ML21165A116
| ML21165A116 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 02/14/2018 |
| From: | Barley W - No Known Affiliation |
| To: | Office of Nuclear Material Safety and Safeguards |
| Snyder A | |
| References | |
| NX-503, Rev 0 | |
| Download: ML21165A116 (60) | |
Text
Unit: N/A HUMBOLDT BAY POWER PLANT CALCULATION COVER SHEET Calculation No. NX-503 HBAPC-20.1 Rev. 12 Page 1 of 1 Sheet 1
of 2 Rev.
0 1439681 Preliminary
[gl Final SAPN:
Type or Purpose of Calculation:
NE Caisson Well Dewatering Assessment Structure, System, or Component:
FSS Area NOL0l-09 Depa rt men t /Group:
FSS No. of Sheets:
Prepared by:
Checked by:
Approved by:
Total [
] = Cover and Rec of Revs [ 2 ] + body [ 11 ] + attach. [
Print/ Signature. '2-:L Gordon Madison RP CALCULATIONS Discipline /
- l-1~/f Designated RP Approver
- K.,.,s Rov.Jbe,.,.,,.y /
~-= :z-1s-18' PrintName RP Manager:W H Barley/ ~
Print/Signature Site Closure Manager Concurrence :_.!.W.!._..!cH"-'B=ar'-.!Cle"'-.L!--/....1,,L.JL.!C'---Ul-4,.,o<"""""-..,.,.._"""'""""4------'---/ ---"~"'-'----_,/....s.L.- ---'---l -=~=------
Print/Signature Date Registered Engineer Approval: (Complete section A for Civil calcs. Complete A or B for others)
A. Insert Engineer Stamp or Seal Below B.
Engineer's full name: -------~N~/
A_
Registration Number: ________
N_/ A_
Expiration Date:
NI A
Section All Calculation No.
Sheet 2 of ___b__
HUMBOLDT BAY POWER PLANT CALCULATION CHANGE SHEET NX-503 Description of Change Reason for Change HBAP C-20.2 Rev.12 Page I of I Rev.
0 New Calculation Assessment of NE Caisson Dewatering well
Purpose:
NE Caisson Dewatering Well Assessment NX-503 Rev. 0 Page 3 of 10 This calculation/ assessment estimates the maximum residual source term surrounding the Northeast Caisson Dewatering Well and compares it with the DCGL for License Termination. To perform this assessment, sediment composite and grab sample results, and gross down-hole gamma measurements were evaluated.
Background Discussion:
During the performance of the Remediation Turnover Survey for the Caisson Area on January 4, 2018, two sediment samples were collected inside the pump casing for NE Dewatering Well #1. It was noted that water containing concrete fines material had been pumped to this well which had b_ecome inoperable during efforts to remove groundwater in the Caisson. The two samples had been collected using a hand auger through an access port cut in the side of the casing. The wet sample results of the two samples were evaluated and indicated elevated activity exceeding the DCGLEMc collectively by a factor of 3 for a 1 m2 area. The following table shows the gamma results from the two samples collected and the EMC fraction calculated based solely on gamma spec results.
Table 1 NE Well 8.~mediation Characterization Sample Results V.
Sample Description Co-60 Cs-137 Eu-152 Eu_.154 Total EMC No.
pCi/g pCi/g pCi/g
. pCi/g Fraction 2018-NE Caisson Well 0044 Sediment Sample A 3.16E+00 1.12E+0l 7.73E+0l 2.28E+00 2.36E+00 (soil) 2018-NE Caisson Well
-1.3f,E+o2*
0045 Sediment Sample*B 5.00E+00 1.15E+0l 4.29E+00. :. 3.95E+00 (soil)
..~.
Since both characterization samples exceeded the DCGLEMu the NE well, along with the three other operational dewatering wells were excluded from the FSS unit which was independently surveyed by ORISE on January 11, 2018. As part of corrective actions for the NE well remediation to determine the extent of condition, additional characterization samples were collected of the material removed and material remnant remaining along with down-hole gamma characterization measurements to determine the extent of the residual source term outside the casing. This issue was captured SAPN 1439210.
For an operational perspective, it should be noted that the well logs indicate that water containing debris material which had accumulated in the suppression chamber was pumped to the well on four separate occasions between February 2017 and May of 2017. After May 18, 2017, the well pump was inoperable and never returned to service.
Assumptions and Inputs:
Drawings indicate 12 inch ID, schedule 80, PVC well casing which became 14 inch OD casing to achieve the 12 inch minimum ID. The ASTM D1785 PVC pipe schedule indicates that 12 inch PVC, schedule 80 piping should have a wall thickness of approximately 0.687 inches, an ID of 11.3 inch and an OD= 12.75 inch. 14 inch schedule 80 PVC is 14 inch OD and 12.4 ID with a 0. 75 wall thickness. The 14 inch pipe
NE Caisson Dewatering Well Assessment NX-503 Rev. 0 Page 4 of 10 dimensions are used in the modeling: 12.4 inch ID and 0. 75 inch wall thickness. PVC pipe density ranges from 1.3 to 1.45 g/cc; 1.4 g/cc is used in the model.
The well was pumped down prior to taking individual measurements and sediment removal to the extent practical. For the purpose of the modeling, a dry well casing is modeled.
The cross-sectional sketch to the right indicates the basic modeling concept and it is not to scale. The MicroShield modeling geometry is called "Annular Cylinder - Internal Dose Point" and is intended to model piping with the source term either inside or outside the piping. In this case, the assumed source term is outside the piping. The thickness of the source term is initially estimated at 8 inches.
Assumed Source Term = 8 inches thick; modeled as concrete with density adjusted to 1.8 g/cc embedded in mud/soils of similar density.
Shi~ld 1,- Well Casing 0. 75 inch thick PVC, modeled
- as Ca.rbon with density adjusted to 1.4 g/cc.
Cylinder radws -:- Inside well casing _6.2 inch radius deRsity adjustment based on wet or dry condition.
Detector (dimensionless) and moves along the axis of the well casing for measurements Bottom of the well: approx.: -108 ft below grade or
-98 elevation. Field measurements indicated bottom as investigated was 23.5 ft below the top of the casing.
NE Caisson Dewatering Well Assessment NX-503 Rev.a Page 5 of 10 Source term modeling was based on a mix of radionuclides expected to be present and contribute to the gamma response ofthe instrumentation: Cs-137 (Ba-137m); Co 60, Eu-152.The relative concentrations can be manipulated based on sample results. Top, of casing is at approximately -75 feet elevation for an overall height of the model of 23 feet (276 inches). However, modeling increments of 3 or 4 foot sections allows better assessment of varying dose rates along the well casing axis.
Source Term:
Several samples were collected from the NE Caisson Well during remediation activities as components and sediment were removed and analyzed by gamma spectroscopy. The results are summarized below:
Sample No.
Description Co-60 pCi/g Cs-137 pCi/g Eu-152 pCi/g 2018-0369 NE Caisson Well Pump (soil)
ND 1.87E+00 ND 2018-0370 Composite Sample above Pump (soil) 1.53E+00 2.06E+0l 3.47E+0l 2018-0373 Sediment Bottom +l ft (soil) 1.31E+00 9.34E+0l 7.19E-01 2018-0375 Bottom of Well (soil) 7.00E-02 4.33E+00 ND 2018-0376 Composite Sample Above Pump 2.00E-02 1.07E+00 ND (water) pCi/ml pCi/ml ND= not detected above method detection levels; Case 1:
The sample resul~s above tend to confirm earlier assumptions.
The Eu-152 dominant sample (2018-0370) was composited from material removed above the pump and it is a reasonable assumption that whatever debris may have been transferred into the well when it was being used as an injection point the debris settled out on top of the pump.
Less than 1 pCi/g of Eu-152 was found in two samples below the pump or on the pump itself.
In Case 1, it is assumed that sample 2018-0373 best represents the residual source term in the gravel pack surrounding the well. Therefore, the relative ratio of Co-60:Cs-137:Eu-152 will be used in the model to represent the gamma source term measured by the scintillation detector.
The input to MicroShield is in units of uCi/cm3 so the following table is developed for ease of reference:
Nuclide Sample 2018-0373 Fractional density corrected MicroShield input Co-60 1.3 pCi/g 1.4%
2.34 pCi/cm3 2.34E-6 uCi/cm3 Cs-137 93.4 pCi/g 97.9%
168.1 pCi/cm3 1.68E-4 uCi/cm3 Ba-137m 1.59E-4 uCi/cm3 Eu-152 0.7 pCi/g 0.7%
1.3 pCi/cm3 1.3E-6 uCi/cm3 The source term assumed density is 1.8 g/cc as indicated above. In the model, the Cs-137 gamma source term is represented by the Ba-137m gamma emission at 94.6% of the Cs-137 concentration. Case 1 is more appropriate for the conservative assumption that a potential exposure pathway includes ingestion of the water at some point in the future. This estimate is based on results from a grab sediment sample collected using a clam-shell sampler inside the
Case 2:
NE Caisson Dewatering Well Assessment NX-503 Rev.a Page 6 of 10 casing nearing the completion of remediation activities with ~1' of material remaining in the bottom of the well. The decision to perform an EMC calculation based on the above sample results was considered inappropriate as the there was no corresponding proximal down-hole gamma measurement response indicating there were source materials in the 8" gravel fill material surrounding the casing.
In Case 2, it is assumed that sample 2018-0370 best represents the residual source term in the gravel pack surrounding the well. Therefore, the relative ratio of Co-60:Cs-137:Eu-152 will be used in the model to represent the gamma source term measured by the scintillation detector.
The input to MicroShield is in units of uCi/cm 3 so the following table is developed for ease of reference:
Nuclide Sample 2018-0370 Fractional density corrected MicroShield input Co-60 1.5 pCi/g 2.6%
2.7 pCi/cm3 2.7E-6 uCi/cm3 Cs-137 20.6 pCi/g 36.3%
37.1 pCi/cm3 3.71E-5 uCi/cm3 Ba-137m 3.51E-5 uCi/cm3 Eu-152 34.7 pCi/g 61.1%
62.5 pCi/cm3 6.25E-5 uCi/cm3 The source term assumed density is 1.8 g/cc as indicated above. In the model, the Cs-137 gamma source term is represented by the Ba-137m gamma emission at 94.6% of the Cs-137 concentration. Case 2 is more appropriate for the assumption that the solid material in the gravel pack moves to the surface in an intrusion scenario.
Limitations:
MicroShield only allows definition of a single source term at a time. Therefore, in the model concept shine through the end cap at the bottom of the well is not considered. A higher measured response at the bottom of the well should be expected if the source term is uniformly distributed.
Modeling is established assuming that the detector is at the centerline of the well casing.
However, based on the ID of the well casing, there may be some bias in individual measurements based on proximity to the casing wall. No stand-off was built-in to minimize this geometry error. The average of several measurements should minimize this bias.
Method Summary / Data:
Down-hole gamma survey data was collected (HBPP-CHAR-CAISSON-DW-00) at six inch increments using a 3" by 3" thick Nal scintillation detector. The collected data allows averaging several measurements along a segment of the well. The multiple measurements identify non-uniformities in the source term and minimize the bias toward individual measurements. From the data plotted in Figure 2, the ncpm line depicts the raw down-hole gamma measurement adjusted for instrument background. The smoothed line shows averaged ncpm data for each 1' span (three data points averaged, the segment 6" above, the original segment, and the segment 6" below). Note that the O' segment corresponds to the top of the casing, and the -22.5' location is the segment located 1' above the casing end cap bottom which was inaccessible because of water. It is also interesting to note that the dominating peak extents (15,000-20,000 ncpm)
NE Caisson Dewatering Well Assessment NX-503 Rev. 0 Page 7 of 10 range from the -7.5' to -14.5' elevation. This elevation range spans the original sediment characterization location collected during the remediation turnover survey from the top layer of material on top of the pump (estimated to be collected at the -10' segment location). The detector response observed for this region was likely from concrete slurry-like materials deposited in the casing which migrated through the perforated portion of the casing during
. remediation activities within the active core region and thus represents a Eu-152 dominated source term..
Figu~e 2 Model 44-162 Gamma Pipe Monitor Results Net CPM vs Casing Depth 25000 ~--------------------------~
18 uR/hr
--ncp sm othed 5000 -+---+~ -------------- ------------------1 The Ludlum Vendor Manual provides a conversion factor associated with the 44-162 probe used for these measurements of 2300 cpm per uR/hr. This conversion factor is based on a Cs-137 source term, however, for the two MicroShield cases considered the dose rate does not change whether the Cs-137 dominant source term is assumed or the Eu-152 dominant source term is assumed.
The Ludlum detector is partially shielded on the back side so the conversion factor is likely based on a 2 pi response rather than the 4 pi response predicted in the MicroShield model. Therefore, the conversion factor is adjusted to compensate for the detection efficiency in the environment to 1200 cpm per uR/hr. Using the 1200 cpm per uR/hr conversion factor, text is overlaid on the graphic above to indicate an approximate observed dose rate. Note that only the exposure
NE Caisson Dewatering Well Assessment NX-503 Rev.a Page 8 of 10 conversion graphic is adjusted. The ncpm data results have only been adjusted for instrument background.
Interpretation of the data plot above reveals that the well effect is likely responsible for the essentially linear detector response from the -22.5' to -12.5' segments. Starting around segment
-12, the detector starts indicating increasing activity from the source term in the gravel pack with a peak response around the -10' segment. The decreasing response from the -9.5' to the -8' segment provides confidence that the deposited source term is likely in a gravel pack volume of approximately 2' in height. It also suggests that the source term did not move vertically within the gravel pack, which is expected given that the well pump has been out of commission since May 2017.
Calculations:
Using the source terms above and MicroShield 9 (See Appendix 1) with the detector at a center-point in a 4 foot section of the casing, initial calculations indicate a dose rate inside the well casing:
Case 1 Source term (Cs-137 dominant) = 81 uR/hr:
75 uR/hr ( 0.6 MeV), 2.5 uR/hr (1.0 Mev), and 3.3 uR/hr (1.5 Mev). These energies reflect the Cs-137 dominant source term and the Co and Eu contribute about 7% to the overall dose rate.
The total residual activity to generate this dose rate would be about 75 uCi around the 4 foot section of casing.
Case 2 Source term (Eu-152 dominant)= 80 uR/hr 5 uR/hr (0.3-0.4 MeV),18 uR/hr ( 0.6 MeV), 8 uR/hr (0.8 MeV), 26 uR/hr (1.0 Mev), and 22 uR/hr (1.5 Mev). These energies reflect the Eu-152 dominant source term and Cs contributes about 23% to the overall dose rate. The total residual activity to generate this dose rate would be about 44 uCi around the 4 foot section of casing. In case 2, the source term is somewhat shorter lived than in the Cs-137 dominant case (T112Cs-137 = 30 yrs; T112 Eu-152 = 13.6 yrs).
The MicroShield predicted dose rates (80 uR/hr) assume the removed sediments sample represents the residual source term concentration and is nominally 5 times the actual measured residual activity. The residual measured activity is actually 19% of that concentration (i.e. 10-18 uR/hr vs. 80 uR/hr).
Comparing the observed dose rate with the MicroShield predicted dose rate a correction to the sample
- concentrations can be made based on the ratio of the observed to predicted dose rate:
15 uR/hr =
the maximum observed dose rate in a 4' section from Figure 2 in the -8 to -12 ft range 80 uR/hr =
the predicted dose rate based on sample 2018-0370 results in a 4' section (i.e. Case
- 2)
The residual concentration is 15/80 or 19% of the sample concentration.
NE Caisson Dewatering WeU Assessment A calculation was done based on the Sample 2018-0370 relative to the DCGLw and DCGLEMc:
Results pCi/g FSS Average Results for NOL 09 Lab Sample#
Co-60 Cs-137 Eu-152 C-14 Sr-90 Co-60 Cs-137 Eu-152 C-14 Sr-90 2018-0370 1.53E+OO 2.06E+Ol 3.47E+Ol 3.18E->OO
- 6.35E-01
- 0.275 *'
ND ND 4.22E-02
- 1.61E-01 DGCLw 3.BOE-.00 7.90E->OO 1.00E+Ol 6.30E->OO 1.S0E-.00 LTP Table 5-1 DGCLw Scaled 3.58E->00 7.45E->00 9.43E->OO 5.94E->OO 1.41E->OO NOL09-01FSSP Table 3 lm2 AF 1.00E+0l 1.40E+Ol 9.l0E-.00 1.80E+04 9.60E+02 LTP Table 5-6 DGC4MC 3.80E+Ol 1.11E+02 9.l0E+Ol 1.13E+05 1.44E+03 DCGLw*AF DGC4MCScaled 3.58E+0l 1.04E+02 8.58E+0l 1.07E405 1.35E403 DCGlw Scaled *AF Sum of Fractions Calculation relative to DCGLw Scaled Unity EMC Calculation relative to DCGLeMC Scaled 7.BSE-.00 Used Scaled DCGls to take credit from dose from CSM Wall.
Used eq 5-7 from LTP, did not adjust for SU Cs-137 and Eu-152 as S.35E-01 these were not detected in any FSS samples cc-... -&>
DCGi;°+ (ArNFartor)(DCGlw) < l Equation 5-7 The spreadsheets are attached as Appendix 2 and included in the electronic file.
Results:
NX-503 Rev. 0 Page 9 of 10 Based on the observed dose rates and the inputs to Case 2 the observed residual concentrations are:
Nuclide Sample 2018-0370 Observed Residual Concentration(x0.19)
Co-60 1.5 pCi/g 0.3 pCi/g Cs-137 20.6 pCi/g 4.0 pCi/g Ba-137m 3.7 pCi/g Eu-152 34.7 pCi/g 6.6 pCi/g
- ~
~esultspCi/g C-14&Sr-90notadjusted ~
FSSAverageResultsforNOL-01::!f __
Co-60 1 Cs-137 Eu-152 C-14 Sr-90 Co-60 Cs-137 Eu-152 C-14 Sr-90 as meuured 3.00E-01 4.00E+OO i 6,60E+oo I 3.18E+oo~ 6.35E-011 0.275
- ND ND 4.22E-02 l.61E-Ol DGClw 3.80E+oo 7.90E+oo 1 1.00E+ol 6.30E+oo 1.SOE+oo LTPTable S-IDGC~Scaled -,-3.SBE-:.:00 -7.45E+oolj 9.43E+oo'. 5._94E+oo 1.41E+oo NOL09-0l FS_SP Table 3_
I lm2 AF
, 1.00E+ol 1.40E+ol. 9.l0E+oo 1.80E+o4 9.60E+o2 LTP Table ~
IDGCl,Mc J 3.SOE-f-01 ii1E+o2 9.lOE+ol: 1.13E+o5 1.44E+o3 DCGlw*Ao= -
- DGCl,McScaled 3.S8E+ol l.04E+o2, 8.S8E+ol l.07E+o5 1.35E+o3 DCGlw Scaled *AF
~
I
,, - - - I 1sum of Fractions Calculation relative to DC~
2.31E+oo I
Used Scaled DCGLs to take credit from dose from CSMWall. Used I
eq 5-7from LTP, did not adjustfor SU Cs-137 and Eu-152 as these Unity EMC Calculation relative to DCGl,McScaled 3.14E-01 were not detected in any FSS samples r
l I
cc....... -&>
DCGi., + (-Fartor){DCGtw) < 1 Equation 5-7
NE Caisson Dewatering Well Assessment
==
Conclusion:==
NX-503 Rev. 0 Page 10 of 10 The residual contamination in the gravel pack around the well casing exceeds the DCGLw, however, it is 31% of the DCGLEMc and is acceptable to remain in the gravel pack without further remediation effort.
Documents affected by the Calculation:
This calculation may be included or referenced by the Final Status Survey documentation for area NOL0l-09 as required to support License Termination.
References:
Ludlum Model 44-157 & 44-159 & 44-159-1 & 44-162 Gamma Pipe Monitors, September 2016.
(Vendor Manual - Ludlum Measurements Inc.
http://ludlums.com/images/product manuals/M44-157%20&%2044-159%20&%2044-159-1%2Q&%2044-162.pdf)
MicroShield User's Manual, Grove Software, Inc. 1992-2011, GroveSoftwareRadiationSoftware.com.
Appendices:
Appendix 1-MicroShield Case 1 and Case 2 Appendix 2 - Excel Spreadsheets for data analysis.
Appendix 3 - HBPP Laboratory Results Appendix 4 - GEL Lab Results Appendix 5 - Detector Calibration Documentation Appendix 6 - Well logs
Appendix 1-MicroShield Case 1 and Case 2 MicroShield Case 1: Cs-137 dominant source term (Sample 2018-0373)
MicroShield 9.05 Pacific Gas and Electric Co. (9.05-0000)
Date Filename Caisson well 1.msd B
Run Date February 8, 2018 Project Info Caisson Well 1 Checked Run Time 10:50:59 AM Case Title Descr* fon Georne ry 14 inch casing 23 feet dee_p based on am le 2018-0373 11 - Annular yl.inder - Internal Dose Point Source Dimensions leight I Radiu 121.92 cm (4 ft 15.748 cm (6.2 in)
~ 905 cm (0.8 in) 20.32 cm (8.0 in)
Dose Points Inner Source I;= ____ _
A X
- 1 0.0 cm O in)
Shield N CyL Radius Shield 1 Source z
y 60.96 cm (2 ft Shields 0.0 cm 0 iri)
Dimension Material 6.2 in Air
.75 in Carbon 1.4 2.64e+04 in3 Concrete 1.8' X
NX-503 Rev.a Page 1 of 4.
Duration 00:00:00
Nuclide Ba-137m Co-60 Cs-137 Eu-152 Appendix 1-MicroShield Case 1 and Case 2 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library: Grove Ci Btl flCilcn13 6.8837e~005 2.54 70e+006 l.5900e-004 l.013 le-006 3.7484e+004 2.3400e-006 NX-503 Rev. 0 Page 2 of 4 Bq/crnl 5.8830e+OOO 8.6580e-002
+---
7.2734e-005 2.691 le+006 l.6800e-004 6.2160e+OOO 5.6282e-007 2.0824e+004 1.3000e-006 4.81 OOe-002 Buildup: The material reference is Source Integration Parameters Radial 10 Circumferential 10 20 Fluence 1 Her
- Activity Rate (MeV) (Photon l ec MeV/cm1/ ec
- No Buildup 0.03 1.500e+05 '
2.128e-03 0.04 4.772e+04 2.096e-03 0.05 3.081e+03 2.786e-04 0.1 5.921e+03 2.537e-03 0.2 1.560e+03 1.986e-03 0.3 5.631e+03 1.314e-02 0.4 1.309e+03 4.702e-03 0.5 5.905e-04 0.6 1.517e+Ol 0.8 3.708e+03 1.0 1.5 Totals Y Direction (axial)
Results Fluence E po ur E po ure Rate Rate Rate
.eV/cm2/sec mR/hr mR/hr With No With Buildup Buildup bsorb bsorbed Dose Dose Dose Dose Rate Rate Rate Rate mrad/hr mrad/hr mGy/hr mGy/hr No With
- No With B,uildup Buildup Buildup Buildup Buildup 2.720e-03 3.336e-03 5.597e-04 2.109e-05 2.696e-05 1.841e-05 2.353e-05 1.841e-07 2.353e-07 9.268e-06].476e--05 8.091e-06 1.288e-05 S.09k-081i.288e-07 7.421e-07 l.491e-06 6.479e-07 1.302e-06 *6.479 -o9h.302e-08 9.520e-03 3.881e-06 1.456c-.05 3.388e-06 1.271e-05 3.388e-08 1.27le-07 7.567e-03 3.505e-06 1.335ea05 3.060e-06 1.166 -05 3.060e-08 1.166e-07 2.493e-05 8.371e-05 2.176e-05 7-308e-05 2.176e-07 7.308e-07 9.161e-06 2.75 le-05 7.998e-06 2.402e-05 7.998 -08 2.402 -07 1.620e-03 1.159e-063.1 79c-06 1.0l2c-06 2.775 -06 1.012, -08 2.775e-08 3.847e+Ol 2.961c-02 7.509e-02 2.585 -02 6.555 -02 2.585-e-04 6.555e-04 7.200e-05 1.624e-04 6.286e-05 1.417e-04 6.286e-07 1.417e-06 1.222e-O 2.529e-03 1.067e-03 2.208e-03 1.067e-05 2.208e-05 1.981e+OO 1.862e-03.333e--03 1.626e-03 2.910c-03 1.626e-05 2.910e-05 4.199e+0l 3.284e--02 8.130e--02 2.867e--02 7.097,c-02 2.867e-04 7.097e-04
Appendix 1-MicroShield Case 1 and Case 2
- MicroShield Case 2: Eu-152 dominant source term (Sample 2018-0370)
MicroShield 9.05 Pacific Gas and Electric Co. (9.05-0000)
Date Filename Caisson well l.msd B
Run Date Februar 8, 2018 Project Info Caisson Well 1 Checked Run Time 1:03:54 PM 14 inch casing 23 feet deep based on ampl:e 2018-0370 NX-503 Rev.a Page 3 of 4 Duration 00:00:00 Case Title Descri tion Geometry 11 - Annular ylinder - Internal Dose Point
~=.a..,<-
=--""'~
=
...... --~...JI!
Source. Dimensions Hei t 121.92 cm 4 ft Inner C 1 Radius Inner Cyl Thickness 1.905 cm Source 20.32 cm Dose Points A
X y
z
- 1 0.0 cm (0 in) 60.96 cm (2 ft) 0.0 cm O in)
Shield Shield N Dimension Material Density yl. Radius 6.2 in Air 0.00122 Z*
Shield 1
.75 in Carbon 1.4 Source 2.64e+04 in3 Concrete 1.8
NX-503 Rev. O Page 4 of 4 Appendix 1-MicroShield Case 1 and Case 2
~-------~---=-=----
--~--!'!!!!!!!!!!!=-!!!!!!l!!!!!!!!!!!!!'!!!!!!!!!!!!!!!ll Nuclide Ba-137m Co-60 Cs-137 Eu-152 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library: Grove Ci Bq 11Ci/cm3 1.5196e-005 5.6226e+005 3.51 OOe-005 1.1689e-006 4.3251e+004
- 2. 7000e-006 l.6062e-005 5.9429e+005 3.7100e-005
- 2. 7059e-005 1.0012e+006 6.2500e-005 Buildup: The material reference is Source Integration Parameters Radial Circumferential Y Direction (a ial)
Results Bq/cn.t!
l.2987e+OOO 9.9900e-002 1.3727e+OOO 2.3 l 25e+OOO 10 10 20 Fluence Expo~ ur Ex:posm*
bsorb<..-d Absorbed Absorbed Absorbed Fluence Dose Dose Dose Dose
- Ener Activity Rate Rate Rate Rate eV/cm~/ ec mR/hr mR/hr Rate Rate Rate Rate (MeV) (Photon l ec) eV/cm2/ ec No Buildup With No With mrad/hr mrad/hr mGy/hr mGy/hr No With No With Buildup Buildup Buildup Build,~ Buildup Buildu Buildup 0.03 3.312e+04 4.697e-04 4.655e-065.951e-O 4.064e-06 5.195e-06.06 e-08 5.195e-08 0.04 6.002e+05 2.636e-02 1.166e-04 1.856e-04 1.0lSe-04 1.620e-04 1.018e-06 l.620c-06 0.05 1.481e+05 1.339e-02 2.691e-02 3.568e-057.168 -05 3. 115 -05 6.258 -05 3. 115 -07 6.258e-07 0.1 2.847e+05 1.220e-01 4.577e-01 1.866c-04 7.002 -04 l.629c-04 6. 113 -04 l.629e-06 6. l 13t:-06 0.2 7.502e+04 9.548e-02 3.638e-01 1.685e-04 6.420e-O 1.471e-04 5.60 e-04 1.471e-06 5.605e-06 0.3 2.707e+05 6.318e-Ol 1.198e-034.025e-OJ 1.046e-03 3.513e-03 1.046e-05 3.5 13e-05 0.4 6.291e+04 4.404e-04 1.323e-03 3.845e-04 1.155e-O 3.845c-06 1.155c-05 0.5 5.647e+03 2.839e-02 7.786e-02 5.573e-05 l.528e-04 4.865 -05 1.334 -04 4.865e-07 L 34e-06 0.6 5.484e+05 3.629e+OO 9.201e+OO 7.082e-03 l.796e-02 6.18"e-03 1.*568e-02 6.183e-05 L568e-04 0.8 1.0 1.5 2.755e+05 Totals 2.954e+06 1.820e+OO 4.104e+OO
.462e-O 7.806e-03 3.022e-O 6.815e-03.022e-05 6.815e-05 6.738e+OO 1.395e+Ol 7.206e+OO t 1.290e+Ol 2.054e+0l 4.392e+0l I.242e-02.571e-02 1.084e-02 2.245e-02 l.084e-04 2.245e-04 1.212~-022.l 70c-02 l.058e-02 l.894e-02 1.058 -04 1.894t:-04
NX-503 Rev. 0 Page 1 of4 Appendix 2 -Excel Sheet for Data Analysis Survey Data Evaluation and Smoothing i
L 12 13 1413R 15 16 17 18 19 20 21 22 23 24 25 26 211 281 29i
- ,~
35 1-36:
371 381 391 49l 41I 421 43140R 44!
45'
... I 4_6; 47:
481 49 NE Dewatering Well Gross Gamma Results 12 43137 1004 13 43137 1005 43137 1007 14 431371 1008 15 431371. 1009 J 16 431371 1010 17 431371 1012 '
18 431371 1013 191 -431371 - 1014 :
2cii 43137]
1015 I
211 43137 1
1017 ii1. - 43137 1018 23 43137 1019 24 43137 1021 25 43137 1022
~!} :--t~t;t ~~: ~
281 43137 1026 29t 43137 1027 30]
- 431371. 1028 31 431371.. 1030 43_13
__ 7~ _].~~; __
32 431371 1032 33 43137' 1033 1--
34 !
431371 1035 35!.
431~7T. 1036 I
36; 43131: 1031 I 371 431371 1039 I 38i 43137]
1040 f 391 43137i 1042
~ 431371 1043
-=r 43137)
- 1044 41 43137:
1046 42 43137\\
1047 43:
43137 ! 1048 44; 43137] 1050 451 43137 1051 461 43137i 1052 gcpm ncpm Elevatio~
221731 13671
-22.5 22863_
14361
-22 22158 13656
~
20556 12054
~
19627 11125 -~
20430 11928
~
21129 12627
-19.51 22285 13783
-19 22552 22672 22691 1AVG 22848; 22769.51 2301(
22908'AVG 23131' 23019.5 226951 22779 2311 23750 23901 22988 23286 23762 25142 27031 27735 28466 29156 28220.
2?27-9: __
26692 25065.
233ss1AvG 23629 23493.5 22324 21601I 21314r-2os16 20423 19421 1s1i4r 18579 20636\\AVG 20684 20660 20478 17554' 13863 11618 10010:
8561*
- 14050, 14170
-18.5
-18
~; ::;;1 141931-142771 14598 15248 15399 14486 147841 15260 16640' 18529 19233 19964 20654 19718 1Bm 18190 16563 14991.5 13822 13105 12872 12314 11921 10919 10212 10077 12158 11976 9052 5361 3116 1508 59
-161
--15.51.
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-141
-13.5
-13
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-12
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- 9:5J
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-8.5
-8
-7.5
-7
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-4
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-2
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atio~ ~
smoothe~smoothed2.smoothed 59 o,
i 1508
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.1561; -
}ll~j _
-lr 3328.333i" 3819.2; r
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- 5202.6" 6i75.714:
90521
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-2.s r 11062r 9724.8"8850.2sii1 1215~;_
-3r 11403.67r 10695~
9965~
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11068.4" 10902.l*i° 102121
.. -:4r 10402.67r - iiiisi4" 11368.14 109191
-4~sriio11.33r 11oss.Gr 11496.14 11921!
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-5.5:
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-8.5~_1?843.33~. 1!~7:9~ 17~30.79-1 18m:
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~1or 20112r 19669.2""
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- 19004;1857i.14
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-121 16809.671 16889.2, 16985.14
-12.5i" 15561.33" 15939.8,..
16333 19964: '*
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- 16640,
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-13r 14843.33r-* -15313.8" 15763-.71 144861
. -13.5r 14889.67:"
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-14r i504,i°33r - - 14903r i.is&i:s1, 15248 145981 14277' 14193:
14517.5_,
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54 13656 14361 13671 r
-14.5 15081.67, 14801.6: 14712.141
_ -~i:
1470!.67: ~ ~1~_?43:~ 1~74.0~j
-15.51 14356 14566.7 14677.36:
-16.,.-1432!i17." ___ 14418.9" 14515.711
-16.5(.14406.5"- 1435:z."s" 14361. 1i'.
-~i,i ~4431.3_~r 14331.4 14283.43i
-17.5: 14315.51 14302.8 14212.86
.,~1: ;.i: _~_,l =~1
-19.51 1:_2779.33:
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-201 1189~.33!
12303:4' 12746.1:_~,,
-20.S 11702.33!
12278' 12790.57
-211 1227~.3~j_ __ 12624.8; 12774.57,
-21.5 13357!
12973.4:
-22 138961 I
-22.5!
I i
r
Appendix 2-Excel Sheet for Data Analysis Survey Data Graphic Representation:
ncpm NX-503 Rev. 0
- Page 2 of 4 smoothed smoothed2 smoothed3
Appendix 2-Excel Sheet for Data Analysis Comparison of Well Sediment Sample Data with DCGLw and DCGLeMc
'S8fflpll!
Date/Tirne 211iis 1535 ""$1m
_ p1.,..---'-,,--'--'-----,,,,_,-,-_...,,__,...,......,,....,.__,.._
Residual Source term Volume Calculations E_epth of Cylinde.!._ -j 4ft
~Thld:l)ess'_~_PeaGrav.
s11n
~~~l~!t!_f (ODJ 14;in Density of Pea Gravel L~g/~3 vOfoffle-of mate rt al I
'modeled in Column lndudingthe casing 10.6l1t3
- t Lab Sample#
2018-0370 OGCt.,
OGCt.,Scaled 1m2AF
~~~
DGC4MCSaled 9.l0E<OO LBOE<04i 9.60E+02l11P Tol>\\o 5-~
9.10E+ol L13E-+OS1 1.44E+o3 OCGL.w*AF 8.SSE+ol L07 LJSE-t03 DCGl.w Scaled *AF um <>Hr loni lruhrtlon el,1i,e 10-()((;l,....i_e_d _ _._7_.85_ E+OO NX-503 Rev.O Page 3 of 4 Volume of material modeled In casing I
I 4.~!ft3 Unity EMCcalwlatlon re~!ive to OCGL,i~~I~~
Used Scaled DCGL.s to take aedlt from dose from CSM Wall. Used eq 5-7from LTP, did not adjust for SU Cs-137 and Eu-152 as these 8.3SE-01 were not detected In any FSS samples Net Volume of material modeled in Gravel 6.3 ft3
'Net v-olu;e of material modeled-In oc:.. +,..,;.~-:;;;-:... )<1 Eq-5-7 Gr.avel
. 1. 78E+05, an3
~t-M;ss of mattrtat Pea Gravel LME+Ol uCI Comparison of Calculated Data in Gravel Pack with DCGLw and DCGLEMC
. ~~Im.at: l1 resid~al~~;ce te~ left be~~nd and !
partson t~ th! OCGu I
L j
I
________.. __ Results_pC/1
~:~~~-~-r~~ not adjusted FSS Average Resulh fc,rNQL--Or-1-09=---+----l sa*m-p1e 1
\\
~
Date/Tlme I 1Lab Sample#
Co-60 Cs-137 Eu-152 C-14 Sr-90 Co-60 1 Cs-137
!~~~2 C-14 2/l./'J!,_'1535 Sampl~_of*s~dimentO?mp~itedfrom,sedim_ent_d~waterins;box liu~asured 3.00E-01 4.00E+OO 6.60E+OO iiiE+oo 6.
°'
0.275.....,-
ND ND
!_22E~
Residual Source term Volume Calrulatlons I
OGClw 3.SOE+oo-7.90E+oo-LOOE-+Olf
- 6.30E+oo ble 5- ---7 t----+------1
~°!~th ~ -Cylinder 4 ft
'DGCt.,Scaled 3.SBE+O(J ~<00 9.43E<OO,
.Plablei Thickness of PeaGravt 8 In i1m2AF LOOE+Ql L40E-+01 9.l0E+oo-Caslngdiameter(OD)l 14J1n 1
DGC4""
3.BOE+Ol L11E_+02[ 9010E+01! ---+---
0 Oensityof PeaGravel,
1.s'l 1
g/on3
'.OGClt:McScaled 3.SSE-+031 L04E-+Oaj__ 8.SSE-+011 3 OCGLwScaled "'AF Volllmeof !
I material modeled In material I modeled in Casing I
,volume of j
- material modeled in )
'Net Volume of
~~!~~.al Net Mass of material Totill Activity i
10.6ilt3
_ 4.3jlt3 I
d1t3 L78Et05 on3 3.20Et05 8 4.71E<OO uCI Unity EMC calculation relative to OCGLu,w:Scaled 231E+OO OCGLsto take credit 3.14E-01 from dose 5
(t'om..,.-&)
DCaz., + (A,waTanor){OC'._) < 1 Equation 5-7
Appendix 2 -Excel Sheet for Data Analysis Overhead View of NE Well Casing NX-503 Rev.a Page 4 of 4
Appendix 1-MicroShield Case 1 and Case 2 MicroShield Case 1: Cs-137 dominant source term {Sample* 2018-0373)
MicroShield 9.05 Pacific Gas and Electric Co. (9.05-0000)
Date Filename Caisson well 1.msd By Run Date
!ebruary !,"'~018 Project Info Caisson Well 1 Checked Run Time 10:50:59 AM Case Title Description Geom try 14 inch ca ing 23 feet deep based on sampl 2018-0373 A
- 1 11 - Annular y inder - Internal Dose Point Source Dimensions He*ght Inner C 1 Radius Inner yl Thickness Source 121.92 cm (4 ft) 15.748 cm (6.2 in) 1.905 cm 0.8 in 20.32 cm (8.0 in)
Dose Points X
y z
0.0 cm O in) 60.96 cm (2 ft) 0.0 cm (0 in)
Shields Shield N Dimension Material Density I. Radius 6.2 in Air 0.00122 Shield 1
.75 in Carbon 1.4 Source 2.64e+04 in3 Concrete 1.8 z
X NX-503 Rev. 0 Page 1 of 4 Duration 00:00:00
Nuclide Ba-137m Co-60 Cs-137 Eu-152 EDCflO' Activity (MeV) (Photon./ ec) 0.03 1.500e+05 0.04 4.772e+04 0.05 3.081e+03 0.1 5.921e+03 0.2 1.560e+03 0.3 5.631e+03 0.4 1.309e+03 0.5 1 :175e+02 0.6 2.293e+06 0.8 3.708e+03 1.0 4.639e+04 1.5 4.231e+04 Totals 2.600e+06 NX-503 Rev. 0 Page 2 of4 Appendix 1-MicroShield Case 1 and Case 2 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Ci 6.8837e-005 1.0131e-006 7.2734e-005 5.6282e-007 Lower Energy Cutoff: 0.015 Photons< 0.015: Excluded Library: Grove Bq
.. _11Cif ~
3 2.54 70e+006 1.5900e-004
- 3. 7 484e+004 2.3400e-006 2.691 le+006 l.6800e-004 2.0824e+004 1.3000e-006 Bq/cm3 5.8830e+OOO 8.6580e-002 6.2 l 60e+OOO 4.8100e-002 Buildup: The material reference is Source Integration Parameters Fluence Rate
.eV/cm2/ ec No Buildup 2.128e-03 2.096e-03 2.786e-04 2.537e-03 1.986e-03 1.314e-02 4.702e-03 5.905e-04 l.517e+Ol 3.786e-02 6.629e-01 1.107e+OO 1.700e+0l Radial 10 10 20 Circumferential Y Directio!J: (axial)
Results Fluence E pour b:orbed Ab orbed b orb d b *orbed po,u Dose Dose Dose Dose Rate Rate Rate Rate Rate Rate Rate MeV/cmi/
mR/hr mR/hr C
mrad/hr mrad/hr mGy/hr mGy/hr With No With Buildup Buildup Buildup No With No With
_l!uildup Buildup Buildup Buildu 2.720e-03 2.109e-052.696e-OS l.841e-05 2. 5 -05 l.841c-07 2.353e-07 3.336e-03 9.268e-06 1.476e-05 8.091e-06 1.288e-05 8.091e-08 1.28Re-07 5.597e-04 7.421e-07 l.491e-06 6.479 -07 l.302e-06 6.479e-09 1. 02e-08 9.520e-03
.,.881 -06 1.456e-05 3.388e-06 1.271 -05 3.388e-08 l.271e-07 7.567e-03 3.so*e-06 1."3 e-05.060c-06 1.166e-05 3.060e-08 1.166 -07 4.413e-02 2.49..,e-05 8.... 71 e 05 2. 176e-05 7.308e-05 2.176e-07 7.308 -07 l.412e-02 9.161 e-06 2.751e-05 7.9 8e-06 2.402e-O 7.998 -08 2.402e-07 l.620e"-03 1.1 %-06.179 *-06 1.012e~06 2.775e~b6 1.012e-08 2.775c-0"8 3.847e+Ol 2.. 961e-02 7.509e-02 2.585 -02 6.555e-02 2.585e-04 6.555e-04 8.537e-02 7.200 -05 1.624e-04 6.286 -05 1.417e-04 6.286e-07 1.417e-06 1.372e+OO l._22c-03 2.529e-O l.067e-03l2.208e-03 l.067e-05 2.208e~05 1.981e+OO 1.862e-03 3.333c-03 l.626e-03 2.91 Oe-03 l.626e-05 2.910e-05 4.199e+0l 3.284e-02 8.l30e~02 2.867e-O2 7.097 -02 2.867c~O4 7.O97e-04
Appendix 1-MicroShield Case 1 and Case 2 MicroShield Case 2: Eu-152 dominant source term (Sample 2018-0370)
MicroShield 9.05 Pacific Gas and Electric Co. (9.05-0000)
Date Filename Caisson well l.msd B
Run Date February 8, ?.,Q.~
Pt*oject Info Caisson Well 1 Checked Run Time 1:03:54 PM Case Title D
ription Geometry 14 inch asing 23 feet deep based on ample 2018-0370 11 - Annular ylinder - Internal Dose Point Source Dimensions Height Inner C I Radius Inner yl Thickness Source 121.92 cm (4 ft) 15.748 cm 6.2 in 1.905 cm (0.8 in) 20.32 cm (8.0 in)
A X
- 1 0.0 cm (0 in Shield N yl. Radius Shield 1 Source Dose Points y
z 60.96 cm (2 ft)
~:0 c~ (0 ti!}
Shields Dimension 6.2 in
.75 in Material Density Air 0.00122 Carbon 1.4 2.64e+04 in3 Concrete 1.8 z
NX-503 Rev. 0 Page 3 of 4 Duration 00:00:00
Nuclide Ba-137m Co-60 Cs-137 Eu-152 Appendix 1-MicroShield Case 1 and Case 2 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons< 0.015: Excluded Library: Grove Ci Bq JtCi/cm l.5 l 96e-005
. 5.6226e+005 3.5 lOOe-005 1.1689e-006 4.3251e+004
- 2. 7000e-006 1.6062e-005 5.9429e+005 3.7100e-005
- 2. 7059e-005 1.0012e+006 6.2500e-005 Buildup: The material reference is Source Integration Parameters Radial Circumferential Y Direction (a ial)
Results NX-503 Rev. 0 Page4 of4 Bq/cm3 1.2987e+OOO 9.9900e-002 1.3727e+OOO 2.3125e+OOO 10 10 20 Absorbed Absorbed bs.orbcd Ab orb d Fluence Pffi ure xpo ure Dose Dose Dose Dose i nergy' Activity Rate Fluence Rate :~r mR;J:r Rate Rate Rate Rate (MeV) (Photon / c MeV/cm2/.
No With mrad/hr mrad/hr mGy/hr mGy/hr 0.03 3.312e+04 0.04 6.002e+05 0.05 1.481e+05 0.1 2.847e+05 0.2 7.502e+04 0.3 2.707e+05 0.4 6.29fo+04 0.5 5.647e+03 0.6
- 5.484e+OS.
0.8 1.783e+05 1.0 4.716e+05 1.5 2.755e+05 Totals 2.954e+06 No Buildup 4.697e-04 Buildup 6.004e-04 No With No With Buildup Buildup Buildu Buildup HuiJdup Buildup 4.. 65~ -06 5.951 -064.064 -06 5.19:5e-06 4.064e-08 -.19 e-08 2.636e-02 4.196e-02 1.166 -04 l.856e-04 1.018 -04 1.620 -04 1.018e-06 1.620e-06 1.339e-02 2.691e-02 3.568e-05 7.168e-05 3.115e-05 6.258e-05 3.1 lSe-07 6.258e-07 1.220e-01 4.577e-01 l.866e-04 7.002e-04 1.,629-e-04 6. 113e-04 l.629e-06 6.l 13e-06 9.548e-02 3.638e-01 1.685 -046.420.. 04 1.471,e-04 5.605e-04 1.471e-06 5.. 605e-06 6.318e-01 2.122e+OO 1.198e-034.025e-03 1.046e-03 '.'.513e-03 1.046e-05 3.513e-05 2.26le-01 6.788e-01 4.404e-04 l.323 -03 3.845 -04 l.155e-03 3.845e-06 1.155.-OS 2.839e-02 7.786e-02 S.573c-05 1.528e-04 4.865e-05 1. 34e-04 4.865e-07 1 3"4e-06 3.629e-l"00 9.20le+OO
- 7.082e-O 1.7%e-02 6_183e-03 1.568e-02 6.183e-05 1.568~04 1.820e+OO G
.104e+OO 3.462e9 03 7.806e-O'"' '.'.022e-03 6.. 815e-03 3.022e-05 6.8 15e-05
- 6. 738e+00 1.3 95e+0 I li.242e-02 2.5 71 e-02 I. 084e--02 2.245e-02 l.084e-04 2.24 5 -04 7.206e+OO l.290e+Ol li.212e-022. 170e-02 l.058e-02 1.894 -02 1.058 -04 1.894e-04 2.054e+Ol 4.392e+Ol 3.730c-02 8.029e§02 3,.256c 02 7.009c~02 3.256c-04 7.009e-04
NX-503 Rev. 0 Page 1 of 3 Appendix 2-Excel Sheet for Data Analysis Survey Data Evaluation and Smoothing Backgrour 8502 cpm NE Dewatering Well Gross Gamma Results ncpnt.:),ation ~
smoothed smoothed2 smoothed Total Length of pipe 22.5 ft 59 0
Datalogge Measuren Date Time gcpm ncpm Elevation 1508
-o.5" 1561 0
1 43137 945 22173 13671
-22.5 3116
-1' 3328. 333 *,
3819.2 1
2 43137 947 22863 14361
-22 5361
-1.5" 5843' 6202.6" 6175.714 2
3 43137 948 22158 13656
-21.5 9052
-2,8796.333:
8332.6r 7606.857 3
4 43137 950 20556 12054
-21 11976
-2.5; 11062 9724.8' 8850.286 4
5 43137 951 19627 11125
-20.5 12158
-3r 11403.67' 10695" 9965 5
6 43137 952 20430 11928
-20 10077 r
11068.4; 10902.14
-3.51 10815.67 6
7 43137 954 21129 12627
-19.5 10212
-4r 10402.61' 11057.4' 11368.14 7
8 43137 955 22285 13783
-19 10919
-4.5?' 11017.33' 11088.6" 11496.14 8
9 43137 956 22552 14050
-18.5 11921
-5"'
11718" 11647.6"' 11631.43 9
10 43137 959 22672 14170
-18 12314
-5.5"'
12369' 12226.2" 12166.43 10 11 43137 1001 22691 AVG 14267.5
-17.5 12872
-6'r 12763.67,,.
12806.8" 12849.21 11 llR 43137 1003 22848 22769.5 13105
-6.5,, 13266.33..
13420.9"' 13655.5 12 12 43137 1004 23011 14509
-17 13822
-7' 13972.83" 14210.1r 14551.01 13 13 43137 1005 22908 AVG 14517.5
-16.5 14991.5
-7.5r 15125.5' 15334_3t 15474.36 1413R 43137 1007 23131 23019.5 16563
-8"' 16581.5" 16468.7r 16452.36 15 14 43137 1008 22695 14193
-16 18190
-8.5~ 17843.33!"
11641.9r 11530.79 16 15 43137 1009 22779 14277
-15.5 18777 4'
18895' 18780.4" 18408.21 17 16 43137 1010 23100 14598
-15 19718
-9.5:r 19716.33, 19460.6!" 19014.14 18 17 43137 1012 23750 15248
-14.5 20654
-10~
20112" 19669.2'."
19295 19 18 43137 1013 23901 15399
-14 19964
-10.5.,. 19950.33' 19619.6" 19073.57 20 19 43137 1014 22988 14486
-13.5 19233
-11!"
19242" 19004!" 18571.14 21 20 43137 1015 23286 14784
-13 18529
-11.57 18134" 17925.2" 17866.29 22 21 43137 1017 23762 15260
-12.5 16640
-12,-16809.67' 16889.2" 16985.14 23 22 43137 1018 25142 16640
-12 15260
-12.5r 15561.33' 15939.8" 16333 24 23 43137 1019 27031 18529
-11.5 14784
_131" 14843.33' 15313.8' 15763. 71 25 24 43137 1021 27735 19233
-11 14486
-13.5~ 14889.67" 15035.4" 15202.14 26 25 43137 1022 28466 19964
-10.5 15399
-14!" 15044.33' 14903' 14864.57 27 26 43137 1023 29156 20654
-10 15248
-14.5~ 15081.67"'
14801.6,.14712.14 28 27 43137 1025 28220 19718
-9.5 14598
-15"' 14707.67" 14743"' 14674.07 29 28 43137 1026 27279 18777
-9 14277
-15.5*
14356' 14566.l' 14677.36 30 29 43137 1027 26692 18190
-8.5 14193
-16"' 14329.17" 14418.9" 14515. 71 31 30 43137 1028 25065 16563
-8 14517.5
-16.5" 14406.5" 14352.8" 14361. 71 32 31 43137 1030 23358 AVG 14991.5
-7.5 14509
-17 14431.33 14331.4 14283.43 33 31R 43137 1031 23629 23493.5 14267.5
-17.5 14315.5 14302.8 14212.86 34 32 43137 1032 22324 13822
-7 14170
-18 14162.5 14155.9 13989.14 35 33 43137 1033 21607 13105
-6.5 14050
-18.5 14001 13779.5 13619.21 36 34 43137 1035 21374 12872
-6 13783
-19 13486.67 13311.6 13135.79 37 35 43137 1036 20816 12314
-5.5 12627
-19.5 12779.33 12702.6 12819.57 38 36 43137 1037 20423 11921
-5*
11928
-20 11893.33 12303.4 12746.14 39 37 43137 1039 19421 10919
-4.5 11125
-20.5 11702.33 12278 12790.57 40 38 43137 1040 18714 10212
-4 12054
-21 12278.33 12624.8 12774.57 41 39 43137 1042 18579 10077
-3.5 13656
-21.5 13357 12973.4 42 40 43137 1043 20636 AVG 12158
-3 14361
-22 13896 43 40R 43137 1044 20684 20660 13671
-22.5 44 41 43137 1046 20478 11976
-2.5 45
- 42 43137 - 1047 1"/554 9052. -2 46 43 43137 1048 13863 5361
-1.5 47 44 43137 1050 11618 3116
-1 48 45 43137 1051 10010 1508
-0.5 49 46 43137 1052 8561 59 0
Appendix 2 -Excel Sheet for Data Analysis Survey Data Graphic Representation:
ncpm NX-503 Rev. 0 Page 2 of 3 smoothed smoothed2 smoothed3
NX-503 Rev. 0 Page 3 of 3 Appendix 2 -Excel Sheet for Data Analysis Comparison of Well Sediment Sample Data with DCGLw and DCGLEMC Estimate of residual source term left behind and comparison to the DCGLs Sample Dateflime lab Sample II Co-60 Results pCi/g Cs-137 Eu-152 C-14 FSS Average Results for NOL-01-fJJ Sr-90 Co-60 Cs-137 Eu-152 C-14 Sr-90 2/'l/'JB 1535 Sample of sediment composited from sediment dewatering box Residual Source term Volume Calculations 2018-0370 L53E+oo 2.06E+Ol 3.47E+01 3.18E+<X)" 6.3SE-01" 0.275 "
ND ND 4.22E-02' 1.61E-01' Depth of Cylinder 4 ft Thickness of Pea GravE 8 in Casing diameter {OD) 14 in Density of Pea Gravel 1.8 g/cm3 Volume of material modeled in Column indudin1 the casing 10.6 ft]
Volume of material modeled in Casing 4.3 ft3 Net Volume of material modeled in Gravel 6.3 ft]
Net Volume of material modeled in Gravel L 78E+05 an3 Net Mass of material modeled in Gravel 3.20E+05 g Total Activity ll!ft in Pea Gravel l.94E-t01 uCi DGClw 3.llOE+oo 7.90E+oo l.OOE+Ol 6.30E+oo LSOE+oo LTPTable S-1 DGClwScaled 3.58E+oo 7.45E+oo 9.43E+oo 5.94E+oo lm 2 AF l.OOE+Ol l.4CE+Ol 9.lOE+oo l.ll0E-t04 DGC4wc 3.llOE+Ol l.llE-!02 9.lOE+Ol l.13E+05 DGC41ri1cScaled 3.58E+Ol l.04E-t02 8.58E+Ol UJ7E+05 Sum of Fractions Calculation relative to DCGLwScaled Unity EMC calculation relative to DCG4McScaled l.41E+<D NOLO!l-01 FSSP Table 3 9.60E-t02 LTP Table S-6 l.44E+03 DCGlw'AF l.35E+03 DCGlw Scaled 'AF 7.SSE+oo Used Scaled DCGLs to take aedit from dose from CSM Wall. Used eq 5-7 from LTP, did not adjust for SU Cs-137 and Eu-152 as these IL.35E-Gl were not detected in any FSS samples 8
\\ConcAvt -&)
DCGLw + (Aria Factor)(DCGLw) < 1 Equation 5-7 Comparison of Calculated Data in Gravel Pack with DCGLw and DCGLEMC Estimate of residual source tenn left behind and comparison to the DCGl.5 Sample Oateflime 2/'l/'JB 1535 Sample of sediment composited from sediment dewatering box Residual Source tenn Volume Calculations Depth of Cylinder 4ft Thickness of Pea Graw 8 in Casing diameter (OD) 14 In Density of Pea Gravel 1.8 g/an3 Volume of material modeled In 10.6 ft3 material modeled in Casing 4.3 ft]
Volume of material modeled in 6.3 ft]
Net Volume of material 1.78E+OS anl Net Mass of material 3.20E+05 B Total Activity 4.nE+oo uCi Results pCi/g C-14&Sr-90 not adjusted FSS Average Results for NOL--01--09 UbSamplel Co-60 Cs-137 Eu-152 C-14 Sr-90 Co-60 Cs-137 Eu-152 As Measured 3.00E-01 4.00E+oo 6.60E+oo 3.IBE+oo' 6.35E-01' 0.275,
ND ND DGClw 3.llOE+oo 7.90E+oo LOOE+Ol 6.30E+oo LSOE+oo LTPTableS-1 DGClw Scaled 3.58E+oo 7.45E+oo 9.43E+oo 5.94E+oo lm 2 AF l.OOE+Ol L4CE+Ol 9.lOE+oo 1.ll0E-t04 DGCla.c 3.llOE+Ol U1E+02 9.lOE+Ol l.13E+05 DGC~1r,1cScaled 3.58E+Ol l.04E+02 8.58E+Ol l.07E+05 SUm of Fractions Calailation relative to DCGLwScaled Unity EMC Calculation relative to OCG~1r,1cScaled 1.41E+<D NOLO!l-01 FSSP Table 3 9.60E+02 LTP Tobie S-6.
l.44E+03 DCGlw'AF L35E+03 DCGlw Scaled 'AF 2.31E+<D DCGlsto take credit 3.1AE-Gl from dose ii
\\Co11.:-Au*-S)
<"l DCGL.,
(Ar*a Foacw)( DCGLw)
Equation 5-7 C-14 Sr-90 4.22E-02, L61E-01,
Appendix 3 - HBPP Lab Results NX-503 Rev. 0 Page 1 of 50
Appendix 3 - HBPP Lab Results GAMMA S P E C T R U M A N A L Y S I S Detector DET0S Report Generated On Sample Identification Sample Title Sample.Information 1/4/2018 5:07:51 PM Sample Type Sample Geometry Peak Locate Threshold Peak Locate Range (in channels)
Peak Area Range (in channels)
Identification Energy Tolerance Sample Size 2018-0044 Caisson NE Well #1 Soil 3.00 100 -
100 -
1.000 4096 4096 keV l.556E+003 g Sample A Sample Taken On Acquisition Started 1/4/2018 1/4/2018
.3:00:00 PM 4:08:15 PM Live Time Real Time Dead Time 800.0 seconds 807. o_. seconds 0.8? %
'Energy Calibration Used Done On Efficiency Calibration Used Done Qp _
Efficiency ID
?/29/2010
- 4/lS/2011 DS lL HD Performed by~ ~
~
Andrsori; Abrams, Burrell, Date
/-9'-/, f Eckhardt, Stephens, Stover Reviewed by O. -b,o,AD~
Date J.'l*.t8"1 (Print/Signature:IAlderman, Anderson)
Appendix 3 - HBPP Lab Results Peak Locate Analysis Report 1/4/2018 5:07:51 PM Page 2
PE AK LOCATE REPORT Detector Name:
DET05 Sample
Title:
Peak Peak Peak Peak Caisson NE Well #1 Locate Performed on:
Sample A 1/4/2018 100 4096 3.00 5:07:51 PM Peak No.
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 Locate From Channel:
Locate To Channel:
Search Sensitivity:
Centroid Channel 244.19 323.99 489.78 592.24 688.87 712~55 735.50 822.53 888.14.
977.82 1128,52
- 1172.73 1323.51 1357.61 1377.76 1438.82 1447.24 1557.99 1735.02 1928.43 2010.35 2172.25 2180.13 2224.71 2304.07 2347.40 2426.65 2468.09 2549.80 2599.54 2666~17 2817,38 2897.27 2916.13 2923.55 3060.97 Centroid Uncertainty 0.0826 0.2994 0.1180 0.3435 0.0819 0.3279 0.2664 0.1686 0.1554 0.3329 0,3073 0.3351 0.1044 0.3298 0.2412 0.3429 0,2711 0.1073 0.1547 0.1032 0.2240 0.1152 0.2121 0.1058 0.3382 0.1516 0.1993 0.3080 0.2044 0.1909 0.1487 0.0963 0.3085 0.3106 0.3309 0.2487 Energy (keV) 121.88 161.72 244.82 296.14 344.42 356.29 367.57 411.29 444.14 488.88 564.38 586.55 661.92 678.92 688.98 719.53 723.75 779.18 867.66 964.39 1005.17 1086.25 1090.11 1112.52 1152.20 1173.77 1213.43 1234.11 1274.99 1299.81 1333.09 1408.62 1448.35 1458.08 1461.23 1529.96
? = Adjacent peak noted Errors quoted at 2.000 sigma Peak Significance 88.22 5.52 38.23 3.71 72.76 4.20 6.10 15.76 19.27 4.43 5.08 4.22 35.01 4.60 7.22 3.55 5.24 36.84 17.60 33.46 6.66 27.58 10.32 32.56 3.63 15.16 8.71 3.88 8.42 8.10 15.26 35.51 3.33 4.39 3.38 4.78 NX-503 Rev. O Page 3 of 50
Appendix 3 - HBPP Lab Results Peak Analysis Report 1/4/2018' 5:07:51 PM Page 3
PE AK ANALYSIS REPORT Detector Name:
DET05 Sample
Title:
Caisson NE Well #1 Sample A Peak Analysis Performed on:
1/4/2018 5:07:51 PM Peak Analysis From Channel:
100 Peak Analysis To Channel; 4096 Peak ROI ROI Peak Energy No. start end centroid (keV)
F l
F 2
F 3
F 4
F 5
F 6
F 7
F 8
F 9
F 10 F
11 F
12 F
13 F
14 F
15 M 16 m 17 F
18 F
19 F
20 F
21 M 22 m 23 F
24 F
25 F
26 F
27 F
28 F
29 F
30 F
31 F
32 M 33 m 34 m 35 F
36 239-319-473-587-684-709-730-817-882-972-1122-1168-1317-1355-1372-1432-1432-1551-1728-1921-2003-2165-2165-2217-2300-2340-2419-2462-2544-2595-2658-2809-2889-2889-2889-3053-248 327 494 597 694 716 740
- 827 893 981 1134 1178 1329 1363 1381.
1451 1451 1564 1741 1935 2016 2187 2187 2231.
2311 2354 2433 2473 2557 2606 2673 2824 -
2927 2927 2927 3067 244.16 323.77 489.80 592.36 688.85 712.56 735.11 822.49 888.16 977.59 1128.51 1172.84 1323.52 1357.53 1377.63 1438.71 1447.16 1558.01 1734.96 1928.43 2010.01 2172.22 2179.95 2224.77 2304.16 2347.32 2426.69 2468.07 2549.88 2599.55 2666.15 2817.33 2896.86 2916.34 2922. 64 3060.23 121.88 161.72 244.82 296.14 344.42 356.29 367.57 411.29 444.14 488.88 564.38 586.55 661.92 678.92 688.98 719.53 723.75 779.18 867.66 964.39 1005.17 1086.25 1090.11 1112.52 1152.20 1173,77 1213.43 1234.11 1274.99 1299.81 1333.09 1408.62 1448.35 1458.08 1461.23 1529.96 M = First peak in a multiplet region m = Other peak in a _multiplet region F = Fitted single~
Errors quoted at 2.000 sigma FWHM Net Peak Net Area Continuum
{keV)
Area Uncert.
Counts 1.11 1.26 1.14 1.43 1.24 1.16 1.88 1.30 1.33 1.35 1.50 1.48 1.47 0.87 1.40 1.48 1.48 1.54 1.67 1.66 2.19 1.79 1.79
- l. 76 1.30 1.94 1.79 1.73 1.65 1.92 1.90 1.95 2.21 2.21 2.22 2.55 3.29E+004 5.33E+002 5.56E+003 2.94E+002 l.70E+004 l.71E+002 5.62E+002 1,19E+003 1.50E+003 l.72E+002 2.37E+002 1.84E+002 4.71E+003 1.22E+002 2.76E+002 l.00E+002 2.01E+002 4.24E+003 l.21E+003 3.96E+003 4.02E+002 2.84E+003 4.73E+002 3.52E+003 S.74E+001 9.86E+002 3.18E+002 7.83E+001 2.30E+002 3.48E+002 8.47E+002 4.59E+003 7.45E+001 9.64E+001 7.80E+001 l.50E+002 377.76 106.08 165.90 72.25 261.62 58.00
- 68. 9_4 84.05
- 90. 9'.6 52.92 52.59 51.54 140.35 45.01 51.97 41.68 50.01 132.44 78.01 126.36 48.34 106.57 50.26 118.14 30.94 66.11 41.19 26.24 33.93 38.93 58.05 130.73 18.14 21.15 19.29 23.19 6.19E+003 3,89E+003 5.88E+003 2.03E+003 l.54E+003 9.94E+002 l.27E+003 l.17E+003 l.29E+003 9.15E+002 l.01E+003 9.00E+002 9.49E+002 5.64E+002 6.43E+002 7.26E+002 7.46E+002 8.33E+002 7.93E+002 5.68E+002 4.18E+002 3.46E+002 3.14E+002 4.27E+002.
3.46E+002 3.50E+002 2.37E+002 l.62E+002 1.29E+002 9.07E+001 8.42E+001 3.02E+001 3.18E+001 2.90E+00l 2.50E+001 1.30E+001 NX-503 Rev. O Page 4 of 50
Appendix 3 - HBPP Lab Results Interference Corrected Activity Report 1/4/2018 5:07:51 PM Page 4
N U C L I D E I D E N T I F I C A T I O N REPORT Sample
Title:
Caisson NE Well #1 Sample A Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\HBPP Eu-3.NLB.
Nuclide Name
0.949 1173.22*
1332.49*
0.989 661.65*
0.965 121.78*@
244.69*@
295.93*@
329.35 344.27*
367.71*@
411.11* @
443.98*@
488.66*@
564.03*@
586.26*@
688.63*@
719.33*@
778.89*
810.43 867.32*@
919.31 926.25 964.01*
1085.78*@
1089.68*@
1112.02*@
1212.84*@
1249.80 1299.04*@
1407.95*
14.57. 54* @
1528.07 0.738 723.30*@
873.19 1004.76*@
1274.45*
Yield
(%)
10.67 100.00 100.00 85.12 28.40 7.49 0.43 0.13 26.50 0.86 2.21 0.30 0.41 0.48 0.45 0.84 0.26 12.74 0.31 4.16 0.40 0.25 14.40 10.00 1.68 13.30 1.38 0.18 1.61 20.70 0.49 0.26 19.70 11.50 17.90 35.50 Activity (pCi/g
)
2.85517E+OOO 3.23663E+OOO 3.07874E+OOO l.11893E+001 7.27036E+001 6.47661E+001 6.94839E+001 7.32926E+001 7.91146E+001 7.17256E+001 7.11693E+002 6.44153E+001 8.64819E+001 7.36776E+001 6.909778+001 8.21424E+001 7.76400E+001 7.45267E+001 7.69279E+001 8.748178+001 8.70968E+001 8.32064E+001 7.763758+001 7.70793E+001 8.41519E+001 7.70134E+001 2.23309E+OOO 6.49329E+OOO 2.27769E+OOO
- =Energy line found in the spectrum.
Activity Uncertainty 7.22529E-001 2.716248-001 2.67794E-001 7.055958-001 4.07962E+OOO 4.129098+000 1.743398+001 3.90130E+OOO
- 1. o52:osE+oo1
- 6. 324°67E+OOO 5.80813E+001 2.01536E+001 l.98160E+001 2.11207E+001 l.35449E+001 3.45103E+001 4.57985E+OOO 5.92540E+OOO 4.28283E+OOO 5.32399E+OOO l.01541E+001 4.91716E+OOO l.08331E+001 9.54139E+OOO S.12678E+OOO l.73973E+001 5.67783E-001 8.36634E-001 3.56249E-001
@=Energy line not used for Weighted Mean Activity Energy Tolerance:
1.000 keV Nuclide confidence index threshold=
0.30 Errors quoted at 2.000 sigma NX-503 Rev. 0 Page 5 of 50
Appendix 3 - HBPP Lab Results Interference Corrected Activity Report 1/4/2018 5:07:51 PM Page 5
INTERFERENCE CORR E *c TED REPORT
- ~************
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/g
)
Uncertainty K-40 0.972 2.855172E+000 7.225290E-001 Co-60 0.949 3.156564E+000 1.906986E-001 Cs-137 0.989 l.118927E+001 7.055949E-001 Eu-152
@ 0.965 7.726755E+001 2.203574E+000 Eu-154
@ 0.738 2.277693E+000 3.562492E-001
? = 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 UN I D E N T I F I E D PE AK S...... l...
F F
F F
F F
Peak No.
2 6
14 25 28 M 33 36 M =
m =
F =
Peak Locate Performed on:
1/4/2018 5:07:51 PM Peak Locate From Channel:
Peak Locate To Channel:
Energy Peak Size in (keV)
Counts per Second 161.72 6.6605E- 001 356. 29~
2.1421E-001 678.92 l.5261E-001 1152.20 7.1688E-002 1234.11 9.7884E-002 1448.35 9.. 3151E-002 1529.96
- 1. 8695E-001 First peak in a multiplet region Other peak in a multiplet region Fitted singlet 100 4096 Peak CPS
% Uncertainty 19.91 33.85 36.87 53.95 33.50 24.34 15.51 Peak
'fype Tol.
Nuclide S-.
1"i
'f e, f z.l,. F" IS.2._
.;,r.,4~22t
~IA. u-,.
.SI.\\M 1/12./t/O Eu.lS-2.
Sum 111z./1i.1-J:"IA..1.5"2...
Sum l'f o '11/ 'Io tE"-,.s.* 2.
Sum l'1ot/ IZ?.. J:U. 1,2.
Errors quoted at 2.000 sigma "This peak has been ruled out based on the folfowlng:
High error I poor FWHM
!!'No plant derived Radionuclide at the defined energy Short nuclide half-life rules out presence D Lack of first associated branching ratio gammas Initial &:
Date
/. 'I-I f'
- k-zzg-01 >~~
NX-503 Rev. O Page 6 of 50
Appendix 3 - HBPP Lab Results Nuclide MDA Report 1/4/2018
- 5:07:52 PM Page 6
N U C L I D E MDA REPORT
+
+
+
+
+
Detector Name:
Sample Geometry:
Sample
Title:
Nuclide Library Used:
- Nb-94 Ag-108m Cs-134 cs-137 Eu-152 Eu-154 Energy (keV)
~1460.81*
1173.22*
1332.49*
702.63 871.10 79.20 433.93 614.37 722.95 569.31
-604.70 795.84 661.65*
121. 78*
244.69*
295.93*
329.35
- 344.27*
367.71*
411.11*
443.98*
488.66*
564.03*
586,26*
688.63*
719.33*
778.89*
810.43 867.32*
919.31 926.25 964.01*
1085.78*
1089.68*
- 1112.02*
1212.84*
1249.80 1299.04*
1407.95*
1457.54*
1528.07 723.30*
DET05 Caisson NE Well #1 Sample A C:\\GENIE2K\\CAMFILES\\HBPP Eu-3.NLB Yield
(%)
10.67 100.00 100.00 100.00 100.00 7.10 89.90 90.40 90.50 15.43 97.60 85.40 85.12 28.40*
7.49 0.43 0.13 26.50 0.86 2.21 0.30 0.41 0.48 0.45 o*. 84 0.26 12.74 0.31 4.16 0.40 0.25 14.40 10.00 1.68 13.30 1.38 0.18 1.61 20.70 0.49 0.26 19.70 Line MDA Nuclide MDA (pCi/g
) (pCi/g
)
Activity (pCi/g 9.SlE-001 3.53E-001 2.00E-001 3.52E-001 6.00E-001 3.51E+000 3.04E-001 3.75E-001 4.SlE-001 2,26E+000 3.36E-001 4.21E-001 3.97E-001 8.66E-001 5.83E+O00 5.46E+001 2.04E+002 8.69E-001 2,59E+001 1.06E+001 8.97E+001 S.70E+001 6.29E+001 6.23E+001 3.21E+001 1.0SE+002 2.93E+000 l.28E+002 9.62E+000 l.02E+002 1.66E+002 2.63E+000 2.75E+000 1.57E+001 2.79E+000 2.17E+001 l.80E+002 l.17E+001 6.25E-001 2.22E+001 1.04E+002 l.44E+000 9.SlE-001
- 2.86E+000 2.00E-001 3.24E+000 3.088+000 3.~2E-001 3.36E-002 6.62E-002 3.04E-001 -l.40E+0O0
-5.35E-002 3.12E-001
-1. 76E-002 3.36E-001 -1.20E+000
-2.62E-001
-1. 93E-001 3.978-001 l.12E+001 6,25E-001 7.27E+001 6.48E+001
.6. 95E+001 9.48E+001 7.33E+001 7.91E+001 7.17E+001 7.12E+002 6.44E+001 8.65E+001 7.37E+001 6.91E+001 8.21E+001 7.76E+001 3.69E+001 7.~SE+00l 3.59E+001
-l.18E+002 7.69E+001 8.7SE+001 8.71E+001 8.32E+001 7.76E+001 1.09E+002 7.71E+001 8.42E+001 7.70E+001 2.70E+002 6.41E-001 2.23E+00O Dec. Level
) (pCi/g
)
4.268-001
- 1. 738-001 2,97E-001 1.74E+000 1.S0E-001 1.85E-001 2.22E-001 1,12E+000 1,66E-001 2.07E-001 1,95E-001 4.30E-001 2.90E+000 2.70E+001 l.01E+002 4.28E-001 l.27E+001 5.23E+000 4.42E+001 2.BOE+00l 3.09E-l-001 3.06E+001 1.57E+001 5.15E+001 l.44E+000 6,32E+001 4.73E+000 5.0lE+00l 8.13E+001 1.29E+000 1.33E+000 7.59E+000 l,36E+000 l.05E+001 8,73E+001 5.57E+000 2.88E-00l
- 1. 00E+00l S.00E+00l 1.06E~oo1 NX-503 Rev. O Page 7 of 50
Nuclide
+
Appendix 3 - HBPP Lab Results MDA Report 1/4/2018 5:07:52 PM Page 7
Nuclide Energy
(%)
(pCi/g
) (pCi/g
)
(pCi/g Eu-154 873.19 11.50 4.33E+OOO 6.41E-001 4.51E-001
. 1004. 76*
17.90 1.85E+OOO 6.49E+OOO 1274.45*
35.50 6.41E-001 2.28E+OOO Eu-155 105.31 20.70 1.39E+OOO 1.39E+OOO -5.43E-001 Pb-206 803.10 100.00 3.SlE-001 3.81E-001 -8.52E-002 Ac-228 338.32 11.40 2.27E+OOO 1.42E+OOO -3.05E+001 911. 07 27.70 1.42E+OOO
-7.03E-002 969.11 16.60 S.43E+OOO
-1.63E+OOO Th-234 63.29 3.80 6.46E+OOO S.70E+OOO -l.22E+OOO 92.59 5.41 S.70E+OOO 1.15E+OOO U-235 143.76 10.50 2.18E+OOO 4.SOE-001 -6.22E-001 163.35 4.70 S.32E+OOO
-3.31E+OOO 185.72 54.OD. 4.50E-001 2.77E-001 205.31 4.70 5.07E+OOO 8.39E-001 Np-237 311.98 38.60 6.33E-001 6.33E-001 4.53E-002 Am-241 59.54 35.90 6.87E-001
- 6. 87E-_001 -4.09E-002
+=Nuclide identified during the nuclide identification
- =Energy line found in the spectrum
)
(pCi/g 2.14E+OOO 9.04E-001 3.07E-001 6.92E-001 1.87E-001 l.12E+OOO
. 6. 95E-001 2.69E+OOO 3.20E+OOO 2.83E+OOO 1.08E+OOO 2.64E+OOO 2.23E-001 2,51E+DOO 3.13E-001 3.40E-001
> = Calcul~ted 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 NX-503 Rev. O Page 8 of 50
)
Appendix 3 - HBPP Lab Results GAMMA S P E C T R U M A N A L Y S I S
- ~*************
Detector DET05 Report Generated On Sample Identification Sample Title
- 1/4/2018 5:12:36 PM Sample Information 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 2018-0045 Caisson NE Well #1 Soil 3.00 100 -
4096 100 -
4096
- 1. 000 keV 1.544E+003 g 1/4/2018 3:05:00 1/4/2018 4:25:59 800,0 seconds 811. 5 seconds
,6)
Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID Sample b PM PM 7/29/2010 4/15/2011 D5 lL HD P~dby ~ ~
~
, Anderson, Abrams, Burrell, Date
/ - f~ti' Eckhardt, Step~ens, Stover Reviewed by
<)>. ~"'--
Da t.e
- f. 'I. I&
(Print/Signature: /Alderman, Anderson)
NX-$03 Rev. O Page 9 of 50
Appendix 3._ HBPP Lab Results Peak Locate Analysis Report 1/4/2018 5:12:37 PM Page 2
PE AK LOCATE REPORT Detector Name:
DET05 Sample
Title:
Caisson NE Well #1 Sample b Peak Locate Performed on:
1/4/2018 5:12:36 PM Peak Locate From Channel:
100 Peak Locate To Channel:
4096 Peak Search Sensitivity:
3.00 Peak Centroid Centroid Energy Peak No.
Channel Uncertainty (keV)
Significance 1
, 244.20 0.0710 121.88 117.06 2
324.02 0.2490 161.81 8.30 3
334.60 0.3439 167.30 5.05 4
489.79 0.1021 244.81 50.07 5
496,29 0.4021 247.99 4.39 6
569.92 0.4014 284.90 4.16 7
592.13 0.2603 296.00 8.02 8
688.86 0.0710 344.42 96.03 9
712.62 0.3170 356.27 4.74 10 735.68 0.2179 367.68 11.12 11 822.37 0.1478 411. 25 22.21 12 888.08 0.1345 444.13 25.58 13 977.80 0.2746 488.93 6.36 14 1120:25 0.2999 564.49 5.14 15 1172.85 0,2831 586.53 5.73 16 1313.19 0.3927 656.74 3.49.
17 1323.49 0,1056 661. 90 34.05 18 1357.30 0.3001 678.88 4.82 19 1377.67 0,2172 688.88 8.32 20 1438.44 0.3926 719.55 3.42*
21 1446.95 0.2506 723.52 7.29 22 1558.00 0.0930 779.18 48.02
- 23 1620~91 0.2583 810.58 6.72 24 1735.03 0.1321 867.70 23.95 25 1746.88 0.2900 873.57 5.17 26 1839.48 0.2709 919.91 4.92 27 1853.21
- 0.2973 926.71 4.28 28 1928.50 0.0899 964.41 43.26 29 1992.75 0.3535 996.56 3.05 30 2010.09 0.1873 1005.21 10.04 31 2112:30 0.1004 1086.27 36.06 32
. 2180.24 0.1862 1090.12 12.42 33 2224.73 0.0938 1112.51 41.06 34 2247.12 0.2919 1123.84 4.89 35 2304.91 0.2909 1152.41 3.82 36 2347.25 0.1357 1173.70 19.82 37 2426.65 0.1820 1213.44 10.65 38 2468.27 0.2619 1234.23 5.35 39 2500.96 0.2836 1250.42 5.33 40 2550.13 0.1870 1275.02 10.79 41 2599.47 0.1606 1299.68 12.98 NX-503 Rev. 0 Page 10 of 50
Peak Locate Analysis Report Peak Centroid Centroid Appendix 3 - HBPP Lab Results 1/4/2018 Energy 5:12:37 PM Page 3
Peak No.
Channel Uncertainty (keV)
Significance 42 2666.25 0.1339 1333.11 19.07 43 2817.39 0.0848 1408.61 46.41 44 2897.01 0.2221 1448.25 6.22 45 2916.67 0.2389 1458.25 6.17 46 3061.10 0.2037 1530.25 6.96
? = Adjacent peak noted Errors quoted at 2.000 sigma NX-503 Rev. O Page 11 of 50
Appendix 3 - HBPP Lab Results Peak Analysis Report 1/4/2018 5:12:37 PM Page 4
PE AK A N A L Y S I S REPORT Detector Name:
DET05 Sample
Title:
Caisson NE Well #1 Sample b Peak Analysis Performed on:
1/4/2018 5:12:36 PM Peak Analysis From Channel:
100 Peak Analysis To Channel:
4096 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum
- No. start end centroid (keV)
(keV)
Area Uncert.
Counts F
1 239-248 244.18 121. 88 1.12 6.00E+004 504.65 9.24E+003 M
2 320-339 323.94 161.81 1.31 l.21E+003 136.99 5.46E+003 m
3 320-339 334.93 167.30 1.32 4.69E+002 115.31 5.69E+003 M
4 484-500 489.80 244.81 1.18
- 1. 01E+004 218.77 3.49E+003 m
- 5 484-500 496.16 247.99 1.18 2.52E+002 84.91 2.95E+003 F
6 567-574 569.90 284.90 0.79 l.54E+002 81.48 2.46E+003 F
7 587-597*
592.08 296.00 1.18 5.38E+002 88.29 2.95E+003 F
8 683-694 688.85 344.42 1.25 3.05E+004 348.08 2.48E+003 F
9 707-717 712.53 356.27 1.36 3.15E+002 71.92
- 1. 97E+003*
F 10 730-740 735.34 367.68 1.62 9.73E+002 87.13 l.91E+003 F
11 818-827 822.41 411.25 1.22 l.94E+003 105.42
- 1. 57E+003 F
12 882-893 888.14 444.13 1.36 2.62E+003 116.46 1.81E+003 F
13 974-980 977.69 488.93 1.30 3.06E+002
- 66. 51*
9.85E+002 F
14 1122-1134 1128.73 564.49 2.74 5.32E+002 72.84 l.67E+003 F
15 1169-1178. 1172.80 586.53 1.36 2.78E+002 64.86 l.32E+003 M 16 1311-.1329 1313.16 656.74 1.49
- 6. 98E+001
- 50.74 7.70E+002 m 17 1311-1329 1323.49 661.90 1.49 4.78E+003 144.28 1.07E+003 F
18 1354-1363 1357.44 678.88 1.33 2.01E+002 59.67 1.16E+003 F
19 1371-1383 1377.43 688.88 1.63 5.14E+002 68.70 1.41E+003 M 20 1432-1450 1438.77 719.55 1.54 l.52E+002 52.79 l.15E+003 m 21 1432-1450 1446.69 723.52 1.54 3.44E+002 62.18
- 1. 03E+003 F
22 1551..:. 1564 1558.00 779.18,
1.54 7.48E+003 175.27 l.36E+003 F
23 1614-1625 1620.80 810.58
- 1.32 2.24E+002 55.86 l.07E+003 M 24 1729-1752" 1735.03 867.70 1.56 l.96E+003 99.93
- 1. 06E+003 m 25 1729-1752 1746.78 873.57 1.56 l.97E+002 53.76
- 1. 05E+003 M 26 1837-1856 1839.. 45 919,91 1.37 l.34E+002 48.46 5.16E+002 m 27 1837-1856 1853.06 926.71 1.37 l.20E+002 46.48 6,55E+002
- F 28 1921-1933 1928.48 964,41 1.69 6,99E+003 166.57 8.01E+002 F
29 1987-1999 1992.78 996.56 1.47 8.80E+001 42.87 7.52E+002 F
30 2004-2016 2010.09 1005.21 1.85 6.15E+002 62.12 7.27E+002 M 31 2165-2187 2172.25 1086.27 1.80 4.87E+003 139.03 5.37E+002 m 32 2165-2187. 2179.97 1090.12 1.81 8.58E+002 65.27 4.72E+002 F
33 2217-2231 2224.76 1112,*51 1.81 5.95E+003 152.67 6.30E+002 F
34 2241-2254 2247.42 1123.84 2.85 3.13E+002 49.01 6.02E+002 F
35 2297-2311 2304.59 1152.41 2.22 l.88E+002 44.40 6.45E+002 F
36 2340- 2354 2347.19 1173.70 1.81 l.49E+003 82.78 6.29E+002 F
37 2419-2431 2426.70 1213.44 1.83 4.85E+002 51.85 3.52E+002 F
38 2464-2475 2468.30 1234.23
- 1. 71 l.49E+002 35.82 3.04E+002 F
39 2493-2504 2500.71 1250.42 1.40 9.20E+001 30.09 2.36E+002 F
40 2542-2554 2549.93 1275.02 1.88 4.30E+002 47.02 2.12E+002 F
41 2594-2604 2599.29 1299.68 1.80 6.19E+002 52.97 l.44E+002 F
42 2660- 2673 2666.20 1333.11 1.98 l.38E+003 73.28 9.138+001 NX-503 Rev. O Page 12 of 50
Appendix 3 - HBPP Lab Results Peak Analysis Report 1/4/2018 5:12:37 PM Page 5
Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)
(keV)
Area Uncert.
Counts F
43 2809-2824 2817.31 1408.61 1.94 7.41E+003 166.24 6.89E+001 F
44 2889-2903 2896.65 1448.25 2.13 l.95E+002
- 29. 9?
8.72E+001 F
45 2912-2920 2916.68 1458.25 1.47 l.06E+002 28.83 1.23E+002 F
46 3054-3068 3060.81 1530.25 2.33 3.10E+002 33.53
- 1. 97E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma NX-503 Rev. O Page 13 of 50
Appendix 3 - HBPP Lab Results Interference Corrected Activity Report 1/4/2018 5:12:37 PM Page 6
N U C L I D E I D E N T I F I C A T I O N REPORT
- ~*******************************************************
Sample
Title:
Caisson NE Well #1 Sample b Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\HBPP Eu-3.NLB Nuclide Name Co-60 Cs-137
- Bu-152
- Eu-154 Id Confidence 0.952 0.990 0.974 0.967 IDENTIFIED NUCLIDE$
Energy (keV) 1173.22*
1332.49*
661. 65*
121.78*@
244.69*@
295.93*
329.35 344.27*
367.71*@
411.11* @
443.98*@
488.66*@
564.03*@
586.26*@
688.63*@
719.33*@
778.89*
810.43*@
867.32*@
919.31*@
926.25*@
964.01*
1085.78*@
1089.68*@
1112.02*@
1212.84*@
1249.80*@
1299.04*@
1407.95*
1457.54*@
1528.07 723.30*@
873.19*@
1004.76*@
1274.45*
Yield
(%)
100.00 100.00 85.12 28.40 7.49 0.43 0.13 26.50 0.86 2.21 0.30 0.41 0.48 0.45 0.84 0.26 12.74 0.31 4.16 0.40 0.25 14.40 10.00 1.68 13.30 1.38 0.18 1.61 20.70 0.49 0.26 19.70 11.50 17.90 35.50 Activity (pCi/g
)
4.936988+000 S.07229E+000 l.14520E+001 1.333628+002 l.18586E+002 1.279648+002 l.32102E+002 l.38132E+002 l.17372E+002 l.25250E+003 l.15677E+002 l.95446E+002 l.12352E+002 l.29781E+002 l,25794E+002 L 38115E+002 1.76017E+002 l.21557E+002 9,0582SE+001 l.28222E+002 l.36840E+002 l.51253E+002 l.59202E+002 l,41754E+002 l.19376E+002 l.79938E+002 l.38092E+002 1,369528+002 8.50135E+001 3.84748E+000 4,43731E+000 l,00209E+001 4.28790E+000
- =Energy line found in the spectrum.
Activity Uncertainty 3.702398-001 3.81956E-001 7.24173E-001 7.410488+000 7.15843E+O00 2.203?1E+001 6.89972E+000 l,42541E+001 8.91976E+000 8.82646E+001 2.59493E+001 2.90620E+001 2.702738+001 1.871888+001 4.42073E+001 7.63102E+O00 4.46578E+001 8.39998E+000 3.29879E+001 5.00140E+001 7.04428E+O00 8.43325E+O00 l.43203E+001 7.79520E+000 1.417598+001 5.961538+001 1.391018+001 7.989788+000 2.366i4E+001 7.247908-001 1.229468+000 1.112~88+000 5.20273E-001
@=Energy line not used for Weighted Mean Activity Energy Tolerance :
1.000 keV Nuclide confidence index threshold=
0.30 Errors quoted at 2.000 sigma NX-503 Rev. O Page 14 of 50
Appendix 3-HBPP Lab Results Interference Corrected Activity Report 1/4/2018 5:12:37 PM Page 7
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/g
)
Uncertainty Co-60 0.952 5.002532E+000 2.658440E-001 Cs-137 0.990 1.145197E+001 7.241727E-001 Eu-152
@ 0.974 1.358144E+002 3.676180E+000 Eu-154
@ 0.967 4.287898E+000 5.202730E-001
? = 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 PE AK S 1/4/2018 100 4096 F
F F
F F
F F
F F
Peak Locate Performed on:
Peak Locate From Channel:
Peak Locate To Channel:
Peak Energy Peak Size in No.
(keV)
Counts per Second M
2 161. 81 1.5076E+000 m 3 167.30 5.8619E-001 m 5 247.99 3.1478E-001 6
284.90 1.9237E-001 9
356.27 ~
3.9353E-001 M 16 656.74 8.7236E-002 18 678.88 2.5088E-001 29 996.56 1.0999E-001 34 1123.84 3.9151E-001 35 1152.41 2.3513E-001 38 1234.23 1.8571E-001 44 1448.25 2.4342E-001 46 1530.25 3.8770E-001 M = First peak. in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma 5:12:36 PM Peak CPS Peak Tol.
Uncertainty Type Nuclide 11.36
$1,A.t'I\\ '111+1J. :;2.
24.59
)4'.IA. 'l~-+1-:J.:J....
33.72 1:~~o< IZ 2 -f I l Z,..
52.94 22.84
~,4c. 2Z."
72.71 eu,n- £1,t IS-~
29.73 Eu.rs-~
48.72 EK,..s-io +,11~.r-15.65 Sum
+- 111 ~
23.60 JAM.
'IP 24.11 Sum 11-:J.~ Ill 2.
15.39 5LtM
'{0/-/'(pg 10, 81 Sµm I z.Z-//'fQ iJ "This peak has been ruled out based on the folrowlng:
0 High error/ poor FWHM
)lf No plant derived Radionuclide at the defined energy Short nuclide half-Hfe rules out presence Lack of first associated branqifng raUo gammas lnlllal AM-:
Dale l
,-f-f y Ae za 'I'~ I tvM.. /~"-
NX-503 Rev. 0 Page 15 of 50
Appendix 3 - HBPP Lab Results Nuclide MDA Report
. 1/4/2018 5:12:37 PM Page 8
NUCLIDE MDA REPORT
+
+
+
+
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 Energy
"(keV) 1460.81 1173.22*
1332.49*
702.63 871.10 79.20
- 433.93 614.37 722.95 569.31 604.70 795.84 661.65*
121.78*
244.69*
295.93*
329.35 344.27*
367.71*
411.11*
443.98*
488.66*
564.03*
- 586.26*
688.63*
719.33*
778.89*
810.43*
867.32*
919.31*
926.25*
964.01*
1085.78*
1089.68*
1112.02*
1212.84*
1249.80*
1299.04*
1407.95*
1457.54*
"1528.07 723.30*
DET05 Caisson NE Well #1 Sample b C:\\GENI82K\\CAMFILES\\HBP~ Eu-3.NLB Yield
' (t) 10.67 100.00 100.00 100.00 100.00 7.10 89.90 90.40 90.50 15.43 97.60 85.40 85.12 28.40 7.49 0.43 0.13 26.50 0.86 2.21 0.30 0.41 0.48 0.45 0.84 0.26 12.74 0.31 4.16 0.40 0.25 14.40 10.00 1.68 13.30 1.38 0.18 1.61 20.70 0.49 0.26 19.70 Line MDA Nuclide MDA (pCi/g
) (pCi/g
)
3.358+000 4.738-001 2.0lE-001 4.SSE-001 7.83E-001 4.318+000 3.73E-001 4.78E-001 5.70E-001 2.888+000 4.288-001 S.59E-001 3.718-001 1.068+000 3.26E+OOO 6.62E+001 2.53E+002 1.148+000 3.198+001 l.21E+001
- 1. 07E+002 5.468+001 8.lOE+OOl 7.41E+001 S.13E+001 l.33E+002 3.768+000
- 1. 368+002 9.55E+OOO 7.32E+001 1.30E+002
. 3. 03E+OOO 3.438+000 l.93E+001 3.40E+OOO 2.538+001 l.62E+002 l.42E+001 9.288-001 4.558+001 1.468+002 1.708+000 3.35E+OOO 2.0lE-001 4.55E-001 3.73E-001 4.28E-001 3.718-001 9.288-001 8.02E-001 Activity (pCi/g 8.94E+OOO 4.948+000 5.078+000
- 1. 058-001 5.938+000
-3.018+000
-2.298-001 1.478-001
-2.398-001
-2.85E+OOO
-3.23E-001
-4.58E-001 l.lSE+OOl
- 1. 33E+002 l.19E+002 1.28E+002
-4.71E-001 l.32E+002 1.388+002 l.17E+002 l.25E+003 1.16E+002 1.95E+002 l.12E+002 l.30E+002 1.26E+002 1.38E+002 1.76E+002 1.22E+002 9.06E+001 1.28E+002 1.378+002 1.51E+002 1.59E+002 l.42E+002 l.19E+002 1.~0E+002 l.38E+002 1.37E+002 8.508+001
-4.88E+001 3.858+000 Dec. Level
) (pCi/g
)
1.62:S+OOO 2.328-001 9.55E-002 2.258-001 3.888-001 2.148+000 l.84E-001 2.368-001 2.828-001 l.42E+OOO 2.128-001 2.76E-001 1.82E-001 S.29E-001 l.61E+OOO 3.28E+001 l.25E+002 5.628-001
- 1. 58E+001 S.9SE+OOO 5.28E+001 2.68E+001 4.00E+OOl 3.65E+001 2.53E+001 6.54E+001 l.8SE+OOO 6.67E+001 4.69E+OOO 3.57E+001 6.368+001 1.498+000 1.68E+OOO 9.38E+OOO 1.67E+OOO l.23E+001
- 7. 83E+001.
6.SOE+OOO 4.39E-001 2.17E+001 7.08E+001 8.36E-001 NX-503 Rev. O Page 16 of 50
Appendix 3 - HBPP Lab Results Nuclide MDA Report 1/4/2018 5:12:37 PM Page 9
+
Nuclide Name Eu-154 Eu-155 Pb-206 Ac-228 Th-234 U-235 Np-237 Am-241 Energy (keV) 873.19*
1004.76*
1274.45*
105.31 803.10 338.32 911.07 969.11 63.29 92.59 143.76 163.35 185.72 205. 31 311.98 59.54 Yield
(%)
11.50 17.90 35.50 20.70 100.00 11.40 27.70 16.60 3.80 5.41 10.50 4.70 54.00 4.70 38.60 35.90 Line MDA Nuclide MDA Activity (pCi/g
) (pCi/g
)
(pCi/g 3.46E+OOO 2.39E+OOO 8.02E-001 l.72E+OOO S.OlE-001 2.79E+OOO l.88E+OOO 7.19E+OOO 7.93E+OOO 7.lSE+OOO 2.68E+OOO 6.83E+OOO S.SlE-001 6.30E+OOO 7.84E-001 8.29E-001 8.02E-001 4.44E+OOO l.OOE+OOl 4.29E+OOO l.72E+OOO -6,0lE-001 5.0lE-001 -2.04E-002 l.88E+OOO -4.86E+OOO 6.02E-001
-4.68E+001 7.lSE+OOO
- 3.698-001
-8.03E-001 S.SlE-001 -l.37E+OOO 8.04E+OOO 2.858-002 l.68E+OOO 7.84E-001 -2.66E-001 8.29E-001 -2.lOE-001
+=Nuclide identified during the nuclide identification
- =Energy line found in the spectrum Dec. Level
) (pCi/g
)
l.70E+OOO l.17E+OOO 3.88E-001 8.SSE-001 2.47E-001 l.38E+OOO 9.29E-001 3.57E+OOO 3.94E+OOO 3.56E+OOO
- 1. 33E+OOO 3.39E+OOO 2.74E-001 3.13E+OOO 3.88E-001 4.llE-001
>=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 NX-503 Rev. 0 Page 17 of 50
Appendix 3 - HBPP Lab Results GAMMA S P E C T R U M A N A L Y S I S Detector DET03 Report Generated On
_Sample Identification Sample Title Sample Information 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 2/1/2018 12:54:41 PM 2018-0369 NE Caisson Well Pump Soil 3.00 100 -
100 -
1.000 4096 4096 keV 1.678E+003 g 2/1/2018 2/1/2018 11:00:00 AM 12:03:55 PM 800.0 seconds 800.2 seconds 0.03 %
Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 3/4/2011 S/13/2011 D3 lL HD Performed by ?rlJJd ~
Date.2~1-if Alderman, Anderson, Abrams, Burrell, Eckhardt, Stephens, Stover Reviewed by ~
. Date :Z-1 llf"'
(Print/Signature: ~
m,Anderson)
-503 Rev. 0 Page 18 of 50
Appendix 3 - HBPP Lab Results Peak Locate Analysis Report 2/1/2018 12:54:41 PM Page 2
PE AK LOCATE REPORT Detector Name:
DET03 sample
Title:
NE Caisson Well Pump Peak Locate Performed on:
2/1/2018 12:54:41 PM Peak Locate From Channel:
100 Peak Locate To Channel:
4096 Peak Search Sensitivity:
3.00 Peak Centroid Centroid Energy Peak No.
Channel Uncertainty (keV)
Significance 1
477.27 0.3799 238.47 3.32 2
703~86 0.3658 351.90 3.20 3
1217.54 0.3553 608.96 3.71 4
1322.69 0.1819 661. 49 12.92 5
2921. 38 0.2615 1460.48 4.32
? a: Adjacent peak noted Errors quoted at 2.000 sigma NX-503 Rev. 0 Page 19 of 50
Peak Analysis Report Appendix 3 - HBPP Lab Results 2/1/2018 12:54:41 PM Page 3
P 8 AK A N A L Y S I S REPORT F
F F
F F
M =
m =
F =
Detector Name:
DET03 Sample
Title:
NE Caisson Well Pump Peak Analysis Performed on:
2/1/2018 Peak Analysis From Channel:
Peak Analysis To Channel:
Peak ROI ROI Peak Energy FWHM No. start end centroid (keV)
(keV) 1 473-481 477.13 238.47 1.05 2
699-708-703.77 351.90 1.36 3
1213-1222 1217.55 608.96 1.54 4
1317-1328 1322.57 661.49 1.60 5
2914-2928 2921.26 1460.48 2.28 First peak in a multiplet region Other peak in a multiplet region Fitted singlet Errors quoted at 2.000 sigma 12:54:41 PM 100 4096 Net Peak Net Area Area Uncert.
8.28E+001 24.74 9,598+001 22.01 7.598+001 18.14 8.608+002 58.08 1.36E+002 22.92 Continuum counts 1.28E+002 6.82E+001 l.87E+001 1.72E+001 0.008+000 NX-503 Rev. 0 Page 20 of 50
Appendix 3 - HBPP Lab Results Interference Corrected Activity Report 2/1/2018 12:54:41 PM Page 4
NUCLIDE I D E N T I F I C A T I O N REPORT Sample
Title:
NE caisson Well Pump Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\HBPP.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV)
(%)
(pCi/g
)
Uncertainty K-40 0.983 1460.81*
10.67 4.46919E+000 7.927458-001 Cs-137 0.996 661.65*
85.12 1.87364E+000 l.63918E-001 Pb-212 0.891 238.63*
44.60 1.55856E-001 4.74340E-002 300.09 3.41 Bi-214 0.471 609.31*
46.30 2.84144E-001 6.98287E-002 1120.29 15.10 1764.49 15.80
- =Energy line found in the spectrum.
@=Energy line not used for Weighted Mean Activity Energy Tolerance:
1.000 keV Nuclide confidence index threshold=
0.30 Errors quoted at 2.000 sigma NX-503 Rev. O Page 21 of 50
Appendix 3 - HBPP Lab Results Interference Corrected Activity Report 2/1/2018 12:54:41 PM Page s
- ~**:***************************************** J*************
INTERFERENCE CORRECTED REPORT Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence
. (pCi/g
)
Uncertainty K-40 0.983 4.4691878+000 7.9274488-001
....Cs-137 0.996 1.873642E+000 1.6391768-001 Pb-212 0.891 1.558563E-001 4.7434008-002 Bi-214 0.471 2.841438E-001 6.9828678-002
? = nuclide is part of an undetermined solution X = nuclid~ rejected by the interference analysis
@=nuclide contains energy lines not used in Weighted Mean Activity Errors quoted *at 2.000 sigma UN IDEN TI F *IE D Peak Locate Performed on:
Peak Locate From Channel:
Peak Locate To Channel:
Peak Energy Peak Size in.
P E A K S 2/1/2018 100 4096 Peak CPS 12:54:
Tol.
No.
(keV)
Counts per Second
% Uncertainty Nuclide F
2 351. 90 1.1982E-001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma 22.97
~
""""'!> z..,.&1 NX-503 Rev. 0 Page 22 of 50
Appendix 3 - HBPP Lab Results Nuclide MDA Report 2/1/2018 12:54:41 PM Page 6
+
+
Detector Name:
Sample Geometry:
Sample
Title:
Nuclide Libr~ry Used:
Nuclide Name K-40 Co-60 Nb-94 Ag-108m Cs-134 Cs-137 Eu-152 Eu-154 Eu-155 Ac-228 Th-234 U-235 Np-237 Am-241 Energy (keV) 1460.81*
1173.22 "1332.49 702.63 871.10 433.93 614.37 722.95 569,31 604.70 w 795.84 661.65*
121. 78.
244.69 344.27 778.89 964.01 1085.78 1112.02 1407.95 123.07 723.30 873.19 996.32 1004.76 1274.45 105.31
- 338.32 911.07 969.11 63.29 92.59 143.76 185.72 311. 98 59.54 DET03 NE Caisson Well Pump C:\\GENI82K\\CAMFILES\\HBPP.NLB Yield Line MDA Nuclide MDA Activity
(%)
(pCi/g aaA} (pCi/g
) (pCi/g 10.67 100.00 100.00 100.00 100.00 89.90 90.40 90.50 15.43 97.60 85.40 85.12 28.40 7.49 26.50 12.74 14.40 10.00 13.30 20.70 40.50 19.70 11.50 10.30 17.90 35.50 20.70 11.40 27.70 16.60 3.80 5.41 10.50 54.00 38.60 35.90 8.928-002 8.32E-002 7.868-002 4.968-002 6.128-002 5.778-002 S.68E-002 6.308-002 2.768-001 5.278-002 6.19E-002 5.25E-002 l.78E-001 6.79E-001 2.18E-001 4.168-001 5.00E-001 7.208-001 4.89E-00l 4.058-001 1.248-001
- 2. 948-001 4.758-001 6.038-001 3.268-001 l.41E-001 2.14E-001 4.728-001 2.918-001 4.48E-001 2.56E+OOO l,13E+OOO 3.72E-001 8.lBE-002 l.17E-001 3.478-001 8.92E-002 7.868-002 4.96E-002 5.688-002 S.27E-002 S.25E-002 l.78E-001 1.248-001 2.14E-001 2 *. 918-001 1.138+000 8.188-002 l.17E-001 3.478-001 4.478+000 5.768-002 5.138-002 3.248-003 4.p3E-002
-1. 32E-002
-4.518-002 2.lSE-002
-l.33E-001
-3.848-002 2.02E-002
- 1. 87E+OOO 2.lBE-001 2.6SE-001 9.62E-002
-2.53E-003
-5.67E-002 l.40E-001 3.038-001 2.68E-001 1.50E-001 1.338-001 1.058-001 1.788-001
-5.27E-002
-8.95E-002 l.14E-001 7.368-002 2.79E-001 l.33E-001
-1.0SE+OOO l.25E+OOO
-1. 12E-002 6.53E-002
-7.65E-003 9.29E-002
+=Nuclide identified during the nuclide identification
- =Energy line found in the spectrum Dec. Level
) (pCi/g 0.008+000 3.76E-002 3.49E-002 2.22E-002 2.7SE-002 2.698-002 2.58E-002 2.85E-002 l.24E-001 2.408-002 2.75E-002 2.33E-002 8.58E-002 3.24E-001 l.03E-001
- 1. 85E-001 2.26E-001 3.238-001 2.168-001
- 1. BOE-001 S.98E-002
- 1. 33E-001 2.108-001 2.6BE-001 l.44E-001 5.858-002 1.028-001 2.23E-001 1.34E-001 2.04E-001 1.208+000 5.418-001 1.778-001 3.91E-002 S.48E-002 l.64E-001 Q 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 NX-503 Rev. O Page 23 of 50
Appendix 3 - HBPP Lab Results GAMMA S P E C T R U M A N A L Y S I S Detector *DET03 Report Generated On Sample Identification Sample Title Sample Information 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 2/1/2018 4:58:57 PM 2018-0370 NE Caisson Well Composite Sample Above Pump Soil 3.00 100 -
100 1.000 4096 4096 keV 1.541E+003 g 2/1/2018 2/1/2018 3:35:00 PM 4:43:19 PM 800.0 seconds 803.5 seconds 0.43 %
Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 3/4/2011 5/13/2011 DJ lL F Performed by 1Vf::Jj i ~
Date_.__:J~,.... f...;;.*..;;.t....;;1 ____
Alderman, Anderson, Abrams, Burrell,. Eckhardt, Stephens, Stover NX~
Rev. O Page 24 of 50
Peak Locate Analysis Report Appendix 3 - HBPP Lab Results 2/1/2018 4:58:58 PM Page 2
PE AK LOCATE REPORT Detector Name:
DET03
- *Sample
Title:
NE Caisson Well Peak Locate Performed on:
2/1/2018 4:58:57 PM Peak Locate From Channel:
100 Peak Locate To Channel:
4096
- Peak Search sensitivity:
3.00 Peak Centroid Centroid Energy Peak No.
Channel Uncertainty (keV)
Significance 1
243.76 0.1359 121.74 35.12 2
489.51 0.1797 244.68 15.75 3
688~46 0.1258 344.22
- 31.89 4
711.89 0.4910 356.01 3.06 5
735.43 0.3531 367.67 4.54 6
822.02 0.2508 411.10 7.90 7
887.61 0.2413 443.94 7.94 8
928.12 0.4107 464.04 3.00 9
1322.58 0.1015 661.50 39.03 10 1376.74 0.3675 688.51 3.83 11 1556.96 0.1528 778.69 18.21 12 1734~01 0.2190 867.23 8.65 13 1927.38 0.1472
- 963.85 16~34 14 2009.08 0.2956 1004.78 3.03 15 2170.82 0.1607 1085.65 14.95 16 2179.04 0.3391 1089.50
- 4 ~01 17 2223.38 0.1483 1111.84 16.69 18 2345.56 0.1940 1172.91 9.26 19 2425.45 0.3052 1212.83 3.91 20 2548.46 0.2827 1274.17 4.43 21 2597.55 0.2753 1298.92 4.36 22 2664.75 0.2139 1332.22 7.98 23 2815.60 0.1343 1407.71 18.30 24 3058.02 0.3180 1528.79 3.27
? = Adjacent peak noted Errors quoted at 2.000 sigma NX-503 Rev. O Page 25 of 50
Appendix 3 - HBPP Lab Results Peak Analysis Report 2/1/2018 4:58:58 PM Page 3
PE AK ANALYSIS REPORT Detector Name:
DET03 Sample
Title:
NE Caisson Well Peak Analysis Performed on:
2/1/2018 4:58:58 PM Peak Analysis From Channel:
100 Peak Analysis To Channel:
4096 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)
(keV)
Area Uncert.
Counts F
1 240-247 243.92 121,74 1.17 1,24E+004 225.66 2.30E+003 F
2 485-493 489.53 244.68 1.18 2.31E+003 109.04 l.37E+003 F
3 683-692 688.42 344.22 1.31 7.41E+003 171.33 9.18E+002 F
4 709-714 711.99 356.01 0.77 5.68E+001 42.55 4.64E+002 F
5 730-740 735.29 367,67 1.42 2.46E+002 50.14 8.24E+002 F
6 817-826 822.08 411.10 1.33 4.66E+002 58.43 7.56E+002 F
7 882-892 887.69 443,94
- 1. 5.7 7.11E+002 65.51 7.91E+002 F
B 923-931 927.88 464.04 1.06 6.60E+001 41.37 6,49E+002 F
9 1317-1327 1322.58 661.50 1.59 8.69E+003 183.80 3,95E+002 F
10
- 1371-1382 1376.58 688.51 1.63 1.20E+002 34.61 3,32E+002 F
11 1551-1562 1556.90 778,69 1.75 1.93E+003 90.21 2.96E+002 F
12 1729-1739 " 1733.97 867.23 1.74 4,88E+002 53.36
-3.08E+002 F
13 1921-1933 1927.23 963.85 1.92 l.81E+003 87.61 2.65E+002 F
14 2004-2014 2009.11 1004.78 2.06 l.52E+002 32.10 1.45E+002 M 15 2164-2185 2170,91 1085.65
- 1. 95. 1.23E+003 73.33 l,85E+002 m 16 2164-2185 2178.62 1089.50 1.95 1.96E+002 33.65
- 1. 76E+002 F
17 2217-2229 2223.33 1111,84 2.02
- 1. 54E+003 80.38 l.66E+002 F.18 2340- 2352 2345.53 1172.91 1.81 4.68E+002 49.1;5 l.76E+002 F
19 2419-2431 2425.42 1212. 83 2.23 1.35E+002 28.52 l.01B+002 F
20 2542-2554. 2548.22 1274,17 1.99 l.21E+002 25.39 5.83E+001 F
21 2592-2604 2597.77 1298,92 2.28 1.60E+002 27.71 4.85E+001 F
22 2657-2671 2664.43 1332.22 2.40 4.34E+002 42.17 3.00E+00l F
23 2808-2822 2815.57 1407.71 2.20 2.06E+003 91.15 '
3.57E+001 F
24 3052-3064 3058.07 1528.79 2.20 6.61E+001 17.55 l.40E+001 M = First peak in a multiplet region m
- Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma NX-503 Rev. o Page 26 of 50
Appendix 3 - HBPP Lab Results Interference Corrected Activity Report 2/1/2018 4:58:58 PM Page 4
NUCLIDE I D E N T I F I C A T I O N REPORT Sample
Title:
NE Caisson Well Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\HBPP.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV)
(%)
(pCi/g
)
Uncertainty Co-60 0.987 1173.22*
100.00 1.50467E+000 1.75236E-001 1332.49*
100.00 1.54694E+000 1.71485E-001 Cs-137 0.996 661.65*
85.12 2.06112E+001 l.22721E+000 Eu-152 0.997 121. 78* @
28.40 3.33233E+001 l.94105E+000 244.69* @
7.49 2.86817E+001 2.12438E+000 344.27*
26.50 3.34059E+001 1.88469E+000 778.89*
12.74 3.48958E+001 2.39163E+000 964.01*
14.40 3.44289E+001 2.29082E+000 1085.78* @
10.00 3.72422E+001 2.84158E+000 1112.02* @
13.30 3.56045E+001 2.54018E+000 1407.95*
20.70 3.70702E+001 2.58151E+000
- =Energy.line found in the spectrum.
@=Energy line not used for Weighted Mean Activity Energy Tolerance:
1.000 keV Nuclide confidence index threshold=
0.30 Errors quoted at 2.000 sigma NX-503 Rev. 0 Page 27 of 50
Appendix 3 - HBPP Lab Results Interference Corrected Activity Report*
2/1/2018 4:58:58 PM Page s
INTERFERE.NC E CORRECTED REPORT Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/g
)
- Uncertainty Co-60 0.987 1.5262668+000 1.225629E-001 Cs-137 0.996 2.061119E+001 1.227211E+000 Eu-152 0.997 3.466724E+001 1.120161E+000
? = 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 PE AK S 2/1/2018 100 4096 Peak Locate Performed on:
Peak Locate From Channel:
Peak Locate To Channel:
Peak Energy Peak Size in No.
(keV)
Counts per Second F
4 356.01 7.09828-002 F
5 367.67 3.07578-001 F
6 411.10 5.8243E-001 F
7 443.94 8.8927E-001 F
8 464. 04i 8.2551E-002 F
10 688.51
- 1. 5027E-001 F
12 867.23 6.1018E-001 F
14 1004.78 l.9030E-001 m 16 1089.50 2.4523E-001 F
F F
F 19 1212.83 l.6932E-001 20 1274.17 1.5080E-001 21 1298.92 2.00438-001 24 1528.79 8.2572E-002 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma 4:58:57 PM Peak CPS Peak Tol.
Uncertainty Type Nuclide 74.93
- ~c.1 -zz!I 20.38
£u,st 12.54 cit IS~
9.21 EIJ.. I.S'" d-62.64 28.79 Sum Ft,</'J-1..
10.93
&-iu~- ~
21.08 Sum 17.15 f.""-l>~/(5'°f 21.06
~IA.(~p-21.04 Tol.
E
- z.~-,,
u-17.28
(.{(:,(
26.57
/PJ. t-/tltl "This peak has been ruled out based on the ronowing:
- fJ High error/ poor FWHM 1
- 'ii No plant derived Radionuclide at the defined energy D Short nuclido hair-lire rules out presence D Lack of first associated branching rati9 gammas Initial I->>-
Dale.-
'. ::Z,
.aca..;;i
...(._-..:..\\ ~=-----
NX-503 Rev. o Page 28 of 50
Appendix 3 - HBPP Lab Results Nuclide MDA Report 2/1/2018 4:58:58 PM Page 6
- ~**
NUCLIDE MD A REPORT
)
+
+
+
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 Ac-228 Th-234 U-235 Np-237 Am-241 Energy (keV) 1460.81
~1173.22*
1332.49*
702.63 871.10 433.93 614.37 722.95 569.31 604.70 795.84 661. 65*
121.78*
244.69*
344.27*
778.-89*
964.01*
1085.78*
"1112.02*
1407.95*
123.07 723.30 873.19 996.32 1004.76 1274.45 105.31 338.32 911.07 969.11 63.29 92.59 143.76 185.72 311.98 59.54 DET03 NE Caisson Well C:\\GENIE2K\\CAMFILES\\HBPP.NLB Yield Line MDA Nuclide MDA Activity
(%) (pCi/g aaA) (pCi/g
) (pCi/g 10.67 100.00 100.00 100.00 100.00 89.90 90.40 90.50 15.43 97.60 85.40 85.12 28.40 7.49 26.50 12.74 14.40 10.00 13.30 20.70 40.50 19.70 11.50 10.30 17.90 35.50 20.70 11.40 27.70 16.60 3.80 5.41 10.50 54.00 38.60 35.90 2.llE+000 2.37E-001 l.18E-001 2.318-001 3.858-001 2.238-001 2.35E-001 2.8SE-001 l.44E+000 2.238-001 2.77E-001 2.458-001 6.078-001 2.24E+O00 6.89E-001 l.67E+000 l.71E+000 2.00E+000 1.66E+000 6, 48E-001 l,07E+0O0 1.31E+000 2.598+000 2.31B+00O 1.53E+00O 6.858-001 l.03E+00O 1.76E+000 8.768-001 2.718+000 l.09E+001 4.51E+00O l.46E+00O 3.008-001 4.88E-001 1.368+000 2.118+000 4.70E+000 l.18E-001 l.SOE+000 l.SSE+000 2.31E-001 l.SSE-001 5.48E-002 2.23E-001 -8.46E-002
-1. 638-001 l.53E-001 2.23E-001 -6.41E-001
-1.31E-001
-2.428-001 2.458-001 2.06E+001 6.07E-001 3.338+001 2.87E+001 3.348+001 3.49E+001 3.44E+001 3.72E+001 3.56E+001 3.71E+001 6.SSE-001 -3.65E+O00 4.84E-001
-1.09E+000 l.28E-001 1.98E+000 1.07E+000 1.03E+000 5.73E-001 8.76E-001 -5.90E+000
-3.28E-002
-2.63E+OOO 4.51E+OO0 5.0lE+000
- 1. 21E+000 3.00E-001 7.16E-003 4.23E-003 4.88E-001 -l.47E-001 l.36E+000 -8,39E-001
+=Nuclide identified during the nuclide identification
- =Energy line found in the spectrum Dec. Level
) (pCi/g l.0lE+000 l.14E-001 5.44E-002 1.138-001 l.89E-001 1.098-001 l.lSE-001 l.39E-001 7.04E-001
- 1. 098-001 1,358-001 1.198-001 3.00E-001 l.l0E+00O 3.38E-001 8.llE-001 8.28E-001 9.57E-001 7.96E-001 3.00E-001 5.31E-001 6.40E-001 l.27E+0O0 l.12E+OO0 7.43E-001 3,30E-001 5.12E-001 8.64E-001 4.25E-001 1.33E+00O 5.39E+0O0 2.23E+000 7.22E-001 l.48E-001 2.40E-001 6.70E-001
>=Calculated MOA is zero due to zero counts in the region, or the region is outside the spect rum, or MDA has not been calculated
@=Half-life too short to be able to perform the decay correction NX-503 Rev. 0 Page 29 of 50
Appendix 3 - HBPP Lab Results
- Nuclide MDA Reper~
2/1/2018 3:52:21 PM Page 7
@=Half-life too short to be able to perform the de~ay correction GAMM A S P E C T R U M AN ALY.SIS Detector DET03 Report Generated On Sample Identification Sample Title Sample Information
- Sample Type Sample Geometry Peak Locate Threshold Peak Locate Range (in channel s)
Peak Area Range (in channels)
Identification Energy Tolerance Sample Size Sample Taken On *
- Acquisition Started Live Time Real Time Dead Time 2/1/2018 3:53:26 PM 2018-0373 NE Caisson Well Sediment Bottom Soil 2.50 100 -
4096 100 -. 4096 1.000 keV l.628E+003 g 2/1/2018 2/1/2018.
800.0 seconds 803.9 seconds 0.49 %
Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency ID 3/4/2011 5/13/2011 D3 lL HD Performed by 'ltf.}J)j_ ~
Alderman; Anderson, Abrams, Burrell, Date 2,l*"~
Eckhardt, Step~ens, St over Date ~ ~I-/$
Anderson)
NX-503 Rev. 0 Page 30 of 50
Appendix 3 - HBPP Lab Results Peak Locate Analysis Report 2/1/2018 3:53:27 PM Page 2
PE AK LOCATE REPORT Detector Name:
DET03 Sample
Title:
NE Caisson Well Peak Locate Performed on:
2/1/2018 3:53:26 PM Peak Locate From Channel:
100 Pec].k Locate To Channel:
4096 Peak Search Sensitivity:
2.50 Peak Centroid Centroid Energy Peak No.
Channel uncertainty (keV)
Significance 1
244.37 0.4578 121.82 2.99 2
878.83 0.4223 439.52 3.31 3
1218.24 0.4238 609.31 2.99 4
1322~55 0.0682 661.48 85.66 5
1556.91 0.3478 778.75 3.89 6
1838.97 0.4388 919.67 2.54 7
1927.27 0.3912 963.84 3.12 8
, 2345. 69 0.2048 1172.96 8.18 9
2664.75 0.2044 1332.28 8.88 10 2815.65 0.3159 1407.81 3.86 11 2921.47 0.2616 1460.52 4.98
? = Adjacent peak noted Errors quoted at 2.000 sigma NX-503 Rev. O Page 31 of 50
Appendix 3 - HBPP Lab Results Peak Analysis Report 2/1/2018 3:53:27 PM Page 3
P. E AK ANALYSIS REPORT Detector Name:
DET03 Sample
Title:
NE Caisson Well Peak Analysis Performed on:
2/1/2018 3:53:26 PM Peak Analysis From Channel:
100 Peak Analysis To Channel:
4096 Peak ROI ROI" Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV)
(keV)
Area Uncert.
Counts F
1 240-247 244.08 121.82 1.18 2.99E+002 81.62 2,34E+003 F
2 874-883 878.87 439.52 0.96
- 1. 27E+002 62.64 1.72E+003 F
3 1215-1223 1218.25 609.31 1.04 5,90E+001 32.07 3.28E+002 F
4 1317-1327 1322.54 661.48 1.59 4.16E+004 396.58 2.74E+002 F
5 1553-1562 1557.03 778.75 1.17 4.0lE+00l 15.2,7 2.97E+001 F
6 1835-1841-1838.86 919.67 1.17 l.47E+001 10.95 l.51E+001 F
7 1922-1933 1927.22 963.84 1.34 3.69E+001 15.42 3.82E+001 F
8 2339-2352
- 2345.63 1172.96 2.01 4.18E+002 40.96
- 2. 67E+001 F
9 2658-2671 2664.55 1332.28 2,16 4.05E+002 40.56
- 1. 21E+001 F
10. 2809-2821 2815.78 1407.81 1.78 4.62E+001 13.75 1.65E+000 F
11 2914-2928 2921.34 1460.52 2.06 l.16E+002 2i.59 3.63E+000 M = First peak in a multiplet region m = Other peak in a multiplet region F
- Fitted singlet Errors quoted at 2.000 sigma NX-503 Rev. 0 Page 32 of 50
Appendix 3-HBPP Lab Results Interference Corrected Activity Report 2/1/2018 3:53:27 PM Page 4
NUCLIDE I D E N T I F I C A T I O N REPORT Sample Title; NE Caisson Well Nuclide Library Used: C:\\GENIE2K\\CAMFILES\\HBPP Eu3.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV)
(%)
(pCi/g
)
Uncertainty K-40 0.987 1460.81*
10.67 3.95140E+000 7.63516E-001 co-60 0.991 1173.22*
100.00 1.27025E+000 1.40060E-001 1332.49*
100.00 1.36378E+000 1.5496SE-001 Cs-137 0.995 661.65*
85.12 9.34344E+001 5.27621E+000 Eu-152 0.384 121.78* @ 28.40 7.61339E-001 2.11994E-001 344.27 26.50 778.89*
12.74 6.85449E-001 2.63584E-001 964.01*
14.40 6.64030E-001 2.793628-001 1085.78
@ 10.00 1112.02
@ 13.30 1407.95*
20.70 7.86084E-001 2.37699E-001 Bi-214 0.483 609.31*
46.30 2.27552E-001 1.24447E-001 1120.29 15.10 1764.49 15.80
- =Energy line found in the spectrum.
@=Energy line not used for Weighted Mean Activity Energy Tolerance:
1.000 keV Nuclide confidence index threshold=
0.30 Errors quoted at 2.000 sigma NX-503 Rev. 0 Page 33 of 50
Appendix 3 - HBPP Lab Results Interference Corrected Activity Report 2/1/2018 3:53:27 PM Page s
- ~**~****************************l *************
INTERFERENCE CORRECTED RE PI O RT ijuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/g
)
Uncertainty K-40 0.987 3.951404E+OOO 7.635155E-001 co-60 0.991 1.312306E+000 1.039082E-001
/cs-137 0.995 9.343441E+001 S.276213E+000
/Eu-152 0.384 7.190008E-001 l.492276E-001 Bi-214 0.483 2.275518E-001 1.244465E-001
? = 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 IDENTIFIED PE AK S
~F F
Peak No.
2 6
M =
m =
F =
Peak Locate Performed on:
Peak Locate From Channel:
Peak Locat~ To Channel:
Energy (keV) 439.52 919.67
.* ~~~".~£\\:_.
- '"Peak Size in Counts per Second
- 1. SBlBE-001 1.8348E-002 2/1/2018 100 3:53:26 PM 0
- ak CPS tf* Tol.
% Unc*ertainty Type Nuclide 49.50 ~ :!i~- Jt'lt) 74.61
(__:t,:
,.... -,sz.
First peak in a multiplet region Other peak in a multiplet region Fitted singlet
,w\\,J--t-ii Errors quoted at 2.000 sigma "This peak has been ruled out based on the following:
High error I poor FWHM
[3111oplant derived Radionuclide at the delined energy Short nuclide half-life rules out presence Lack of first associated branching ratio ~ammas Initial /fl(~
Date,~l...t:Z:.11<<.:.I.;..;* t::..l-----
NX-503 Rev. O Page 34 of 50
Appendix 3 - HBPP Lah Results Nuclide MDA Report 2/1/2018 3:53:27 PM Page 6
NU CL I D.E MD A REPORT
+
+
+
+
Detector Name:
Sample Geometry:
Sample
Title:
Nuclide Library Used:
Nuclide Name K-40 Co-60 Nb-94 Ag-108m Cs-134*
- Cs-137 Eu-1..$2 _
Eu-154 Eu-155 -
Pb-206 Ac-228 Th-234 U-235 Np-237 Am-241 Energy (keV) 1460.81*
1173.22*
1332.49*
702.63 871.10 79.20 433.93 614.3?
722.95 569.31 604.70
- 795.84 661.65*
!!' *121:. 78*
- 3*44.27 778.89*
964.01*
1085.78 1112.02
_1407.95*
123.07 723.30 87,3,.19 996.32 1004.76 1274.50 105.31 803.10 338.32 911.07 969.11 63.29 92.59 143.76 163.35 185.72 205.31 311. 98 59.54 DET03 NE Caisson Well C:\\GENIE2K\\CAMFILES\\HBPP Eu3.NLB Yield Line MDA Nuclide MDA Activity*
Dec. Level
) (pCi/g
(%)* (pCi/g aaA) (pCi/g
) (pCi/g 10.67 100.00 100.00 100.00 100.00 7.10 89.90
.90.40 90.50 1s : 43
- 97. 60 85.40 85.12 28 ~40
. 26. so 12.74 14.40 10.00 13.30 20.70 40.50 19.70 11.50 10.30 17.90 35.50 20.70 100.00 11.40 27 : 70 16.60 3.80 5.41 10.50 4.70 54.00 4.70 38.60 35.90 4.52E-001 9.48E-002 7.31E-002 6.52E-002 l.03E-001 3.59E+OOO 3.33E-001.
2.07E-001 9.25E-002 1.3'2E+OOO 2.12E-001.
- 9. 75E-:002 1.9SE-001
- 5. 82E-0_01 9.SOE-001 S.07E-001 6.35E-001 l.26E+OOO 9.54E-001 l.64E-001 4.52E-001 4,45E-001 8.12E-001 8.408-001 S.34E-001 2.06E-001 :
8.818-001 9.49E-002 2.09E+OOO 3. 89E-001 6.87E-001 L 05E+001 3.82E+OOO 1.57E+OOO 3.46E+OOO 3.49E-001 4.05E+OOO 5.92E-001 l.40E+OOO 4.52E-001 7.31E.;.002 6.52E-002 9. 25E-002 3.95E+OOO 1.80E-001 l.27E+OOO 4.33E-002 1.36E+OOO 3.20E-002 l.96E-004 2.99E-002 2.30E-002 4.81E-002
-1.35E+OOO l.77E+OOO
-l.72E-002 1 ~6SE-001
-1.228~001 l,OlB-001 8,38E-004 4.32E-002 9.75E-002 --3 ~738-001 6.45E-001
-l.61E-002 l.04E-001
- l,95E-001
- 1. 64E-00lr
- 2.06E-001 8.81E-001 9.49E-002 3.89E-001 3.82E+OOO 3,49E-001 5.928-001 1.40E+OOO
-3.64E~oo2 4.52E-002 9.34E+001 9.42E-002 7.61E-001 2.878-001 1,14E+OOO
- 4,69E-001 6.85E-001 2.308-001 6.64E-001 2.93E-001 1.llE+OOO 5.91E-001 7.SOE-001 4.478-001 7.86E-001 S.88E-002
-1.708-001 2.248-001
. 2.16E-001 2,09E-001
-7.llE-001 3. 788-001
-4.14E-001 3 ; 85E-001
.-3.37E-002
- 2.47E-001
. 4.56E-002 9.04E-002 1.988-001 4.36E-001 6.448-002 4.448-002 4.97E-002 1.03E+OOO 3.47E-001 1.83E-001
-l.29E-001 3.22E-001 6.71E-001 5.17E+OOO 1. 44E+OOO l.89E+OOO 2.78E-001 7.74E-001
-7.47E-001 1.71E+OOO 2.52E-001 1.72E-001
-l.61E+OOO 2.00E+OOO
-l.16E-001 2.92E-001 3.69E-001 6.88E-001
+=Nuclide identified during the nuclide identifi cation
- =Energy line found in the spectrum NX-503 Rev. O Page 35 of 50