.812E+006

1. 82 2E+007 1.086E+007 3.886E+006 1.870E+005 7.000E+005 2.425E+006

4. 3 80E+007 6.058E+005 1.820E+007 7.464E+006 5.204E+006 3.736E+007 3.338E+007 4.507E+007 3.036E+007

1. 771E+007 5.416E+007

1. 2 06E+006 4.853E+007 3.756E+006 3.428E+007 1.520E+006

1. 656E+006 9.542E+006

1. 288E+006 1.325E+007

1. 2 4E+006

1. 78E+006 1.58E+005 1.53E+005 l.49E+005 1.59E+005 2. 3 0E+005

1. 92 E+005 l.87E+005 6.06E+005 Activity (pCi/SQM )

1.580E+007 5.907E+00 5 7.367E+004 9.02 6E+004 8.561E+004

-2.064E+004

-2.794E+004 6.407E+004 2.735E+006 6.541E+004

-3. 3 57E+006 3. 2 42E+005 4.444E+004

- 1. 817E+005 2.045E+005

-1. 032E+006

1. 584E+007 8. 92 4E+005

-2.973E+006

- 6.052E+004

- 3.925E+004 3.070E+005 5.027E+007 7.000E+004

-6.197E+006 3.160E+006 5.670E+005

- 1. 494E+006 1.607E+007 3.564E+007

-2.495E+007

-6. 256E+006

-2.475E+007 4.655E+005 5.885E+007 2.160E+006 2.569E+007 8.118E+004

- 7.115E+004

-2.699E+00 6 1.837E+005 5.737E+00 6 Dec. Level (pCi/SQM )

5.515E+005 8.560E+005 7.349E+004 7.087E+004 9.009E+004 6.728E+004 7.761E+004

7. 388E+004 4.056E+006 1.091E+005 5.268E+006 9.031E+005 4.652E+005

1. 2 40E+005 8.948E+004 8.425E+005 8.476E+006 5.055E+006

1. 703E+006 8.767E+004 3.424E+005 1.175E+006 2. 120E+007 2.900E+005 8.686E+006 3.561E+006 2.461E+006 1.768E+007

1. 57 6E+007 2.152E+007 1.411E+007

8. 2 63E+006 2. 522E+007 5.610E+00 5 2.254E+007

1. 744E+006 1.576E+007 7.187E+005 7.650E+005 4.398E+006 5.962E+005 6.147E+006

[474]

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Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( "ci )

(pCi/SQM ) (pCi/SQM)

(pCi/SQM

)

(pCi/SQM)

Eu-15 2 1249.94 0.19 8.591E+007 6.06E+005 -9.066E+007 3. 92 9E+007 1299.14

1. 63

9. 310E+006 5.854E+006

4. 22 1E+006 1408.01

21. 07 6.842E+005 3.027E+005 3.071E+005 1457.64 0.50

9. 72 5E+007 3.599E+008 4.713E+007 1528.10

0. 2 8

4. 335E+007 5.084E+005 1.892E+007 Eu-154 123.07 40.40 4.978E+005 4.77E+005 2.663E+005 2.435E+005 247.93 6.89 2.416E+006

-2.875E+006 1.167E+006 591. 76 4.95 3. 248E+006

-6.121E+005 1. 529E+006 692.42

1. 78 8.46~E+006

-l.893E+006 3.944E+006 723.30 20.06 9.498E+005 5.157E+005 4.489E+005 756.80 4.52 3.300E+006

-3.535E+005 1.532E+006 873.18 12.08 l.27 4E+006 3.738E+005 5.894E+005 996.29 10.48 1.578E+006 5.882E+005 7. 299E+005 1004.76

18. 01 9.137E+005 O.OOOE+OOO

4. 22 5E+005 1274.43 34.80 4.766E+005 2.873E+005 2.182E+005 1596.48

1. 80

6. 3 90E+006

-8.073E+006 2.751E+006 Eu-1 55

45. 30

1. 31

1. 112E+007

4. 22E+005 9.867E+006

5. 395E+006 60.01

1. 22

1. 4 66E+007 5.678E+006 7.150E+006 86.55*

30.70

4. 219E+005

1. 578E+005 2.039E+005 105.31 21.10 1.023E+006

-1. 971E+005 5.010E+005

+

Tl-208 583.19*

85.00 1.370E+005 1.37E+005

2. 472E+005 6.301E+004

+

Bi-211 351.07*

13.02 9.879E+005 9.88E+005 1.775E+006 4.672E+005 Pb-211 404.85 3.78

4. 308E+006 4.31E+006 9.507E+004 2.054E+006 427.09

1. 76 8.518E+006

- 8.525E+006 4.037E+006 832.01 3.52 4.450E+006

- 3.082E+006 2.066E+006 Bi-212 39.86

1. 06

1. 2 63E+007 2.88E+006 -6. 3 46E+006

6. 111E+006 727.33

6. 67 2.878E+006 1.070E+005

1. 361E+006 785.37

1. 10 1.538E+007 2.691E+006 7. 199E+006 1620.50

1. 4 7 8.141E+006

-3.440E+006 3. 52 3E+006

+

Pb-212 115.18 0.60 3.540E+007 3.11E+005 1.520E+00 7

1. 733E+007 238.63*

43.60 3.112E+005 2.312E+005 1.492E+005 300.09*

3.30 3.798E+006 3.285E+006 1.804E+006 Pb212 -XR 74.82

10. 2 8 2. 2 54E+006

1. 28E+00 6 2.891E+005 1.106E+006 77.11 17.10

1. 277E+006

- 1.999E+005 6.259E+005 87.35 3.97 5.724E+006

- 8.113E+005 2.807E+006 89.78

1. 46 1.503E+007

- 4.459E+006 7.367E+006

+

Bi - 21 4 609.32*

45.49 2.858E+005 2.86E+005

1. 261E+006

1. 32 4E+005 768.36 4.89 3.513E+006

-5.4 14E+005

1. 64 7E+006 806.18

1. 2 6

1. 25 8E+007

1. 389E+007 5.855E+006 934.06 3.11 5.454E+006 2.325E+006 2.535E+006 1120.29*

14.92 8.493E+005 9.021E+005 3.808E+005 1155. 21

1. 63 1.020E+007

-1. 7 50E+OO 6 4.695E+006 1238.12 5.83 3.773E+006 4.009E+006 1.769E+006 1280.98

1. 43

1. 091E+007

- 7. 218E+006 4.967E+006 1377.67 3.99 4.028E+006 1.789E+006

1. 832E+006 1385.31 0. 7 9

1. 891E+007

-1. 2 64E+007 8.535E+006 1401. 52

1. 33 1.081E+007

- 1. 395E+007 4.852E+006 1407.99 2.39 6. 022E+006 2.664E+00 6 2.703E+006 1509. 21 2.13 7.060E+006 1.387E+00 6 3.169E+006 1661. 27

1. 05 9.618E+006

-3.607E+00 6 4.028E+006

[475]

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.L:JL/I"l.

.1.'\\.C:t,JU.L L.

U/.l.V/ L. V.l.V

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0 Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

(.~* )

(pCi/SQM)

(pCi/SQM )

(pCi/SQM )

(pCi/SQM )

+

Bi-214 1729.59 2.88 4.833E+006 2.86E+005 2. 2 61E+006 2.125E+006 1764.49 15.30 1.391E+006 1.846E+006 6.401E+005 1847.4 3 2.0 3 6.945E+006 5.553E+005 3.043E+006 2118.51 1.16 O.OOOE+OOO O.OOOE+OOO O.OOOE+OOO

+

Pb-214 241.99*

7. 25

1. 871E+006 3.61E+005

1. 3 90E+006 8.973E+005 295. 22

• 18.42 6.805E+005 5.886E+005 3. 232E+005 351.93*

35.60 3.613E+005 6.493E+005 1.709E+005 785.96

1. 06 1.590E+007 2.516E+006 7.434E+006 Pb214-XR 74.8 2 5.80 3.995E+006 2.25E+006 5.125E+005 1.960E+006 77.11 9.70 2.252E+006

-3.523E+005 1.103E+006 87.35 2.24 1.015E+007

-1.438E+006 4.976E+006 89.78 0.82 2.676E+007

-7.938E+006

1. 312E+007 Ra-22 6 186.21 3.64

5. 213E+006

5. 21E+006 3.190E+006 2.540E+006 Ac-22 8 129.07 2.42 8.149E+006 8.34E+005 - 4.845E+006 3.984E+006 209.25 3.89 4.751E+006 7.961E+005 2. 309E+006 270.24

3. 4 6 4.756E+006

1. 555E+006 2. 2 92E+006 328.00 2.95 5.485E+006 4.085E+005 2. 62 9E+006 338.32

11. 2 7

1. 4 78E+006 2.503E+005 7.086E+005 409.46

1. 92 8.4 2 0E+006

-4.985E+006 4.011E+006 463.00 4.40 3.814E+006 8.598E+005 1.814E+006 794.95

4. 25 3.799E+006

- 6.029E+005 1.771E+006 911.20 25.80

8. 3 41E+005 6.794E+005 3.942E+005 964.77 4.99 4.423E+006

-6.482E+005 2.090E+006 968.97 15.80

1. 426E+006 2.485E+006 6.747E+005 1588.20 3.22 4.822E+006 2.144E+006 2.164E+006

+

Pa-231 27.36*

10.30 7.745E+005 7.74E+005 3.985E+005 3.661E+005 283.69

1. 70 1.006E+007 2. 2 86E+006 4.850E+006 300.07*

2.47 5.075E+006 4.389E+006 2.410E+006 302.65 2.20 7.461E+006

-1. 42 1E+006 3.586E+006 330.06

1. 40 1.169E+007 2.815E+006 5.606E+006 Th-234 92.38 2.13 1.006E+007 l.01E+007 4.977E+006 4.9:7E+006 92.80 2.10 1.018E+007 5.078E+006 4.987E+006 112.81 0.21 1.031E+008 3.383E+007 5.054E+007 U-235 143.76 10.96 1.764E+006 3.33E+005

1. 468E+005 8.615E+005 163.33 5.08 3.705E+006

1. 967E+006

1. 807E+006 185.71

57. 2 0 3.326E+005

1. 759E+005

1. 621E+005 2 02.11

1. 08

1. 739E+007 1.185E+007 8.458E+006 205.31 5.01 3.825E+006 7.092E+005 1.8 62E+006 Am-241 59.54 35.90 4.945E+005 4.95E+005 8.410E+004 2.412E+005

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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

[476]

GA MM A S P E C T R U M ANALYSIS

'* ~***********************************~*********************************

_lename: 54 52 iport Generated On 1mple Title tmple Description 1mple Identification 1mple Type tmple Geometry iak Locate Threshold iak Locate Range (in channels) iak Area Range (in channels) lentification Energy Tolerance tmpl e Si ze 1mple Taken On

quisition Started

_ve Time ial Time iad Time 9/13/2016 3 : 21: 23 PM B306100BFJWC022GD Steam Tunnel Unit-1 022 1 mete r 3.00 85 -

85 -

10.000 81 92 81 92 keV 1.000E+OOO S meters 9/ 13 / 2 016 3 :11: 2 0 PM 600.0 seconds 601.5 seconds 0 -24 ~-

Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 1/13/2015 8/9/2016 UNNELSTS 1 METER DATAVALIDATED DATE/-t-L1 TIME-5,zs:

a~&

[477]

J f

.J.....1/ L..V.J..V

....J

• £....L * £......J L 1:J.

'***********************************~********************'"***************

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

5452 Sample

Title:

B306l00BFJWC022GD Peak Analysis Performed on:

9/13/2016 3:21: 23 PM Peak Analysis From Channel:

85 Peak Analysis To Channel:

8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)

(keV)

Area Uncert.

Counts 1

296-306 300.55 74.79 0.99 9.81E+001 73.64 5.25E+002 2

949-960 954.82 238.56 0.84 7.95E+001 42.47 1.49E+002 3

1175-1190 1180.60 295. 06 0.96 1.05E+002 40.19 9.93E+001 4

1 401-1415 1407.78 351. 92 1.18 l.52E+00 2 40.10 8.69E+001 5

2170- 2180 2175.07 543.90 0.79 1.46E+001 15.51 1.74E+001 6

2 324-2335 2330.80 582.86 0.44 3.85E+001 24.89 4.65E+001 7

2428 -

2444 2436.73 609.36

1. 52 1.78E+002 34.10 3.61E+001 8

2 638-2652 2644.50 661.34 0.41 4.72E+001 19.55

1. 68E+001 9

447 2-4487 4480.21 1120.40

1. 51 4.10E+001 2 0.11 2.00E+OOl 10 4945-4958 4951.89 1238.31 0.65 2.87E+001 14.39

8. 2 6E+OOO 11 5831-5855 5842.50 1460.89

1. 98 3.15E+002 38.51 1.43E+001 12 7050- 7064 7057.74 1764.51 1.12 4.33E+001 16.58 8.68E+OOO

= First peak in a multiplet region

= Other peak in a multiplet region

= Fitted singlet

rors quoted at 2.000 sigma

[478]

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I N T E R F E R E N C E C O R R E C T E D R E P O R T Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/S me \\

Uncertaint:*

K-40

1. 000 1.645913E+007 2.469353E+006 V

Ba-133 0.321 Cs-137

1. 000 2.038351E+005 8.797364E+004 Tl -208

1. 000 1.560117E+005 1.024872E+005 X

Bi-211 0.999 Pb-212 0.974 1.854582E+005 2.151379E+005 Bi-214 0.61 2 1.470458E+006 2.558410E+005 Pb-214 0.977 1.150892E+006 2.912421E+005

?

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 2.000 sigma

[479]

' '-'-'.l....l... '-'..L. '-'.L.L'-"'-

~V.L..-'-'-'-"'-'--A L.l.'-"'-..L V..L '-.:J J.\\.'-1::-".._.,,,.L....._.

U N I D E N T I F I E D Peak Locate Performed on:

Peak Locate From Channel:

Peak Locate To Channel:

Peak Energy P E A K S 9/13/2 01 6 85 8192 Peak CPS 3: 21 : 23 PM No.

(keV)

Peak Size in Counts per Second

's Uncertainty Peak Type 1

74.79 1.63 47E-001 5

543.9 0 2.4271E-002 M

First peak in a multiplet region m

Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

75. 08 Tol.

10 6.5 0 Tol.

Tol.

Nuclide Pb214-XR Ba-133 Pb212-XR Pb212-XR Pb2 14-XR Cs-138

[480]

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N U C L I D E MD A R E P O R T

+

+

Detector Name:

Sample Geometry:

Sample

Title:

Nuclide Library Used:

Nuclide Name K-40 Cr-51 Mn-54 Co-5 8 Co-6 0 Nb-94 Sn-113 Cs-134 Cs-137 Eu-152 Energy (keV) 1460. 82

• 320.08 834.85 810.76 1173. 23 1332.49 702.65 871. 09 255.1 3 391.70 475.36 563. 2 5 569.33 604.7 2 795.86 801. 95 1038.61 1167.97 1365.19 661.66*

121.78 244.70 295.94 344. 2 8 367.79 411.12 443.96 488.68 563.99 586. 2 6 67 8. 62 688.67 719.35 778.90 810.45 867. 3 7 919. 33 964.08 1 085.87 1089.74 1112.07 1212.95 54 52 1 meter B306100BFJWC022GD C:\\GENIE2K\\CAMFILES \\ Zion Lib-BNL. NLB Yield

( % )

10.66 9.91 99.98 99.45 99.85 99.98 99.81 99.89 2. 11 64.97

1. 48 8.34 15.37 97.62 85.46 8.69 0.99

1. 79 3.0 2 85.10 28.67 7.61 0.45 26.60 0.86 2.24 2.83 0.42

0. 4 9 0.46 0.47 0.86

0. 28 12.96

0. 32

4. 2 6 0.4 3 14.65

10. 2 4

1. 73 13.69

1. 43 Line MDA Nuclide MDA (pCi/S me ) (pCi/S me)

1. 42 8E+006

1. 643E+006

1. 692E+005

1. 676E+005 1. 733E+005 1.489E+005 1. 583E+005

1. 525E+005 8.745E+006 2.517E+005 1.078E+007 1.783E+006

1. 002E+006 2.560E+005 1.849E+005 1.867E+006 1.750E+007 9.264E+006 3.679E+006 1.106£+005 7.619E+005 2.575E+006 4.562E+007 6.581E+005 1.901E+007 7.656E+006 5.438E+006 3.685E+007 3.030E+007 4.591E+007 3.459E+007

1. 832E+007 5.654E+007 1. 139E+006 5.190E+007 3.726E+006 3. 895E+007 1.506E+006 1.730E+006

1. 026E+007

1. 28 8E+006

1. 2 69E+007 1.43E+006

1. 64E+006

1. 69E+005 1.68E+005

1. 4 9E+005 1.52E+005 2.52E+005 1.85E+005 l. 11E+005 6.58E+00 5 Activity (pCi/S me )

1. 64 6E+007

- 6.560E+004

8. 29 6E+004 2.8 2 9E+004 1.800E+004 1.144E+004 9.504E+00 3

- 6.546E+004 2.085E+006

-1. 598E+005

-5.561E+006

-1. 756E+006

-7.486E+004

-1. l 74E+00 5 3.396E+00 3

-8.800E+005 3.312E+006

-7. 2 99E+006

-2.219E+006 2.038E+005

-1.244E+005 5.951E+005 5.983E+007

-2.796E+005 2. 39 4E+006 3. 33 6E+006

-1. 856E+006 1.916E+007

-2. 2 99E+007

-4. 314E+007

1. 327E+007 1.137E+007

- 1.844E+007

-6.072E+005 8.954E+006

-2.954E+006

-8. 254E+006

4. 314E+005 5.158E+005

-2.947E+006 9.017E+004

-3.171E+006 Dec. Level (pCi/S me) 6.4 34E+00 5 7.883E+005 7.899E+004 7.822E+004 7.992E+004 6.728E+004 7.400E+004 7.050E+004

4. 23 6E+006

1. 201E+005 5.111E+006 8.369E+005 4.709E+005

l. 232E+005

8. 603E+004 8.7 02E+005 8.115E+006

4. 25 9E+006

1. 599E+006 4.946E+004 3.733E+005

1. 2 50E+006 2. 211E+007 3.161E+005 9.088E+006 3.657E+006 2.578E+006 1.742E+007 1.422E+0 07 2.194E+007

1. 62 2E+007 8.570E+006 2.641E+007

5. 2 78E+005 2.4 23E+007

1. 72 9E+006

1. 809E+007 7.117E+005 8.023E+005 4.757E+006 5.962E+005 5.866E+006

[481]

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Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( z )

(pCi/S me ) (pCi/S me)

(pCi/S me )

(pCi/S me )

Eu-152 1249.94 0.19 9.173E+007 6.58E+005 5.137E+007 4.221E+007 1299.14

1. 63 1.019E+007

3. 333E+006 4.660E+006 14 08.01

21. 07 8.125E+005 7.862E+005 3.712E+005 1457.64 0.50 9.906E+007 3.408E+008 4.803E+007 152 8.10

0. 28

4. 214E+007 l.423E+006 1.832E+007 Eu-154 123.07 40.40

5. 381E+005 5.33E+005 -9.638E+003 2.637E+005 247.9 3 6.89 2.680E+006

-l.587E+006

1. 2 99E+006 591.76 4.95 3.433E+006

1. 501E+006

1. 62 2E+006 692.42

1. 78 9.665E+006

-4.420E+006 4.546E+006 723.30 20.06 8.560E+005 2.791E+005 4.020E+00 5 756.80

4. 52 3.273E+006

-2.519E+006

1. 519E+00 6 873.18 12.08 l.285E+006

-8.287E+002 5.951E+005 996. 2 9 10.48 l.476E+006 2.364E+005 6.790E+005 1004.76 18.01 9.054E+005 1.397E+005 4. 183E+005 1274.43 34.80

5. 330E+005 4.590E+005

2. 464E+005 1596.48

1. 80 7.179E+006 5.576E+006 3.146E+006 Eu-155

45. 30

1. 31 1.042E+007 8.44E+005 - 3.441E+006 5.043E+006 60. 01

1. 22

1. 576E+007

- 1. 304E+006 7.701E+006 86.55 30.70 8.440E+005 1.013E+006 4.149E+005 105.31 21.10 1.073E+006

- 5. 92 6E+005

5. 26 4E+005

+

Tl-208 583.19*

85.00

1. 546E+005 1.55E+005 1.560E+005 7.182E+004 Bi-211 351.07*

13.02 1.083E+006 1.08E+006 3.009E+006 5.146E+005 Pb-211 404.85 3.78

4. 2 93E+006

4. 2 9E+006 -1.463E+006 2.046E+006 427.09

1. 76

9. 2 76E+006

-6.533E+006 4.416E+006 832.01 3.52 4.592E+006

-2.192E+006 2.137E+006 Bi-2 12 39.86

1. 06 1.177E+007 2.60E+006 -8.572E+006 5.678E+006 727.33 6.67 2.597E+006 2.451E+006

1. 22 0E+006 785.37 1.10 1.413E+007 4.716E+006 6.571E+006 1620.50

1. 47 7.884E+006

-1. 2 45E+006 3.395E+006

+

Pb-21 2 115.1 8 0.6 0 3.674E+007 3.11E+005 -1.763E+007

1. 800E+007 238.63*

43.6 0 3.106E+005 3.733E+005

1. 4 90E+005 300.09*

3.3 0 4.194E+006

7. 369E+006 2.002E+006 Pb212-XR 74.82 10.28 2.622E+006 l.48E+006 7.659E+006

1. 290E+006

77. 11

17. 10

1. 478E+006

- 3.570E+005

7. 2 64E+005 87.35 3.97 6.455E+006

1. 641E+006 3.173E+006 89.78

1. 46 1.696E+007 2.687E+006 8.333E+006

+

Bi-214 609. 32

• 45.49 2. 915E+005 2.91E+005

1. 378E+006 1.353E+005 768. 36 4.89 3.921E+006 1.130E+006

1. 851E+006 806. 1 8

1. 2 6 1.268E+007

-3.488E+006 5.903E+006 93 4.0 6 3.11 6.023E+006 5. 143E+006 2.8 2 0E+006 1120. 2 9*

14.92 9.144E+005

1. 331E+006 4.134E+005 1155.21

1. 63

1. 27 7E+007 8.693E+006 5.979E+006 1238.12*

5.83 1.612E+006 2.506E+006 6.881E+005 128 0.98

1. 43

l. 273E+007 2.797E+006 5.877E+006 1377.67 3.99 4.187E+006

-3.035E+006

1. 911E+006 1385. 31 0.79 2.005E+007

-7.968E+006 9.104E+006 1401. 52

1. 33 1.135E+007

-3.381E+006 5.124E+006 1407.99 2.39 7.151E+006 6.919E+006 3. 2 67E+006 1509. 21 2.13 7.060E+006

1. 256E+006 3.169E+006 1661. 2 7

1. 05

1. 23 0E+007 5.077E+006

5. 371E+006

[482]

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Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV)

( ';, )

(pCi/S me)

(pCi/S me)

(pCi/S me)

(pCi/S me)

+

Bi-2 14 1729.59 2.88 3.588E+006 2.91E+005 l.196E+005 l.503E+006 1764.49*

15.30 7.910E+005 1.777E+006 3.400E+005 1847.43 2.03

7. 122E+006

-l.375E+006

3. 132E+006 2118.51 1.16 O.OOOE+OOO O. OOOE+OOO O.OOOE+OOO

+

Pb-2 14 241.99*

7. 2 5

1. 868E+006 3.96E+005 2.245E+006 8.957E+005 295. 22

• 18.42 7.513E+005

1. 32 0E+006 3.586E+005 351. 93*

35.60 3.960E+005 1.100E+006

1. 882E+005 785.96

1. 06

1. 469E+007 5.278E+005 6.834E+006 Pb2 14-XR 74.82 5.8 0 4.648E+006 2.61E+006 1.358E+007 2.286E+006 77.11 9.7 0 2.606E+006

-6.294E+005

1. 281E+006 87.35 2. 2 4 1.144E+007 2.909E+006 5.623E+006 89.78 0.82 3.020E+007 4.784E+006 1.484E+007 Ra-2 2 6 186.21

3. 64 5.510E+006 5.51E+006 1.444E+004 2.688E+006 Ac-228 129.07 2.4 2 8.687E+006 7.77E+005 -3.838E+006 4.253E+006 209. 2 5 3.89 4.993E+006 2.643E+006 2.430E+006 270. 2 4 3.46 5.107E+006

-1. 831E+006 2.467E+006 328.00 2.95 5.571E+006

-1.843E+006 2.672E+006 338. 32

11. 27 1.612E+006 6.514E+005 7.759E+005 409.46

1. 92 8.733E+006

- 9.720E+005 4.168E+006 463.00 4.40 3.743E+006

- 5.467E+005

1. 779E+006 794.95

4. 25 3.771E+006

- 1.759E+005

1. 757E+006 911. 20 25.80 7.774E+005

-4.059E+005 3.659E+005 964.77 4.99 4.506E+006 4.551E+006 2.132E+006 968.97 15.80 1.426E+006

1. 578E+006 6.747E+005 1588.20

3. 22 4.565E+006 4.4 62E+005

2. 035E+006 Pa-23 1 27.36 10.30 7.900E+005 7. 90E+005 7.585E+005 3.739E+005 283.69

1. 70

1. 049E+007 8.048E+006 5. 063E+006 300.07 2.47 7.199E+006

- 4.638E+006 3.471E+006 302.65 2.20 7.650E+006

- 3. 348E+006 3.680E+006 330. 0 6

1. 40 l.187E+007

-1. 912E+006 5.697E+006 Th-234 92.38 2.13 1.119E+007 1.12E+007 -2.478E+OOE 5.495E+006 92.80 2.10 1.119E+007

-6.375E+006 5.493£+006 112. 81

0. 21 l.055E+008

-1.143E+008 5.172E+007 U-235 143.76 10.96 l.854E+006 3.55E+005 -5.706E+005 9.068E+005 163.33 5.08 3.967E+006

- l.542E+006

1. 938E+006 185.71

57. 2 0 3.554E+005 2.393E+005

1. 734E+005 202.11

1. 08 1.715E+007

-6.146E+006 8.342E+006 205.31 5.01 3.767E+00 6

-2.043E+006

1. 832E+006 Am-24 1 59.54 35.90

5. 2 67E+005

5. 27E+0 05 -9. 52 9E+003 2.573E+005

+ = Nuclide identified during the nuclide identification

• = Energy line found in the spectrum

> = Calculated MDA is zero due to zero counts in the region, or the region is outside the spectrum, or MDA has not been calculated

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