ML19295G866

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Revised Final Status Survey (FSS) Report - Phase 2, Release Record - Unit 2 East & West Steam Tunnel Valve Houses Survey Units 06215 & 06216
ML19295G866
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 09/01/2019
From: Montt D
ZionSolutions
To:
Office of Nuclear Material Safety and Safeguards
Shared Package
ML19295G627 List:
References
ZS-2019-0090
Download: ML19295G866 (302)
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Text

ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 PREPARED BY / DATE: 09/01/2019 David Montt, Radiological Engineer REVIEWED BY / DATE: 09/01/2019 Robert Massengill, Radiological Engineer APPROVED BY / DATE: 09/01/2019 D. Wojtkowiak, C/LT Manager

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

................................................................................................ 7

2. SURVEY UNIT DESCRIPTION ...................................................................................... 8
3. CLASSIFICATION BASIS ............................................................................................. 11
4. DATA QUALITY OBJECTIVES (DQO) ...................................................................... 12
5. SURVEY DESIGN ........................................................................................................... 15
6. SURVEY IMPLEMENTATION .................................................................................... 20
7. SURVEY RESULTS ........................................................................................................ 21
8. QUALITY CONTROL .................................................................................................... 28
9. INVESTIGATION AND RESULTS .............................................................................. 28
10. REMEDIATION AND RESULTS.................................................................................. 29
11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ...................................... 29
12. DATA QUALITY ASSESSMENT (DQA) ..................................................................... 29
13. ANOMALIES ................................................................................................................... 29
14. CONCLUSION ................................................................................................................. 29
15. REFERENCES ................................................................................................................. 30
16. ATTACHMENTS ............................................................................................................. 31 ATTACHMENT 1 SURVEY UNIT MAPS ..............................................................................32 ATTACHMENT 2 ISOCS GEOMETRY................................................................................35 ATTACHMENT 3 QC MEASUREMENT ASSESSMENTS .......................................................42 ATTACHMENT 4 EBERLINE REPORT.................................................................................45 ATTACHMENT 5 ISOCS ANALYTICAL REPORTS .............................................................46 70

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 LIST OF FIGURES Figure 1 - Unit 2 East and 2 West Main Steam Valve Houses ....................................................... 9 Figure 2 - Unit 2 East Main Steam Valve House Detail ............................................................... 10 Figure 3 - Unit 2 West Main Steam Valve House Detail ............................................................. 11 Figure 4 - Unit 2 East Main Steam Valve House ISOCS Survey and Sample Map ..................... 22 Figure 5 - Unit 2 West Main Steam Valve House ISOCS Survey and Sample Map ................... 23 LIST OF TABLES Table 1 - Dose Significant Radionuclides and Mixture ................................................................ 13 Table 2 - Base Case DCGLs (BcDCGLB) from LTP Chapter 5, Table 5-3 ................................. 14 Table 3 - Operational DCGLs (OpDCGLB) from LTP Chapter 5, Table 5-4............................... 15 Table 4 - Surrogate Ratios ............................................................................................................ 17 Table 5 - Investigation Levels....................................................................................................... 18 Table 6 - Synopsis of the Survey Design ...................................................................................... 19 Table 7 - Unit 2 East Main Steam Valve House - ISOCS Results for FSS .................................. 24 Table 8 - Basic Statistical Properties of ISOCS Measurements in the Unit 2 East Main Steam Valve House ........................................................................................... 24 Table 9 - Unit 2 West Main Steam Valve House- ISOCS Results for FSS .................................. 25 Table 10 - Basic Statistical Properties of ISOCS Measurements in the Unit 2 West Main Steam Valve House ........................................................................................... 26 Table 11 - FSS Concrete Core Taken in East Main Steam Valve House Analysis by Eberline .. 27 Table 12 - FSS Concrete Core Taken in West Main Steam Valve House Analysis by Eberline . 27 Table 13 - Summary of ISOCS Replicate Measurements for QC Unit 2 East Valve House ....... 28 Table 14 - Summary of ISOCS Replicate Measurements for QC Unit 2 West Valve House ...... 28

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 LIST OF ACRONYMS AND ABBREVIATIONS ALARA As Low As Reasonably Achievable AMCG Average Member of the Critical Group BcDCGL Base Case Derived Concentration Guideline Level BcSOF Base Case Sum of Fractions BFM Basement Fill Model DQA Data Quality Assessment DQO Data Quality Objective DCGL Derived Concentration Guideline Level EMC Elevated Measurement Comparison FOV Field of View FSS Final Status Survey GW Groundwater HTD Hard-to-Detect HSA Historical Site Assessment IC Insignificant Contributor ISOCS In Situ Object Counting System LTP License Termination Plan LBGR Lower Bound of the Gray Region MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration OpDCGL Operational Derived Concentration Guideline Level OpSOF Operational Sum of Fractions QAPP Quality Assurance Project Plan

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 QC Quality Control RE Radiological Engineer ROC Radionuclides of Concern SOF Sum of Fractions TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region UCL Upper Confidence Level ZNPS Zion Nuclear Power Station ZSRP Zion Station Restoration Project

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey units 06215 and 06216, Unit 2 East and West Steam Tunnel Valve Houses, was generated for the Zion Station Restoration Project (ZSRP) in accordance with ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting (Reference 1) and satisfies the requirements of Section 5.11 of the Zion Station Restoration Project License Termination Plan (LTP) (Reference 2).

The FSS Sample Plans for survey units 06215 and 06216 were developed in accordance with ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development (Reference 3) the ZSRP LTP, and guidance from NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Reference 4).

Final Status Survey was performed on the Unit 2 East and West Steam Tunnel Valve Houses to demonstrate that the concentrations of residual radioactivity were equal to or below site-specific Derived Concentration Guideline Levels (DCGL) corresponding to the dose criterion in 10 CFR 20.1402. In accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 and Table 5-19, the Turbine Building survey unit has a MARSSIM classification of 3. Though both Unit 2 Valve houses were Class 3 survey units, 100% of all surface areas were surveyed during FSS.

A Sample Plan was designed based upon use of the Sign Test as the nonparametric statistical test for compliance. Both the Type I () and Type II () decision error rates were set at 0.05. The Canberra In Situ Object Counting System (ISOCS) and was selected as the primary instrument used to perform FSS. To ensure 100% of the surface area was surveyed in accordance with the classification, twenty (20) ISOCS measurement locations were selected in each Valve House (for a total of 40 measurements) using several adjusted Field of View (FOV) geometries as specified in ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures (Reference 5).

The results of the FSS showed that the Operational Sum of Fractions (OpSOF) for all 40 ISOCS measurements taken was less than one (1) when applying the respective Operational DCGL (OpDCGL) from ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey (Reference 6) for the Turbine Building basement. Of the forty (40) measurements taken, none exceeded a OpSOF of 0.5. The mean concentration for each ROC was below the Base Case DCGL (BcDCGL).

As all measurements were less than the OpDCGL, the Sign Test was not performed. The null hypothesis is rejected and the Unit 2 East and West Steam Tunnel Valve Houses are acceptable for unrestricted release.

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

2. SURVEY UNIT DESCRIPTION Both the Unit 2 East and West Steam Tunnel Valve Houses were located on the 570 foot elevation and housed the East and West Main Steam Valves. The Valve Houses were adjacent to each of the Containment buildings (see Figures 1, 2 and 3) on the East and West sides of Unit 2 were a mirror image of the footprint for Unit 1 Valve Houses (see Figure 1). The entrances into the Unit 2 East and West Steam Tunnel Valve Houses were from each of the Main Steam Tunnels leading to each respective containment structure Valve Houses at the Turbine Building 570 foot elevation. (See Figures 1, 2 and 3) The surface area of each of the Unit 2 Valve House structural survey units is 240 m2. The Unit 2 Valve House surface area is slightly less than the Unit 1 Valve Houses as the middle wall, common to both unit Valve Houses, was removed in the Unit 2 Valve Houses.

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Figure 1 - Unit 2 East and 2 West Main Steam Valve Houses Unit 1 West MS Unit 2 West MS Valve House Valve House Unit 1 East MS Unit 2 East MS Valve House Valve House North

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Figure 2 - Unit 2 East Main Steam Valve House Detail Unit 2 East MS Valve House

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Figure 3 - Unit 2 West Main Steam Valve House Detail Unit 2 West MS Valve House 2

3. CLASSIFICATION BASIS Survey unit 06100 (Turbine Building) was classified in accordance with ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 7). In accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 and Table 5-19, the Turbine Building survey unit was assigned a MARSSIM classification of 3. In April, 2016, an FSS was conducted on the Turbine Building basement structure. The surface area of the Unit 2 East and West Steam Tunnel Valve Houses was included with the Turbine Building for the DCGL calculation however, the surface area was not included in the FSS of the Turbine Building basement. In addition, the demolition of the Valve Houses occurred two years after the demolition of the Turbine Building basement. Consequently, a separate FSS was required of the Valve Houses prior to backfill.

The Unit 2 East and West Steam Tunnel Valve Houses were classified, as the Turbine Building, in accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 as a Class 3 survey unit. A final classification assessment was performed in accordance with procedure ZS-LT-300-001-002 as part of the survey design for FSS. Upon completion of Survey Unit Classification basis for final classification, which included a review of the Zion Station Historical Site Assessment (HSA) (Reference 8), the classification for survey design remained as Class 3.

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 The FSS Radiological Engineer (RE) performed a visual inspection and walk-down of the survey units on 04/19/2018 prior to performing FSS. The purpose of the walk-downs was to evaluate and assess the physical condition of the survey unit, access points, travel paths and identify potentially hazardous conditions.

4. DATA QUALITY OBJECTIVES (DQO)

Final Status Survey planning and design hinges on coherence with the Data Quality Objective (DQO) process to ensure, through compliance with explicitly defined inputs and boundaries, that the primary objectives of the survey is satisfied. The DQO process is described in the ZSRP LTP. The appropriate design for a given survey is developed using the DQO process as outlined in Appendix D of MARSSIM.

The DQO process incorporated hypothesis testing and probabilistic sampling distributions to control decision errors during data analysis. Hypothesis testing is a process based on the scientific method that compares a baseline condition to an alternate condition. The baseline condition is technically known as the null hypothesis.

Hypothesis testing rests on the premise that the null hypothesis is true and that sufficient evidence must be provided for rejection. In designing the survey plan, the underlying assumption, or null hypothesis was that residual activity in the survey unit exceeded the release criteria. Rejection of the null hypothesis would indicate that residual activity within the survey unit does not exceed the release criteria. Therefore, the survey unit would satisfy the primary objective of the FSS sample plan.

The primary objective of the FSS sample plan is to demonstrate that the level of residual radioactivity in survey units 06215 and 06216 did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).

ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of the Zion Station (Reference 9) established the basis for an initial suite of potential ROC for the decommissioning of the Zion Nuclear Power Station (ZNPS). LTP Chapter 2 provides detailed characterization data that described contamination levels in the basements. Concrete core samples, collected during characterization surveys, were obtained at biased locations where there were elevated contact dose rates and/or evidence of leaks/spills. The collected core samples were analyzed for the presence of plant-derived radionuclides.

LTP Chapter 6, section 6.5.2 discusses the process used to derive the ROC for the decommissioning of ZNPS, including the elimination of insignificant dose contributors (IC) from the initial suite. LTP section 6.5.2 also states that the Auxiliary Building basement ROC and the IC percentage of 5% for adjusting ROC DCGLs will also be applied to all other Basements including those for the Main Steam Valve Houses unless

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 different values are justified by the results of continuing characterization or FSS HTD analysis. Table 1 presents the ROC for the Auxiliary Building basement and, therefore, the Valve House structural surfaces and the normalized fractions based on the radionuclide mixture.

Table 1 - Dose Significant Radionuclides and Mixture

% of Total Activity Radionuclide (normalized)(1)

Co-60 0.92%

Cs-134 0.01%

Cs-137 75.32%

Ni-63 23.71%

Sr-90 0.05%

(1) Based on maximum percent of total activity from Table 20 of TSD 14-019, normalized to one for the dose significant radionuclides.

A fundamental precursor to survey design is to establish a relationship between the release criteria and some measurable quantity. This is done through the development of DCGLs. The DCGLs represent average levels of radioactivity above background levels and are presented in terms of surface or mass activity concentrations. Chapter 6 of the LTP describes in detail the modeling used to develop the DCGLs for structures.

The End State basements will be comprised of steel and/or concrete structures which will be covered by at least three feet of clean soil and physically altered to a condition which would not realistically allow the remaining structures, if excavated, to be occupied. The exposure pathways in the Basement Fill Model (BFM) are associated with residual radioactivity in floors and walls released through leaching into water contained in the interstitial spaces of the fill material. The BFM assumes that the inventory of residual radioactivity in a given building is released either instantly or over time by diffusion, depending on whether the activity is surficial or volumetric, respectively. The activity released into the fill water will adsorb onto the clean fill, as a function of the radionuclide-specific distribution coefficients, resulting in equilibrium concentrations between the fill and the water. Consequently, the only potential exposure pathways after backfill, assuming the as-left geometry, are associated with the residual radioactivity in the water contained in the fill.

The final outputs of the BFM are the basement DCGL, in units of pCi/m2, which are calculated using the BFM Groundwater (GW) and BFM Drilling Spoils Dose Factors (LTP Chapter 6, Tables 6-24 and 6-25). The DCGLs for basement structure surfaces are calculated separately for the GW and Drilling Spoils scenarios and for the summation of both scenarios. The summation DCGL is designated as the BcDCGL and is used during

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 FSS to demonstrate compliance (analogous to the DCGLW as defined in MARSSIM).

The BcDCGLs are radionuclide-specific concentrations that represent the 10 CFR 20.1402 dose criterion of 25 mrem/year and are calculated for each ROC and each backfilled Basement.

When applied to structures, the DCGLs are expressed in units of activity per unit of area (pCi/m2). The unity rule is applied when there is more than one ROC. The measurement results for each singular ROC present in the mixture are compared against their respective DCGL to derive a dose fraction.

The BcDCGLs for the unrestricted release of the Turbine Building (including the Main Steam Valve houses) are provided in Table 2. The IC dose percentage of 5% was used to adjust the Turbine Building BcDCGLs to account for the dose from the eliminated IC radionuclides.

Table 2 - Base Case DCGLs (BcDCGLB) from LTP Chapter 5, Table 5-3 Turbine Building Radionuclide BcDCGLB (pCi/m2)

Co-60 7.03E+07 Ni-63 2.18E+09 Sr-90 7.74E+05 Cs-134 1.59E+07 Cs-137 2.11E+07 Each radionuclide-specific BcDCGL is equivalent to the level of residual radioactivity (above background levels) that could, when considered independently, result in a Total Effective Dose Equivalent (TEDE) of 25 mrem per year to an Average Member of the Critical Group (AMCG). To ensure that the summation of dose from each source term is 25 mrem/yr or less after all FSS is completed, the BcDCGLs are reduced based on an expected, or a priori, fraction of the 25 mrem/year dose limit from each source term. The reduced DCGLs, or Operational DCGLs can be related to the BcDCGLs as an expected fraction of dose based on an a priori assessment of what the expected dose should be based on the results of site characterization, process knowledge and the extent of planned remediation. The OpDCGL is then used as the DCGL for the FSS design of the survey unit (calculation of surrogate DCGLs, investigations levels, etc.). Details of the OpDCGLs derived for each dose component and the basis for the applied a priori dose fractions are provided in TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey. The OpDCGLB for FSS of the Unit 2 East and West Valve Houses are provided in Table 3.

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Table 3 - Operational DCGLs (OpDCGLB) from LTP Chapter 5, Table 5-4 Turbine Building Radionuclide DCGLB (pCi/m2)

Co-60 5.98E+06 Ni-63 1.85E+08 Sr-90 6.58E+04 Cs-134 1.35E+06 Cs-137 1.79E+06 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the OpDCGL.

The ISOCS was selected as the primary instrument used to perform FSS of basement surfaces due to the fact that an ISOCS measurement will provide results that can be used directly to determine total activity with depth in concrete and, the surface area covered by a single ISOCS measurement is large (a nominal FOV of 10-30 m2) which essentially eliminates the need for a scan surveys. In addition, after an ISOCS measurement is collected, it can be tested against a variety of geometry assumptions to address uncertainty in the source term geometry if necessary. Response checks were required prior to issuance and after each use. Control and accountability of ISOCS units was required to assure data quality.

As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual recorded value was used as the recorded FSS result for measurement and/or sample values that are less than Minimum Detectable Concentration (MDC). Negative values were recorded as zero. For radionuclides less than MDC, the value representing the highest abundance was selected. Results were not reported as less than MDC. Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC.

In accordance with the LTP for laboratory analysis, MDCs less than 10% of the OpDCGL were preferable while MDCs up to 50% of the OpDCGL were acceptable. The maximum acceptable MDC for measurements obtained using field instruments was 50%

of the applicable OpDCGL.

5. SURVEY DESIGN Guidance for preparing FSS plans was provided in procedure ZS-LT-300-001-001. The source term geometry for ISOCS efficiency calibration, (i.e., concentration depth profile

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 and areal distribution of the residual radioactivity in structures), is required to generate efficiency curves (i.e., efficiency as a function of energy) for the ISOCS gamma spectroscopy measurements. The ISOCS efficiency calibration basis chosen for the FSS of the Main Steam Valve Houses concrete are documented in ZionSolutions TSD 14-022.

The ISOCS geometry utilized for the Main Steam Valve Houses employed a 28 m2 FOV.

A second geometry employing a 2.5 meter stand-off was also used. The selection of this latter geometry was necessitated in situations where there was limited accessibility due to structural constraints.

Sample size determination for the FSS of Turbine Building basement is addressed in LTP Chapter 5, section 5.5.2.2. The surface areas of the Main Steam Valve Houses were not originally included in the Turbine Building basement survey unit. Consequently, the weighted average of the ISOCS measurements taken in the Main Steam Valve Houses will be added to the systematic mean of the Turbine Building Basement FSS. This is addressed in LTP Chapter 5, section 5.5.6.1. The total basement area used in the weighted average calculation is the adjusted surface area used to calculate the DCGLs in LTP Chapter 6, section 6.6.8. The adjusted area for the Turbine Building from LTP Chapter 5, Table 5-23 is 27,135 m2. In accordance with TSD 14-014, End State Surface Areas, Volumes, and Source Terms of Ancillary Buildings (Reference 10), the total surface area of each of the two Unit 2 Main Steam Valve Houses is 240 m2.

This sample plan for each of the Unit 2 East and West Main Steam Valve Houses consisted of twenty (20) judgmental measurement/sample locations, ensuring 100% areal coverage of the surface area. Figures 4 and 5 in this record, and in Attachment 1, Survey Unit Maps, illustrate the locations of the ISOCS measurements taken.

The DQO process determined that Co-60, Ni-63, Sr-90, Cs-134, Cs-137 would be the ROC in survey units 06215 and 06216. During FSS, concentrations of Hard-to-Detect (HTD) ROC Ni-63 and Sr-90 are inferred using a surrogate approach as specified in LTP section 5.2.11. Cs-137 is the principle surrogate radionuclide for Sr-90 and Co-60 is the principle surrogate radionuclide for Ni-63. The mean, maximum and 95% Upper Confidence Level (UCL) of the surrogate ratios were calculated from Auxiliary Building basement concrete core sample analytical results collected and presented in TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms (Reference 11) and LTP Chapter 5, Table 5-15, which is reproduced in Table 4 below.

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Table 4 - Surrogate Ratios Auxiliary Building Ratios Mean Max 95%UCL Ni-63/Co-60 44.143 180.450 154.632 Sr-90/Cs-137 0.001 0.002 0.002 For the FSS of survey units 06215 and 06216, the surrogate OpDCGLs for Co-60 and Cs-137 are based on the maximum ratios from Table 4.

Equation 1 1

=

1 2 3

+ + +

2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the OpDCGLs for the Turbine Building presented in Table 3 and the maximum ratios from Table 4, the following surrogate calculations were performed for FSS units 06215 and 06216; Equation 2 1

(137) = = 1.70 + 06 /2 1 0.002

+

1.79 + 06(137) 6.58 + 04(90)

The surrogate OpDCGL that was used for Cs-137 in FSS units 06215 and 06216 for direct comparison of sample results to demonstrate compliance is 1.70E+06 Ci/m2.

Equation 3 1

(60) = = 8.75 + 05 /2 1 180.45

+

5.98 + 06(60) 1.85 + 08(63)

The surrogate OpDCGL that was used for Co-60 in FSS units 06215 and 06216 for direct comparison of sample results to demonstrate compliance is 8.75E+05 Ci/m2.

For these Class 3 basement structure survey units, the Investigation Levels for ISOCS measurement results are those levels specified in LTP Chapter 5, Table 5-25 and are reproduced below in Table 5.

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Table 5 - Investigation Levels Classification Direct Investigation Levels Class 3 >0.5 Operational DCGLW In compliance with ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS) (QAPP) (Reference 12), replicate measurements were to be performed on 5%

of the static measurement locations.

Table 6 provides a synopsis of the survey design for survey units 06215 and 6216.

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Table 6 - Synopsis of the Survey Design FEATURE DESIGN CRITERIA BASIS Survey Unit Area 240 m2 LTP Ch. 5, Table 5-23

  • = 0.3
  • UBGR = SOF of 1
  • LBGR = SOF of 0.5 Number of Static 20 (judgmental)
  • Type I error = 0.05 Measurements
  • Type II error = 0.05
  • / = 3 (adjusted)

MARSSIM Table 5-5 100% Areal Coverage Measurement Spacing LTP Chapter 5, Sec. 5.5.2.2 (Planned for 28 m2 FOV)

  • Co 5.98E+06 pCi/m2 Operational DCGLs for Turbine
  • Ni 1.85E+08 pCi/m2 Building Basement OpDCGLB
  • Sr 6.58E+04 pCi/m2 Unit 2 East and West Main Steam
  • Cs-134 - 1.35E+06 pCi/m2 Valve House, (LTP Chapter 5,
  • Cs-137 - 1.79E+06 pCi/m2 Table 5-4) 2 Concrete Core samples selected for HTD HTD ROC Analysis (LTP Chapter 5, section 5.1)

ROC analysis Measurement

>Operational DCGLW (LTP Chapter 5, Table 5-25)

Investigation Level Scan Survey Area ZS-LT-300-001-001, 240 m2 100% areal scan coverage Coverage Attachment 1 QC 5% Duplicate ISOCS Measurements (LTP Chapter 5, section 5.9)

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

6. SURVEY IMPLEMENTATION For the judgmental measurements performed in this survey units 06215 and 06216, compliance with the unrestricted release criteria was demonstrated through a combination of direct measurements using the ISOCS and analysis of concrete core samples obtained from the Main Steam Valve Houses. The concrete core data was used to validate the ratios of gamma emitters to HTD ROC.

A walk down was performed by FSS personnel on 04/18/18. A turnover survey and groundwater pump out was required to permit acceptance of the Main Steam Valve House survey units for FSS. Characterization data from 2012 and 2013, including ten (10) concrete core samples did not identify any conditions precluding turnover, however turnover surveys were utilized to confirm demolition work in the area had not altered conditions. The Main Steam Valve House was deemed acceptable for turnover and FSS commenced on 04/19/18.

Field Logs (ZS-LT-300-001-001 Attachment 14) were used to document field activities and other information pertaining to the performance of the FSS. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job.

ZionSolutions TSD 14-022 provides the initial justification for the selection of reasonably conservative geometries and efficiency calibrations for the ISOCS based on the physical conditions of the remediated surface and the anticipated depth and distribution of activity.

All ISOCS measurements were acquired using an approved geometry. One source to detector distance was utilized to ensure 100% measurement coverage. The primary ISOCS geometry utilized was 3M90D_CP_2IN, and is described in detail in Attachment 2.

The ISOCS detector was positioned horizontally or vertically to the surface at the center-point of each selected measurement location. The exposed face of the detector was positioned at a distance of 3 meters from the surface with the 90-degree collimation shield installed; this orientation corresponded to a nominal FOV of 28 m2 for walls.

The measured activity for each gamma-emitting ROC (and any other gamma-emitting radionuclides positively detected by ISOCS) was recorded in units of pCi/m2.

Background was not subtracted from any measurement. An OpSOF calculation was performed for each measurement by dividing the reported concentration of each ROC by the OpDCGL for each ROC to derive an individual ROC fraction. The individual ROC fractions were then summed to provide a total OpSOF value for the measurement.

One (1) duplicate measurement was taken with the ISOCS on each of the two Unit 2 Valve Houses during FSS. The locations selected for duplicate measurements were at location 018 in the East Valve House, and at location 003 in the West Valve House.

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FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 These locations were randomly selected using the Microsoft Excel RANDBETWEEN function. The number of replicate measurements satisfies the requirement that a minimum of 5% percent of the number of measurements that will be used for duplicate samples in accordance with the QAPP.

7. SURVEY RESULTS The SOF or unity rule was applied to the data used for the survey planning, data evaluation and statistical tests for basement surfaces since multiple radionuclide-specific measurements were performed and concentrations inferred based on known relationships.

The application of the unity rule served to normalize the data to allow for an accurate comparison of the various data measurements to the release criteria. When the unity rule was applied, the DCGLw (used for the nonparametric statistical test) becomes one (1).

The BcDCGLB is directly analogous to the DCGLW as defined in MARSSIM. The use and application of the unity rule was performed in accordance with section 4.3.3 of MARSSIM.

As previously stated, as the extent of this survey was the acquisition of judgmental measurements at biased locations, compliance was demonstrated by direct comparison of each measurement result to the release criterion. For building surfaces, areas of elevated activity are defined as any area identified by measurement/sample (systematic or judgmental) that exceeded the OpDCGL but was less than the BcDCGL. Any area that exceeded the BcDCGL would have required remediation. No measurement taken during the FSS of the Unit 2 East and West Steam Tunnel Valve Houses exceeded the OpDCGLs. Additionally, as the Unit 2 East and West Steam Tunnel Valve Houses are classified as Class 3, no measurement exceeded an OpSOF of 0.5, which would have required an investigation and possible reclassification.

The sample population consisted of twenty (20) direct measurements for each of the Unit 2 Valve houses acquired using the ISOCS. The concentrations for Ni-63 and Sr-90 are inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15. The complete ISOCS gamma spectroscopy reports are presented in Attachment 5. The ISOCS measured concentration results from the Unit 2 East Valve House are listed in Table 7.

Direct measurement locations were denoted on the concrete surfaces of the Unit 2 East and West Valve Houses by marking an approximate 4 meter by 4 meter grid pattern using a random start point that was overlaid over the exposed surface, providing sufficient overlap between locations to ensure 100% areal coverage. ISOCS measurement locations are shown below in Figures 4 and 5 as well as in Attachment 1.

[21]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Figure 4 - Unit 2 East Main Steam Valve House ISOCS Survey and Sample Map

[22]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Figure 5 - Unit 2 West Main Steam Valve House ISOCS Survey and Sample Map

[23]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Table 7 - Unit 2 East Main Steam Valve House - ISOCS Results for FSS Co-60 Ni-63(1) Sr-90(1) Cs-134 Cs-137 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B3-6215A-FSFC-001-GD 2.36E+04 4.26E+06 1.73E+01 6.54E+04 8.63E+03 0.080 B3-6215A-FSFC-002-GD 6.14E+04 1.11E+07 2.12E+02 4.83E+04 1.06E+05 0.168 B3-6215A-FSFC-003-GD 0.00E+00 0.00E+00 1.10E+03 2.61E+03 5.52E+05 0.327 B3-6215A-FSFC-004-GD 2.98E+04 5.38E+06 3.92E+02 0.00E+00 1.96E+05 0.150 B3-6215A-FSWC-005-GD 5.33E+03 9.62E+05 0.00E+00 4.72E+04 0.00E+00 0.041 B3-6215A-FSWC-006-GD 1.07E+03 1.93E+05 1.38E+02 6.07E+04 6.88E+04 0.087 B3-6215A-FSWC-007-GD 2.56E+04 4.62E+06 5.48E+01 8.07E+04 2.74E+04 0.105 B3-6215A-FSWC-008-GD 2.84E+04 5.12E+06 8.42E+01 1.20E+04 4.21E+04 0.066 B3-6215A-FSWC-009-GD 1.62E+04 2.92E+06 8.78E+01 6.44E+04 4.39E+04 0.092 B3-6215A-FSWC-010-GD 1.29E+03 2.33E+05 2.72E+02 6.14E+04 1.36E+05 0.127 B3-6215A-FSWC-011-GD 3.98E+04 7.18E+06 1.85E+00 3.27E+04 9.23E+02 0.070 B3-6215A-FSWC-012-GD 7.55E+03 1.36E+06 8.92E+00 3.03E+04 4.46E+03 0.034 B3-6215A-FSWC-013-GD 1.77E+04 3.19E+06 1.21E+02 5.29E+04 6.07E+04 0.095 B3-6215A-FSWC-014-GD 8.46E+03 1.53E+06 3.30E+01 7.55E+04 1.65E+04 0.075 B3-6215A-FSWC-015-GD 3.69E+04 6.66E+06 0.00E+00 5.04E+04 0.00E+00 0.079 B3-6215A-FSWC-016-GD 1.71E+04 3.09E+06 0.00E+00 1.77E+04 0.00E+00 0.033 B3-6215A-FSWC-017-GD 0.00E+00 0.00E+00 1.59E+02 4.68E+04 7.94E+04 0.081 B3-6215A-FSWC-018-GD 2.03E+03 3.66E+05 1.92E+01 8.05E+04 9.62E+03 0.068 B3-6215A-FSWC-019-GD 2.03E+04 3.66E+06 0.00E+00 5.10E+04 0.00E+00 0.061 B3-6215A-FSWC-020-GD 4.00E+04 7.22E+06 5.72E+01 3.55E+04 2.86E+04 0.089 (1) Concentrations are inferred Twenty (20) ISOCS measurements were taken in the Unit 2 East Main Steam Valve House. No measurement exceeded a OpSOF of one. The mean OpSOF was 0.096 and the max OpSOF was 0.327.

In order to assess the dose contribution from the Unit 2 East Main Steam Valve House, the concentration of each ROC in each judgmental measurement was also compared against the respective Base Case DCGLs. The calculation of the mean BcSOF for the Unit 2 East Main Steam Valve House and the resultant dose is presented in Table 8.

Table 8 - Basic Statistical Properties of ISOCS Measurements in the Unit 2 East Main Steam Valve House Individual Measurement Metrics Total Number of Systematic Measurements = 20 Number of Quality Control Measurements = 1 Number of Judgmental/Investigational Measurements = 0 Total Number of Measurements = 21 Mean Systematic Measurement OpSOF = 0.096 Max Individual Systematic Measurement OpSOF = 0.327 Number of Systematic Measurements with OpSOF >1 = 0

[24]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Table 8 (continued) - Basic Statistical Properties of ISOCS Measurements in the Unit 2 East Main Steam Valve House Statistical Quantities - Systematic Measurement Population Mean Median Max Min BcDCGL Avg. SOF Avg. Dose ROC Std. Dev.

(pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) per ROC Per ROC Co-60 1.91E+04 1.74E+04 6.14E+04 0.00E+00 1.68E+04 7.03E+07 0.000 0.007 Ni-63 3.45E+06 1.71E+04 1.11E+07 0.00E+00 3.03E+06 2.18E+09 0.002 0.040 Sr-90 1.38E+02 5.60E+01 1.10E+03 0.00E+00 2.50E+02 7.74E+05 0.000 0.004 Cs-134 4.58E+04 4.94E+04 8.07E+04 0.00E+00 2.41E+04 1.59E+07 0.003 0.072 Cs-137 6.91E+04 2.80E+04 5.52E+05 0.00E+00 1.25E+05 2.11E+07 0.003 0.082 The mean BcSOF from measurements taken on basement structural surfaces in the Unit 2 East Main Steam Valve House is 0.008. This is derived by summing the average BcSOF per ROC resulting from the average concentration in Table 8. The mean BcSOF equates to a dose of 0.205 mrem/yr.

The ISOCS measured concentration results from the Unit 2 West Valve House are listed in Table 9.

Table 9 - Unit 2 West Main Steam Valve House- ISOCS Results for FSS Co-60 Ni-63(1) Sr-90(1) Cs-134 Cs-137 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B3-6216A-FSFC-001-GD 2.02E+04 3.65E+06 1.57E+02 2.30E+04 7.84E+04 0.086 B3-6216A-FSFC-002-GD 2.89E+04 5.22E+06 7.28E+02 7.57E+04 3.64E+05 0.304 B3-6216A-FSFC-003-GD 1.07E+03 1.93E+05 5.80E+02 5.38E+04 2.90E+05 0.212 B3-6216A-FSFC-004-GD 2.27E+04 4.10E+06 2.10E+02 7.09E+04 1.05E+05 0.140 B3-6216A-FSWC-005-GD 9.63E+03 1.74E+06 6.96E+01 0.00E+00 3.48E+04 0.032 B3-6216A-FSWC-006-GD 2.98E+04 5.38E+06 1.35E+02 2.25E+04 6.75E+04 0.090 B3-6216A-FSWC-007-GD 4.14E+04 7.47E+06 6.00E+01 2.81E+04 3.00E+04 0.086 B3-6216A-FSWC-008-GD 3.55E+04 6.41E+06 1.75E+01 5.56E+03 8.73E+03 0.050 B3-6216A-FSWC-009-GD 0.00E+00 0.00E+00 6.38E+01 3.61E+04 3.19E+04 0.046 B3-6216A-FSWC-010-GD 1.42E+04 2.56E+06 1.66E+01 3.60E+04 8.32E+03 0.048 B3-6216A-FSWC-011-GD 2.17E+04 3.92E+06 8.24E+01 4.19E+04 4.12E+04 0.080 B3-6216A-FSWC-012-GD 3.97E+03 7.16E+05 6.12E+01 3.75E+04 3.06E+04 0.050 B3-6216A-FSWC-013-GD 2.98E+04 5.38E+06 2.98E+01 2.07E+03 1.49E+04 0.044 B3-6216A-FSWC-014-GD 6.80E+03 1.23E+06 5.04E+01 3.85E+04 2.52E+04 0.051 B3-6216A-FSWC-015-GD 3.55E+04 6.41E+06 3.60E+01 5.61E+04 1.80E+04 0.093 B3-6216A-FSWC-016-GD 2.68E+04 4.84E+06 1.36E+02 3.86E+04 6.79E+04 0.099 B3-6216A-FSWC-017-GD 0.00E+00 0.00E+00 6.52E+02 7.90E+04 3.26E+05 0.251 B3-6216A-FSWC-018-GD 2.27E+04 4.10E+06 3.42E+01 7.48E+04 1.71E+04 0.091 B3-6216A-FSWC-019-GD 0.00E+00 0.00E+00 5.30E+01 3.38E+04 2.65E+04 0.041 B3-6216A-FSWC-020-GD 3.91E+03 7.06E+05 8.06E+02 6.22E+04 4.03E+05 0.288 (1) Concentrations are inferred

[25]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Twenty (20) ISOCS measurements were taken in the Unit 2 West Main Steam Valve House. Of the 20 measurements taken, no measurement exceeded a OpSOF of 0.5. The mean OpSOF was 0.109 and the max OpSOF was 0.304.

In order to assess the dose contribution from the Unit 2 West Main Steam Valve House, the concentration of each ROC in each judgmental measurement was also compared against the respective Base Case DCGLs. The calculation of the mean BcSOF for the Unit 2 West Main Steam Valve House and the resultant dose is presented in Table 10.

Table 10 - Basic Statistical Properties of ISOCS Measurements in the Unit 2 West Main Steam Valve House Individual Measurement Metrics Total Number of Systematic Measurements = 20 Number of Quality Control Measurements = 1 Number of Judgmental/Investigational Measurements = 0 Total Number of Measurements = 21 Mean Systematic Measurement OpSOF = 0.109 Max Individual Systematic Measurement OpSOF = 0.304 Number of Systematic Measurements with OpSOF >1 = 0 Statistical Quantities - Systematic Measurement Population Mean Median Max Min BcDCGL Avg. SOF Avg. Dose ROC Std. Dev.

(pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) per ROC Per ROC Co-60 1.77E+04 2.10E+04 4.14E+04 0.00E+00 1.37E+04 7.03E+07 0.000 0.006 Ni-63 3.20E+06 3.78E+06 7.47E+06 0.00E+00 2.47E+06 2.18E+09 0.001 0.037 Sr-90 1.99E+02 6.67E+01 8.06E+02 1.66E+01 2.60E+02 7.74E+05 0.000 0.006 Cs-134 4.08E+04 3.80E+04 7.90E+04 0.00E+00 2.40E+04 1.59E+07 0.003 0.064 Cs-137 9.95E+04 3.34E+04 4.03E+05 8.32E+03 1.30E+05 2.11E+07 0.005 0.118 The mean BcSOF from measurements taken on basement structural surfaces in the Unit 2 East Main Steam Valve House is 0.009. This is derived by summing the average BcSOF per ROC resulting from the average concentration in Table 10. The mean BcSOF equates to a dose of 0.231 mrem/yr.

Four (4) concrete core samples, two (2) for each Valve House, were acquired at 10% of the locations where ISOCS measurements were collected with the locations selected at random. The first top 1/2 inch puck from each concrete core sample, representing the concrete from the exposed surface to a depth of 1/2 inch were analyzed, were counted at an off-site laboratory (Eberline) for gamma emitters and HTDs to confirm the surrogate ROCs.

[26]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 The results of the analysis of concrete core samples taken in the Unit 2 East Main Steam Valve House is presented in Table 11 below.

Table 11 - FSS Concrete Core Taken in East Main Steam Valve House Analysis by Eberline B3-6215A-FSFC-003-CV ROC Result Uncertainty MDC (pCi/g) (pCi/g) (pCi/g)

Co-60 0.00E+00 9.77E-02 1.51E-01 Ni-63 1.35E+00 1.10E+00 1.83E+00 Sr-90 2.43E-01 2.64E-01 5.38E-01 Cs-134 0.00E+00 8.07E-02 1.73E-01 Cs-137 7.00E+01 7.39E+00 7.81E-01 B3-6215A-FSWC-013-CV ROC Result Uncertainty MDC (pCi/g) (pCi/g) (pCi/g)

Co-60 1.98E-01 7.80E-02 1.67E-01 Ni-63 1.03E+00 1.00E+00 1.68E+00 Sr-90 3.47E-01 2.20E-01 4.32E-01 Cs-134 0.00E+00 2.86E-02 9.06E-02 Cs-137 3.51E-01 1.27E-01 1.83E-01 In the two concrete core samples taken in the Unit 2 East Valve House, one or more of each ROC (Co-60, Ni-63, Sr-90, Cs-137) was less than MDC. Consequently, there was no compelling evidence to challenge the HTD ratios specified in the LTP and presented in Table 4.

The results of the analysis of concrete core samples taken in the Unit 2 West Main Steam Valve House is presented in Table 12 below.

Table 12 - FSS Concrete Core Taken in West Main Steam Valve House Analysis by Eberline B3-6216A-FSFC-002-CV ROC Result Uncertainty MDC Co-60 5.31E-02 1.42E-01 2.48E-01 Ni-63 4.16E-01 9.95E-01 1.69E+00 Sr-90 3.35E-01 2.59E-01 5.19E-01 Cs-134 4.96E-01 2.40E-01 2.77E-01 Cs-137 2.02E+01 2.20E+00 5.26E-01

[27]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Table 12 (continued) - FSS Concrete Core Taken in West Main Steam Valve House Analysis by Eberline B3-6216A-FSWC-006-CV ROC Result Uncertainty MDC Co-60 7.92E-02 5.37E-02 1.09E-01 Ni-63 1.06E+00 1.11E+00 1.85E+00 Sr-90 4.58E-01 2.51E-01 4.86E-01 Cs-134 0.00E+00 9.04E-02 9.11E-02 Cs-137 2.58E-01 1.08E-01 1.57E-01 All units in pCi/g In the two concrete core samples taken in the Unit 2 West Valve House, one or more of each ROC (Co-60, Ni-63, Sr-90, Cs-137) was less than MDC. Consequently, there was no compelling evidence to challenge the HTD ratios specified in the LTP and presented in Table 4.

8. QUALITY CONTROL The implementation of required Quality Control (QC) measures included the collection of one (1) additional ISOCS measurement at each of the Unit 2 East and Unit 2 West Valve House for replicate measurement analysis. The concentrations for Ni-63 and Sr-90 were inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15.

The replicate ISOCS measurement results are presented in Table 13 for Unit 2 East Valve House, and Table 14 for Unit 2 West Valve House.

Table 13 - Summary of ISOCS Replicate Measurements for QC Unit 2 East Valve House Co-60 Ni-63(1) Sr-90(1) Cs-134 Cs-137 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B3-6215AF-QWC-018-GD 3.47E+04 5.77E+04 3.85E+04 6.26E+06 7.70E+01 0.105 (1) Concentrations are inferred Table 14 - Summary of ISOCS Replicate Measurements for QC Unit 2 West Valve House Co-60 Ni-63(1) Sr-90(1) Cs-134 Cs-137 Measurement ID OpSOF (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B3-6216AF-QFC-003-GD 8.77E+03 1.74E+04 2.86E+05 1.58E+06 5.72E+02 0.191 (1) Concentrations are inferred The complete ISOCS gamma spectroscopy reports for the duplicate measurements are presented in Attachment 3. All duplicate ISOCS measurements met the required acceptance criteria.

9. INVESTIGATION AND RESULTS No measurements were taken for an investigation during the performance of FSS in this survey unit.

[28]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

10. REMEDIATION AND RESULTS No remediation was required prior to performance of FSS.
11. CHANGES FROM THE FINAL STATUS SURVEY PLAN There were no addendums to the FSS plan, however, there were changes to the ISOCS survey plans as noted earlier in this Release Record. Those changes were required due to structural interferences restricting placement of ISOCS detectors that were not obvious when the FSS plan was first written. The changes in ISOCS measurement locations were made to ensure 100% areal coverage of the survey unit.
12. DATA QUALITY ASSESSMENT (DQA)

The DQO sample design and data were reviewed in accordance with ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment (Reference 13),

for completeness and consistency. Documentation was complete and legible. Surveys and the collection of measurements were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 3.

The preliminary data review consisted of calculating basic statistical quantities (e.g.,

mean, median, standard deviation). All data was considered valid and the values reported below the MDC, and values with uncertainties that exceeded two standard deviations.

All measurement results were individually reviewed and validated. The FOV for the number of measurements taken was sufficient to meet the desired areal coverage of 100%. The instrumentation used to perform the FSS were in calibration, capable of detecting the activity with an adequate MDC and successfully response checked prior to and following use. An adequate number of replicate measurements were taken and the results meet the acceptance criteria as specified in the QAPP.

The analytical results for all 40 ISOCS measurements taken were less than an OpSOF of 0.5.

13. ANOMALIES No anomalies were observed during the performance or analyses of the survey.
14. CONCLUSION A total of forty (40) ISOCS measurements were taken in the Unit 2 East and West Main Steam Valve Houses (20 ISOCS measurements in each). The FOV for the Circular Plan geometry used for the majority of the ISOCS measurements was 28 m2, which equated to an areal coverage 100% of the surface area (including the floor and the four (4) walls) of

[29]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 the Unit 2 East and West Main Steam Valve Houses. The total surface area for each Valve House was 240 m2.

ISOCS measurements indicated that no measurement exceeded a OpSOF of 0.5. As all measurements were below 50% of the OpDCGL, no Sign Test was necessary or performed. The mean BcSOF for survey unit 06215 was 0.008, which equates to a dose of 0.205 mrem/yr. The mean BcSOF for survey unit 06216 was 0.009, which equates to a dose of 0.231 mrem/yr.

Survey units 06215 and 06216 are acceptable for unrestricted release.

15. REFERENCES
1. ZionSolutions procedure ZS-LT-300-001-005, Final Status Survey Data Reporting
2. Zion Station Restoration Project License Termination Plan
3. ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development
4. NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual
5. ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures
6. ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey
7. ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification
8. Zion Station Historical Site Assessment
9. ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of the Zion Station
10. ZionSolutions TSD-14-014, End State Surface Areas, Volumes, and Source Terms of Ancillary Buildings
11. ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms
12. ZionSolutions ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS)
13. ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment

[30]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

16. ATTACHMENTS Attachment 1 - Survey Unit Maps Attachment 2 - ISOCS Geometry Attachment 3 - QC Measurement Assessments Attachment 4 - Eberline Report Attachment 5 - ISOCS Analytical Reports

[31]

ATTACHMENT 1 SURVEY UNIT MAPS

[32]

FSS RELEASE RECORD UNIT 2 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNITS 06215 & 06216 Overview of Structural Survey Units

[33]

FSS RELEASE RECORD UNIT 2 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNITS 06215 & 06216

[34]

ATTACHMENT 2 ISOCS GEOMETRY

[35]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

[36]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

[37]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

[38]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

[39]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

[40]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216

[41]

ATTACHMENT 3 QC MEASUREMENT ASSESSMENTS

[42]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Replicate Measurement Assessment Survey Unit # 06000 Survey Unit Name Unit 2 East Main Steam Valve House Sample Plan # B1-06215A-F Sample

Description:

Comparison of systematic and QC ISOCS measurements at location #18. The standard measurement ID are B3-6215A-FSWC-018-GD. The comparison measurements ID is B3-6215A-FQWC-018-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Comparison Acceptable Value Error Range Value Error Ratio (Y/N)

Cs-137 1.04E+06 2.83E+05 3.7 N/A 1.32E+06 3.23E+05 0.8 N Comments/Corrective Actions: Cs-137 was less Table is provided to show acceptance criteria than MDC in both the standard and comparison used to assess split samples.

measurement. K-40 was substituted, however the resolution is outside of the acceptance range. Based on the professional judgment of the Radiological Engineer, the same conclusion was reached for each measurement. No further action is necessary.

[43]

FSS RELEASE RECORD UNIT 2 EAST & WEST STEAM TUNNEL VALVE HOUSES SURVEY UNITS 06215 & 06216 Replicate Measurement Assessment Survey Unit # 06000 Survey Unit Name Unit 2 West Main Steam Valve House Sample Plan # B3-06216A-F Sample

Description:

Comparison of systematic and QC ISOCS measurements at location #03. The standard measurement ID are B3-6216A-FSFC-003-GD. The comparison measurements ID is B3-6216A-FQFC-003-GD.

STANDARD COMPARISON ROC Activity Standard Resolution Agreement Activity Standard Compariso Acceptable Value Error Range Value Error n Ratio (Y/N)

Cs-137 2.90E+05 5.55E+04 5 05-2.0 2.86E+05 5.35E+04 1.0 Y Comments/Corrective Actions: There was Table is provided to show acceptance criteria acceptable agreement between the standard used to assess split samples.

measurement and the replicate measurement. Based on the professional judgment of the Radiological Engineer, the same conclusion was reached for each measurement. No further action is necessary.

[44]

ATTACHMENT 4 EBERLINE REPORT

[45]

EBERLINE ANALYTICAL CORPOF<ATION 601 SCM<BOfW f'.;/OAD 0At< RIDGE. TENNf:SSEE y7e:50 E:FxVICES PHONE (865) 481-0683 FAX (865) 483-l+621 EBS-OR-43799 June 5, 2018 Patricia Giza Zion Solutions, LLC 101 Shiloh Blvd Zion, IL 60099 CASE NARRATIVE Work Order# 18-05068-0R SAMPLE RECEIPT This work order contains fomteen solid samples received 05/15/2018. Samples were analyzed for Total Strontium, Tritium, Nickel-63 and by Gamma Spectroscopy.

CLIENT ID LAB ID CLIENT ID LAB ID B3-06213AFIWC-Ol 1CV 18-05068-04 B3-062 l 6-AFSFC-002CV 18-05068-11 B3-06213-AFIFC-015CV 18-05068-05 B l-062 l 4-AFSWC-005CV 18-05068-12 B3-062 l 4-AFIFC-OO 1CV 18-05068-06 B l-06214-AFSFC-004CV 18-05068-13 B3-06214-AFIWC-009CV 18-05068-07 B 1-06214-AFSFC-OO 1CV 18-05068-14 B3-062 l 5-AFSWC-O 13CV 18-05068-08 B l-06213-AFSWC-009CV 18-05068-15 B3-06215-AFSFC-003CV 18-05068-09 B l-062 l 3-AFSFC-004CV 18-05068-16 B3-06216-AFSWC-006CV 18-05068-10 B l-06213-AFSFC-002CV 18-05068-17 ANALYTICAL METHODS Total Strontium was analyzed using EIChroM Method SRW01 Modified. Tritium was performed using Method LANL ER-210 Modified. Nickel-63 was performed using Method ASTM 3500-Ni Modified.

Gamma Spectroscopy was performed using EPA Method 901.1 Modified.

Laboratory qualifiers are as follows:

U - Result is less than the MDA.

ANALYTICAL RESULTS Combined Standard Uncertainty is reported at I-sigma value.

Minimum Detectable Activity (MDA) values for data represented in this report are sample-specific.

MDA measurements are determined based on factors and conditions including instrument settings, aliquot size and matrix type.

Page 1 of 3

[46]

ANALYTICAL RESULTS CONTINUED TOT AL STRONTIUM Samples were prepared by aliquoting as appropriate and leaching in acids followed by adding Strontium recovery carriers to each sample. Chemical separations were conducted using selective extractions.

Strontium precipitate was mounted on tared filter media. Chemical recovery was determined by Strontium carrier mass determinations. Samples were counted by gas flow proportional counting and corrected for Yttrium-90 ingrowth.

Samples demonstrated acceptable results for all Total Strontium analyses. Strontium-90 results are reported from Total Strontium due to secular equilibrium. Chemical recovery was acceptable for all samples. The Total Strontium method blank demonstrated an acceptable result. Results for the Total Strontium duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Total Strontium laboratory control sample demonstrated an acceptable percent recovery.

TRITIUM A representative aliquot of each sample was equilibrated with Tritium free water. Equilibrates were diluted and transferred into round-bottomed distillation flasks and attached to single stage stills. A portion of each middle distillation fraction was transferred to a liquid scintillation vial and cocktail was added.

Samples were then counted by beta liquid scintillation.

Samples demonstrated acceptable results for all Tritium analyses. The Tritium method blank demonstrated an acceptable result. Results for the Tritium duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique.

Results for the Tritium laboratory control sample demonstrated an acceptable percent recovery.

NICKEL-63 A representative aliquot of each sample was placed into an appropriately sized beaker. Stable elemental Nickel carrier was added to each sample prior to digestion. Samples were digested in concentrated Nitric acid. After digestion, samples pH was adjusted and Nickel-63 was precipitated selectively with Dimethylglyoxime. Precipitates were selectively separated, redissolved, and residual acid was effectively neutralized. Sample residuals were placed into scintillation vials, scintillation cocktail was added and Nickel-63 activity was determined by beta liquid scintillation.

Samples demonstrated acceptable results for all Nickel-63 analyses. The Nickel-63 method blank demonstrated an acceptable result. Results for the Nickel-63 duplicate demonstrated an acceptable relative percent difference and normalized difference. Results for the Nickel-63 laboratory control sample demonstrated an acceptable percent recovery.

GAMMA SPECTROSCOPY Samples for Gamma Spectroscopy analysis was prepared by transferring a known mass/aliquot of each homogenized sample to a standard geometry container. Samples were counted on a High Purity Germanium (HPGe) gamma ray detector.

Page 2 of 3

[47]

ANALYTICAL RES UL TS CONTINUED GAMMA SPECTROSCOPY CONTINUED Samples demonstrated acceptable results for all gamma-emitting radionuclides as reported. Some Cobalt-60 and Cesium-137 results demonstrated slightly high method detection limits. Some samples demonstrated results that are greater than the method detection limit. These results are reported from the Canberra Gamma Apex "Nuclide MDA Report" and are not positive. These results are qualified as non-detect (U). The method blank demonstrated acceptable results for all radionuclides as reported. Results for the Actinium-228 replicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Cesium-13 7 and Potassium-40 replicate demonstrated an acceptable relative percent difference and normalized difference.

Results for the Cobalt-60 and Cesium-137 laboratory control sample demonstrated an acceptable percent recovery.

CERTIFICATION OF ACCURACY I certify that this data repm1 is in compliance with the terms and conditions of the Purchase Order, both technically and for completeness, for other than the conditions detailed above. Release of the data contained in this hard copy data package has been authorized by the cognizant project manager or his/her designee to be accurate as verified by the following signature.

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rvt.R, McDougal Laboratory Manager Date: 6/5/2018 Eberline Analytical wants and encourages your feedback regarding our performance providing radioanalytical services. Please visit http://eberlineanalytical.com/ to provide us with feedback on our services.

Page 3 of 3

[48]

Printed: 6/5/2018 2:25 PM Page 1 of 19 Report To: Work Order Details:

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Type ID Date i Date Date ID Units 18-05068-01

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LCS KNOWN 05/15/18 00:00 5/15/2018 5/18/2018 18-05068 Tritium LANL ER-210 Modified  ; 2.24E+02 8.08E+OO pCi/g 18-05068-01 LCS SPIKE 05/15/18 00:00 5/15/2018 5/18/2018 18-05068 Tritium LANL ER-210 Modified i 2.02E+02 5.40E+OO 1.25E+01 3.70E+OO pCi/g 18-05068-02 i MBL BLANK 05/15/18 00:00 i 5/15/2018 5/18/2018 18-05068 Tritium LANL ER-210 Modified i 1.51E+OO 2.18E+OO 2.19E+OO 3.69E+OO u pCilg 18-05068-03 DUP B3-06213AFIWC-011 CV 05/02/18 09:00 . 5/15/2018 5/18/2018 18-05068 Tritium LANL ER-210 Modified i 3.25E+OO 2.25E+OO 2.26E+OO 3.72E+OO u pCi/g 18-05068-04 i DO 83-06213AFIWC-011CV 05/02118 ' 5115/20 5/18/2018 18-05068 Tritium LANL ER-210 Modified .15E+OO 2.21E+OO 2.21E+OO 3.75E+OO u pCi/g

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J-" ________ LANL ER-210 Modified i 5.68E-01 i 2.16E+OO 2.16E+OO 3.69E+OO u pCi/g 18-05068-08 TRG 83-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018 5/18/2018 18-05068 Tritium LANL ER-210 Modified i -9.63E-01 2.15E+OO 2.15E+OO 3.75E+OO u pCi/g f-- --*-------*-*---- -*---*-*- -*---~----+ *---, *-*--

18-05068-09 TRG 83-06215-AFSFC-003CV 04/26/18 13:40 5/15/2018 5/18/2018 18-05068 Tritium LANL ER-210 Modified i 5.37E-01 2.04E+OO 2.04E+OO 3.49E+OO u pCi/g i

18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35  : 5/15/2018 : 5/18/2018 18-05068 i Tritium LANL ER-210 Modified 5.47E-01 ' 2.08E+OO i 2.08E+OO 3.55E+OO u pCi/g

  • ---*-*-- -~-*-- i 18-05068-11 i TRG i 83-06216-AFSFC-002CV 04/26/18 15:20  ; 5/15/2018 5/1912018 18-05068 Tritium LANL ER-210 Modified i 2.65E+OO 2.21E+OO 2.22E+OO 3.69E+OO u pCilg 18-05068-12 ' TRG  : 81-06214-AFSWC-005CV 05/05/18 14:35 5/15/2018 5/19/2018 18-05068 Tritium LANL ER-210 Modified i 2.15E+OO 2.08E+OO 2.09E+OO 3.48E+OO u pCi/g f--- - - - : ------* . -----*----- '

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' 2.04E+OO 3.48E+OO pCi/g 18-05068-14 i TRG 81-06214-AFSFC-001CV 05/05/1815:15 , 5/15/2018 '. 5/19/2018 18-05068 Tritium LANL ER-210 Modified i 2.71E+02 5.98E+OO 1.63E+01 3.54E+OO pCi/g 18-05068-15 , TRG 81-06213-AFSWC-009CV 05/05/18 09:05  : 5/15/2018 5/19/2018 18-05068 Tritium LANL ER-210 Modified i O.OOE+OO  ! 2.05E+OO 2.05E+OO 3.54E+OO u pCi/g 18-05068-16 i TRG 81-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 i 5/19/2018 18-05068 i Tritium LANL ER-210 Modified -7.61E-01 i 2.13E+OO  : 2.13E+OO 3.71E+OO u pCiig 18-05068-17 i TRG 81-06213-AFSFC-002CV 05/05/18 13:00 5/15/2018 5/19/2018 18-05068 i Tritium LANL ER-210 Modified ' -5.66E-01  : 2.12E+OO 2.12E+OO 3.67E+OO u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect

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EBERLINE ANALYTICAL ) 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [49]

Printed: 6/5/2018 2:25 PM Page 2 of 19 Report To: Work Order Details:

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05/15/18 00:00 5/15/2018 5/17/2018 18-05068 Nickel-63 4.58E+01 pCi/g 18-05068-01 LCS SPIKE 05/15/18 00:00 ! 5/15/2018 5/17/2018 18-05068 Nickel-63 9.03E+OO 8.81E+01 2.05E+OO pCi/g

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18-05068-08 TRG 83-06215-AFSWC-013CV 04/26/1813:00 5/15/2018

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EBERLINE ANALYTICAL EBERLINE 601 ALYTICAL SCARBORO ROAD OAK RIDGE, TN 37830 ON 865/481-0683 FAX 865/483-4621 [50]

Printed: 6/5/2018 2:25 PM Page 3 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical SDG:

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. 5/15/2018 5/15/2018 : 18-05068 ; Holmium-166m EPA 901.1 Modified -2.19E-02 6.12E-02  : 6.13E-02 3.34E-02

  • u pCi/g 18-05068-02 MBL BLANK 05/15/18 00:00 5/15/2018

- 5/15/2018 18-05068 lodine-129 EPA 901.1 Modified 2.42E-03  ! 1.57E-02  : 1.57E-02 2.34E-02 u  : pCi/g 18-05068-02 ! MBL BLANK 05/15/18 00:00  : 5/15/2018 5/15/2018 : 18-05068 ! Potassium-40 EPA 901.1 Modified 5.07E-01 5.95E-01 5.95E-01 9.92E-01  ; u pCi/g 18-05068-02 ! MBL BLANK 05/15/18 00:00 i --

5/15/2018 ; 5/15/2018 , 18-05068 Manganese-54 EPA 901.1 Modified -5.28E-03

3.07E-02 3.07E-02 4.72E-02  ! u pCi/g 18-05068-02 MBL BLANK

- 05/15/18 00:00 5/15/2018 , 5/15/2018 18-05068 Niobium-94 EPA901.1 Modified 7.19E-03  : 3.07E-02 3.07E-02 4.87E-02 I u pCi/g 18-05068-02 ; MBL BLANK 05/15/18 00:00  ! 5/15/2018 5/15/2018 : 18-05068 .: Lead-210 EPA 901.1 Modified 3.46E-01 2.73E-01 2.74E-01 4.34E-01  : u pCilg 18-05068-02 MBL BLANK 05/15/18 00:00 l 15/2018 5/15/2018 18-05068 Lead-212 EPA 901.1 Modified 5.68E-02 4.16E-02 4.17E-02 6.65E-02 u pCi/g nrnc~.n?  :

---*--* u pCi/g

<O MBL BLANK 05115/18 00:00 5/15/2018 5/1512018 18-05068 Lead-214 EPA 901.1 Modified 4.12E-02  : 6.21E-02  : 6.21E-02 9.75E-02 18-050 MBL BLANK 05/15/18 00:00 5/15/2018 5/15/2018 18-05068 Promethium-145 EPA 901.1 Modified 7.39E-03 i 2.75E-02 2.75E-02 4.14E-02 u pCi/g 18-05068-02 MBL BLANK 05/15/18 00:00 5/15/2018 5/15/2018 18-05068 Radium-226 EPA 901.1 Modified 9.97E-02 7.68E-02  ! 7.69E-02 1.24E-01 ' u pCi/g 10.n~n1SRM MBL BLANK 05/15/18 00:00 5/15/2018 5/15/2018 18-05068 ! Antimony-125 EPA 901.1 Modified -3.50E-02  : 9.31E-02 9.32E-02 1.23E-01 u pCi/g i .....

18-05068-02 MBL BLANK ~15/18 00:00 5/15/2018 5/15/2018 18-05068 ! Thorium-234 EPA 901.1 Modified 6.76E-01 3.39E-01 3.41E-01 5.49E-01 u pCilg 18-05068-02 MBL BLANK 15/18 00:00 ; 5/15/2018 5/15/2018 18-05068 EPA 901.1 Modified 1.56E-01  : 1.12E-01 1.12E-01 1.80E-01  ! u pCi/g 1n - M MBL BLANK 05/15/18 00:00 i 5/15/2018 ' 5/15/2018 / 18-05068 ; Uranium-235 EPA901.1 Modified -4.57E-03 I 3.33E-01 3.33E-01 1.82E-01 u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

(::> EBERLINE ANALYTICAL EBERLINE AL YTICAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [52]

Printed: 61512018 2:25 PM Page 5 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical ,,._,, .. **----

__ Zion Solutions, LLG ____

SDG:

Purchase Order:

677118

  • -=-*** ---*--*----~--*-*--*-**-~ --*-*--*----A*-----*~---*---- "-m-*-*--*-* *m*------*---**--*--

Final Report of Analysis 101 Shiloh Blvd Analysis Category: _____ ENVIRONMENTAL ________

Zion, IL 60099 Sample Matrix: so Lab ID i Sample Type Client ID Sample Date Receipt Date  :

Analysis Date Batch ID Analyte Method Result cu CSU MDA Qualifier Report Units 18-05068-03 DUP B3-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Actinium-228 EPA 901-1 Modified 2.51E-01 6.12E-01 6.12E-01 9A1E-01 u pCi/g 18-05068-03 DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068

  • --q--,-,*--------*---------------~,,

Silver-108m EPA 901-1 Modified 4.59E-02 2-26E-01 2-26E-01 3.35E-01 u pCi/g 18-05068-03 : DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Americium-241 EPA 901-1 Modified -6A6E-01 1A8E+OO 1A8E+OO 1.85E+OO u oCi/o

  • ------------.,_--*-*---*=--------"-*-*-------

18-05068-03 DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Barium-133 EPA 901-1 Modified 1.03E+OO 1.38E+OO 1-38E+OO 1.83E+OO u oCi/Q 18-05068-03 DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Bismuth-214 EPA 901-1 Modified

' U4E+OO 4.88E-01 4.91E-01 1A2E+OO u pCi/g 18-05068-03 DUP 83-06213AFIWC-011 CV

--*---*-*-~ ---~-----~--------*--*---

05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Cobalt-60 EPA 901-1 Modified -5.14E-02 1-27E-01 1-27E-01 1-31E-01 u pCi/g 18-05068-03 DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Cesium-134 EPA 901-1 Modified  : -1.71E-01 5.51E-01 5-51E-01 3.32E-01 u pCi/g

.co *---

n...,

DUP B3-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Cesium-137 EPA 901-1 Modified  : 2.83E+03 2.95E+02 3.29E+02 3.74E+OO pCi/g

,co .... - .... ~ ...........

-- DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Europium-152 EPA 901-1 Modified i 4.12E+OO 5A4E+OO 5A4E+OO 8-86E-01 u pCi/g 18-05068-03 DUP 83-06213AFIWC-011CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 ~u,v~,u, 154 EPA 901-1 Modified -7.33E-02  : 3.16E-01 i 3.16E-01 4.73E-01 u pCi/g 18-05068-03 i DUP B3-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Europium-155 EPA 901-1 Modified 1.96E+OO 1A2E+OO  : 1A3E+OO 2.37E+OO  : u pCi/g 18-05068-03 ' DUP 83-06213AFIWC-011 CV 05/02/18 09:00 f 5/15/2018 5/15/2018 18-05068 ' Holmium-166m EPA 901-1 Modified i -4.51E-02  ! 4.01E-01 4.01E-01 5.88E-01 u pCi/g 18-05068-03 DUP  : 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 : lodine-129 EPA 901-1 Modified -1.93E+01  ; 3.19E+OO 3.34E+OO 3.27E+OO u pCi/g 1n -- -- M  ;

DUP B3-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Potassium-40 EPA 901-1 Modified 7.97E+OO 1-68E+OO 1.73E+OO 3.36E+OO u pCi/g 18-05068-03 : DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 ; 18-05068 , ---o-"

. EPA 901-1 Modified -6.07E-02 i 1-85E-01  : 1.85E-01 2.67E-01 u pCi/g 18-05068-03 DUP 83-06213AFIWC-011

.._ CV 05/02/18 09:00 i 5/15/2018 5/15/2018 18-05068 i

. --------~--- Niobium-94 EPA 901-1 Modified 9.92E-02 i 1.70E-01 l UOE-01 2.62E-01 u  : pCi/g 18~05068-03 J

i DUP

- 83-06213AFIWC-011 CV

- - --------- 05/02/18 09:00 5/15/2018 ' 5/15/2018 18-05068 Lead-210 EPA 901-1 Modified -L67E+01 1A2E+01  :. 1A2E+01 L76E+01 u pCi/g 18-05068-03 i DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 : 5/15/2018 18-05068 i Lead-212 EPA 901-1 Modified

' -7.03E-02 i 1-36E+OO 1-36E+OO 2.14E+OO u pCi/g 18-05068-03  ! DUP  : 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 , 5/15/2018 18-05068 i Lead-214 EPA 901-1 Modified L82E+OO ' 2.16E+OO 2.17E+OO 3.60E+OO u pCi/g 18-05068-03 DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 ' -- ,.__-" ___ - '*-*-

18-05068 ' ~- ,, 1.08E+02 i 9.57E+OO L11E+01 3.55E+OO u i pCi/g S,AOOU~

18-05068-03 DUP 83-06213AFIWC-011 CV 05/02/18 09:00  ; 5/15/2018 i 5/15/2018 18-05068 ; Radium-226 EPA90U M U4E+OO  : 4-88E-01  ; 4.91E-01 1A2E+OO u ' pCi/g 18-05068-03 i DUP

' 83-06213AFIWC-011 CV 05/02/18 09:00 i 5/15/2018 - 5/15/2018 18-05068 '. A.::'.--.. , '25  : 4.98E+OO 4.98E+OO 5.63E+OO u  : pCi/g 18-05068-03 i DUP 83-06213AFIWC-011 CV 05/02/18 09:00 i 5/15/2018 5/15/2018 18-05068 i Thorium-234 EPA 901-1 Modified 3A7E+OO 1.36E+01 L36E+01 1.72E+01 u pCi/g 18-05068-03 DUP 83-06213AFIWC-011 CV 05/02/18 09:00 _ 5/15/2018 5/15/2018 18-05068 i Thallium-208 EPA 901-1 Modified L03E+OO i 2A1E+OO i 2A1E+OO 9-25E-01 u pCi/g

! ' u 18-05068-03 DUP 83-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 :  !'---:.. - ..,,,~ EPA 901-1 Modified 7.33E+OO i 1-25E+01

' 1.25E+01 6.22E+OO  : pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE ANALYT'CAL EBERLINE CAL CORPORATION 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [53]

Printed: 6/5/2018 2:25 PM Page 6 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical -****** *--* . --*---*--*--.-*- ---*--*---**-**-**-** -**-*-

___ Zion Solutions, LLC _____________ _

SDG:

Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report ID Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units 18-05068-04 DO 83-06213AFIWC-011CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Actinium-228 EPA 901 _1 Modified 5_28E-01 3_79E-01 3_80E-01 7_02E-01 u

--~m-"-*m-~-* ---=-"""=*---*-*-*-"'""

18-05068-04 DO B3-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Silver-108m EPA901_1 Modified -6_39E-02 2_30E-01 2_30E-01 3_30E-01 u

*------------------- --*---~*-----~----------*-".""-**"---"*~*--------*---=----*-+-----**---------------------------------------------

18-05068-04 DO B3-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Americium-241 EPA 901 _1 Modified -1_28E+OO 1.48E+OO 1.49E+OO 1_84E+OO u

*--------- -------- ----- --------------------------+--------------------------------+------*--*----------------~------

18-05068-04 DO B3-06213AFIWC-011CV 05/02/1809:00 5/15/2018 5/15/2018 18-05068 Barium-133 EPA901_1 Modified 1_81E+OO 1_81E+OO 1_83E+OO u

------------------------------------------ ------------------*----- -------------------+------------------*----------*----------------------------------

18-05068-04 DO 83-06213AFIWC-011CV 05/02/1809:00 - 5/15/2018 5/15/2018 18-05068 Bismuth-214 EPA901_1 Modified 1.47E+OO 1.47E+OO 1_34E+OO u

--*--*---------------------------*--------------- *------------1------------------------------------'--------------------------,-----

18-05068-04 DO

-*-*------m,,,>,,

B3-06213AFIWC-011 CV 05/02/18 09:00 5/15/2018

  • 5/15/2018 18-05068 Cobalt-60 EPA 901 _1 Modified 1_22E-01 1_22E-01 1_10E-01 u

-w~---------*""' --*"""'*-----"-------

18-05068-04 DO B3-06213AFIWC-011CV 05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Cesium-134 EPA 901 _1 Modified 7_14E-01 3_28E-01 u 18-05068-04 DO B3-06213AFIWC-011 CV

---*---------------"--"-s-------*-----------

05/02/18 09:00 5/15/2018 5/15/2018 18-05068 Cesium-137 EPA 901_1 Modified 3.28E+02 2_86E+OO 18-05068-04 DO B3-06213AFIWC-011 CV 05/02/18 09:00 EPA 901 _1 Modified 5_44E+OO 8_66E-01 u 18-05068-04 DO B3-06213AFIWC-011 CV 05/02/18 09:00 EPA 901_1 Modified -2_90E-01 3_29E-01 3_29E-01 4_38E-01 u 18-05068-04 DO B3-06213AFIWC-011 CV 05/02/18 09:00 EPA 901.1 Modified 1_24E+OO 1_95E+OO u 18-05068-04 DO B3-06213AFIWC-011 CV 05/02/18 09:00 EPA 901 _1 Modified 4_01E-01 5_59E-01 u 18-05068-04 DO 83-06213AFIWC-011 CV 05/02/18 09:00 2_66E+OO 3_34E+OO u 18-05068-04 DO B3-06213AFIWC-011 CV 05/02/18 09:00 1_74E+OO 1_54E+OO 18-05068-04 DO B3-06213AFIWC-011 CV 2_85E-01 u

B3-06213AFIWC-011CV 18-05068-04 05/02/18 EPA901_1 Modified 2.40E-01 u pCi/g 18-05068-04 Lead-210 EPA 901.1 Modified 1_76E+01 u 18-05068-04 Lead-212 EPA 901 _1 Modified 1_39E+OO 2_16E+OO u 18-05068-04 DO B3-06213AFIWC-011CV Lead-214 EPA 901_1 Modified 2_90E+OO 4_07E+OO u 18-05068-04 DO B3-06213AFIWC-011 CV 18-05068 Promethium-145 EPA 901.1 Modified 1_07E+01 3_53E+OO u

---DO--

18-05068-04 83-06213AFIWC-011 CV 18-05068 Radium-226 1_34E+OO u DO B3-06213AFIWC-011 CV 05/02/18 18-05068 Antimony-125 4_96E+OO 5_61E+OO u DO 83-06213AFIWC-011 CV 18-05068 Thorium-234 1_36E+01 1_71E+01 u DO B3-06213AFIWC-011 CV 05/02/18 18-05068 Thallium-208 EPA 901.1 Modified 2.40E+OO 9_00E-01 u DO 83-06213AFIWC-011 CV 18-05068 Uranium-235 EPA 901_1 Modified 1_25E+01 6_19E+OO u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE ANALYTiCAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [54]

Printed: 6/5/2018 2:25 PM Page 7 of 19 Report To: Work Order Details:

Eberline Analytical f- *-*-,**w Patricia Giza

              • -<<-**-------**-****--- . *-* **-***- -*****-*---*-*--**-***--*-* ********- t,,.-, .*. ,..

SDG: 18-05068

____ Zion Solutions, LLC ,-em*m

    • ----*-----*---~----- ,___ Purchase Order:
  • -------------- 677118 ---~~----~- -~---"'-------~*---*-*--**-**------*----*-**

Final Report of Analysis 101 Shiloh Blvd

--*------*--------- . ----**-------*--*- - """"'-**-*-- r~-**- Analysis Category:

ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample ' Client Sample Receipt Analysis Batch Report ID Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units 18-05068-05 : TRG 83-06213-AFIFC-015CV 05102118 08 :45 5/1512018 511512018 18-05068 Actinium-228 EPA 901.1 Modified 6.88E-01 4.42E-01 4.43E-01 7.70E-01 u pCi/g 18-05068-05 TRG 83-06213-AFIF C-015CV 05/02/18 08:45 i 5/15/2018 5/15/2018 18-05068 Silver-108m EPA 901.1 Modified C 1.94E-02 1.37E-01 1.37E-01 2.14E-01 u pCi/g 18-05068-05 : TRG 83-06213-AFIFC-015CV 05/02/18 08:45  : 5/15/2018 5/15/2018 18-05068 , Americium-241 EPA 901.1 Modified i -1.29E+OO 1.23E+OO 1.23E+OO 1.83E+OO u pCi/g 18-05068-05 ; TRG 83-06213-AFIFC-015CV 05/02/18 08:45 i 5/1512018 511512018 18-05068 i Barium-133 EPA 901.1 Modified -3.79E-01  : 2.13E+OO 2.13E+OO 1.84E+OO u pCilg 18-05068-05 i TRG 83-06213-AF IFC-015CV 05102/18 08:45  : 5/1512018 511512018 18-05068 Bismuth-214 EPA 901.1 Modified [ 1.24E+OO  : 1.66E+OO 1.66E+OO 1.15E+OO u pCilg 18-05068-05 i TRG 83-06213-AFIFC-015CV 05102118 08:45 5/15/2018 5/1512018 18-05068 Cobalt-60 EPA 901.1 Modified 3.73E-02  ; 1.08E-01 1.08E-01 1.42E-01 u pCilg 18-05068-05 TRG 83-06213-AFI F C-015CV 05/02118 08:45  : 5115/2018 5/1512018 18-05068 Cesium-134 EPA 901.1 Modified 9.00E-02 7.98E-01  : 7.98E-01 1.99E-01 u pCi/g 18-05068-05 TRG i 83-06213-AFIFC-015CV 05102/18 08:45  ! 5/1512018 511512018 18-05068 ; Cesium-137 EPA901.1 Modified I 1.19E+03  ; 1.22E+02 1.37E+02 3.17E+OO pCi/g

,oncnco_ns  ! TRG 83-06213-AFIFC-015CV 05/02118 08:45  ; 5/15/2018 5/15/2018 18-05068 ~v,ve,v* 152 EPA 901.1 Modified 1.32E+OO 6.44E+OO 6.44E+OO 8.97E-01 u pCilg 18-05068-05 : TRG 83-06213-AFIFC-015CV 05/02/18 08:45  : 5115/2018 511512018 18-05068 ' ~v,ve,v* i54 EPA 901.1 Modified  ! -1.11E-01 3.29E-01 3.29E-01 4.75E-01 u pCi/g 18-05068-05 TRG 83-06213-AF IFC-015CV 05102/18 08:45 5115/2018 5/1512018 18-05068 Europium-155 EPA 901.1 Modified 2.86E-01 1.32E+OO 1.32E+OO 1.99E+OO u pCi/g 18-05068-05 : TRG 83-06213-AFIFC-015CV 05102118 08:45

*------~-

5/15/2018 5/15/2018 18-05068 Holmium-166m EPA 901.1 Modified 1.62E-01 I

2.28E-01 2.29E-01 3.66E-01 u pCilg 18-05068-05 18-05068-05 '

i TRG TRG 83-06213-AFIFC-015CV 83-06213-AFI FC-015CV 05/02118 08:45

  • ---t 05102/18 08:45 i 5115/2018 5115/2018

~------

5/1512018 5/1512018

,,_,,,,_,,, 18-05068".'

18-05068 )

lodine-129 Potassium-40 EPA 901.1 Modified EPA 901.1 Modified 4.58E+02 7.48E+OO  ;

1.89E+02 1.56E+OO '

1.90E+02 1.61E+OO 1.07E+01 1.38E+OO u pCi/g pCi/g 18-05068-05 TRG 83-06213-AFIFC-015CV 05102118 08:45  ! 5/15/2018 5115/2018 18-05068 [ Manganese-54 EPA 901.1 Modified 4.62E-02 i 1.13E-01  : 1.13E-01 1.85E-01 . u pCi/g 18-05068-05 ) TRG 83-06213-AFIFC-015CV 05/02118 08:45 i 5115/2018

  • 5115/2018 18-05068 , Niobium-94 EPA 901.1 Modified -5.32E-02 i 1.06E-01 1.06E-01 1.56E-01

. u pCi/g 18-05068-05 ' TRG 83-06213-AFIFC-015CV 05102/18 08:45  : 5/1512018 5/1512018 18-05068 : Lead-210 EPA 901.1 Modified -2.15E+02  ; 2.44E+01 2.68E+01 2.51E+01 u pCi/g I

  • I 18-05068-05 TRG  ; 83-06213-AFIFC-015CV 05102/18 08:45  : 5/1512018 5/15/2018 18-05068 i Lead-212 EPA 901.1 Modified 9.83E-01  : 1.41E+OO 1.41E+OO 3.18E+OO u pCilg 18-05068-05 ) TRG 83-06213-AFIFC-015CV 05/02118 08:45 j 5115/2018 511512018 18-05068 Lead-214 EPA 901.1 Modified 1.98E+OO  ; 3AOE+OO 3.41E+OO 4.89E+OO u pCi/g 18-05068-05 i TRG 83-06213-AFIFC-015CV 05102/18 08:45 i 5115/2018 I 5/1512018 18-05068 Promethium-145 EPA 901.1 Modified -1.36E+01  : 2.56E+OO  : 2.66E+OO 6.22E+OO u pCi/g i 5/1512018 ...... ..,,.,_ ... ..,,...

18-05068-05 i TRG  : 83-06213-AFIFC-015CV 05102/18 08:45 5/1512018 , 18-05068 EPA 901.1 Modified  : 1.24E+OO  : 1.66E+OO ' 1.66E+OO 1.15E+OO u pCilg 18-05068-05 I TRG 83-06213-AFI FC-015CV 05/02118 08:45 I 5/1512018 5/1512018 18-05068 ~"'" "v"y "v

  • - EPA 901.1 Modified i -6.17E+OO .i 5.98E+OO ' 5.98E+OO 6.61E+OO u pCilg 18-05068-05 i TRG 83-06213-AFIFC-015CV 05/02118 08:45  ! 5115/2018 . 511512018 18-05068 -*l 1,v11u, ""

- EPA 901.1 Modified -7.58E+OO  ; 1.11E+01 1.11E+01 1.66E+01 u pCi/g 18-05068-05 I TRG 83-06213-AFIFC-015CV 05102118 08:45 I 5/1512018 5/15/2018 18-05068 Thallium-208 EPA 901.1 Modified i 1.37E+OO i 2.70E+OO 2.70E+OO 4.58E-01 u pCilg 18-05068-05 TRG 83-06213-AFIFC-015CV 05/02118 08:45 5/1512018 5/1512018 18-05068 , Uranium-235 EPA 901.1 Modified -1.42E+01 j 1.91E+01 1.91E+01 8.33E+OO u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE ANALYTICAL EBERLINE 601 SCARBORO ROAD OAK RIDGE, TN 37830 l YTICAL CORPORATION 865/481-0683 FAX 865/483-4621 [55]

Printed: 6/5/2018 2:25 PM Page 8 of 19 Report To: Work Order Details:

Eberline Analytical Patricia Giza SDG: 18-05068

____ Zion _Solutions, _LLC _____________ _

Final Report of Analysis 101 Shiloh Blvd i--- Zion, IL 60099 Lab Sample Client Sample Receipt Analysis Batch Report ID Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units

,..._1_8_-0_5_o6_8_-o___6_____ TR__ G

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__ 1 __8__

-0_5_o6_a-_o_6___,___TR_G _________ s__3__-__0_62_1_4__-_A_F__1_F__c_-_0__0_1_c_v________+*-*.2~?3i18_1_3_:3?___5_11_5_12_0~-~1_5_12_0:~___2_~:_o5_o_68____/\rri_':':_';i_um_-2~_1+--*E_P_A_9___0_1_._1____M ___o_d_ifi_ed___, ___ -9_.0_6_E__-_0_2_, _____1_.4_1_E

____+_o_o_ _1_A__1_E+ __o_o_ _1_.7_7_E_+o_o_____ u_________________,.eP_Ci/g:.___...

18-05068-06 : TRG B3-06214-AFIFC-001CV 05/03/1813:30 5/15/2018 5/15/2018 18-05068 Barium-133 EPA901.1 Modified ' -9.20E-01 1.66E+OO 1.66E+OO 1.72E+OO U pCi/g 18-05068-06 TRG B3-06214-AFIFC-001CV 05/03/1813:30 5/15/2018 5/1 18-05068 Bismuth-214 EPA 901.1 Modified 1.60E-01 1.43E+OO 1.43E+OO 1.22E+OO U pCi/g

-*-----*--**----------**--**--- --- - - - - - _. **---*--*---------**-*****--**--***** - - t - - - * - - - * - - - - - - * * * - * - - - - - - - + - * * * * - - - - - * - - - - - - - - - - - - * - - - - - - - - - - - * - - - - - - - * - * * * ' - - " - - - 1 18-05068-06 ; TRG 83-06214-AFIFC-001 CV 05/03_1_~~~~C:____!5_1_15/2018 -*---~'-.:1_512018 _1!J:?5068 _ ---~~~o___ f--_E_P_A _____9__0_1_.1_M_od_ifi_,e_d_ __,__1_.8__4__E_-o_1_.,____8_._58__E __-o_2___ ,c....__8._63_E_-_o2

__ _ _1_.6_7E_-_o_1 _________________P,_C~_ii_::_9 _____,

18-05068-06 i TRG 83-06214-AFIFC-001 CV _ 05/03/18 13:30 -- 5/15/2018 _ 5/15/2018 18-05068 c..:.sium-134**-+---E_P_A__9_0_1_.__1___M __o_di_fie_d___+_-_6.4__7_E-_02________ 5._2_3_E_-_01_____5 __ __-_0_1_ _2_.8_8_E-_0_1_______u

.2_3E ____________-'-pC_i..c/g'-----I 18-05068-06 : TRG B3-06214-AFIFC-001CV 05/03/1813:30  : 5/15/2018 5/15/2018 18-05068 Cesium-137 EPA901.1 Modified 2.55E+03 2.47E+02 2.80E+02 1.68E+OO pCi/g

- , ~ ..-:~:.0_6~~:~FIFC-001 ~':!___-___ 05/03/18 13:30 5/15/2018 5/15/2018 18-05068 LUO --e------ ..--15-2-t**----*-E--PA-9-01-.1-M ____o__d-ifi-,e-d ___ __, _____3__3_6_E_+_O__o_:__4___9_9_E._+O--O---s-4-_9_9_E_+_00____8___6--4E---01____u__________pc.__Ci/;__g-18-05068-06 TRG B3-06214-AFIFC-001CV 05/03/18 13:30 5/15/2018 5/15/2018 18-05068 Europium-154 EPA 901.1 Modified -3.26E-01 3.23E-01 3.23E-01 4.18E-01 U pCi/g 18-05068-06 TRG 83-06214-AFIFC-001CV 05/03/1813:30  ; 5/15/2018

  • 5/15/2018 18-05068
  • Europium-155 EPA 901.1 Modified 2.03E+OO 1.47E+OO  ; 1.47E+OO 1.86E+OO U , pCi/g 18-05068-06 TRG B3-06214-AFIFC-001CV 05/03/1813:30 [ 5/15/2018 5/15/2018 18-05068 Holmium-166m EPA901.1 Modified -2.83E-01 3.71E-01 i 3.71E-01 5.19E-01 U pCi/g 18-05068-06 TRG B3-06214-AFIFC-001CV 05/03/1813:30  ! 5/15/2018 5/15/2018 18-05068 lodine-129 EPA901.1 Modified i -1.33E+02 i 1.23E+01 i 1.41E+01 1.43E+OO U pCi/g 18-05068-06 TRG B3-06214-AFIFC-001CV 05/03/18 13:30 5/15/2018 5/15/2018 18-05068 Potassium-40 EPA 901.1 Modified 6.59E+OO  : 1.67E+OO  ; 1.70E+OO 1.90E+OO pCi/g 18-05068-06 : TRG B3-06214-AFIFC-001CV 05/03/18 13:30  : 5/15/2018
  • 5/15/2018 18-05068 EPA 901.1 Modified -8.49E-02 1.71 E-01 , 1.71 E-01 2.46E-01 U pCi/g 18-05068-06 TRG 83-06214-AFIFC-001 CV 05/03/18 13:30 , 5/15/2018 5/15/2018 18-05068 Niobium-94 EPA 901.1 Modified -8.04E-02 1.66E-01 i 1.66E-01 2.36E-01 U pCi/g 18-05068-06 TRG 83-06214-AFI FC-001 CV 05/03/1813:30 ' 5/15/2018 i 5/15/2018 i 18-05068 Lead-210 EPA 901.1 Modified 9.08E+OO , 8.99E+OO 9.01 E+OO 1.32E+01 U pCi/g 18-05068-06 ' TRG 83-06214-AFIFC-OO 1CV 05/03/18 13:30  : 5/15/2018 5/15/2018 18-05068 I Lead-212 EPA 901.1 Modified 8.56E-01  : l .60E+OO , 1.60E+OO 2.02E+OO U pCi/g 18-05068-06 TRG B3-06214-AFIFC-001CV 05/03/1813:30  ; 5/15/2018 , 5/15/2018 18-05068 , Lead-214 EPA 901.1 Modified 1.34E+OO l 2.63E+OO 2.63E+OO 3.31E+OO U pCi/g 18-05068-06 TRG 83-06214-AFIFC-001 CV 05/03/18 13:30 j 5/15/2018 5/15/2018 18-05068 : Promethium-145 EPA901.1 Modified 6.12E+01  ; 5.57E+OO , 6.40E+OO 2.60E+OO U pCi/g 1

18-05068-06 TRG B3-06214-AFIFC-001CV 05/03/18 13:30  ! 5/15/2018 5/15/2018 18-05068 Radium-226 EPA 901.1 Modified 1.60E-01 1.43E+OO  ; 1.43E+OO 1.22E+OO ' U pCi/g 18-05068-06 TRG 83-06214-AFIFC-001 CV 05/03/1813:30  ; 5/15/2018 ; 5/15/2018 18-05068 * .. ::....... . -- EPA 901.1 Modified -1.60E+OO 3.60E+OO 3.61E+OO 4.58E+OO U pCi/g 18-05068-06 i TRG 83-06214-AFIFC-001 CV 05/03/18 5/15/2018 5/15/2018 18-05068 Thorium-234 EPA901.1 Modified -4.60E+OO i 1.30E+01 1.30E+01 1.63E+01  ; U pCi/g

+*-*--------+---------"------~----------"------**-------=--*--1 TRG 83-0621~- -ire,-uu CV 05/03/1813:30 5/15/2018; 5/15/2018 18-05068 Thallium-208 EPA901.1 Modified 2.70E+OO 1.82E+OO 1.82E+OO 5.55E-01 U pCi/g 1n --- *- n~ TRG 83-06214-AFIFC-001 CV 05/03/1813:30  : 5/15/2018 5/15/2018 , 18-05068 Uranium-235 EPA901.1 Modified 3.12E+OO 1.42E+01 i 1.42E+01 5.89E+OO  ; U , pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

( __@

EBERLINE ANAL YTl CAL EBERLINE 601 SCARBORO ROAD OAK RIDGE, TN 37830 CAL (ORPORATIOl'l 865/481-0683 FAX 865/ 483-4621 [56]

Printed: 6/5/2018 2:25 PM Page 9 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical _____ Zion Solutions, LLG_ ------.-. **-*

Purchase Order:

SOG:

677118

---*-*-*"'*-* *-*-*-*--*-*-*-- -----*-*------"'"" ---------------------------------*--- """'"""----------- ------~------------"

Final Report of Analysis

"""""w*-

101 Shiloh Blvd Anatvsis Cate;:;::,y: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch  : Report ID Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier

Units 18-05068-07

~--~~----*-- TRG 83-06214-AFIWC-009CV

""""""'-"""""""'"---W~***-----------~

05/03/18 15:30 5/15/2018 5/15/2018 18-05068

~*--*-----------~***,-**-*----~--------,-,-,w,,_,, Actinium-228

______._ EPA 901.1 Modified 4.76E-01 5.07E-01 5.07E-01 8.61E-01 u pCi/g i

~-

18-05068-07 TRG B3-06214-AFIWC-009CV

---~,-,----------------

05/03/18 15:30 5/15/2018 5/15/2018 18-05068 Silver-108m EPA 901.1 Modified 1.20E-01 1.68E-01 1.68E-01 2.75E-01 u i pCi/g 18-05068-07 TRG 83-06214-AFIWC-009CV 05/03/18 15:30 : 5/15/2018 5/15/2018 18-05068 Americium-241 EPA 901.1 Modified -1.71E+OO 1.72E+OO 1.72E+OO 2.78E+OO u pCi/g

,,,,-----~ -------~~- .---*-------~---- ' *-------------*-

18-05068-07 TRG B3-06214-AFIWC-009CV 05/03/18 15:30 5/15/2018 5/15/2018 18-05068 Barium-133 EPA 901.1 Modified -2.95E+OO 3.35E+OO 3.36E+OO 2.78E+OO i u pCi/g

,,,,-,------,--------------~--,---------------  !  :

18-05068-07 TRG B3-06214-AFIWC-009CV 05/03/18 15:30

  • 5/15/2018 5/15/2018 18-05068 Bismuth-214 EPA 901.1 Modified 1.11E+OO 2.56E+OO 2.56E+OO 1.36E+OO u pCi/g

~-----"' ------

18-05068-07 TRG B3-06214-AFIWC-009CV 05/03/18 15:30 5/15/2018 5/15/2018 18-05068 Cobalt-60 EPA 901.1 Modified 1.26E-02 6.67E-02 6.67E-02 2.50E-01 u pCi/g 18-05068-07 TRG 83-06214-AFIWC-009CV 05/03/18 15:30 5/15/2018 : 5/15/2018 18-05068 Cesium-134 EPA 901.1 Modified -1.61E-01 1.23E+OO 1.23E+OO 2.63E-01

  • u  : pCi/g
  • ~ _n,;n~"-07 , TRG i B3-06214-AFIWC-009CV 05/03/18 15:30 [ 5/15/2018 5/15/2018 18-05068 Cesium-137 EPA 901.1 Modified f 2.35E+03 2.40E+02 2.69E+02 3.78E+OO pCi/g 18-05068-07 : TRG B3-06214-AFIWC-009CV 05/03/18 15:30 5/15/2018 5/15/2018 18-05068 Europium-152 EPA 901.1 Modified 2.07E+OO 9.86E+OO 9.86E+OO 1.01E+OO u pCi/g 18-05068-07 TRG 83-06214-AFIWC-009CV 05/03/18 15:30 5/15/2018 5/15/2018 18-05068 Europium-154 EPA 901.1 Modified -3.09E-02 3.35E-01 3.35E-01 5.16E-01 i u  : pCi/g 18-05068-07 TRG B3-06214-AFIWC-009CV 05/03/18 15:30 : 5/15/2018 5/15/2018 18-05068 Europium-155 EPA 901.1 Modified 5.94E-01 1.54E+OO 1.54E+OO 3.01E+OO u pCi/g 18-05068-07 TRG B3-06214-AFIWC-009CV 05/03/18 15:30 5/15/2018 5/15/2018 18-05068 : Holmium-166m EPA 901.1 Modified -3.59E-01 3.15E-01 i 3.15E-01 4.25E-01 u pCi/g 18-05068-07 i TRG B3-06214-AFIWC-009CV 05/03/18 15:30 i 5/15/2018 5/15/2018 : 18-05068 lodine-129 EPA 901.1 Modified 1.05E+03 4.33E+02 4.36E+02 1.73E+01 u pCi/g 18-05068-07 TRG B3-06214-AFIWC-009CV 05/03/18 15:30 , 5/15/2018 5/15/2018 18-05068 , Potassium-40 EPA 901.1 Modified 7.99E+OO 1.94E+OO 1.98E+OO 1.84E+OO pCi/g 18-05068-07 i TRG B3-06214-AFIWC-009CV 05/03/18 15:30 , 5/15/2018 5/15/2018 18-05068 i .. ,_ .. "_., ___ : EPA 901.1 Modified 1.56E-02 1.40E-01 1.40E-01 2.21E-01 u  : pCi/g 18-05068-07 TRG B3-06214-AFIWC-009CV 05/03/18 15:30 5/15/2018 ' 5/15/2018 18-05068 .. --*-* n EPA 901.1 Modified -6.95E-02 1.05E-01 1.05E-01 2.09E-01 u pCi/g 18-05068-07 TRG 83-06214-AFIWC-009CV 05/03/18 15:30 : 5/15/2018 5/15/2018 18-05068 Lead-210 EPA 901.1 Modified -4.37E+02 , 4.70E+01 5.21E+01 3.90E+01 u pCi/g 1K-< "' TRG B3-06214-AFIWC-009CV 05/03/18 15:30 i 5/15/2018 5/15/2018 18-05068 : Lead-212 EPA 901.1 Modified -3.23E-01 1.22E+OO 1.22E+OO 4.81E+OO u pCi/g 18-05068-07 TRG 83-06214-AFIWC-009CV 05/03/18 15:30 5/15/2018 5/15/2018 18-05068 i Lead-214 EPA 901.1 Modified 1.51E+OO  ! 5.19E+OO i 5.19E+OO 7.50E+OO u pCi/g 18-05068-07 TRG B3-06214-AFIWC-009CV 05/03/18 15:30 ! 5/15/2018 , 5/15/2018 18-05068 Promethium-145 EPA 901.1 Modified -2.79E+01 5.03E+OO , 5.23E+OO 1.00E+01 u i pCi/g 18-05068-07 TRG 83-06214-AFIWC-009CV 05/03/18 15:30 5/15/2018 5/15/2018 . 18-05068 Radium-226 EPA 901.1 Modified 1.11E+OO  ; 2.56E+OO 2.56E+OO 1.36E+OO u pCi/g 18-05068-07 TRG i B3-06214-AFIWC-009CV 05/03/18 15:30 i 5/15/2018 , 5/15/2018 18-05068 i .,,.,.,_.,, *~o EPA 901.1 Modified -9.73E-01 i 4.04E+OO 4.04E+OO 1.02E+01 u pCi/g 18-05068-07 TRG B3-06214-AFIWC-009CV 05/03/18 15:30 ; 5/15/2018 5/15/2018 18-05068 Thorium-234 EPA 901.1 Modified -8.85E+OO : 1.30E+01  ; 1.30E+01 2.52E+01 u pCi/g 1s,_n,;n~s,_n7 TRG B3-06214-AFIWC-009CV 05/03/18 15:30 \ 5/15/2018 5/15/2018 18-05068 i Thallium-208 EPA 901.1 Modified 5.02E-01  : 4.08E+OO 4.08E+OO 7.59E-01 u pCi/g 18-05068-07 i TRG

- 83-06214-AFIWC-009CV 05/03/18 15:30 / 5/15/2018 5/15/2018 , 18-05068 i Uranium-235 EPA901.1 Modified -4.21E+01 i 2.93E+01 2.94E+01 1.25E+01 u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE ANA.LYTiCAL CAL CORPORATION 865/481-0683 FAX 865/ 483-4621 [57]

Printed: 6/5/2018 2:25 PM Page 10 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical ****** *.---"~-" ** ** ************"* --~~-----*w" ---***---*****-*----.--*-*** ..

_____ZionSolutions, LLC _____

SDG:

    • ---**_Purchase Order:_ 677118 ____ *******-~---*--**------------**** __

Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTA

'"'"""*-*---***-------*---*--*------*----*----*- *--*--------~--------,---------~

Zion, IL 60099 Sample Matrix: so i  :

Lab Sample Client Sample Receipt Analysis Batch Report Analyte Method Result cu CSU MDA Qualifier ID Type ID Date Date Date ID  : Units 18-05068-08 TRG B3-06215-AFSWC-013CV

=---~*-=*=,*---------** _,, __ ""-**--

04/26/18 13:00 5/15/2018 5/15/2018 18-05068 Actinium-228 EPA 901.1 Modified  : 5.16E-01 : 2.03E-01 2.05E-01 3.76E-01 pCi/g 18-05068-08 TRG B3-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018 5/15/2018 18-05068 Silver-108m EPA 901.1 Modified  ! 4.43E-03 4.59E-02 4.59E-02 8.53E-02 u pCi/g 18-05068-08 TRG B3-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018 5/15/2018 18-05068 Americium-241 EPA 901.1 Modified  : 4.79E-02 1.26E-01 1.26E-01 1.68E-01 u pCi/g

---*-*-- -~-*--*------*-*---*-*-----*---*

18-05068-08 TRG B3-06215-AFSWC-013CV 04/26/18 13:00  ; 5/15/2018 . 5/15/2018 18-05068 Barium-133 EPA 901.1 Modified  : -1.85E-01 1.16E-01 1.17E-01 1.09E-01 u pCi/g 18-05068-08 TRG B3-06215-AFSWC-013CV 04/26/18 13:00 , 5/15/2018 5/15/2018 18-05068 Bismuth-214 EPA 901.1 Modified 6.52E-01 2.19E-01 2.22E-01 3.49E-01 pCi/g 18-05068-08 TRG 83-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018 5/15/2018 18-05068 Cobalt-60 EPA 901.1 Modified 1.98E-01 7.80E-02 7.86E-02 1.67E-01 pCi/g

- "-"-'"" '.=*m_,_ ----------*---*

18-05068-08

*---**--~--

TRG 83-06215-AFSWC-013CV 04/26/18 13:00

. 5/1 5/15/2018 18-05068 Cesium-134

~-*------------

EPA 901.1 Modified  : -3.17E-03 2.86E-02 2.86E-02 9.06E-02 u pCi/g 18-05068-08 TRG B3-06215-AFSWC-013CV 04/26/18 13:00 , 5/15/2018 , 5/15/2018 18-05068 Cesium-137 EPA901.1 Modified 3.51E-01 1.27E-01 1.29E-01 1.83E-01 pCi/g

=--------*-'""' -

18-05068-08 TRG B3-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018 5/15/2018 18-05068 '  :::u, -~*-* w 152 EPA 901.1 Modified 1.70E-02 2.39E-01  : 2.39E-01 2.30E-01 u pCi/g

--~-=,'~-~----- ' -----------*---,,

18-05068-08 TRG , __

B3-06215-AFSWC-013CV 04/26/18 13:00  : 5/15/2018 5/15/2018 18-05068  :::::u1-,...., ... ,11-154 EPA 901.1 Modified  : 3.98E-02 2.17E-01 2.17E-01 1.16E-01 u pCi/g 18-05068-08 TRG 83-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018 5/15/2018 18-05068 Europium-155 EPA 901.1 Modified 3.34E-01 ! 1.36E-01 1.37E-01 2.08E-01 u pCi/g

. ,----,------------ ------- *---------------~-------~-=-  :

18-05068-08 TRG 83-06215-AFSWC-013CV 04/26/18 13:00 : 5/15/2018 5/15/2018 18-05068  : Holmium-166m EPA 901.1 Modified 5.22E-02 1.01E-01 1.01E-01 9.66E-02 u pCi/g

  • ---~---------

18-05068-08 TRG B3-06215-AFSWC-013CV 04/26/18 13:00  ; 5/15/2018 5/15/2018 18-05068 1 lodine-129 EPA 901.1 Modified *6.01E-03 8.27E-02 8.27E-02 1.07E-01 u pCi/g 18-05068-08 TRG 83-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018

  • 5/15/2018 18-05068 Potassium-40 EPA901.1 Modified 5.75E+OO 1.27E+OO

' 1.30E+OO 1.48E+OO pCi/g 18-05068-08 TRG 83-06215-AFSWC-013CV 04/26/18 13:00  : 5/15/2018 5/15/2018 18-05068 Manganese-54 EPA 901.1 Modified i 7.66E-02 6.92E-02 6.93E-02 1.24E-01 u pCi/g 18-05068-08 i TRG B3-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018

  • 5/15/2018 18-05068 Niobium-94 EPA 901.1 Modified 3.81E-02 6.22E-02 6.23E-02 1.06E-01 u pCi/g 18-05068-08 ' TRG B3-06215-AFSWC-013CV 04/26/18 13:00 i 5/15/2018 5/15/2018 18-05068 : Lead-210 EPA 901.1 Modified  ! 1.17E+OO 8.92E-01 8.94E-01 1.50E+OO u pCi/g 18-05068-08 ' TRG 83-06215-AFSWC-013CV 04/26/18 13:00  ! 5/15/2018 5/15/2018 18-05068 i Lead-212 EPA 901.1 Modified 3.95E-01 . 1.45E-01 1.47E-01 2.18E-01 u pCi/g 18-05068-08 ' TRG 83-06215-AFSWC-013CV 04/26/18 13:00 i 5/15/2018
  • 5/15/2018 18-05068 : Lead-214 EPA 901.1 Modified 6.51E-01 1.64E-01 1.68E-01 3.30E-01 pCi/g

' u 18-05068-08 TRG 83-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018 5/15/2018 18-05068 , Promethium-145 EPA 901.1 Modified 5.53E-02 8.78E-02 8.78E-02 1.43E-01 pCi/g 18-05068-08 TRG B3-06215-AFSWC-013CV

-- 04/26/18 13:00  ; 5/15/2018  ! 5/15/2018 18-05068 : Radium-226 EPA 901.1 Modified 6.52E-01 2.19E-01 2.22E-01 3.49E-01 pCi/g 18-05068-08 TRG B3-06215-AFSWC-O 13CV 04/26/18 13:00 / 5/15/2018 , 5/15/2018 18-05068 Antimony-125 EPA 901.1 Modified 9.92E-03 ! 1.63E-01 1.63E-01 2.74E-01 u pCi/g

_____Thonum-234 u

! 04/26/18 13:00  ; 5/15/2018 5/15/2018 18-05068 EPA 901.1 Modified 2.13E+OO 1.28E+OO 1.28E+OO 1.86E+OO pCi/g 18-05068-08 TRG 83-06215-AFSWC-013CV ,,,,,  :

18-05068-08

  • TRG 83-06215-AFSWC-013CV 0 4 / 2 6 ~ ~ 5/15/2018
  • 5/15/2018 18-05068 Thallium-208 EPA901.1 Modified 4.43E-01 ! 2.22E-01  ; 2.23E-01 4.80E-01 u pCi/g

,(n *--*-no TRG B3-06215-AFSWC-013CV 04/26/18 13:00 5/15/2018 5/15/2018 18-05068 Uranium-235 EPA 901.1 Modified 4.26E-01 i 8.94E-01  ! 8.95E-01 5.20E-01 u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE ANALYT!CAL EBERUNE

! 601 SCARBORO ROAD OAK RIDGE, TN 37830 CAL CORPORATION 865/481-0683 FAX 865/483-4621 [58]

Printed: 6/512018 2:25 PM Page 11 of 19 Report To- Work Order Details:

Patricia Giza 18-05068 Eberline Analytical ,--------

Zion Solutions, LLC Purchase Order:

SDG:

677118 ________

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Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL

      • ---------- ---"----------------~----

Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report ID Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units 18-05068-09 TRG 83-06215-AFSFC-003CV 04126118 13:40 5115/2018 5/1612018 18-05068 Actinium-228 EPA 901_1 Modified i 6_29E-01 3_52E-01 3_53E-01 6.48E-01 u pCi/g 18-05068-09 TRG 83-06215-AFSFC-003CV 04126/18 13:40 5115/2018 5/1612018 18-05068 Silver-108m EPA 901_1 Modified 6_92E-03 6_66E-02 6_66E-02 1_56E-01 u pCilg 18-05068-09 TRG 83-06215-AFSFC-003CV 04126/18 13:40 5115/2018 5/1612018 18-05068 Americium-241 EPA901_1 Modified  : -6.46E-01 3_34E-01 3_36E-01 3_72E-01 u pCilg 18-05068-09 TRG 83-06215-AFSFC-003CV . ____________

04/26118 13:40 5115/2018 5/1612018 18-05068 Barium-133 EPA 901 _1 Modified 3_71E-02 2_06E-01 2_06E-01 3_85E-01 u pCilg

~-------------------*--------------"-*-*-*-

18-05068-09 ..,, TRG 83-06215-AFSFC-003CV" 04126118 13:40 5/15/2018.__,_,,_,

5/1612018 18-05068

~"-""~'"'"~--,-,--,-,-,_, ______

Bismuth-214 EPA 901 _1 Modified  : 7_91E-01 3_44E-01 3.46E-01 6_06E-01 pCilg 18-05068-09 TRG 83-06215-AFSFC-003CV 04/26118 13:40 5115/2018 5/16/2018 18-05068 Cobalt-60 EPA901_1 Modified  ! -4_94E-03 i

9_77E-02

' 9_77E-02 1_51E-01 u pCi/g 18-05068-09 TRG 83-06215-AFSFC-003CV 04/26118 13:40  : 5115/2018 5/1612018 18-05068 ' Cesium-134 EPA 901_1 Modified I -5_00E-03 8_07E-02 8_07E-02 1_73E-01 u pCi/g i

18-05068-09 TRG 83-06215-AFSFC-003CV 04126/18 13:40  : 5115/2018 5/1612018 18-05068 ; Cesium-137 EPA901_1 Modified I 7_00E+01 7_39E+OO 8_21E+OO 7_81E-01 pCilg

TRG 18-05068-09 83-06215-AFSFC-003CV 04126118 13:40 5/1512018 5/16/2018 18-05068 i - "'"

cu1 .... ,..,-,,,'I.JL. EPA 901_1 Modified -3_59E-01 i 9_44E-01 9_44E-01 6_04E-01 u pCilg 5115/2018 5116/2018 18-05068 ",..., EPA 901 _1 Modified 1_70E-01 2_04E-01 2_04E-01 3_03E-01 u pCilg 18-05068-09 18-05068-09 TRG TRG 83-06215-AFSFC-003CV 83-06215-AFSFC-003CV 04126/18 13:40 04/26118 13:40 5115/2018 5116/2018 18-05068 :

LUl'""I'"-'

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.__""I'"- 'I.JV EPA901_1 Modified i -4_20E-02 I 2_63E-01 2_63E-01 4_15E-01 u pCi/g 18-05068-09 TRG B3-06215-AFSFC-003CV 04/26118 13:40  : 5/1512018 5/1612018 18-05068 : Holmium-166m EPA 901 _1 Modified I 2_84E-02 1_39E-01 1_39E-01 2_24E-01 ' u pCilg 18-05068-09 TRG 83-06215-AFSFC-003CV 04126118 13:40  ; 5/1512018 5/1612018 18-05068 i lodine-129 EPA901_1 Modified i -1.49E-02 4_44E-01 4.44E-01 5_62E-01 u pCilg

~-*--

18-05068-09 :.,

18-05068-09 TRG TRG

__ 83-06215-AFSFC-003CV 83-06215-AFSFC-003CV 04/26118 13:40 04/26/18 13:40 5/1512018

5/1512018 511612018 5116/2018 18-05068 18-05068 Manganese-54

,n EPA 901_1 Modified EPA 901 _1 Modified I

7_13E+OO

-2_74E-02 :

1_78E+OO 9_97E-02  :

1_82E+OO 9_97E-02 1_94E+OO 1.48E-01 u pCilg pCilg 18-05068-09 : TRG 83-06215-AFSFC-003CV 04126/18 13:40 5/1512018 5116/2018 18-05068 ! Niobium-94 EPA 901_1 Modified l 6_82E-02 7_61E-02 7_62E-02 1_36E-01 u  : pCilg 18-05068-09 TRG 83-06215-AFSFC-003CV 04/26/1813:40  ; 5/1512018 5/1612018 18-05068 I Lead-210 EPA 901 _1 Modified  ! 2_18E-01 3_01E+OO 3_01E+OO 3_82E+OO u pCilg 18-05068-09 ' TRG i 83-06215-AFSFC-003CV 04126118 13:40 5115/2018 5116/2018 18-05068 Lead-212 EPA 901_1 Modified  : 1_10E-01 ' 2_71E-01 2_71E-01 4_37E-01 u pCi/g 18-05068-09 TRG B3-06215-AFSFC-003CV 04126118 13:40  : 5115/2018 5/1612018 18-05068 Lead-214 EPA 901_1 Modified  ! 7_31E-01 i 4_37E-01 4_39E-01 8_28E-01 u pCilg 18-05068-09 TRG 83-06215-AFSFC-003CV 04126/18 13:40 5115/2018 5/1612018 18-05068 , Promethium-145 EPA 901 _1 Modified I 2_35E+OO I 4_57E-01  ; 4_72E-01 6_21E-01 u I pCilg

- I 1n -- -- M TRG i 83-06215-AFSFC-003CV 04126/18 13:40

! 5/1512018 : 5/1612018

* 18-05068 Radium-226 EPA 901_1 Modified I 7_91E-01 3.44E-01 ' 3.46E-01 6_06E-01 pCilg 18-05068-09 TRG 83-06215-AFSFC-003CV 04126/18 13:40 5115/2018 ' 5/1612018 18-05068 M<"""-"' *--

EPA 901 _1 Modified .1 1_72E-01 8.48E-01 ' 8.48E-01 1_24E+OO u pCilg 18-05068-09 TRG ' 83-06215-AFSFC-003CV 04126/18 13:40 i 5115/2018 5/1612018 18-05068 ; Thorium-234 EPA 901_1 Modified I 6_65E+OO  : 2_88E+OO 2_90E+OO 4_01E+OO u pCilg 18-05068-09 TRG 83-06215-AFSFC-003CV 04126/18 13:40  : 5115/2018 , 5116/2018 18-05068 : Thallium-208 EPA901_1 Modified i 2_65E-01 i 4_73E-01 4_73E-01 7_31E-01 u  : pCilg 18-05068-09 TRG 83-06215-AFSF C-003CV 04/26118 13:40  : 5115/2018 5/16/2018 18-05068 Uranium-235 EPA 901 _1 Modified J 9_74E-01  : 2_31E+OO  : 2_31E+OO 1_18E+OO u pCilg CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect

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EBERLINE A NAi

,--,,._ y,irA'L EBERLINE A_NAL YTICAL CORPORATIOt>J 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [59]

Printed: 6/5/2018 2:25 PM Page 12 of 19 Report To: Work Order Details:

Eberline Analytical ,,, ..............

Patricia Giza SDG:

....... ..... .. -.----*--*--*-*--*- ....... --~*--*---

18-05068 ... .. ....

Purchase Order:

.....- .. Zion Solutions, LLC --,- ...... *------ --**---------*---*-* *-*--"------*--*-*--------**---*-*-*---------------*--*-*--*--*---"-*----*----~------* 677118 Final Report of Analysis

- 101 Shiloh Blvd

~-----**---*---------*---- --**-- ------*----*-----

Zion, IL 60099 Analysis e,;aregory Sample MatriK' ENVIRONMENTAL so Lab Sample Client Sample Receipt Analysis Batch Report ID Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units 18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 Actinium-228 EPA901.1 Modified 5.87E-01  :

2.73E-01 .75E-01 5,12E-01 pCi/g

~-~**-*--*---... --*~*=-----*-- *-~--- ---*-*-*-------* **-*---*------....*-*-*--*--~-*- *--*---*"----*-

18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 Silver-108m EPA 901..1 Modified  : -1.64E-02 7 . 63E-02 . 63E-02 7.76E-02 u pCi/g 18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 Arnericium-241 EPA 901..1 Modified  : -5.89E-02 8,79E-02 l ,80E-02 u

_________ _____..__ ~----------"

1..64E-01 pCi/g 18-05068-10

,  : TRG ,., 83-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018

' -------"-------*="-----",""--'

18-05068 Barium-133 EPA901.1 Modified  : -7.20E-02 *

1..05E-01 .05E-01 1.20E-01 u pCi/g 18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 Bismuth-214 EPA 901..1 Modified  ! 7.37E-01 1.91E-01 . 94E-01 3.05E-01 pCi/g I----------

18-05068-10

"_, ____,.,..,_, TRG 83-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 ' 5/16/2018 18-05068 ; Cobalt-60 EPA 901..1 Modified "--------" ________

7 . 92E-02 "_.,,__,.. ___________

5 . 37E-02  : . 39E-02 1..09E-01 u pCi/g 18-05068-10 TRG B3-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 Cesium-134 EPA 901..1 Modified i -1.56E-01 9,04E-02  ! .07E-02 9.11E-02  : u pCi/g 18-05068-10 i TRG B3-06216-AFSWC-006CV 04/30/18 08:35  : 5/15/2018 5/16/2018 18-05068 : Cesium-137 EPA 901..1 Modified 2,58E-01 ' 1.08E-01 .09E-01 1,57E-01 pCi/g 18-05068-10 TRG B3-06216-AFSWC-006CV 04/30/18 08:35 ' 5/15/2018 5/16/2018 18-05068 ~u,vpou, ,52 EPA 901..1 Modified i 1.92E-01  : 1.85E-01 .85E-01 2.33E-01 u

18-05068-10 ; TRG 83-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 Europium-154 EPA 901.1 Modified i 9..59E-02 L81E-01 ,81E-01 1..18E-01 u i

  • - u 18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35  : 5/15/2018 : 5/16/2018 18-05068 ' :u,vpov,., 155 EPA 901.1 Modified 7,63E-02 l 1.46E-01 .46E-01 1. 95E-01 pCi/g 18-05068-10 TRG B3-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 Holmium-166m EPA 90L1 Modified 5,61E-02 1..18E-01 .18E-01 9.87E-02 u pCi/g 18-05068-10 TRG 83-06216-AFSWC-006CV 04130118 08:35

....I 511512018 511512018 ' 18-05068 :- lodine-129

~

EPA 901..1 Modified 8.67E-02 7 . 39E-02 .40E-02 1..13E-01 u ' pCi/g 18-05068-10 TRG ' B3-06216-AFSWC-006CV 04/30/18 08:35 j 5/15/2018 5/16/2018 18-05068 Potassium-40 EPA 901.1 Modified 4,81E+OO U5E+OO . 17E+OO 1.08E+OO pCi/g 18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 ' ....... ,::, .... ,,.............. EPA 901.1 Modified 2 . 11E-02  : 6.37E-02 ' I .37E-02 1..03E-01 u  : pCi/g 18-05068-10 i TRG 83-06216-AFSWC-006CV 04/30/18 08:35 , 5/15/2018 5/16/2018 18-05068 Niobium-94 EPA 901..1 Modified 3.35E-02 6.53E-02 I .53E-02 1..09E-01 u ,-

pCi/g 18-05068-10 TRG B3-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 ! Lead-210 EPA 901..1 Modified  ! 1..17E+OO  : 8B6E-01 I ,89E-01 1.49E+OO u pCi/g 18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35 5/15/2018 5/16/2018 18-05068 j Lead-212 EPA 901.1 Modified 3,95E-01 l 1.82E-01 .83E-01 2.84E-01 ' pCi/g 18-05068-10 TRG B3-06216-AFSWC-006CV 04/30/18 08:35 , 5/15/2018 5/16/2018 18-05068 : Lead-214 2,81E-01 .85E-01 3,81E-01 pCi/g EPA 901..1 M o d i f i e ~ ~ 1  !

18-05068-10 TRG ' 83-06216-AFSWC-006CV 04/30/18 08:35 i 5/15/2018 i 5/16/2018 18-05068 i Promethium-145 EPA 901 . 1 Modified -02  ! 8 . 75E-02 I . 75E-02 1.31E-01 u i pCi/g 1

::~::":: 10 TRG . 83-06216-AFSWC-006CV 04/30/18 08:35  : 5/15/2018 5/16/2018 18-05068  ! Radium-226 EPA 901 . 1 Modifi;d ,37E-01  ; 1.91E-01 i . 94E-01 3.05E-01 i pCi/g 18-05068-1 0 TRG 83-06216-AFSWC-006CV 04/30/18 08:35  ! 5/15/2018 5/16/2018 ' 18-05068 ! ,.;;.,,v.,y I.CO EPA 901..1 Modified 1 . 37E-01 ' 1. 59E-01 ..59E-01 2 . 80E-01 u pCi/g 18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35 \ 5/15/2018 5/16/2018 , 18-05068 Thorium-234 EPA 901.1 Modified 2,01E+OO  : ,44E+OO 1,44E+OO 2 . 36E+OO u pCi/g 18-05068-10 TRG 83-06216-AFSWC-006CV 04/30/18 08:35  : 5/15/2018 5/16/2018 18-05068 Thallium-208 EPA 901..1 Modified 2.90E-01  ! 1.92E-01  : . 93E-01 4.00E-01 u pCi/g 18-05068-10 TRG  : 83-06216-AFSWC-006CV 04/30/18 08:35 I 511512018 5/16/2018 : 18-05068 i Uranium-235 EPA 901..1 Modified -4.12E-01 t 1 . 01E+OO . 01E+OO 5. 11E-01 u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Norrnal Sample;DO=Duplicate Original;U=Non-detect

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EBERLINE ANALYT!CAL EBERLINE 601 SCARBORO ROAD OAK RIDGE, TN 37830 CAL CORPORATION 865/481-0683 FAX 865/483-4621 [60]

Printed: 61512018 2:25 PM Page 13 of 19 Report To: Work Order Details:

Eberline Analytical ********

Patricia Giza ......... -*-**

SDG:

.. ~. *--

18-05068

    • -'-"-**-e*woe-.--*-------*-****-*-.,*** . ....

Zion Solutions, LLC Purchase Order: 677118

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Zion, IL 60099 Sample Matrix: so . Report Lab Sample Client Sample Receipt Analysis Batch ID Type ID Date Date Date Analyte Method Result cu CSU MDA Qualifier ID  ; Units 18-05068-11

  • TRG B3-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018

~---*-*-*----*-*--------------

18-05068 Actinium-228 EPA 901.1 Modified 7.17E-01  :: 5.60E-01 5.62E-01 9.88E-01 u pCi/g 18-05068-11 . TRG B3-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 Si1ver-108m EPA 901.1 Modified 7.43E-02 1.63E-01 1.63E-01 2.67E-01 u pCi/g 18-05068-11 TRG B3-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 ' Americium-241 EPA 901.1 Modified -5.16E-01  : 3.33E-01 3.34E-01 5.04E-01 u pCi/g

**-~--------------*----*"i *--------~*-*  ;

18-05068-11 TRG B3-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 Barium-133 EPA 901.1 Modified  ; 1.24E-02 i 1.65E-01 1.65E-01 5.34E-01 u pCi/g

  • ---~--------------*-~---- --*----------*,,----"""~---------~----,,--------*---

18-05068-11 TRG 83-06216-AFSFC-002CV 04/26/18 15:20 , 5/15/2018 5/16/2018 18-05068 Bismuth-214 EPA 901.1 Modified  : 9.55E-01 4.94E-01 4.96E-01 8.22E-01 u pCi/g 18-05068-11 TRG B3-06216-AFSFC-002CV 04/26/18 15:20 , 5/15/2018 5/16/2018 18-05068 EPA 901.1 Modified 5.31E-02 1.42E-01 1.42E-01 2.48E-01 u pCi/g 18-05068-11 i TRG B3-06216-AFSFC-002CV

,----------+---------------------------: ----

04/26/18 15:20 5/15/2018 5/16/2018 18-05068 Cesium-134 EPA 901.1 Modified 4.96E-01

. 2.40E-01 2.41E-01 2.77E-01 u pCi/g 18-05068-11 TRG B3-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 ; Cesium-137 EPA 901.1 Modified i 2.03E+01  ! 2.20E+OO 2.43E+OO 5.26E-01 pCi/g 18-05068-1  : TRG B3-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 : Europium-152 EPA 901.1 Modified

,N,e--,m*-,*

3.44E-01 8.06E-01 8.06E-01 8.34E-01 u pCi/g 18-05068-11 ' TRG B3-06216-AFSFC-002CV 04/26/18 15:20 ! 5/15/2018 5/16/2018 18-05068 Europium-*154 EPA 901.1 Modified -1.23E-01 12E-01  ; 4.13E-01 4.24E-01 u pCi/g 18-05068-11

TRG  ; 83-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 Europium-155 EPA 901.1 Modified i 5.37E-01  ; 2.79E-01 2.80E-01 5.88E-01 u pCi/g 18-05068-11 \ TRG B3-06216-AFSFC-002CV 04/26/18 15:20 , 5/15/2018 5/16/2018 18-05068 ; Holmium-166m EPA 901.1 Modified  ; -1.29E-01 2.79E-01 2.79E-01 3.47E-01 u pCi/g 18-05068 :  : -7.75E+OO  : u 18-05068-11 , TRG  ; B3-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 lodine-129 EPA 901.1 Modified i 3.72E+OO 3.74E+OO 2.41E+OO  ; pCi/g 18-05068-11  : TRG B3-06216-AFSFC-002CV

--~--~-- - - * - - - - -

04/26/18 15:20 5/15/2018 16/20 18-05068 Potassium-40 EPA 901.1 Modified 8.04E+OO 2.43E+OO i 2.46E+OO 2.97E+OO  :

pCi/q 18-05068-11 TRG 83-06216-AFSFC-002CV 04/26/18 15:20 ; 5/15/2018 5/16/2018 18-05068 , Manganese-54 EPA 901.1 Modified 9.11E-02 1.45E-01 i 1.45E-01 2.46E-01 u pCi/q 18-05068-11 TRG B3-06216-AFSFC-002CV

_ _ _ _ _ _ _ _ ,m 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 ., __ ,_, -

n EPA901.1 Modified -8.88E-02 1.53E-01 1.53E-01 2.16E-01 u  : pCi/g 18-05068-11  : TRG I B3-06216-AFSFC-002CV 04/26/18 15:20 ; 5/15/2018 5/16/2018 18-05068 Lead-210 EPA 901.1 Modified -9.76E+OO i 3.71 E+OO 3.74E+OO 6.20E+OO u . pCi/g 18-05068-11 TRG B3-06216-AFSFC-002CV 04/26/18 15:20 ' 5/15/2018 ' 5/16/2018 18-05068 Lead-212 EPA 901.1 Modified -9.72E-03 9.45E-02 ' 9.45E-02 7.10E-01 u ' pCi/g 18-05068-11 TRG  : B3-06216-AFSFC-002CV 04/26/1815:20  : 5/15/2018 5/16/2018 18-05068 ; Lead-214 EPA901.1 Modified 1.64E+OO 8.52E-01 8.56E-01 1.23E+OO : pCi/g j "1v,-*1.. ....:::: '

18-05068-11 TRG  ; B3-06216-AFSFC-002CV 04/26/18 15:20 ! 511512018 5/16/2018 18-05068 '4 At::. EPA 901.1 Modified 4.51E-02 3.86E-01 3.86E-01 1.29E+OO u pCi/g 18-05068-11 TRG B3-06216-AFSFC-002CV 04/26/18 15:20 i 5/15/2018 5/16/2018 18-05068 ' Radium-226 EPA 901.1 Modified 9.55E-01 4.94E-01  ; 4.96E-01 8.22E-01 u pCi/g 18-05068-11 TRG i B3-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 ; Antimony-125 EPA901.1 Modified -6.83E-01 1.07E+OO 1.07E+OO 1.52E+OO ; u pCi/g 18-05068-11 TRG  ; 83-06216-AFSFC-002CV 04/26/18 15:20 ! 5/15/2018 5/16/2018 18-05068 ' Thorium-234 EPA 901.1 Modified -1.55E+OO , 2.52E+OO 2.52E+OO 4.67E+OO u  ; pCi/q 18-05068-11 TRG  ! B3-06216-AFSFC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 ' Thallil'--'nA EPA 901.1 Modified 7.01E-01 2.91E-01 2.94E-01 1.20E-01  ; pCi/g 18-05068-11 TRG 63-06216-AFS FC-002CV 04/26/18 15:20 5/15/2018 5/16/2018 18-05068 [ Uranium-235 EPA 901.1 Modified -1.58E-01 , 3.80E+OO 3.80E+OO 1.87E+OO u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect EBERLINE EBERLINE CAL CORPORATION

~ ANALYT!CAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [61]

Printed: 6/5/2018 2:25 PM Page 14 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical __ .... Zion Solutions, LLC Purchase Order:

SDG:

677118

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Final Report of Analysis 101 Shiloh Blvd Analysis Category:

            • - - ***sample Matrix~ SO ENVIRONMENTAL Zion, IL 60099 Lab Sample Client Sample Receipt ' Analysis Batch Report ID i

Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units 18-05068-12 ' TRG B1-06214-AFSWC-005CV 05/05/1814:35 5/15/2018 5/16/2018 18-05068 Actinium-228 EPA901.1 Modified ' 6.46E-01 5.15E-01 5.16E-01 9.17E-01 U pCi/g

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18-05068-12 TRG TRG B1-06214-AFSWC-005CV B1-06214-AFSWC-005CV

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Bismuth-214 Cobalt-60 EPA901.1 Modified i 6.66E-01 3.27E-01

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EPA901.1 Modified ' 4.21E-02 1.42E-01 3.29E-01 1.42E-01 5.46E-01 2.26E-01 U pCi/g pCi/g

" - * - - * - -..- - * - - * - * * * - - - * - ~ - - - - - - - - - - - - - , - * - - - - * - * - - - - - - - - * - - * - - * * - -...-**-'-**"""""" _____* - - J - - - - - * * * * - - - - * - - - - " * ~ - -...,*--**-*---*------**--*--*--***-**------**-*--*-*******-****-*--------1 18-05068-12 TRG B1-06214-AFSWC-005CV 05/05/1814:35 5/15/2018 5/16/2018 18-05068 Cesium-134 EPA 901.1 Modified -9.90E-01 3.60E-01 3.63E-01 2.24E-01 U pCi/g

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    • --- 05/05/1814:35  : 5/15/2018 5/16/2018 18-05068 Cesium-137 EPA901.1 Modified 1.33E+OO

- + - - - - - - - - - - ' - - - - - , . . . . ; . . . - - , -.., - - . * - - - -...- - - - - - * - -.....-1------*--------+-----~-*---...----------*--*----*-------....-.., - - . - - - - - 1 3.29E-01 3.36E-01 3.96E-01 pCi/g 18-05068-12 ~--~..1_::~6~1.4-A!'.:SWC-005CV 05/05/1814:35 5/15/2018 5/16/2018 18-05068 ; ~u, .. " .... '52 EPA901.1 Modified -2.40E-01 4.67E-01 4.67E-01 3.70E-01 U pCi/g 18-05068-12 ; TRG B1-06214-AFSWC-005CV 05/05/1814:35 5/15/2018, 5/16/2018 18-05068 i ~"' .. c-* '5' EPA901.1 Modified -1.50E-01 3.66E-01 3.67E-01 1.84E-01 U pCi/g 18-05068-12 I TRG B1-06214-AFSWC-005CV 05/05/1814:35  : 5/15/2018 5/16/2018 18-05068 i  ::u, .. c*---* :c EPA901.1 Modified 5.44E-02 1.95E-01 1.95E-01 2.88E-01 U pCi/g 18-05068-12 : TRG B1-06214-AFSWC-005CV 05/05/1814:35 [ 5/15/2018 5/16/2018 18-05068 Holmium-166m EPA901.1 Modified , -5.73E-02 2.70E-01 2.70E-01 1.46E-01 U pCi/g 18-05068-12 : TRG B1-06214-AFSWC-005CV 05/05/18 14:35 i 5/15/2018 ' 5/16/2018 18-05068 lodine-129 EPA 901.1 Modified 5.31E-04 2.86E-02 2.86E-02 1.05E-01 U pCi/g 18-05068-12 TRG ' B1-06214-AFSWC-005CV 05/05/1814:35  ! 5/15/2018 5/16/2018 , 18-05068  ! Potassium-40 EPA901.1 Modified i 5.38E+OO 2.56E+OO 2.57E+OO , 3.76E+OO pCi/g 18-05068-12 TRG B1-06214-AFSWC-005CV 05/05/1814:35 1 5/15/2018 5/16/2018 18-05068  ! ...... EPA901.1 Modified -8.35E-02 1.43E-01 1.43E-01 2.11E-01 U pCi/g

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18-05068-12 TRG B1-06214-AFSWC-005CV 05/05/1814:35 i 5/15/2018 5/16/2018 18-05068 f Niobium-94 EPA901.1 Modified 9.26E-02  : 1.22E-01 1.22E-01 2.09E-01 U pCi/g 18-05068-12 TRG B1-06214-AFSWC-005CV 05/05/1814:35 [ 5/15/2018 5/16/2018 18-05068 Lead-210 EPA901.1 Modified 1.95E+OO 1.29E+OO 1.29E+OO 2.04E+OO U pCi/g 18-05068-12 , TRG B1-06214-AFSWC-005CV 05/05/1814:35 5/15/2018 5/16/2018 ' 18-05068 ; Lead-212 EPA901.1 Modified 3.08E-01  ; 1.92E-01 1.93E-01 3.07E-01 , U pCi/g

  • ------;--------*-------------------... - - - - - - - - * - + - - - - - - - - - - * - - - - ' - - - - - - -...---------------*---...i.....--J 1-1_8_-0_5_0__6a-_12__,'__ G__.,* ___s_...1_-o-6_2_14_-A_F___s_w_c_.._o_o5_c_v_ _ _-+-*?.5_1_05_11_8_1__4_:3_5~__5_11_5_12_0_18__5_11_6_1_2_0__

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1 1 1 18-05068-12 B1-06214-AFSWC-005CV 05/05/1814:35 \ 5/15/2018

  • 5/16/2018 . 18-05068 Radium-226 EPA901.1 Modified 6.66E-01 ' 3.27E-01 3.29E-01 5.46E-01 pCi/g

,_.1_8--0-5-06-8--1_2_,___T-RG-*~--B-1--0-62_1__4_-A_F_S_W_C___ 00_5_C_V____ _,__05_/_05-/1_8._1_4-:3_5___+-5-/1-5/-20-18-5/16/2018 18-05068 ....-.....-.. ,-.~

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  • U pCi/g

~--------*-*---*

18-05068-12 TRG B1-06214-AFSWC.005CV 05/05/1814:35

  • 5/15/2018 5/16/2018 18-05068
  • Uranium-235 EPA901.1 Modified -8.81E-01  : 1.48E+OO 1.48E+OO
  • 7.97E-01 U pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

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EBERLINE ANALYTICAL EBERLINE 601 SCARBORO ROAD OAK RIDGE, TN 37830 LYTICAL CORPORATION 865/481-0683 FAX 865/483-4621 [62]

Printed: 6/5/2018 2:25 PM Page 15 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical ,*..

Zion_Solutions, LLC SDG:

          • -****-*--~-*--*m**m***-**,---***- ****- ... **-** ,,,~ *--***----***.,-**---

Purchase Order: 677118

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    • ----*-*"""""'"'-"---*---->*--"-""-------*-*-----*-*--*---=---*--*-"-""'--"----- -

Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL

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Zion, IL 60099 Sample Matrix: so Lab ID

! Sample Type Client ID Sample Date Receipt Date Analysis Date Batch ID Analyte Method Result cu CSU MDA Qualifier Report Units 18-05068-13 ' B1-06214-AFSFC-004CV 05/05/18 14:55 5/15/2018 5/16/2018 Actinium-228 EPA 901.1 Modified 3.91E-01 u 18-05068-13 i TRG TRG B 1-06214-AFSFC-004CV 05/05/18 14:55 5/15/2018

, ----~-18-05068 5/16/2018 18-05068

- ---------"*-*-*-- --*-*----*-----*~*--*-m :-mw""'4A2E-01 Silver-108m EPA 901.1 Modified

-1.91E-03 3.91E-01 7.95E-02 7.95E-02 6.97E-01

--~-~-------*= ----*-*-*

1.57E-01 u pCi/g pCi/g

--- *=---------~*~-~-------,-,-"_______

18-05068-13 TRG B1-06214-AFSFC-004CV 05/05/18 14:55 5/15/2018 5/16/2018 18-05068 Americium-241 EPA901.1 Modified UOE-01 2.54E-01 2.54E-01 3.38E-01 u pCi/g 18-05068-13

------~,-----------*----------~--- ---

TRG B1-06214-AFSFC-004CV 05/05/18 14:55 5/15/2018 , 5/16/2018

--=------* ------------

18-05068 Barium-133 EPA 901. 1 Modified  : 3.79E-02 1.76E-01 1.76E-01 3.37E-01 u pCi/g 18-05068-13 l TRG B 1-06214-AFSFC-004CV 05/05/1814:55  : 5/15/2018 5/16/2018 18-05068 Bismuth-214 EPA 901.1 Modified 1.04E+OO 3.00E-01 3.05E-01 5.83E-01 pCi/g 18-05068-13 TRG B1-06214-AFSFC-004CV 05/05/18 14:55 i 5/15/2018 : 5/16/2018 18-05068 Cobalt-60 EPA 901.1 Modified -2A5E-02  : 1.03E-01 1.03E-01 1A5E-01 u pCi/g

,--~-----~-----------

18-05068-13 : TRG B1-06214-AFSFC-004CV 05/05/18 14:55 5/15/2018 5/16/2018 18-05068 Cesium-134 EPA 901.1 Modified 2.76E-02 7.97E-02 7.97E-02 1.78E-01 u pCi/g 18-05068-13 i TRG B1-06214-AFSFC-004CV 05/05/18 14:55  : 5/15/2018 5/16/2018 18-05068 Cesium-137 EPA 901.1 Modified 4.16E+01 4.13E+OO 4.65E+OO 3.77E-01 pCi/g 18-05068-13 [ TRG B1-06214-AFSFC-004CV 05/05/18 14:55 I 511512018 5/16/2018 ' 18-05068 ' Europium-152 EPA 901. 1 Modified  : 3.06E-01 7.54E-01 7.54E-01 5AOE-01 u pCi/g 18-05068-13 I TRG B1-06214-AFSFC-004CV 05/05/18 14:55  ; 5/15/2018 ' 5/16/2018 18-05068 Europium-154 EPA 901. 1 Modified 1A5E-01 i 2.59E-01 2.59E-01 2.77E-01 u pCi/g 18-05068-13 TRG B 1-06214-AFSFC-004CV 05/05/18 14:55  ! 5/15/2018 5/16/2018 18-05068 Europium-155 EPA 901.1 Modified 4.39E-01 2.78E-01  ; 2.79E-01 3.88E-01 u pCi/g 18-05068-13 TRG B1-06214-AFSFC-004CV 05/05/18 14:55 I 511512018 5/16/2018 18-05068 , Holmium-166m EPA901.1 Modified 1.51E-02 8.18E-02 8.18E-02 2.09E-01 u pCi/g

~

18-05068-13

* 05/05/1814:55 5/15/2018 5/16/2018 18-05068 : lodine-129 EPA 901.1 Modified -1.55E+OO 3.70E-01  : 3.79E-01 2A8E-O u pCi/g TRG B1-06214-AFSFC-004CV 18-05068-13 TRG B1-06214-AFSFC-004CV 05/05/1814:55 ) 5/15/2018 5/16/2018 18-05068 : Potassium-40 EPA901.1 Modified i 6.79E+OO 2.05E+OO  : 2.08E+OO 2.64E+OO pCi/g j 5/15/2018 ' 5/16/2018 ! 18-05068 i ' u

18-05068-13 TRG B1-06214-AFSFC-004CV 05/05/18 14:55 18-05068-13 TRG B1-06214-AFSFC-004CV 05/05/18 14:55 , 5/15~_6/2018 18-05068 Niobium-94 EPA 901.1 Modified -1A7E-02 8.85E-02 8.85E-02 1.35E-01 u pCi/g 18-05068-13~G--., B1-06214:AFSFC-004CV 05/05/1814:55 I 5t15t 1612018 18-05068 : Lead-210 EPA 901.1 Modified I 3.23E+OO 1.72E+OO  : 1.73E+OO 2.89E+OO  : u pCi/g 18-05068-13 TRG B1-06214-AFSFC-004CV 05/05/1814:55 i 5/15/2018 5/16/2018 18-05068 : Lead-212 EPA 901.1 Modified 5.64E-01 2.52E-01 2.54E-01 7.69E-01 u pCi/g i u TRG B1-06214-AFSFC-004CV 05/05/18 14:55  : 5/15/2018 5/16/2018 18-05068 ; Lead-214 EPA 901.1 Modified 8.85E-01  : 5.79E-01 5.81E-01 9.29E-01 pCi/g 18-05068-13 i TRG B1-06214-AFSFC-004CV 05/05/18 14:55 i 5/15/2018 5/16/2018 18-05068 : Promethium-145 EPA 901.1 Modified 7.29E-01 l 2AOE-01 I 2A3E-01 3.97E-01 u  : pCi/g 18-05068-13 f TRG i B1-06214-AFSFC-004CV 05/05/18 14:55 i 5/15/2018 : 5/16/2018 18-05068 i Radium-226 EPA 901.1 Modified 1.04E+OO l 3.00E-01  : 3.05E-01 5.83E-01 pCi/g 18-05068-13 / TRG B1-06214-AFSFC-004CV 05/05/18 14:55 / 5/15/2018 i 5/16/2018 : 18-05068 Antimony-125 EPA 901.1 Modified -3.85E-01  : 5.64E-01 ' 5.64E-01 8.76E-01 u pCi/g 18-05068-13 i TRG B1-06214-AFSFC-004CV 05/05/1814:55 i 5/15/2018 5/16/2018 18-05068 Thorium-234 EPA901.1 Modified 2.01E+OO  : 2.60E+OO i 2.61E+OO 3.51E+OO u pCi/g 18-05068-13 i TRG  : B1-06214-AFSFC-004CV 05/05/1814:55 [ 5/15/2018 5/16/2018 ' 18-05068 Thallium-208 EPA 901. 1 Modified

' 4.65E-01 ' 4.14E-01 4.14E-01 7.02E-01 u pCi/g 18-05068-13 [ TRG B1-06214-AFSFC-004CV 05/05/18 14:55 i 5/15/2018 5116/2018 18-05068 I VJQlllUI Me

-~ EPA 901.1 Modified 1.55E+OO i 2.39E+OO 2.39E+OO 1.13E+OO u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect EBERLINE EBERLINE ON

~ ANALYTICAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/ 483-4621 [63]

Printed: 61512018 2:25 PM Page 16 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical * *****-. """' ***~*w**-*---***a. ****-**-n-m,.,_.,~._ _ _._****

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SDG:

677118 Final Report of Analysis *- Analysis Category: ENVIRONMENTAL- -* _ , _______..____ ,___,_

101 Shiloh Blvd Zion, IL 60099 Sample Matrix: SO Lab Sample Client Sample

  • Receipt Analysis Batch Report ID , Type ID Date Date Date ID Analyte Method i Result cu CSU MDA Qualifier Units 18-05068-14 TRG B1-06214-AFSFC-001CV 05/05/18 15:15 f 5/15/2018 5/16/2018 18-05068 f Actinium-228 EPA 90U Modified 6,95E-01 4,52E-01 4,54E-01 7,82E-01 U pCi/g 18-05068-14 TRG B1-06214-AFSFC-001CV 05/05/1815:15 ' 5115/2018 5/1612018 18-05068 Silver-108m EPA90U Modified 4,11E-03 UOE-01 UOE-01 1.76E-01 U pCi/g 18-05068-14 TRG B1-06214-AFSFC-001CV 05/05/1815:15 5/15/2018 5/16/2018 18-05068 Americium-241 EPA 90U Modified I -U4E-01 H2E-01 1,62E-01 2,25E-01 U pCi/g 18-05068-14 TRG B1-06214-AFSFC-001CV 05/05/1815:15 l 5/15/2018 5/16/2018 18-05068 : Barium-133 EPA 90U Modified 2,06E-02 f 9A8E-02 9A8E-02 2,60E-01 U pCi/g

__1_18_-_05_06__S-_~'--,,T_R_G____s_1-_0_62_1_4-_A_F_S_Fc_,-_0_01_c_v______ __0_5_10_5_11_8__1_5:1~-- ;_5115/2018 5/16/2018 18-05068 Bismuth-214 EPA 901,1 Modified R03E-01 2,96E-01 2,99E-01 4,89E-01 pCi/g 1

18-05068-14 ' TRG 61-06214-AFSFC-001 CV 1

05/05/18 15: 15 T 018 18-05068---C-ob-a-lt--6-0_1_,_E_P_A_9_0_1, M--o-difie-d-t--- 6,8-7E*-*0*2---

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18-05068-14 : TRG B1-06214-AFSFC-001CV 05/05/1815:15 i 5/15/2018 5/16/2018 18-05068 Cesium-134 EPA 90U Modified -4,36E-02  : 8,90E-02 8,90E-02 1,94E-01 U pCi/g 18-05068-14 j TRG  : B1-06214-AFSFC-001CV 05/05/18 5:15 5/15/2018 5/16/2018 18-05068 ; Cesium-137 EPA 90U Modified 1A8E+01  : 1.84E+OO L99E+OO 3,09E-01 pCi/g 18-05068-14 ' TRG B1-06214-AFSFC-001CV 05/05/1815:15  ! 5/15/2018 5/16/2018 18-05068 , Europium-152 EPA 90U Modified 3,75E-02 i 4,30E-01 4,30E-01 3,62E-01 U pCi/g

,,------c----------------,-----+-------**--'---,--,----**------------:-----'----j-,--------'*--'-------------------------------------'-------1 18-05068-14 TRG B1-06214-AFSFC-001CV 05/05/1815:15  : 5/15/2018 5/16/2018 18-05068 Europium-154 EPA90U Modified U4E-01 2,55E-01 2,55E-01 1,84E-01 U pCi/g 18-05068-14 TRG , B1-06214::AFSFC-001cv ----1--0_51_05_1_18__ 15__:1___5_!"""51_1_5_1_20_1_8_, ____ 51_16_1_20_1_8 ______

18_-_05_o_6_8 ,_E_ur_o'-pi_um_-1_55---1 _ _E_PA_90_1_,1_M_o_d_ifi_,e_d______;__4_,7_2_E_-0_1--'-,_2___2_8_E_-0_1_'__2_,_29_E_-o_1_ _ _

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4 1 18-05068-14 TRG , B1-06214-AFSFC-001CV 05/05/1815:15 i 5/15/2018. 5/16/2018 18-05068 ! Holmium-166m EPA90U Modified 2.08E-01 2.06E-01 2,06E-01 1,52E-01 U pCi/g 1e :::::.,.. TRG B1-06214-AFSFC-001CV 05/05/1815:15 [ 5/15/2018: 5/16/2018 18-05068 Jodine-129 EPA90U Modified 3,54E-01 8.68E-02 8,87E-02 L39E-01  : U pCi/g 18-05068-14 TRG  : B1-06214-AFSFC-001CV 05/05/1815:15 i 5/15/2018 , 5/16/2018 18-05068 Potassium-40 EPA 901-1 Modified 7,23E+OO 1,94E+OO 1.98E+OO 225E+OO I pCi/g 18-05068-14 TRG B1-06214-AFSFC-001CV 05/05/1815:15 i 5/15/2018 , 5/16/2018 18-05068  ! Manganese-54 EPA 901-1 Modified -4,05E-02 1.17E-01 1.17E-01 1.74E-01 U pCi/g 1: ,., ,., :.. TRG , u ,-v-- ,: 1,,v 05/05/1815:15 ) 5/15/2018 5/16/2018 18-05068 i Niobium-94 EPA 901.1 Modified 1.21E-01 I UOE-01 UOE-01 HOE-01 U pCi/g 1

18-05068-14 TRG ' B1-06214-AFSFC-001CV 05/05/1815:15  : 5/15/2018: 5/16/2018 18-05068 I Lead-210 EPA90U Modified 1.47E+OO 1,30E+OO 1-31E+OO 1,98E+OO i U pCi/g 18-05068-14 TRG B1-06214-AFSFC-001CV _ _ _--1t-*-05_i0_5__,1__ 18_1_5_:1_5--{*-5-i_15_12_0_1_8_5_i_16___,2__0_18 __ 1S-_0_5_0_68""Ti___L_ea____d_-2_1_2_,__E_P_A_9_o_1_,1_M_od_ified_ _,,,.._7_,32_E-01_1 __,*___3_,39_E-0_1_+ __3_A11_E-0_1__5_,34_E_-0_1_ _ _ _ _ _ _ _P_C_iig_-i

,,__1_8_-0_5_06_8---_1_4--+--TR_G_~1_-0_6_2_14_-_AF_S_F_C_-o_o_1_c_v_ _ __,___0_51_0_51_18, 15:15 , 5/15/2018 5/16/2018 18-05068 i Lead-214 EPA 901.1 Modified 8,67E-01  ; 4,57E-01  ! 4,59E-01 6,95E-01 , , pCi/g 18-05068-14 TRG B1-06214-AFSFC-001CV 05/05/1815:15 I 5/15/2018--5/16/2018 18-05068 i Promethium-145 EPA 901-1 Modified -5,72E-01 I 1,93E-01 1,95E-01 2,12E-01 U pCi/g

.,,_1_8--0-5-06-8--1-4--+--TRG 81-06214-AFSFC-001CV 05/05/18 15:15 \ 5/15/2018 5/16/2018 18-05068 \ Radium-226 EPA 901.1 Modified 8.03E-01 2.96E-01 2.99E-01 4.89E-01 f  : pCi/g 1---------------------------1---------+----~-----------~------'1-------------+--------------------------+-------~--------.1 18-05068-14 TRG B1-06214-AFSFC-001CV 05/05/1815:15 / 5/15/2018

  • 5/16/2018 18-05068
  • Antimony-125 EPA90L1 Modified -2,58E-01 I 6,19E-01 I 6,19E-01 8,10E-01 U ' pCi/g 18-05068-14 TRG ' B1-06214-AFSFC-001CV 05/05/1815:15 i 5/15/2018 5/16/2018 18-05068 : Thorium-234 EPA901.1 Modified 1.98E+OO ; 1.48E+OO 1A8E+OO 2,25E+OO , U  : pCi/g

,,__1_8-_0_5_06-8--1-4*---TR-G--i~B1-0---6-21---4-A_F_S_F_C--0-0-1C_V _ _ _ _ _,,__ 05-/0_5_/1_8_1_5,_:1-5~/,-5-/-15-/2_0_1_8--5-/-16-/2-0-18___18--0-50--6-8---/--T-ha-JJ-iu-m--2-0-8---+--E-P-A-9-0-1-,1-M-od-ified---;-,-7_,99-E-01-1+-j-3-,8-8-E--0-1-,-3-_9--o-E--0-1--6-.6-7--E--0-1----~---p-Ci/g--.1 18-05068-14 TRG ' B1-06214-AFSFC-001CV 05/05/1815:15 i 5/15/2018 , 5/16/2018 18-05068 [ Uranium-235 EPA 901.1 Modified -4,56E-01 [ 1,66E+OO ' 1,66E+OO 7.90E-01 U I

pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE ANALYTICAL EBERLINE 601 SCARBORO ROAD OAK RIDGE, CAL CORPORATION TN 37830 865/481-0683 FAX 865/483-4621 [64]

Printed: 6/5/2018 2:25 PM Page 17 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical Zion Snl, ,+\ons, LLC Purchase Order:

SDG:

-*--- *~ . *--*,, ***--*-----"-** -**-**- "*--..*---****---**-----*--

677118 Final Report of Analysis 101 Shiloh Blvd

~----****-** ---------- -.--*-*-

Analysis : ___ ,,v,.r ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch '  ! Report Analyte Method Result cu CSU MDA Qualifier ID Type ID Date Date Date ID i Units 1n *- *- ac TRG B1-06213-AFSWC-009CV 05/05/18 09:05 5/15/2018 5/16/2018 18-05068 Actinium-228 EPA 901.1 Modified 3.41E-01 4.07E-01 4.07E-01 7.00E-01 u pCi/g

  • - *- Ov

~----. -------------~-------=-*- --- '

18-05068-15 TRG 81-06213-AFSWC-009CV 05/05/18 09:05 5/15/2018 5/16/2018 18-05068 Silver-108m EPA901.1 Modified 4.07E-02 UOE-01 1.10E-01 1.81E-01 u pCi/g

~---*--*-*- -*--------------------,--

1n * - * - - .tt:.

i TRG 81-06213-AFSWC-009CV 05/05/18 09:05 5/15/2018 5/16/2018

  • 18-05068 Americium-241 EPA 901.1 Modified  : -1.68E-01 9.15E-02 9.19E-02 2.88E-01 u pCi/g

,t~  :: *-

Ov

.~5 ; TRG 81-06213-AFSWC-009CV

  • -*-*-~-------~----------------

05/05/18 09:05 5/15/2018 5/16/2018 18-05068 ; Barium-133 EPA 901.1 Modified -1.31E-02 8.15E-02 8.15E-02 3.26E-01 u pCi/g 18-05068-15 TRG B1-06213-AFSWC-009CV 05/05/18 09!05 ' 5/15/2018 5/16/2018 18-05068

  • Bismuth-214 EPA 901.1 Modified 8.12E-01 3.50E-01 3.52E-01 5.04E-01 pCi/g

-~-------*

18-05068-15 '

18-05068-15 TRG TRG 81-06213-AFSWC-009CV 81-06213-AFSWC-009CV 05/05/18 09:05 05/05/18 09:05 5/15/2018

, 5/15/2018 ! 5/16/2018 5/16/2018 , _18-05068 18-05068

~---*--*-*

, _ ~ _ , , , , -Cobalt-60--~--"

Cesium-134 EPA 901.1 Modified EPA 901.1 Modified 5.16E-02 7.41E-03

' 1.09E-01 6.93E-02 1.09E-01 6.93E-02 1.83E-01 1.91E-01 u

u pCi/g pCi/g i ' u 18-05068-15 i TRG 81-06213-AFSWC-009CV 05/05/18 09:05 5/15/2018 5/16/2018 18-05068 Cesium-137 EPA 901.1 Modified  : 6.95E-02 1.51E-01 1.51E-01 2.31E-01 pCiig 18-05068-15 TRG  : 81-06213-AFSWC-009CV 05/05/18 09:05 , 5/15/2018 5/16/2018 18-05068 Europium-152 EPA 901.1 Modified -5.74E-03 '

3.91E-01 3.91E-01 4.56E-01 u pCi/g 18-05068-15 TRG 81-06213-AFSWC-009CV

~~~+r5/2018 5/16/2018 18-05068 i Eur?£.i_<Jm-1.54 EPA 901.1 Modified -1.07E-01 3.22E-01 3.22E-01 2.31E-01 u pCi/g 18-05068-15 TRG 81-06213-AFSWC-009CV /15/2018 5/16/2018 18-05068 : Europium-155 EPA 901.1 Modified 3.52E-01 ' 2.65E-01 2.66E-01 4.29E-01 u pCi/g 18-05068-15 TRG 81-06213-AFSWC-009CV 05/05/18 09:05 5/15/2018 5)16/2018 18-05068 , Holmium-166m EPA901.1 Modified 8.18E-02 1.94E-01 1.94E-01 1.80E-01 u pCi/g 18-05068-15 TRG B1-06213-AFSWC-009CV 05/05/18 09:05  ; 5/15/2018 5/16/2018 18-05068 i lodine-129 EPA 901.1 Modified -3.21E+OO  ! 1.60E+OO 1.61E+OO 1.15E+OO u pCi/g an

- --*- . TRG 81-06213-AFSWC-009CV 05/05/18 09:05 i 5/15/2018 5/16/2018 18-05068 ' Potassium-40 EPA 901.1 Modified 4.95E+OO , 1.53E+OO 1.55E+OO 3.21E+OO u pCi/g Ov 18-05068-15 TRG

. 81-06213-AFSWC-009CV

, 05/05/18 09:05  : 5/15/2018 5/16/2018 18-05068 j C EPA 901.1 Modified 2.87E-02 1.01E-01 1.01E-01 1.66E-01 u i pCi/g 18-05068-15 TRG 81-06213-AFSWC-009CV 05/05/18 09:05  : 5/15/2018 5/16/2018 18-05068 ; Niobium-94 EPA 901.1 Modified -5.07E-02  : .19E-01 1.19E-01 1.74E-01 u pCi/g 18-05068-15 TRG i B1-06213-AFSWC-009CV 05/05/18 09:05  ; 5/15/2018 ; 5/16/2018 18-05068 Lead-210 EPA 901.1 Modified -1.86E+OO i 2.27E+OO 2.27E+OO 3.37E+OO u pCi/g 18-05068-15

' TRG  ! 81-06213-AFSWC-009CV 05/05/18 09:05  : 5/15/2018 ; 5/16/2018 18-05068  ! Lead-212 EPA 901.1 Modified 6.66E-01 2.83E-01 2.85E-01 4.15E-01 pCi/g 18-05068-15 TRG  ! 81-06213-AFSWC-009CV 05/05/18 09:05

  • 5/15/2018 5/16/2018 18-05068 ; Lead-214 EPA 901.1 Modified 5.50E-01 3.55E-01 3.56E-01 5.35E-01 pCi/g 18-05068-15 TRG 81-06213-AFSWC-009CV 05/05/18 09:05  ; 5/15/2018 , 5/16/2018 18-05068 i -** ___,,,u, "- 145 EPA 901.1 Modified -9.94E-01  : 4.91E-01 4.94E-01 6.30E-01 u pCi/g 18-05068-15 TRG  ! 81-06213-AFSWC-009CV 05/05/18 09:05  : 5/15/2018 5/16/2018 , 18-05068 : Radium-226 EPA 901.1 Modified 8.12E-01 i 3.50E-01 i 3.52E-01 5.04E-01 i pCi/g 18-05068-15 TRG  : 81-06213-AFSWC-009CV 05/05/18 09,05  ! 5/15/2018 5/16/2018 18-05068 i Antimony-125 EPA901.1 Modified -2.43E-01 4.00E-01 ' 4.00E-01 5.66E-01 u pCi/g

.. : .,..,. ,.,. . I:; ; TRG  : 81-0621~-~;-- *" 05/05/18 09:05 5/15/2018 5/16/2018 18-05068 I Thorium-234 EPA 901.1 Modified -5.86E-01 5.34E-01  : 5.35E-01 2.67E+OO u pCi/g 18-05068-15 TRG  : 81-06213-AFSWC-009CV 05/05/18 09:05 5/15/2018 , 5/16/2018 18-05068 ' Thallium-208 EPA901.1 Modified 1.11E+OO i 6.05E-01 6.08E-01 5.88E-01 i

pCi/g 18-05068-15 TRG  : 81-06213-AFSWC-009CV 05/05/18 09:05 5/15/2018

  • 5/16/2018 18-05068 ; Uranium-235 EPA 901.1 Modified 7.19E-01 I 1.87E+OO i 1.87E+OO 1.03E+OO ' u ' pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect EBERLINE i EBERLINE ANAL YTiCAL CORPORATION

~ ANALYTICAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/483-4621 [65]

Printed: 6/5/2018 2:25 PM Page 18 of 19 Report To: Wolk Order Details:

Patricia Giza 18-05068**"-*-----*

Eberline Analytical ,_ ___

  • - . - ~--* ... .... -*****-**-------***------**---

Zion_Solutions, LLC ___ --

            • -**-W SDG:

Purchase Order: 677118

        • ---~--*--**-**--**"* "_,_ ___ -****

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Final Report of Analysis ,---------*

101 Shiloh Blvd Analysis Category: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report Type Date Date Analyte Method Result cu CSU MDA Qualifier ID ID Date ID i Units 18-05068-16 .....,,....,.

TRG _,_ B1-06213-AFSFC-004CV

~""*

05/05/18 10:25 5/15/2018 5/16/2018 18-05068 Actinium-228 EPA901.1 Modified 2.71E-01 2.63E-01 2.64E-01 4.48E-01 u pCi/g 18-05068--16 :______________________

TRG B 1-06213-AFSF C-004CV - 05/05/18 10:25

~-----

5/15/2018 5/16/2018 18-05068 Silver-108m

*--*~--"-------

EPA 901.1 Modified  : -4.64E-02 7.64E-02 1.65E-02 8.78E-02 u pCi/g 18-05068-16 TRG B1-06213-AFSFC-004CV 05/05/18 10:25  ; 5/15/2018 5/16/2018 18-05068 Americium-241 EPA901.1 Modified -3.24E-01 1.64E-01 1.64E-01 1.66E-01 u pCi/g 18-05068-16 TRG B1-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 5/16/2018 18-05068 Barium-133 EPA901.1 Modified 4.21E-02 5.65E-02 5.65E-02 1.48E-01 u pCi/g 18-05068-16 TRG 81-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 5/16/2018 18-05068 Bismuth-214 EPA901.1 Modified 5.87E-01 2.07E-01 2.09E-01 2.89E-01 pCi/g ~

. . ------~----

18-05068-16 TRG B 1-06213-AFSF C-004CV 05/05/18 10:25 ' 5/15/2018 5/16/2018 18-05068 Cobalt-60 EPA 901.1 Modified -3.44E-02 7.29E-02 7.29E-02 9.75E-02 u pCi/g

--*-.-----**'--* ----'°"""' -~---~-,,-------~ --------,,~------,---- -'cw~,---~w,w 18-05068--16 TRG B1-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 , 5/16/2018 18-05068 Cesium-134 EPA901.1 Modified i 1.45E-03 3.33E-02 3.33E-02 1.07E-01 u pCi/g 18-05068-16 TRG 81-06213-AFSFC-004CV 05/05/18 10:25

  • 5/15/2018 5/16/2018 18-05068 Cesium-137 EPA901.1 Modified i 1.07E+OO 2.02E-01 2.09E-01 2.24E-01 pCi/g f-------- --w ----------

18-05068-16 ,---w-----~'" TRG 81-06213-AFSFC-004CV

___________ 05/05/18 10:25 5/15/2018 5/16/2018 18-05068 Eur- 0 . - ... " ' : EPA901.1 Modified  : -9.15E-02 2.80E-01 2.80E-01 2.17E-01 u pCi/g i

18-05068-16 TRG B1-06213-AFSFC-004CV 05/05/18 10:25 ' 5/15/2018 , 5/16/2018 18-05068 Europium-154 EPA 901.1 Modified  : 4.68E-02 1.76E-01 1.76E-01 1.12E-01 u pCi/g

--c- ----*-----* '

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wwvOU TRG B1-06213-AFSFC-004CV 05/05/18 10:25 r 5/15/2018 , 5/16/2018 18-05068 Eur ... EPA901.1 Modified  : -2.09E-02 1.19E-01 1.19E-01 1.91E-01 u pCi/g 18--05068-16 i TRG B 1-06213-AFSF C-004CV 05/05/18 10:25 ' 5/15/2018 5/16/2018 18-05068 , Holmium-166m EPA 901.1 Modified i -1.41E-02 1.16E-01 1.16E-01 9.99E-02 u pCi/g 18-05068--16 i TRG B1-06213-AFSFC-004CV 05/05/18 10:25 i 5/15/2018 i 5/16/2018 18-05068 i lodine-129 EPA901.1 Modified  : 4.29E-02 i 4.69E-02 4.69E-02 1.25E-01 u pCi/g 18-05068--16 i TRG B1-06213-AFSFC-004CV 05/05/18 10:25 i 5/15/2018 5/16/2018 18-05068 Potassium-40 EPA 901.1 Modified  : 6.36E+OO . 1.21E+OO 1.25E+OO 1.01E+OO pCi/g

"-------~- 05/05/18 10:25 ' 5/15/2018 i 5/16/2018 18-05068 ***-**:::,-* *- -

. EPA 901.1 Modified -6.77E-03 5.96E-02 5.96E-02 9.13E-02 u pCi/g 18-05068--16 1e-::::;:;:;.,u TRG TRG 06213-AFSFC-004CV 81-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 , 5/16/2018 18-05068 i Niobium-94 EPA 901.1 Modified 8.75E-03 5.96E-02 i 5.96E-02 9.15E-02 u pCi/g 18-05068-16 i TRG B1-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 , 5/16/2018 18-05068 Lead-210 EPA901.1 Modified 1.29E+OO 1.19E+OO 1.19E+OO 1.64E+OO u pCi/g 18-05068-16 i TRG 81-06213-AFSFC-004CV 05/05/18 10:25  ; 5/15/2018 , 5/16/2018 18-05068 Lead-212 EPA 901.1 Modified i 4.56E-01  ; 1.27E-01 l 1.30E-01 2.37E-01 pCi/g 18--05068-16  ! TRG 81-0621" v*

- 05/05/18 10:25 5/15/2018 5/16/2018 18-05068 , Lead-214 EPA 901.1 Modified 5.99E-01 i 1.72E-01 i 1.75E-01 2.59E-01 pCi/g 18-05068-16 [ TRG 81-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 5/16/2018 18-05068

  • Promethium-145 EPA 901.1 Modified 5.93E-02 ' 1.26E-01 i 1.26E-01 1.69E-01 u pCi/g 18-05068--16 j TRG B1-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 5/16/2018 18-05068 I Radium-226 EPA 901.1 Modified 5.87E-01 i 2.07E-01 2.09E-01 2.89E-01 pCi/g 18-05068-16 ; TRG B 1-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 , 5/16/2018 18-05068 "'"'"7 . ._ ..... EPA901.1 Modified 3.82E-02 1.83E-01 i 1.83E-01 2.81E-01 u pCi/g 18-05068-16 i TRG B1-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 5/16/2018 18-05068 : Thorium-234 EPA901.1 Modified 2.23E+OO i 1.40E+OO i 1.40E+OO 1.94E+OO u pCi/g 1~ -- *- 1C i TRG B1-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018
  • 5/16/2018 ' 18-05068 l Thallium-208 EPA 901.1 Modified 4.50E-01 i 2.04E-01  ! 2.06E-01 4.78E-01 u pCi/g 18-05068-16 i TRG B 1-06213-AFSFC-004CV 05/05/18 10:25 5/15/2018 : 5/16/2018 18-05068 Uranium-235 EPA 901.1 Modified 3.09E-01  : 7.21E-01 i

7.21E-01 4.80E-01 u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

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EBERLINE ANALYT!CAL EBERLINE 601 SCARBORO ROAD OAK RIDGE, L YTICA,L CORPORATION TN 37830 865/481-0683 FAX 865/483-4621 [66]

Printed: 6/5/2018 2:25 PM Page 19 of 19 Report To: Work Order Details:

Patricia Giza 18-05068 Eberline Analytical * ,_._, ..._..-.-.-*-**-*-----*--*-*w**-**'""

---***--***Zion Solutions,_LLC SOG:

677118 Final Report of Analysis 101 Shiloh Blvd .., ________ ""=--- ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units ID 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 5/16/2018 18-05068 Actinium-228 EPA901.1 Modified 3.22E-01 2.26E-01 2.26E-01 4.15E-01 u 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 5/16/2018 18-05068 Silver-108m EPA901.1 Modified -9.65E-02 8.09E-02 8.11E-02 9.11E-02 u 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 5/16/2018 18-05068 Americium-241 EPA 901.1 Modified 7.14E-02 2.44E-01 2.44E-01 3.15E-01 u 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 5/16/2018 18-05068 EPA 901.1 Modified 8.52E-02 1.81E-01 1.81E-01 3.09E-01 u 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 5/16/2018 18-05068 Bismuth-214 EPA901.1 Modified 3.10E-01 3.24E-01 3.24E-01 5.37E-01 u

--~- . ----*- *--*--'-*m---*------*--,,*=---------------*==-----

18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 5/15/2018 Cobalt-60 EPA 901.1 Modified 8.50E-03 5.49E-02 5.49E-02 7.82E-02 u

*---~-*-- --*-*-*

18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 5/15/2018 EPA 901.1 Modified 6.82E-02 6.82E-02 1.10E-01 u

-~~*------,w-*--*-,--,---*-

18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 5/16/2018 EPA 901.1 Modified 1.02E+01 3.04E-01 18-05068-17 TRG B 1-06213-AFSF C-002CV 05/05/18 13:00 5/16/2018 EPA 901.1 Modified 8.39E-01 5.05E-01 u 18-05068-17 TRG B 1-06213-AFSFC-002CV 05/05/18 13:00 5/16/2018 1.58E-01 2.54E-01 u 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 3.39E-01 u 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 1.73E-01 u 18-05068-17 TRG B1-06213-AFSFC-002CV 2.44E-01 u pCi/g 18-05068-17 TRG B1-06213-AFSFC-002CV 1.27E+OO 1.47E+OO 18-05068-17 TRG B 1-06213-AFSFC-002CV 6.22E-02 7.54E-02 u 18-05068-17 TRG B1-06213-AFSFC-002CV 4.99E-02 7.83E-02 u 18-05068-17 TRG B1-06213-AFSFC-002CV 1.58E+OO 2.39E+OO u 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 3.58E-01 u 18-05068-17 TRG 05/05/18 13:00 7.67E-01 u 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 3.94E-01 u 18-05068-17 TRG B1-06213-AFSFC-002CV 05/05/18 13:00 EP 5.37E-01 u B1-06213-AFSFC-002CV Thallium-208 05/05/18 13:00 EPA901.1 1.24E+OO CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect 0

EBERLINE

~ .AN.A.LYTICAL 601 SCARBORO ROAD OAK RIDGE, TN 37830 865/481-0683 FAX 865/ 483-4621 [67]

ZS-WM-131

/

Revision 0 ZIONSOLUTIONSiic An Ene *gySolutions Company Information Use Attaclunent 1 - Chain-of-Custody Form 1 e- oso sa REC'D MAY 1 5 2018 Sample ID Sample Matr Sample Sample Container Sample Date Sample Time Analysis Type Preservative Remarks Log ix Type Vol Unit Type Qty 0.0-0.5" J B3-06213AFIWC-Ol 1CV NA NA Concrete 57.94 Cm 3 Puck I 05-02-2018 0900 5ROC/HTD NA 93.79g 0.0-0.5"

( B3-062 I 3-AFIFC-O l 5CV NA NA Concrete 57.94 Cm 3 Puck I 05-02-2018 0845 5ROC/HTD NA 121.03g 0.0-0.5" l9 B3-06214-AFIFC-OOI CV NA NA Concrete 57.94 Cm 3 Puck I 05-03-2018 1330 5ROC/HTD NA 105.79g 0.0-0.5" Cm3 1 B3-062 l 4-AFIWC-009CV NA NA Concrete 57.94 Puck I 05-03-2018 1530 5ROC/HTD NA 97.96g 0.0-0.5" Cm3 6 B3-06215-AFSWC-013CV NA NA Concrete 57.94 Puck I 04-26-2018 1300 5ROC/HTD NA 128.37g 0.0-0.5" (7\ B3-062 l 5-AFSFC-003CV NA NA Concrete 57.94 Cm3 Puck I 04-26-2018 1340 5ROC/HTD NA 86.71g 0.0-0S'

() B3-062 l 6-AFS WC-006CV NA NA 57.94 Cm 3 Puck I 5ROC/HTD NA 124.13g

\ Concrete 04-30-2018 0835 0.0-0.5

Cm 3

\\ B3-06216 AFSFC-002CV NA NA Concrete 57.94 Puck I 04-26-2018 1520 5ROC/HTD NA 85.09g 0.0-0.5"

\1 B l-062 I 4-AFSWC-005CV NA NA Concrete 57.94 Cm3 Puck I 05-05-2018 1435 5ROC/HTD NA 104.84g 0.0-0.5"

\ 'l B 1-06214-AFS FC-004CV NA NA Concrete 57.94 Cm 3 Puck I 05-05-2018 1455 5ROC/HTD NA 90.02g 0.0-0.5" B 1-06214-AFS FC-00 I CV NA NA 57.94 Cm 3 Puck I 5ROC/HTD NA 142.60g

\~ Concrete 05-05-2018 1515 0.0-0.5"

\'? B l-062 I 3-AFSWC-009CV NA NA Concrete 57.94 Cm 3 Puck I 05-05-2018 0905 5ROC/HTD NA 108.80g 0.0-0.5"

\\J i B1-06213-AFSFC-004CV NA NA 57.94 Cm 3 Puck I 5ROC/HTD NA 123.56g

,~

Concrete 05-05-2018 1025 0.0-0.5 B 1-06213-AFS FC-002CV NA NA Concrete 57.94 Cm 3 Puck I 05-05-2018 1300 /5ROC/HTD NA 144.65g" Rt~ *i~ 5- ,s- \~/ f)'15o

[68]

ZS-WM-131 Revision 0 ZIONSOLUTIONSLLC An EnergySolurions Company 1e-ososa REC'D MAY 15 2018 Information Use Laborato1y: Date Submitted To Lab: Ship Container No.: Cooler Temperatur Airbill Number:

e: (£De'/. h}efovernt *f Eberline Labs NIA r107 oi,45 1o57 Relinquished by: Date (mm/dd/yyyy): Time: Received by: Date: (mm/dd/yyyy): Time:

Reed R. Smith 05-14-2018 0819

~ithord f Relinquished by: Date (mm/dd/yyyy): Time: Received by: Time:

!b:30 Relinguished by: Time:

V7.50 Date (mm/dd/yyyy): Time: Time:

Comments PO# 677118. 7 Day turnaround. 5-ROC/HTD.

[69]

ATTACHMENT 5 ISOCS ANALYTICAL REPORTS

[70]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/23/2018 1:15:18 PM Sample Title B306215AFSFC001GD Sample Description East U2 Valve House Floor Sample Identification Sample Sample Type Geometry Gamma Direct 3M90D CP 2IN vV Peak Locate Threshold 3 .00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10. 00 0 keV Sample Size 2.830E+001 M... 2 Sample Taken On 4/23/2 0 18 1:05:00 PM Acquisition Started 4/23/2 0 18 1:05:17 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 %

Energy Calibration Used Done On 12i28/2017 V Efficiency Calibration Used Done On 2/1/2018 V Efficiency ID 3M90D CP 2 IN v' v~~ v~. l(7.1t~lc.¢ l//-i.J/ g cYJ' Zo

[71]

Peak Analysis Report 4/ 23 /2018 1 :15:18 PM Page 2

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

Detector Name: 62 79 Sample

Title:

B306215AFSFC001GD Peak Analysis Performed on: 4/23/2018 1 :15:18 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 2 85- 312 300.22 75.02 0. 82 2 .07E+00 2 84.51 3.51E+002 2 945- 963 953.52 238.50 0. 33 2 .15E+001 33.67 7.45E+001 3 1172 - 11 89 1180.22 295.22 1. 50 3.20E+001 24.43 3.60E+001 4 1399- 1416 1407.43 352.06 0.98 5.07E+001 26.50 3.83E+001 5 2323 - 2340 2331.71 583.21 0 .32 2.43E+001 13.57 6.66E+OOO 6 2428 - 2445 2436.80 609.49 0.96 4.63E+001 16.49 6.67E+OOO 7 2638 - 2655 2646.55 66 1 .93 0.89 7.33E +OOO 15.28 1.57E+001 8 4473- 4492 4482.10 1120.63 0.54 2 .43E +001 11.79 2.73E+OOO 9 5835- 5854 5844.78 1460.91 0.99 9 . 57E +001 20.35 2.32E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[72]

Interference Corrected Activity Report 4/ 23/2 018 1:15:18 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306215AFSFC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.34236E+006 3 .08330E+005 Cs-137 1.000 661. 66* 85.10 8.63266E+00 3 1.80390E+004 Tl-208 1.000 583.19* 85.00 2.68861E+004 1 .53301E+004 Pb-212 1. 000 238.63* 43.60 2.85977E+004 4.49965E+004 Bi-214 0.73 5 609.32* 45.4 9 9.78543E+004 3.67485E+004 1120.29* 14.9 2 2.11747E+005 1.04276E+005 1764.49 15.30 Pb- 2 14 1.000 295.22* 18.42 1.12257E+005 8.75610E+004 351.93* 35.60 1.01414E+005 5.51637E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

[73]

Interference Corrected Activity Report 4/23/2018 1:15:18 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nucl ide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1. 342358E+006 / 3. 083299E+005 Cs -13 7 1. 000 8.632658E+003

  • l.803902E+004 Tl -2 08 1. 000 2.688612E+004 1.533013E+004 Pb-2 12 1. 000 2.859770E+004 4.499649E+004 Bi -2 14 0.735 l.104368E+005 3.465915E+004 Pb -2 14 1. 000 l.044946E+005 4.667348E+004

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

@=Nuclide contains energy lines not used i n Weighted Mean Activity Errors quoted at 2.000 sigma

[74]

Interference Corrected Activity Report 4/ 2 3/2018 1:15:18 PM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/23/2018 1 :15:18 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts pe r Second  % Uncertainty Type Nuclide 1 75.02 3.4562E-001 40.75 M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[75]

Nuclide MDA Report 4/23/2018 1: 1 5:18 PM Page 6

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSFC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.8 2

  • 10.66 1.669E+005 1 .67E+005 J l .342E+00 6 6.448E+004 Co-60 1173. 2 3 99.85 3.873E+004 3. 87E+004 2 . 678E+004 1. 756E+004 13 3 2.49 99.98 3.882E+004 2.358E+004. 1 1.749E+004 Nb-94 70 2 .65 99.81 3.550E+004 3.55E+004 3.525E+003 1.635E+004 8 71. 09 99.89 3.901E+004 -2 .929E+004 1.795E+004 Ag-108m 433.90 90 . 50 4.188E+004 4.19E+004 1. 2 96E+004 1.974E+004 614.30 89.80 4.952E+004 4.461E+004 2.331E+004 722.90 90.80 4. 2 61E+004 -9.529E+003 1.974E+004 Cs-134 604.72 97.6 2 4 .5 19E+004 4.41E+004,/"6. 542 E+004 2.127E+004 795.86 85.46 4.407E+004 2.050E+004 2.030E+004

+ Cs- 137 661.66* 85.10 3.089E+004 3.0 9E+004 8.633E+003 1.385E+004 Eu-152 121. 78 2 8.67 2.127E+005 1.40E+005 1.838E+00 5 1.040E+005 344.28 2 6.60 1.790E+005 7.546E+004 8.593E+004 1408.01 21.07 1.395E+005 9 .709E+004 6.037E+004 Eu-154 123.07 40.40 l.484E+005 1.09E+005 4.600E+004 7.256E+004 723.30 2 0.06 1.929E+005 - 5 .045E+004 8.940E+004 1274.43 34.80 1.091E+005 1.117E+005 4.913E+004 Eu-155 86.55 30.70 2 .570E+00 5 2 .57E+005 4.688E+004 1.261E+005 105.31 21.10 3.108E+005 3 . 731E+005 1 . 522E+005

+ Tl-208 583.19* 85.00 1. 991E+004 1.99E+004 2.689E+004 8.459E+003 Bi-212 727.33 6.67 5.768E+005 5.77E+005 2.403E+004 2.671E+005

+ Pb-212 238.63* 43.60 7.438E+004 7.44E+004 2.860E+004 3.539E+004

+ Bi-214 609.32* 45.49 3.801E+004 3.80E+004 9.785E+004 1.615E+004 1120. 2 9* 14.92 1.166E+005 2.117E+005 4.650E+004 1764.49 15.30 2.347E+005 1.762E+005 1.025E+005

+ Pb-214 2 95.22* 18.42 1.344E+005 7 .9 0E+004 1. 123E+ 005 6.247E+004 351.93* 35.60 7.900E+004 1.014E+005 3.679E+004 Ra-226 186.21 3.64 1 .261E+006 1.26E+006 1.048E+006 6.112E+005 Ac-228 338.32 11. 27 3.631E+005 1.68E+005 4.411E+005 1.732E+005 911.20 25.80 1.680E+005 -6.125E+004 7.783E+004 968.97 15.80 2.255E+005 4.005E+004 l.024E+005 Am-241 59.54 35.90 2 .763E+005 2 .76E+005 2 .292E+005 1.351E+005

+= Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[76]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6 2 79 Report Generated On 4/23/2018 10:13:17 AM Sample Title B306215AFSFC002GD \/'

Sample Description East U2 Valve House Floor /

Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 . 83 OE+OOl M 2 /

Sample Taken On 4/23/2018 10:03:00 AM V Acquisition Started 4/23/2018 10:03:16 AM v

Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0.08 % J Energy Calibration Used Done On 12/28/2017 V Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2 IN ~

[77]

Peak Analysis Report 4/ 23 /2018 10:13:17 AM Page 2

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

Detector Name: 62 79 Sample

Title:

B306215AFSFC002GD Peak Analysis Performed on: 4/23/2018 10:13:17 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 293 - 313 300.63 75.13 0.60 9.78E+001 75.29 3.57E+002 2 945- 962 953.94 238.61 0.87 2 .88E+001 30.30 6.12E+001 3 1399 - 1416 1407.30 352.02 0.37 6.55E+001 20.92 1.35E+001 4 2 035- 2052 2043.10 511.05 0.60 2 .78E+001 19.46 1.92E+001 5 24 2 7- 2445 2 435.86 609.25 1.19 3 .41E+001 22.06 2.59E+001 6 2636 - 2654 2645.84 661.75 1.14 8.98E+001 23.48 1.43E+001 7 3636- 3653 3644.56 911. 38 0.25 1 .77E+001 14.06 9.26E+OOO 8 5835- 5854 5844.24 1 460.78 1. 75 7.48E+001 18.13 2 . 2 5E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 s igma

[78]

Interference Corrected Activity Report 4/23/2018 10:13:17 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPOR T *****

Sample

Title:

B3062 1 5AFSFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%} (pCi/M"2} Uncertainty K-40 1.000 1460.82* 10.66 l .04875E+006 2 .70138E+005 Cs-137 1. 000 661.66* 85. 1 0 1.05742E+005 3.04406E+004 Pb-212 1. 000 23 8.63* 4 3 .60 3.83549E+004 4.07632E+004 Bi-214 0.44 2 609.32* 45.49 7. 2 0098E+ 004 4.73762E+004 1120.29 14.92 1764.49 15.30 Pb -2 14 0.437 295. 22 18.42 351.93* 35 . 6 0 1.31078E+005 4.62410E+004

  • = Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2 .000 sigma

[79]

Interference Corrected Activity Report 4/23/20 1 8 10:13:17 AM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1.048746E+006 2.701377E+005 /

Cs-137 1.000 1. 0 5 7416E+OOS J 3. 044058E+004 V Pb-212 1. 000 3.8 3 5494E+004 4.076323E+004 Bi-214 0.442 7.200979E+004 4.737623E+004 Pb-214 0.437 1.310777E+OOS 4.624098E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/23/2018 10:13:17 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.13 1 .6293E-001 7 7.0 1 4 511.05 4.6321E-002 70.03 7 911.38 2.9568E-002 79.24 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[80]

Nuclide MDA Report 4/23/2018 10 :13:17 AM Page 5

          • N U C L I D E MDA R E P O R T *****

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 1.635E+005 1 .64E+005 1 .049E+006 6.279E+004 Co-60 1173.23 99 . 85 4.571E+004 3.41E+004../6.137E+004 ~ 2.105E+004 1332.49 99.98 3.413E+004 - 5.378E+003 1.514E+004 Nb-94 702.65 99.81 3.888E+004 3.61E+004 3.756E+004 1.804E+004 871.09 99.89 3.610E+004 -3 .759E+004 1.650E+004 Ag-108 m 433.9 0 90.50 4.123E+004 4.12E+004 -6.040E+002 1.942E+004 614.30 89.80 5.533E+004 3.555E+004 2 .621E+004 722.90 90.80 4. 2 25E+004 1. 328E+004 )- . 956E+004 Cs-134 604.72 97.62 4.757E+004 3.40E+004v' 4.829E+004\/'2.246E+004 79 5 .86 85.46 3.400E+004 -1.994E+004 1.526E+004

+ Cs - 137 661. 66

  • 85.10 3.007E+004 3.01E+004/'1.057E+005 1.344E+004 Eu - 152 121. 78 28.67 2.087E+005 1.78E+005 -2.156E+005 1.020E+005 344.28 26.60 1.777E+005 -5.111E+004 8.527E+004 1408.01 21. 07 1 .864E+005 3.686E+004 8.384E+004 Eu-154 123.07 40. 40 1. 474E+005 9.98E+004 -2.011E+004 7.206E+004 723.30 20.06 1 .929E+005 1.739E+005 8.940E+004 1274.43 34.80 9.985E+004 4.988E+003 4.453E+004 Eu- 1 55 86.55 30.70 2.674E+005 2 . 67E+005 - 4.117E+004 1.313E+005 10 5.31 21.10 3.192E+005 -4 . 138E+004 1.564E+005 Tl-208 583 . 1 9 85.00 4. 92 5E+004 4.92E+004 4.520E+004 2.313E+004 Bi-212 727 . 33 6.67 5.667E+005 5 . 67E+OOS -4.571E+005 2.620E+005

+ Pb-212 238.63* 43.60 6.557E+004 6.56E+004 3.835E+004 3.099E+004

+ Bi-214 609.32* 45.49 7.072E+004 7.07E+004 7.201E+004 3.250E+004 1120.29 14.92 2.738E+005 5.211E+004 1 .251E+005 1764.49 15.30 2. 3 47E+005 - 8.946E+004 1.025E+005

+ Pb-214 295.22 18.42 2.494E+005 4.91E+004 l.937E+005 1 .199E+005 351.93* 3 5.60 4.907E+004 1.311E+005 2 .183E+004 Ra-226 1 86.21 3.64 1. 3 00E+006 1.30E+006 6.298E+005 6.306E+005 Ac-228 338.32 1 1. 27 3.643E+005 1.69E+00 5 1.933E+005 1.738E+005 91 1. 20 25.80 1 .694E+005 1.559E+005 7 . 855E+004 968.97 15.80 2.376E+005 3.365E+004 1.084E+005 Am-241 59.54 35.90 2.745E+005 2.75E+005 1.637E+005 1.342E+005

+=Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[81]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 62 79 Report Generated On 4/23/20 18 10:27:36 AM Sample Title B306 2 15AFSFC003GD v"""/'

Sample Description East U2 Valve House Floor \/

Sample Identification Sample Type Gamma Direct /'

Sample Geometry 3M90D CP 2IN \/

Peak Locate Threshold 3.00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 4/23/2018 10:17:00 AM Acquisition Started 4/23/2018 10:17: 3 5 AM Live Time 600.0 seconds Real Time 600. 5 seconds Dead Time 0.08 %

Energy Calibration Used Done On Efficiency Calibration Used Done On 12/28/2 011 2/1/2018 v~J E fficiency ID 3M90D_ CP_ 2 IN 7)~~ ~{v{ok/c/

ifa,vj;Er oS Jo

\

[82]

Peak Analysis Report 4/2 3 / 2 018 10: 2 7:36 AM Page 2

          • PE AK A N A L Y S I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306215AFSFC003GD Peak Analysis Performed on: 4/23/2018 10: 2 7:36 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 121 - 137 128.61 32.07 0.89 4.48E+001 35.00 8.32E+001 2 292 - 357 300.46 75.08 1. 06 1.54E+001 202.87 1.11E+003 3 946 - 964 955.14 238.91 0.71 3.09E+001 38.50 1.00E+002 4 1398 - 1416 1406.54 351.83 0.73 4.77E +001 28.39 4.53E+001 5 2035- 2052 2043.15 511.06 0.61 3.24E+001 21. 80 2.66E+001 6 2 323- 2340 2331. 79 583. 2 3 0.62 2.70E+001 15.06 8.96E+OOO 7 2429- 2446 2437.51 609.67 0.89 5.45E+001 19.88 1.35E+001 8 2633 - 2658 2645.70 661.72 1. 58 4.69E+002 47.44 2.23E+001 9 5834 - 5854 5844. 1 8 1460.76 0.45 8.23E+001 19. 2 3 2.72E+OOO 10 7052 - 7071 7061. 43 1764.55 0.36 1. 78E+001 10.07 2.22E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[83]

Interference Corrected Activity Report 4/ 23 /2018 10: 2 7: 36 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306215AFSFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES \ Zion Lib-BNL.NLB

. .. . . . .. .. . . . . . . . . . . IDENTIFIED NUCLIDES .. . .................

Nuclide Id Energy Yield Activity Activity Name Confidence {keV) { %) {pCi/MA2 ) uncertainty K-40 1. 000 1460 . 82* 10.66 1 .15437E+006 2.87849E+00 5 Cs- 1 37 1. 000 661.66* 85.10 5.52210E+005 8.67267E+004 Tl-208 1.000 583.19* 85.00 2.98725E+004 l.70164E+004 Pb-212 1.000 238.63* 43.60 4.11306E+004 5 . 16484E+004 Bi-214 0.706 609. 3 2* 45.49 l.15116E+005 4.42080E+004 1120.29 14.92 1764.49* 15.30 1 .95709E+005 1.12018E+005 Pb - 2 14 0.437 295.22 18.42 351.93* 35 . 60 9.546 32 E+004 5 .85619E+004

  • = Energy line found in the spectrum.

@ = Energy l ine not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2 .000 sigma

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Interference Corrected Activity Report 4/23/2018 10: 27:36 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1. 000 l.154367E+006 2.878491E+005 /

Cs-137 1. 000 5. 522 104E+00 5 ./ 8.672669E+004 Tl-208 1. 000 2.987250E+004 l.701643E+004 Pb-212 1. 000 4. 11 3062E+004 5.164845E+004 Bi-214 0.706 l.259763E+005 4.112156E+004 Pb-214 0.437 9.546320E+004 5 .856185E+004

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

@=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

[85]

Interference Corrected Activity Report 4/ 23 /2018 1 0 :27:36 AM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/23/2018 10 : 27: 3 6 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32 .07 7.4671E-002 78. 1 3 2 75.08 2.5686E-002 1316.35 5 511.06 5 . 4082E-002 67.18 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[86]

Nuc l ide MDA Report 4 /23 / 2 018 10: 2 7: 36 AM Page 6

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pci/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460 . 82

  • 10.66 1. 854E+005 1.85E+005 1 . 154E+00 6 7.370E+004 Co-6 0 1173. 23 99.85 3.761E+004 3.55E+004/-3.713E+003 1 . 700E+004 1332 . 49 99.98 3.554E+004 eJ(oot;.Q./ - 3. 520E+004 1 . 585E+004 Nb - 94 702.65 99.81 3.856E+004 3.24E+004 - 1.929E+004 1.788E+004 871. 09 99.89 3.243E+004 - 2.489E+004 1.466E+004 Ag-1 08m 433.90 90.50 5.315E+004 4 . 4 4E+004 -6. 23 7E+003 2 . 538E+004 614.30 89.80 5.766E+004 5.849E+004 2.738E+004 72 2 .90 9 0 .80 4.440E+004 fi.220E+004 2.064E+004 Cs - 134 604 . 72 97.62 5.177E+004 3.63E+004../2.607E+003J'°2.456E+004 795.86 85.46 3.626E+004 -4.824E+002 1 .639E+004

+ Cs - 137 66 1 .66* 85.10 4.075E+004 4.07E+004 5.522E+00 5 1 .878E+004 Eu-152 12 1. 78 28.67 2.204E+005 1 .48E+005 4.662E+004 1.079E+005 344.28 26.60 2.021E+005 8.718E+00 4 9.749E+004 1408.01 2 1.07 1. 478E+005 -2 .716E+00 5 6.454E+004 Eu-154 123.07 40.40 1.544E+005 1 . 02E+005 - 1 . 770E+005 7.553E+004 723.30 20.06 1.994E+005 1. 3 77E+005 9 .265E+004 1274.4 3 34.80 1.018E+005 2 .128E+004 4.548E+004 Eu-155 86 . 55 30.70 2.615E+00 5 2 . 6 2E+OOS 1.025E+005 1 . 284E+005 10 5.3 1 21.10 3.120E+005 1.623E+004 1.528E+005

+ Tl-208 583. 1 9* 85.00 2 .277E+004 2.28E+004 2.987E+004 9.893E+003 Bi-212 727 . 33 6.67 5 . 819E+005 5 . 82E+OOS 2 .106E+005 2 .696E+005

+ Pb-212 23 8.63* 43 . 60 8 . 426E+004 8 . 43E+004 4.113E+004 4 . 033E+004

+ Bi -2 14 609.32* 45.49 5.196E+004 5.20E+004 l.151E+005 2.312E+004 1120.29 14.92 2.771E+005 2 .491E+005 1 .267E+005 1764.49* 15.30 l.296E+005 1.957E+005 4.992E+004

+ Pb- 2 14 295.22 18.42 2.460E+005 8.70E+004 -1.843E+OOS 1.183E+005 351.93* 35.60 8.703E+004 9 .546E+004 4.081E+004 Ra-226 186.21 3.64 1. 411E+006 l.41E+006 -2 .254E+006 6.864E+005 Ac-228 338.32 1 1. 2 7 4.225E+005 1.SlE+OOS -2 .040E+OOS 2 .029E+005 911. 20 25.80 1.512E+005 5 .521E+004 6.945E+004 968.97 15.80 2.433E+OOS 7.317E+003 1.113E+005 Am- 2 41 59.54 35.90 2.721E+005 2.72E+00 5 -9.732E+004 1. 33 0E+005

+ = Nucl ide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[87]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6 2 79 Report Generated On 4/23/2018 1:29:04 PM Sample Title B306215AFSFC004GD v

Sample Description East U2 Valve House Floor \/"'

Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN V Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 MA 2 Sample Taken On 4/23/2018 1:18:00 PM v Acquisition Started 4/23/2018 1 :19:03 PM v

Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 %

Energy Calibration Used Done On 12/28/2017 V Efficiency Calibration Used Done On 2/1/2018 v Efficiency ID 3M90D CP 2IN v

[88]

Peak Analysis Report 4/23/2018 1:29:04 PM Page 2

          • PE AK A N A L Y S I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306215AFSFC004GD Peak Analysis Performed on: 4/23/2018 1:29:04 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start e nd centroid (keV) (keV) Area Uncert. Counts 1 121 - 137 128.82 32.12 0.81 2. 59E+001 28.68 5.71E+001 2 179 - 194 186.50 46.56 0.71 2 . 2 6E +001 31. 2 9 6.94E+001 3 283- 307 298.63 74.63 1. 01 1.34E+00 2 77.63 3 .32E+002 4 946 - 963 954.33 238.70 0.75 2 .45E +001 33.18 7.65E+001 5 1172- 1189 11 80.21 295.22 0.39 4.53E+001 26.72 4.07E+001 6 1398 - 1416 1406.74 351.88 1. 30 5.13E+001 23.71 2.47E+001 7 2034 - 2051 2042.76 510.96 2 .18 4.02E+001 16.62 8.84E+OOO 8 2323 - 2340 2331. 41 583.14 0.77 1 .13E+001 16.44 1 .67E+001 9 2428 - 2445 2436.48 6 0 9 . 41 0.35 4 . 91E+001 17.01 6 . 95E+OOO 10 2636 - 2655 2645.99 661.79 1. 55 1.66E+002 29 . 60 1.51E+001 11 4472 - 4491 4481 . 69 1120.53 0 . 84 2 .15E+001 14.8 2 9.53E+OOO 12 5836- 5856 5845.61 1461.12 1. 73 7.78E+001 19.68 5.25E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[89]

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Sample

Title:

B306215AFSFC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 l .09095E+006 2.91990E+005 Cs-137 1.000 661.66* 85.10 l.95509E+005 4. 2 0381E+004 Tl-208 1.000 583.19* 85.00 l.25055E+004 1.82258E+004 Pb-212 1.000 238.63* 43.60 3. 25 589E+004 4.44314E+004 Bi - 214 0.735 609.32* 45.49 l.03589E+005 3.80108E+004 1120.29* 14.92 l.87301E+005 1.30197E+005 1764.49 15.30 Pb-214 1.000 295 . 22* 18.42 l.58901E+005 9.71289E+004 35 1. 93* 35 . 60 1.02643E+005 4.98558E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0.30 Errors quoted at 2.000 sigma

[90]

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 1.090949E+006 _/2.919896E+005 Cs-137 1. 000 1.95 5 087E+005 4.203813E+004 j Tl-208 1. 000 1.250553E+004 1.822579E+004 Pb-212 1.000 3 . 25 5887E+004 4.443138E+004 Bi-214 0.735 1.101635E+005 3.648762E+004 Pb- 2 14 1. 000 1 .143746E+005 4.435401E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

[91]

Interference Corrected Activity Report 4/23/2018 1: 29:04 PM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on : 4/23/2018 1: 29: 04 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.12 4.3133E-002 110.83 2 46.56 3.7591E-002 138.71 3 74.63 2.2289E-001 58.05 7 510.96 6.6939E-002 41. 37 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[92]

Nuclide MDA Report 4/23/ 2 018 1 : 29:04 PM Page 6

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2 IN Sample

Title:

B306215AFSFC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES \ Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2) (pCi/MA2) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460 . 82* 10.66 2.398E+005 2 . 40E+OOS j 1. 091E+O 0 6 1. 0 0 9E+O 05 Co-60 1173.23 99.85 3.338E+004 3. 3 4E+004

  • 1 . 9 06E+004 ). . 489E+004 1332 . 49 99.98 3.413E+004 2 . 9 83E+oo4 '\1"' 1.s14E+oo4 Nb - 94 702.65 99.8 1 4.046E+004 3 .74E+004 -4. 3 53E+004 1.883E+004 871. 0 9 99.89 3.738E+004 3.857E+002 1.713E+004 Ag- 108m 433.90 90.50 4.458E+004 4.11E+00 4 - 4.915E+004 2.109E+004 614.30 89.80 5.238E+004 4.001E+004 2.474E+004 722.90 90.80 4.112E+004 l.738E+003 1.900E+004 Cs - 134 604.72 97.62 4.663E+004 4 . 04E+004/ -l.615E+004 2.199E+004 795.86 85.46 4.037E+004 Q,()(!_O /-)-.780E+00 4 1. 845E+004

+ Cs-137 661.66* 85.10 3 .142E+004 3.14E+004,/l.955E+005 l.412E+004 Eu-152 121. 78 28.67 2 .079E+005 1.16E+005 1. 3 84E+005 1.016E+005 344 . 2 8 26.60 1.718E+005 3.960E+004 8.233E+004 1408.0 1 2 1. 07 1. 1 56E+005 - 2 .462E+005 4.840E+004 Eu - 154 123.07 40.40 1.449E+005 9 .17E+004 - 4.819E+004 7.083E+004 723.3 0 20.06 l.896E+005 2 . 2 00E+005 8.773E+004 1274.43 34.80 9.174E+004 -2.426E+004 4.047E+004 Eu- 1 55 86.55 30.70 2 .502E+005 2 .50E+005 1.464E+004 1.227E+005 105.31 21.10 3 .1 06E+005 3.539E+003 l .521E+OOS

+ Tl-208 583 . 19* 85.00 3.025E+004 3.03E+004 1.251E+004 1.363E+004 Bi-212 727.33 6.67 5 . 349E+005 5.35E+005 -4.474E+005 2.461E+005

+ Pb-212 238.63* 43.60 7.287E+004 7.29E+004 3.256E+004 3.464E+004

+ Bi-214 609.32* 45.49 3.922E+004 3.92E+004 1 .036E+005 1.675E+004 1120.29* 14.92 1. 897E+005 1 .873E+005 8.303E+004 1764.49 1 5.30 2 . 347E+005 1.762E+005 1.025E+005

+ Pb-214 2 95.22* 18.42 1.427E+005 6.76E+004 1.589E+005 6.660E+004 351.93* 35.60 6.758E+004 1.026E+00 5 3 .108E+004 Ra-226 186.21 3.64 1.334E+006 1.33E+006 2.088E+006 6.478E+005 Ac-228 338.32 11.27 3.885E+005 1.56E+005 - 2 . 016E+005 1.859E+005 911. 20 25 . 80 l.560E+005 1.086E+005 7.183E+004 968.97 15.80 2 .572E+005 2 .552E+005 1.182E+005 Am-241 59.54 35.90 2 .585E+005 2 .59E+005 8.580E+004 1.262E+00 5

+ = Nuclide identified during the nuclide identification

  • = Energy l ine found in the spectrum

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

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

[93]

          • G AMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/23/2018 2 : 22 :06 PM .

\

/

Sample Title B306215AFSWC005GD ../

Sample Sample Description Identification East U2 Valve House Wall v Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 M"2 Sample Taken On 4/23/2018 2:12:00 PM Acquisition Started 4/23/2018 2:12:05 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 %

Energy Calibration Used Done On 12/28/2017 ./

Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN VJ "bl07r 1/4li D~

Y}2i)Y iftoo

[94]

Peak Analysis Report 4 / 23 / 2 018 2 : 22 :06 PM Page 2

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

Detector Name: 6279 Sample

Title:

B306215AFSWC005GD Peak Analysis Performed on: 4/23/2018 2 : 22 :06 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 285 - 346 299.85 74.93 1. 23 2.84E+OOO 193.38 1.03E+00 3 2 945 - 962 953.92 238.6 0 0.40 5.39E+001 33.19 6.71E+001 3 1171- 1188 1179.75 295.10 1. 00 1.05E+001 24.42 4 .25E+00 1 4 1399 - 1416 1407.33 352.03 0.79 7.19E +001 20.77 1.llE+OOl 5 2 0 36 - 2 0 53 2044.28 5 11 .34 0.47 3.41E+001 18.15 l.49E+001 6 2324- 2341 2332.87 583.50 0.38 2. 00E+OOl 14.04 9.00E+OOO 7 2429 - 2446 2437.24 609.60 0.37 3.5 0E+001 19.37 1.80E+001 8 5835 - 5854 5844.59 1460.86 0.58 6 .82E+001 18.42 4.77E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[95]

Interference Corrected Activity Report 4/23/2018 2:22 :06 PM Page 3

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Sample

Title:

B306215AFSWC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 1.000 1460.82* 10.66 9.57208E+005 2 .71443E+005 Tl-208 1.000 583.19* 85.00 2 . 2 0990E+004 1. 5 7348E+004 Pb-2 12 1.000 238.63* 43.60 7.17024E+004 4. 5 6261E+004 Bi-214 0.442 609. 32

  • 45.49 7.39231E+004 4.18714E+004 1120.29 14.92 1764.49 15.30 Pb-214 1.000 295.22* 18.4 2 3.69922E+004 8.58499E+004 351. 93* 35.60 1.43864E+005 4.68118E+004
  • =Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0. 3 0 Errors quoted at 2.000 sigma

[96]

Interference Corrected Activity Report 4/ 23/2 018 2 : 22 : 0 6 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 9.572082E+005 2. 714427E+005 Tl- 2 08 1. 000 2.209900E+004 1 .573 477E+004 Pb-212 1. 000 7.170238E+004 4.562614E+004 Bi-214 0.442 7.3 923 06E+004 4.187141E+004 Pb-214 1. 000 1.1 937 10E+005 4.109898E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/23/2018 2:22 :06 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 74 . 93 4.7339E- 0 03 6808.25 5 511.34 5 .6896E-002 53.17 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[97]

Nuclide MDA Report 4/23/2018 2 : 22 : 06 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nucl i de MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"'2 ) (pCi/M"'2 )

+ K-40 1460 . 82* 10 .66 2 . 259E+005 2. 26E+005 ,,9. 572E+005 9. 397E+004 Co-60 1173.23 99.85 4.034E+004 3.75E+004/-2.484E+004 /1.836E+004 1332.49 99.98 3 . 755E+004 5.327E+003~1.685E+004 Nb- 94 702.65 99.81 3.920E+004 3 .14E+004 -7.126E+003 1.820E+004 871. 0 9 99.89 3.143E+004 -6.326E+004 l.416E+004 Ag-108m 433.90 90.50 3 . 945E+004 3 .94E+004 - 5.066E+004 1.853E+004 614.3 0 89.80 5.363E+004 6.714E+004 2 . 536E+004 722.9 0 9 0 .80 4.370E+004 ) . 949E+004 2.029E+004 Cs - 134 604.72 97.62 4.848E+004 4.0 9E+004\/"4.717E+004~2.291E+004 795.86 85.46 4.086E+004 Cs-137 661. 66 85.10 4.384E+004 4.38E+004~::;g::~~!/;:~~~::~~:

Eu-152 121. 78 2 8.67 2.076E+005 1.59E+005 -1.913E+00 5 1 . 015E+005 344.28 26.60 1.741E+005 9.035E+004 8.347E+004 1408.01 21. 07 1.594E+005 5.384E+004 7.033E+004 Eu-154 123.07 40.40 1.477E+005 9.38E+004 4.686E+004 7.223E+004 723.30 2 0.06 1.946E+005 7. 1 71E+004 9.022E+004 1274.43 34.80 9.384E+004 -4.634E+004 4.152E+004 Eu- 155 86.55 30.70 2.564E+005 2.56E+005 7.447E+00 4 1.258E+005 10 5.31 21.10 3.024E+005 4.466E+005 1.480E+005

+ Tl -208 583. 1 9* 85.00 2.265E+004 2.27E+004 2.210E+004 9.831E+003 Bi-212 727.33 6.67 5.615E+005 5.62E+005 - 1.932E+005 2.594E+005

+ Pb-212 238.63* 43.60 6.870E+004 6.87E+004 7.170E+004 3.255E+004

+ Bi-214 609.32* 45.49 5.901E+004 5.90E+004 7.392E+004 2.665E+004 1120.29 14.92 2 .771E+005 3.402E+005 1.267E+005 1764 . 49 15. 3 0 2 .471E+005 1.982E+005 1.087E+005

+ Pb-214 295. 2 2* 18.42 l .453E+005 4.49E+004 3 .699E+004 6.791E+004 351.93* 35.60 4.490E+004 1 .439E+005 1.974E+004 Ra-226 186.21 3.64 l.295E+006 1.29E+006 -1.077E+006 6.280E+005 Ac-228 338.32 1 1. 27 3.345E+005 1.74E+005 -3.118E+005 1 .589E+005 911. 20 25.80 l.736E+005 2.144E+005 8.066E+004 968.97 15.80 2.753E+005 3.907E+005 1.273E+005 Am - 24 1 59.54 35.90 2.640E+005 2 .64E+005 1.145E+005 1. 2 90E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[98]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/23/2018 2:08: 25 PM v

Sample Sample Sample Title Description Identification B306215AFSWC006GD East U2 Valve House Wal l v Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample *Size 2 .830E+001 MA2 Sample Taken On 4/23/2018 1:58:00 PM Acquisition Started 4/23/2018 1:58:24 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

[99]

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

Detector Name: 6279 Sample

Title:

B306215AFSWC006GD Peak Analysis Performed on: 4/23/2018 2 :08: 2 5 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Cont inuum No. start e nd centroid (keV) (keV) Area Uncert. Counts 1 121- 136 128.70 32.09 1.12 2.95E+001 26.20 4.65E+001 2 284- 347 298.45 74.58 0.49 2.60E+00 2 165.59 7.20E+002 3 945 - 962 953.38 238.47 0.40 2.65E +001 29.98 6.05E+001 4 1173 - 1190 1181.14 295.45 0.70 3.68E+001 24.07 3.32E+001 5 1398 - 1415 1406.90 351. 93 1. 02 4.81E+001 23.30 2.69E+001 6 2324 - 2341 2332.18 583.33 0.32 6.68E+OOO 17.11 2.03E+001 7 2427 - 2444 2435.73 609. 22 0.47 4.06E+001 18.50 1.34E+001 8 2637 - 2654 2645.53 661.67 0.64 5.84E+001 17.86 6.61E+OOO 9 3636 - 3653 3644.95 911. 48 1. 66 2.lOE+OOl 14 .18 9.00E+OOO 10 4473 - 4492 4482.11 1120.63 0. 29 1.83E+001 10.69 2 .68E+OOO 11 5834- 5854 5843.77 1460.66 0.78 7.90E+001 17.78 O.OOE+OOO 12 7050 - 7069 7059.00 1763.94 0.38 1.20E+001 6.93 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[100]

Interference Corrected Activity Report 4/23/2018 2 :08:25 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306215AFSWC006GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. . . . . . . . . . .. . . . . . . . . IDENTIFIED NUCLIDES . .. . . .............. .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.10827E+006 2.67305E+005 Cs-137 1.000 661 . 66* 85.10 6.87879E+004 2 . 2 6014E+004 Tl -2 08 1.000 583.19* 85.00 7.37542E+003 1. 8 92 08E+004 Pb-212 1. 000 238.63* 43.60 3.52661E+004 4.02487E+004 Bi - 214 1. 000 609.32* 45.49 8.57076E+004 4.04043E+004 112 0 .29* 14.92 1.59858E+005 9.41135E+004 1764.49* 15.30 1 . 32 096E+005 7.69959E+004 Pb-214 1.000 295.22* 18.42 1 .29096E+005 8.69622E+004 351.93* 35.60 9.61887E+004 4.87932E+004

  • =Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

[101]

Interference Corrected Activity Report 4/23/2018 2:08:25 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1. 000 1 .108269E+ 0 06 . / 2. 673052E+005 Cs-137 1. 000 6.878788E+004 2.260135E+004

/

Tl-208 1.000 7.375419E+003 1 .892080E+004 Pb -2 1 2 1.000 3.526606E+004 4.024873E+004 Bi-214 1.000 1.038215E+005 3.344244E+004 Pb-214 1. 000 1.040680E+005 4.255269E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

[102]

Interference Corrected Activity Report 4/ 2 3/2018 2 : 08:25 PM Page 5

                    • U N I D E N T I F I E D P EAKS **********

Peak Locate Performed on: 4/23/20 1 8 2: 08: 25 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.09 4.9095E-002 88.93 2 74.58 4.3304E-001 63.73 9 911.48 3.5000E-002 67.5 1 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[103]

Nuclide MDA Report 4/23/2018 2 :08: 25 PM Page 6

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC006GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 3.796E+004 3.80E+004 ).108E+00 6 O.OOOE+OOO Co-60 1173.23 99.85 3.704E+004 3.55E+004.,/'2.369E+003 .;.J...671E+004 1332.49 99.98 3.554E+004 1.065E+003v'l.585E+004 Nb-94 702.65 99.81 3.723E+004 3.70E+004 1 .963E+004 1.721E+004 871.09 99.89 3.696E+004 3.352E+004 1.692E+004 Ag - 108m 433.90 90.50 3.967E+004 3.58E+004 - 1 . 421E+004 1.864E+004 614.30 89.80 5.006E+004 7 . 199E+004 2.358E+004 722.90 90.80 3.581E+004 -l.116E+003 1 . 634E+004 Cs- 134 604.72 97.62 4.803E+004 4.04E+004/'6.066E+004\/"2.269E+004 795.86 85.46 4.037E+004  :/1.764E+004 1.845E+004

+ Cs-137 661.66* 85.10 2.109E+004 2. 11E+OQ4./ 6 .879E+004 8.951E+003 Eu-152 12 1 .78 28.67 2 .014E+005 1 .16E+005 -l.470E+005 9.836E+004 344.28 26.60 1.648E+005 1.445E+004 7.881E+004 1408.01 21. 07 l .156E+005 - 9.189E+004 4.840E+004 Eu- 1 54 123.07 40. 40 1.425E+005 8. 2 7E+004 6.100E+004 6.963E+004 723.30 20.06 1. 621E+005 5 .060E+004 7.400E+004 1274.43 34.80 8.271E+004 - 1.676E+004 3 .596E+004 Eu-155 86.55 30.70 2 .486E+005 2.4 9E+005 8.102E+004 l . 219E+005 105.31 21.10 3.002E+005 2. 32 9E+004 l.469E+005

+ Tl-2 0 8 583. 1 9* 85.00 3 . 263E+004 3.26E+004 7.375E+003 1.482E+004 Bi-212 727.33 6.67 5.294E+005 5.29E+OOS 5.089E+OOS 2.434E+005

+ Pb-212 238.63* 43.60 6.515E+004 6.51E+004 3 . 52 7E+004 3.077E+004

+ Bi-214 609.32* 45.49 5.231E+004 2.98E+004 8.571E+004 2.330E+004 1120.29* 14.92 1.154E+005 1. 599E+005 4.590E+004 1764.49* 15.30 2.979E+004 1. 32 1E+OOS O.OOOE+OOO

+ Pb- 2 14 295. 2 2* 18.42 1. 2 95E+005 6.70E+004 1. 29 1E+005 6 .001E+004 351.93* 3 5.60 6.705E+004 9 .619E+004 3 .082E+004 Ra- 226 186.21 3.64 1. 23 0E+006 1.23E+006 - 6.985E+005 5 .958E+005 Ac- 22 8 338.32 11. 27 3.157E+005 1.68E+005 - 1.641E+005 1.495E+005 911.20 25.80 1 .680E+005 1.322E+004 7.783E+004 968.97 15.80 2.599E+005 2 .652E+005 1.196E+005 Arn-241 59.54 35 .90 2 . 577E+005 2.58E+OO S 1.942E+005 l . 2 58E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[104]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 62 79 Report Generated On 4/24/2018 8:51:53 AM Sample Title B306215AFSWC007GD

/

Sample Description East U2 Valve House Wall v Sample Identification Sample Type Gamma Direct v Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 MA2 V Sample Taken on 4/24/2018 8:41:00 AM Acquisition Started 4/24/2018 8:4 1 : 52 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06 %

Energy Calibration Used Done On 12/28/2 017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

'I)_~ vq 1*1vlcP1 y/zi;/;~ /) /'l()

[105]

Peak Analysis Report 4/24/2018 8:51:53 AM Page 2

          • PE AK A N A L Y S I S REPORT *****

Detector Name: 6279 sample

Title:

B306215AFSWC007GD Peak Analysis Performed on: 4/24/2018 8:5 1 :53 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 283 - 309 299.15 74.76 0.54 2.32E+002 75.19 2.70E+002 2 343- 358 350.05 87.49 0.54 7.00E-001 49.56 1.94E+002 3 946 - 963 954.30 238.70 1. 33 2.24E+001 26.49 4.56E+001 4 1173 - 1190 1181.61 295.57 0.57 2 .26E+001 21.87 2.94E+001 5 1397- 1415 1406.18 351.75 0.76 3.86E+001 22.73 2 .64E+001 6 2428- 2445 2 436.84 609.50 1. 30 3.14E+001 19.68 1 .96E+001 7 4470- 4489 4479.92 1120.09 0.50 1.70E+001 8.25 O.OOE+OOO 8 5836- 5855 5845.35 1461.06 0.94 5 . 30E+001 14.56 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[106]

Interference Corrected Activity Report 4/24/2018 8:51:53 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306215AFSWC007GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10.66 7.43649E+00 5 2 .14259E+005 Eu-1 55 0. 332 86.55* 30.70 1 .2 2198E+00 3 8.65192E+004 1 0 5.31 21.10 Pb-212 1. 000 238.63* 43.60 2.97622E+004 3.55566E+004 Bi-2 14 0.735 609.32* 45.49 6.63387E+004 4.23185E+004 1120. 2 9* 14.92 l .48292E+005 7.29062E+004 1764.49 15.30 Pb-214 1. 000 295.22* 18 . 42 7.92477E+004 7.78031E+004 351.93* 35.60 7.72885E+004 4.69149E+004

  • = Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 . 30 Errors quoted at 2.000 sigma

[107]

Interference Corrected Activity Report 4/24/2018 8:51:53 AM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 7.436492E+0 0 5 2.142590E+005 Eu-155 0. 332 1.221975E+003 8.651922E+004 Pb-212 1. 000 2.976222E+004 3.555656E+004 Bi-214 0. 735 8.699201E+004 3.659962E+004 Pb- 2 14 1.000 7.781094E+004 4.017604E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D P EAKS **********

Peak Locate Performed on: 4/24/2018 8:51: 53 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8 1 92 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 74.76 3.8667E-001 32.4 1 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[108]

Nuclide MDA Report 4/24/2018 8:51:53 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC007GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 3.797E+004 3.80E+004 7.4 3 6E+00 5 O.OOOE+OOO Co-60 1173.23 99.85 3.873E+004 3 .19E+004 ./ _4. 436E+004 1. 756E+004 13 32 .49 99.98 3.189E+004 2 . 557E+004 v-" 1. 402E+004 Nb- 9 4 702.65 99.81 3.329E+004 3.33E+004 - 5. 62 8E+004 1.525E+004 871. 09 99.89 3.738E+004 5.506E+003 1.713E+004 Ag-108m 433.90 90.50 3.733E+004 3.73E+004 l.359E+004 1.747E+004 614.30 89.80 4.844E+004 3.94DE+004 2 .277E+004 722.90 90.80 3.997E+004 6.352E+003 1.842E+004 Cs-134 604.72 97.62 4.687E+004 3. 84E+OD4V8. 066E+004/ 2. 211E+004 795.86 85.46 3 .838E+004 ~.479E+004 1 .745E+004 Cs-137 661. 66 85.10 3.996E+004 4. OOE+oo4./ 2. 740E+004 J1 . 839E+004 Eu-152 121. 78 28.67 1.954E+005 1.40E+005 - 3.714E+004 9.540E+004 344. 2 8 26.60 1.619E+005 5.621E+004 7.735E+004 1408.01 21.07 1.395E+005 1.486E+004 6.037E+004 Eu-154 123.07 40.40 1. 374E+005 8.27E+004 9.546E+004 6.705E+004 723.30 20.06 1. 774E+O 05 1.830E+004 8.161E+004 1274.43 34.80 8.271E+004 -1.331E+005 3.596E+004

+ Eu-155 86.55* 30.70 1. 470E+005 1.47E+005 1.222E+003 7.112E+004 105.31 21.10 2.865E+OOS - 3 . 288E+005 l .401E+005 Tl-208 583.19 85.00 4.145E+004 4.15E+004 -6.036E+003 1.923E+004 Bi-212 727.33 6.67 5.403E+005 5.40E+00 5 5.521E+005 2 .488E+005

+ Pb-212 23 8.63* 43.60 5.773E+004 5.77E+004 2 .976E+004 2 .707E+004

+ Bi-214 609.32* 45.49 6.191E+004 2. 36 E+004 6.634E+004 2 .810E+004 1120. 2 9* 14.92 2.360E+004 1.483E+005 O.OOOE+OOO 1764.49 15.30 2.531E+005 2.092E+005 l.116E+005

+ Pb- 2 14 295.22* 18.42 1.232E+005 6.80E+004 7.925E+004 5.686E+004 351.93* 3 5.60 6.803E+004 7.729E+004 3.131E+004 Ra-226 186.21 3.64 1.198E+006 1. 2 0E+006 7.247E+005 5.800E+005 Ac-228 338.32 11. 27 3.345E+005 1.38E+005 2.189E+005 1.589E+005 911. 20 25.80 1.376E+005 1.502E+004 6.266E+004 968.97 15.80 2 .255E+005 -1.424E+005 1.024E+005 Am-241 59.54 35.90 2 .653E+005 2 .65E+005 1.415E+00 5 1.296E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[109]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/23/2018 3: 03: 52 PM Sample Title B306215AFSWC008GD Sample Description East U2 Valve House Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN v Peak Locate Threshold 3 . 00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 M" 2 Sample Taken On 4/23/2018 2:53:00 PM Acquisition Started 4/23/ 2 018 2:53 : 51 PM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 .06 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2 IN

'})c~~ ll~1 I~!

i/t /;g, IY'7~D

~y~d//~'

[110]

Peak Analysis Report 4/23/2018 3:03:52 PM Page 2

          • PE AK A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B306215AFSWC008GD Peak Analysis Performed on: 4/23/20 1 8 3:03:5 1 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 81 92 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start e nd centroid (keV) (keV) Area Uncert. Counts 1 121- 136 128.74 32.11 0.30 9.78E +OOO 28.30 6.32E+001 2 283- 347 300.24 75.03 0.89 2.16E+002 183 .15 8.74E+002 3 945- 962 953.81 2 38.57 0.40 2 .83E+001 30.98 6.38E+001 4 1399- 1416 1407.09 351.97 0.31 4.34E+001 19.38 1.56E+001 5 2428 - 2445 2436. 22 60 9 .34 0.31 4.64E+001 16.45 6.59E+OOO 6 3635 - 3652 3643 . 97 911. 23 0.61 2 .24E+001 12.4 0 4.59E+OOO 7 5835- 5854 5844.37 1 460.81 0.42 7.37E+001 18.07 2.35E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[111]

Interference Corrected Activity Report 4/ 23/2 018 3: 03: 52 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306215AFSWC008GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) ( %) (pCi/M"' 2 ) Uncertainty K-40 1.000 1460.82* 10.66 1 .03330E +006 2.68906E+005 Pb-212 1. 000 238.63* 43.60 3.75546E+004 4.16340E+004 Bi-214 0.442 609.32* 45.49 9.80016E+004 3.66828E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.437 295.22 18.42 351.93* 35.60 8.69428E+004 4.09113E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2 .000 sigma

[112]

Interference Corrected Activity Report 4/23/2018 3:03: 52 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 l.0 3 3301E+006 2.689059E+005 Pb-212 1.000 3 . 755461E+004 4.163398E+004 Bi-214 0.442 9.800159E+004 3 . 668280E+004 Pb-214 0.4 3 7 8.694278E+004 4.091132E+004

? = Nuclide is part of an undetermined solution X = Nuclide rejected by the interference analysi s

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/23/2018 3:03:51 PM Peak Locate From Channe l : 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nucl i de 1 32.11 1.6301E-002 289.38 2 75.03 3.5971E-001 84 . 86 6 911.23 3.7346E-002 55.32 Tol. Ac - 228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 s igma

[113]

Nuclide MDA Report 4/23/2018 3 :0 3 : 52 PM Pa g e 5

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2 IN Sample

Title:

B306215AFSWC008GD Nuclide Library Used: C =. \GENIE2K\CAMFILES\Zion Lib-BNL. NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) { %) (pCi/M"2 ) (pCi/M"2 ) (pci/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 l.682E+005 l.68E+005~1.033E+00 6 6.514E+004 Co-6 0 1173 . 2 3 99.85 3.704E+004 3.34E+004 -1.468E+00 4 l .671E+004 1332.49 99.98 3.340E+004 2. 841E+00 4 "\./1. . 478E+004 Nb-94 702.65 99.81 3.655E+004 3 .43E+004 2.927E+00 4 l.687E+004 8 71. 09 99.89 3.432E+004 -8.627E+003 1.560E+004 Ag-108m 433.90 90.50 3.757E+004 3. 76E+004 l.618E+004 1.759E+004 614.30 89.80 4.817E+004 2.283E+004 2 . 2 63E+004 722.90 90.80 3.836E+004 -1. 046E+004 1.762E+004 Cs -1 3 4 604.72 97 . 62 4.420E+004 4. 04E+004 V 1 . 204E+004 ~ . 077E+004 795.86 85.46 4.037E+004 -,.J. .800E+004 1.845E+004 Cs -1 37 661. 66 85.10 4.457E+004 4.46E+004 V 4.2D8E+004 '\/2.069E+004 Eu-1 52 121.78 2 8.67 2 .007E+005 l.48E+005 -5 .618E+004 9 .804E+004 344. 2 8 26.60 1.574E+005 - 8.475E+003 7.512E+004 1408.01 2 1. 07 l.478E+005 - 4.421E+004 6.454E+004 Eu-154 123.07 40.40 l.424E+005 9 .17 E+004 - 1.580E+004 6 . 957E+004 723.30 20.06 l.718E+005 2 .615E+003 7.884E+004 1274.43 34.80 9 .174E+004 7.583E+004 4.047E+004 Eu-155 86.55 30.70 2 .573E+005 2 .57E+005 4.345E+004 l .263E+005 105.31 21.10 3 . 018E+005 -2.423E+005 1.477E+005 Tl-208 583.19 85.00 4.568E+004 4.57E+004 - 8.541E+003 2 . 135E+004 Bi-212 727.33 6.67 5 .182E+005 5.18E+005 -l.672E+005 2 .378E+005

+ Pb-212 238.63* 43.60 6.724E+004 6.72E+004 3.755E+004 3.182E+004

+ Bi -2 14 609.32

  • 45.49 3.774E+004 3.77E+004 9.800E+004 l.601E+004 1120.29 14 . 92 2.738E+005 2 .191E+005 l.251E+005 1764.49 15.30 2.215E+005 1 .541E+005 9.584E+004

+ Pb - 214 295.22 18.4 2 2.242E+005 5.22E+004 6.548E+004 l .073E+005 351.93* 35.60 5.219E+004 8.694E+004 2.339E+004 Ra-226 186.2 1 3.64 1.204E+006 1.20E+006 -2 .252E+006 5.828E+005 Ac-228 338.32 11. 27 3. 2 39E+005 l.71E+005 -1.830E+005 l.536E+005 911.20 25.80 1. 708E+005 l.133E+005 7.926E+004 968.97 15 . 80 2.599E+005 2 .658E+005 l.196E+005 Am- 241 59.54 35.90 2.844E+005 2 .84E+00 5 1 .360E+005 l.392E+005

+ = Nucl i de identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[114]

          • GAMM A SPE C TRUM ANALYSIS *****

Filename: 6279 Report Generated On 4 /23/2 018 1: 47 : 0 3 PM Sample Title B306215AFSWC009GD Sample Description East U2 Valve House Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2 IN Peak Locate Threshold 3.00 Peak Locate Range (in channels ) 85 - 8 1 92 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"' 2 Sample Taken On 4/23/2018 1:36:00 PM /

Acquisition Started 4/23/2018 1: 37: 02 PM V Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06  % v Energy Calibration Used Done On Efficiency Calibration Used Done On 12/28/2017 2/1/2018 vV Efficiency ID 3M90D CP 2 IN /

'J)cfr I/cir'~/

Yf(fr o~J5

~

[115]

Peak Analysis Report 4/23/2018 1:47:0 3 PM Page 2

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

Detector Name: 6279 Sample

Title:

B306215AFSWC009GD Peak Analysis Performed on: 4/23/2018 1:47:0 3 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 121- 136 128.10 31. 94 0.53 l.80E+001 24.82 4.50E+001 2 293 - 308 300.47 75.09 0.71 2.0lE+OOl 58.32 2.75E+002 3 945 - 962 953.18 238.42 0.37 -1.58E+001 33. 2 5 8.98E+001 4 1171- 1188 1179.96 295.15 0.27 2.18E +001 21.60 2.92E+001 5 1399- 1416 1407.29 352.02 0 .45 4.70E +001 22.36 2.40E+001 6 2323 - 2340 2331.19 583.08 0.73 2.75E+001 12.99 4.50E+OOO 7 2428- 2445 2436.66 609.45 0.93 3.SOE+OOl 16.03 9.00E+OOO 8 2637 - 2654 2645.31 661.62 0.36 3.73E+001 17.08 9.74E+OOO 9 5834 - 5853 5843.62 1460.62 2 .01 8.44E+001 19.36 2.57E+OOO 10 7052- 7071 7061. 25 1764.50 0.46 l.50E+001 7.75 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[116]

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

Sample

Title:

B306215AFSWC009GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 l. 18444E+006 2. 9 0388E+005 Cs-137 1. 000 661.66* 85.10 4.38889E + 004 2 .08049E+004 Tl- 208 1.000 583 . 19* 85.00 3.03748E+004 1. 4 8012E+004 Pb-2 12 1.000 238.63* 43.60 - 2 . 09844E+004 4.43117E+004 Bi- 2 14 0.706 609.32* 45.49 7.39139E+004 3. 50017E+004 112 0. 29 14.92 1764.49* 15 . 30 1.65153E+005 8.63043E+004 Pb- 2 14 1.000 295.22* 18.42 7.66002E+004 7.67487E+004 351.93* 35.60 9.39711E+004 4.69015E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

[117]

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          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1 .000 1.184441E+006 V2.903880E+005 Cs-137 1. 000 4.388891E+004 2.080488E+004 /

Tl-208 1. 000 3.037477E+004 1.480116E+004 Pb-212 1. 000 - 2 .098443E+004 4.431169E+004 Bi-214 0.706 8.680121E+004 3.243572E+004 Pb-214 1. 000 8.924782E+004 4.002032E+004

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

@=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2. 000 sigma

[118]

Interference Corrected Activity Report 4/23/2018 1 :47: 03 PM Page 5

                    • U N I D E N T I F I E D PE AK S **********

Peak Locate Performed on: 4/23/2018 1 :47: 03 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 31. 94 3.0053E-002 137.64 2 75.09 3 .3531E-002 2 89.87 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[119]

Nuclide MDA Report 4 /23/2 018 1 :47:03 PM Page 6

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2 IN Sample

Title:

B3062l5AFSWC0 0 9GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib -BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 1.783E+005 1 . 78E+005 A . 1 84E+006 7. 019E+004 Co-60 1173.23 99.85 3 . 927E+004 3 . 55E+004 ./ 1 . 678E+004/l. 783E+004 1332.49 99.98 3.554E+004 1.615E+004 1.585E+004 Nb - 94 702.65 99.81 3.329E+004 2.99E+004 -1.554E+003 1.525E+004 87 1 .09 99.89 2.987E+004 -3 .215E+004 1.338E+004 Ag-108m 433.90 90.50 4.377E+004 4.07E+004 1.082E+004 2.069E+004 614.30 89.80 4.817E+004 3 .561E+004 2.263E+004 722.90 90.80 4.074E+004 .,A.534E+004 1 .881E+004 Cs-134 604.72 97.62 4.494E+004 4. 49E+004 ../ 6. 444E+004 v"2 .115E+004 795.86 85.46 4.537E+004 ~.647E+003 2 .095E+004

+ Cs-137 661.66* 85.10 2 . 635E+004 2.63E+004.../4.389E+004 1 .158E+004 Eu - 152 1 2 1.78 28.67 1.974E+005 1.63E+005 - 1.498E+005 9 .640E+004 34 4 .2 8 26.60 1.633E+005 - 6.886E+004 7.808E+004 1408.01 21. 07 1.631E+005 1.387E+005 7 . 215E+004 Eu - 154 123.07 40.40 1.402E+005 1.02E+005 1 .881E+004 6.847E+004 723 .3 0 20.06 l.845E+005 2.562E+005 8.516E+004 1274.43 3 4.80 1.018E+005 4.943E+004 4.548E+004 Eu-155 86.55 30.70 2.371E+005 2 . 37E+005 -6.224E+004 1.162E+005 105.31 2 1 .10 2.769E+005 -2 . 959E+005 1 .352E+005

+ Tl- 2 0 8 583.19* 85.00 1. 690E+004 1 .69E+004 3.037E+004 6.957E+003 Bi-212 727.33 6.67 5.403E+005 5.40E+005 3.982E+005 2 .488E+005

+ Pb-212 238.63* 43.60 7.832E+004 7.83E+004 - 2.098E+004 3.736E+004

+ Bi-214 609.32* 45.49 4.329E+004 2.98E+004 7.391E+004 1.879E+004 1120.29 14.92 2 .671E+005 -1.817E+005 1.218E+005 1764.49* 15.30 2 .979E+004 1.652E+005 O.OOOE+OOO

+ Pb-214 2 95.22* 18.42 1 .219E+005 6.36E+004 7.660E+004 5.618E+004 3 51.93* 35.60 6.357E+004 9.397E+004 2 .908E+004 Ra -22 6 1 86.21 3.64 1.265E+006 1. 2 6E+006 - 7.866E+005 6.130E+005 Ac -22 8 338.32 11. 27 3.318E+005 1.51E+005 9.780E+004 1.576E+005 911.20 25.80 1. 512E+005 1.444E+005 6.945E+004 968.97 15.80 2 .405E+005 1.251E+005 1.099E+005 Am-241 59.54 35.90 2 .369E+005 2.37E+005 7.788E+004 1.154E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[120]

          • GAMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4 /24/2 018 1: 46 : 35 PM Sample Title B306215AFSWC010GD v Sample Description East U2 Valve House Wall V Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN V Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size V Sample Taken On 4/24/2018 1 :36: 0 0 PM Acquisition Started 4/24/2018 1: 36: 34 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 %

Energy Calibration Used Done On Efficiency Calibration Used Done On 12/28/2 017 2/1/2018 vV Efficiency ID 3M90D CP 2 IN v

~ -V.1-Z-l [)IJ-TtI?-1J

'-}-2 5-1 ~ C) 1-L{ g

[121]

Peak Analysis Report 4/24/2018 1: 46 : 35 PM Page 2

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

Detector Name: 6279 Sample

Title:

B306215AFSWC010GD Peak Analysis Performed on: 4/24/2018 1:4 6 :35 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start e nd centroid (keV) (keV) Area Uncert. Counts 1 12 1 - 136 128.58 32 .07 0 . 83 4.02E+001 2 8.24 5 .28E+001 2 290- 309 300.50 75.09 0.86 l.81E+002 66.13 2 .59E+002 3 464- 479 471.05 117.78 1.26 2 . 2 1E+001 41.12 1 .31E+002 4 946- 963 954.90 2 38.85 0.70 2.21E+001 32.04 7.19E+001 5 1172- 11 89 1180.31 2 95.24 0.41 4.69E+00 1 23.68 2 .81E+001 6 1399- 1416 1407.96 352.19 1. 3 0 5.42E+001 22.76 2 .28E+001 7 2326 - 2343 2334.41 583.89 0.31 1.93E+001 13 . 87 8.75E+OOO 8 2 429 - 2446 2437.93 609.77 0.37 3.85E+001 19.62 1.75E+001 9 2 638- 2657 2647.44 662.15 1. 28 l.15E+002 23.87 7.62E+OOO 10 4474 - 4493 4483.16 1120.90 0.67 2.04E+001 10.98 2.61E+OOO 11 5838 - 5858 5847.98 1461.71 1. 60 9.lOE+OOl 19.08 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[122]

Interference Corrected Activity Report 4/24/2 018 1 :46: 35 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample Title : B3062 1 5AFSWC010GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. .. .......... . . ..... IDENTIFIED NUCLIDES .. ........... ...... . .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertainty K-40 0.999 1460.82* 10.66 1 .27719E+006 2.89831E+005 Cs-137 1.000 661.66* 85.10 l. 35981E+005 3.25290E+004 Eu - 152 0.647 121.78* 28.67 3.80914E+004 7.11623E+004 344.28* 26.60 1 .45222E+005 6.49518E+004 1408.01 21.07 Tl- 2 08 0.999 583.19* 85.00 2.12776E+004 l.55403E+004 Pb-212 1.000 238.63* 43.60 2.93623E+004 4. 2 8796E+004 Bi-214 0.735 609.32* 45.49 8.12896E+004 4. 2 5785E+004 1120.29* 14 . 92 l .77939E+005 9.68515E+004 1764.49 15 . 30 Pb- 2 14 1 .00 0 295. 22

  • 18.42 1.64509E+005 8.71541E+004 3 51.93* 35.60 l . 08509E+005 4.83615E+004
  • =Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index* threshold = 0 . 30 Errors quoted at 2 . 000 sigma

[123]

Interference Corrected Activity Report 4/24/2018 1 :46: 35 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 1. 2 77192E+006 / 2. 898313E+005 Cs- 137 1. 000 1. 359811E+005 3.252904E+004 Eu-152 0.647 1.304822E+004 6.278562E+004 Tl -2 08 0.999 2 .127756E+004 1.554026E+004 Pb -2 12 1. 000 2.936231E+004 4.287957E+004 Bi -2 14 0.735 9.694365E+004 3.897810E+004 Pb -2 14 1 .000 1.142379E+005 5.544952E+004

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

@ Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2. 000 sigma

[124]

Interference Corrected Activity Report 4 /24/2018 1 :46: 35 PM Page 5

                    • U N I D E N T I F I E D PE A K S **********

Peak Locate Performed on: 4/24/2018 1: 4 6: 35 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.07 6.6927E-002 70.31 2 75.09 3.0197E-001 36.50 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 00 0 sigma

[125]

Nuc l ide MDA Report 4/24/2018 1: 46: 35 PM Page 6

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC010GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) {pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2)

+ K-40 1460.82* 10.66 3.798E+004 3.80E+004 l. 2 77E+006 O.OOOE+OOO Co-6 0 1173.23 99.85 3.927E+004 2. 94E+004 /1. 2 94E+003 Vl. 783E+004 1332.49 99.98 2.944E+004 - 2 .481E+004 l. 2 80E+004 Nb-94 702.65 99.81 3.442E+004 3.44E+004 2 . 3 94E+004 l.581E+004 871. 0 9 99.89 3.567E+004 - l. 62 7E+004 l.628E+004 Ag-108m 433.90 90.50 4.458E+004 3 . 84E+004 2 .301E+004 2 . 109E+004 614.30 89.80 5.412E+004 6.929E+004 2.561E+004 72 2 .90 90.80 3 .836E+004 8.931E+002 l.762E+004 Cs-134 6 0 4 . 72 97.62 4.780E+004 3.46E+004 /6.144E+004../ 2 . 257E+004 795.86 85.46 3.458E+004 -l.029E+004 l.555E+004

+ Cs - 137 661.66* 85.10 2.336E+004 2.34E+004 l . 360E+00 5 l.009E+004

+ Eu- 152 12 1 .78* 28.67 l.180E+005 8.37E+004 3.809E+004 5.665E+004 344.28* 26.60 8.372E+004 l.452E+005 3.824E+004 1408.01 21 .07 1. 478E+005 -l.166E+005 6.454E+004 Eu-154 123.07 40.40 1. 4 03E+005 7.51E+004 1 . 2 38E+004 6 . 853E+004 723.30 20 . 06 1 . 755E+005 1.307E+004 8.070E+004 1274.43 34.80 7.512E+004 -3.891E+004 3 . 216E+004 Eu-155 86.55 3 0.70 2 .508E+005 2.51E+005 9 . 006E+004 l.230E+005 105.3 1 21.10 2.964E+005 - l .874E+004 l.450E+005

+ Tl-208 583.19* 85.00 2 . 2 52E+004 2.25E+ 0 04 2.128E+004 9.763E+003 Bi-212 727.33 6.67 5 .403E+005 5.40E+005 - 1.134E+005 2.488E+005

+ Pb-212 238.63* 43.60 7.062E+004 7.06E+004 2 . 936E+004 3.351E+004

+ Bi -2 14 609. 32

  • 45.49 5 .853E+004 5.85E+004 8.129E+004 2 .640E+004 1120.29* 14 .92 1 .132E+005 1.779E+005 4.480E+004 1764.49 15.30 2 .531E+005 2.092E+005 1.116E+005

+ Pb-214 295.22* 18.42 l.210E+005 6 . 26E+004 1.645E+005 5.575E+004 351.93* 35.60 6 . 255E+004 1.085E+005 2 .857E+004 Ra-226 186.21 3.64 1.270E+006 1. 27E+O 06 2.490E+005 6.157E+005 Ac-228 338.32 11. 2 7 3.171E+005 1.51E+005 -2.718E+005 l.502E+005 911.20 25 . 80 1 .512E+005 4.733E+004 6.945E+004 968.97 15.80 2.316E+005 -l.367E+005 l.054E+005 Am - 2 41 59.54 35.90 2. 359E+005 2.36E+005 -l.278E+005 l.149E+005

+ = Nucl ide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[126]

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

Filename: 6279 Report Generated On 4/24/ 2 018 10:30:01 AM Sample Title B306215AFSWC011GD Sample Description East U2 Valve House Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 MA2 Sample Taken On 4/24/2018 10:19:00 AM Acquisition Started 4/24/2018 10:20:00 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06 %

Energy Calibration Used Done On 12/28/2 017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

[127]

Peak Analysis Report 4/24/2018 10: 3 0:01 AM Page 2

          • PE AK A N A L Y S I S REPORT *****

Detector Name: 62 79 Sample

Title:

B306215AFSWC011GD Peak Analysis Performed on: 4/24/2018 10 :3 0:01 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 294 - 347 301.36 75.31 0.68 - 1.49E+002 171. 36 9.66E+002 2 946 - 1001 954.78 238.82 0.58 1.24E+002 57.38 8.80E+001 3 1400- 1418 1409.06 352.47 0.78 5.56E+001 22.36 2.04E+001 4 2327 - 2344 2335.25 584.10 0 .32 2 .65E+001 12.85 4.50E+OOO 5 2430 - 2447 2438.35 609.88 0.50 4.05E+001 20.36 1.95E+001 6 4478 - 4497 4487.88 1122.07 0.98 1.35E+001 9.54 2 .52E+OOO 7 5842 - 5861 5851.64 1462.63 0.61 6.84E+001 17.62 2.56E+OOO 8 7061 - 7080 7070.01 1766.69 0.42 2.lOE +OOl 9.17 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 s igma

[128]

Interference Corrected Activity Report 4/24/2 018 10:30:01 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306215AFSWC011GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.995 1460.82* 10.66 9.60941E+005 2. 61147E+005 Tl-208 0.999 583.19* 85.00 2 .92966E+004 1.46338E+004 Pb-212 1.000 238.63* 43.60 l.64861E+005 8.08345E+004 Bi-214 0.997 609.32* 45.49 8.56391E+004 4.42367E+004 1120.29* 14.92 1.17730E+005 8.38429E+004 1764.49* 15.30 2 .31394E+005 1.02675E+005 Pb-214 0.436 295. 22 18.42 351.93* 35.60 1.11302E+005 4.77628E+004

  • =Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2.000 sigma

[129]

Interference Corrected Activity Report 4/24/2018 10 :3 0:0 1 AM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.995 9.609411E+005 2.611465E+005 Tl-208 0.999 2.929663E+004 l.463377E+004 Pb- 212 1. 000 1.648611E+005 8.083447E+004 Bi-214 0.997 1 .102217E+005 3.65 6 050E+004 Pb-214 0.436 1.113017E+005 4 . 77 6 282E+004

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

@=Nuclide contains energy lines not used in Weighted Mean Act i vity Errors quoted at 2 .000 sigma

                    • UN I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/24/2018 10: 3 0 : 01 AM Peak Locate From Channe l : 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

g..

No. (keV) Counts per Second 0 Uncertainty Type Nuclide 1 75.31 -2.4810E-001 -11 5 .12 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[130]

Nuclide MDA Report 4 /24/2 018 10 :3 0:0 1 AM Page 5

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

Detector Name: 62 79 Sample Geometry: 3M90D CP 2 IN Sample

Title:

B3 06215AFSWC011GD Nuclide Library Used: C: \GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M" 2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 1. 782E+005 1.78E+005 9 .609E+00 5 7.011E+004 Co - 6 0 1173.23 99.85 4.336E+004 3.88E+004v"3 . 901E+004 1.987E+004 1332.49 99.98 3.882E+004 3 . 977E+004 ./1 . 749E+004 Nb - 94 702.65 99.81 3.329E+004 3.09E+004 - 1 .148E+004 1.525E+004 871. 09 99.89 3.092E+004 - 2 .770E+004 1.390E+004 Ag- 108m 433.90 90.50 4.013E+004 4.01E+004 - 7.426E+00 2 1.887E+004 614.30 89.80 5.509E+004 6.518E+004 2.609E+004 72 2 .90 90.80 4.225E+004 3 .725E+004 }.956E+004 Cs-134 604.72 97.6 2 5.070E+004 3.99E+004./3.270E+004 v"2.402E+004 795.86 85.46 3.989E+004 - 9.482E+003 1.820E+004 Cs - 137 661. 66 85.10 4.271E+004 4. 2 7E+004..1""9.232E+002\/'1.976E+004 Eu- 152 121. 78 28.67 1.917E+005 1. 2 1E+005 - 3.495E+004 9. 3 54E+004 344.28 26.60 1.746E+005 7.040E+004 8 .3 70E+004 1408.01 2 1 .07 1 . 208E+005 6.935E+004 5. 10 2E+004 Eu-154 123.07 40.40 1. 361E+005 9.98E+004 4.393E+004 6.639E+004 723.30 20.06 1.929E+005 8.352E+004 8.940E+004 1274.43 34.80 9.985E+004 -3 .999E+004 4.453E+004 Eu-155 86.55 30.70 2.454E+005 2 .45E+005 1.536E+005 l.203E+005 105. 3 1 21.10 2.802E+005 - 9.648E+004 1.369E+005

+ Tl-208 583.19

  • 85.00 1. 697E+004 l.70E+004 2.930E+ 0 04 6.988E+003 Bi-212 7 27.33 6.67 6.063E+005 6.06E+005 4.952E+005 2 .818E+005

+ Pb-212 23 8.63* 43.60 1 . 193E+005 1.19E+005 1.649E+005 5.785E+004

+ Bi-214 609.32* 45.49 6 . 095E+004 2.98E+004 8.564E+00 4 2 .761E+004 1120.29* 14.92 l.111E+005 1.177E+005 4 .3 75E+004 1764.49* 1 5.30 2.982E+004 2 .314E+005 O.OOOE+OOO

+ Pb-214 295.22 1 8.42 2.134E+005 6.03E+004 7.795E+00 4 1.019E+005 351.93* 35.60 6.029E+004 1.113E+005 2 .744E+004 Ra-226 1 86.21 3.64 1.248E+006 1. 25E+006 1.640E+005 6 . 049E+005 Ac-228 338.32 11. 27 3.383E+005 1 .38E+005 -3 .021E+005 1 .608E+005 911.20 25.80 1. 376E+005 6.488E+004 6.266E+004 968.97 15.80 2.094E+005 5.171E+004 9.431E+004 Am-24 1 59.54 35.90 2.431E+005 2 .43E+005 -4.023E+004 l.185E+005

+=Nuclide identified during the nuclide identification

  • =Energy line found in the spectrum

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

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

[131]

          • GAMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/24/ 2 018 9:05:37 AM Sample Title B306215AFSWC012GD v

Sample Description East U2 Valve House Wall v""

Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 MA2 V Sample Taken On 4/24/2018 8: 55 : ,00 AM Acquisition Started 4/24/2018 8:55:36 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 % /

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

'J)fiA- V&! j)l/-tliJ

'(/2-J/ tr o T9, C__)~~'L-

[132]

Peak Analysis Report 4 / 24 / 2 018 9:05:37 AM Page 2

          • PE AK A N A L Y S I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306215AFSWC012GD Peak Analysis Performed on: 4/24/2018 9:05:37 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 178 - 194 185 . 79 46.38 1. 05 3.35E+001 32.01 7.05E+001 2 285 - 318 299.28 74.79 0.68 2 .67E+002 85 . 97 2 . 99E+002 3 361 - 379 371.14 92.77 0.56 -1.lOE+OOl 53.94 2 .10E+002 4 1173- 1190 118 1 .33 295.50 0.46 2.25E+001 22.53 2 .85E+001 5 1400- 1417 1408.24 352.26 0. 52 4.20E+001 22.30 2 .50E+001 6 2326 - 2343 2334 . 73 583.97 1. 50 2.39E+001 16.41 l .21E+001 7 2430 - 2447 2438.19 609.84 1.42 3.57E+001 1 7.07 l.13E+001 8 3869- 3886 3877.76 969.65 0.55 l.22E+001 11 .77 6.78E+OOO 9 5839 - 5859 5849.1 0 1461.99 1. 54 7.lOE+OOl 16.85 O.OOE+OOO 10 7056 - 7075 7065.15 1765.48 0.31 1.70E+001 8.25 O.OOE+OOO M First peak in a mul tiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[133]

Interference Corrected Activity Report 4/24/2018 9 :0 5: 3 7 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306215AFSWC012GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.998 1460 . 82* 10.66 9.96610E +005 2 . 51885E+005 Tl- 2 08 0.999 583.19* 85. 00 2.64146E +004 1. 84161E+004 Bi -214 0.706 609.32* 45.49 7 . 53426E+004 3 .71839E+004 1120.29 14.92 1764.49* 15.30 1 .87238E+005 9.20537E+004 Pb-214 1.000 2 95. 22

  • 18.42 7 . 91403E+004 8.00679E+004 351.93* 35.60 8.41411E+004 4.63819E+004
  • = Energy line found in the spectrum.

@ = Energy l ine not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2.000 sigma

[134]

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          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.998 9.966104E+005 2 .518853E+005 Tl-208 0.999 2.641463E+004 1.841610E+004 Bi-214 0.706 9.103898E+004 3.447736E+004 Pb-214 1.000 8.288462E+004 4.013431E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

                    • U N I D E N T I F I E D P E AK S **********

Peak Locate Performed on: 4/24/2018 9:05:37 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % un*certainty Type Nuclide 1 46.38 5.5817E-002 95.58 2 74 . 79 4.4548E-001 32.16 3 92.77 - l.8268E-002 -492. 1 5 8 969.65 2.0373E-002 96 . 2 6 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[135]

Nuclide MDA Report 4/24/ 2 018 9:05: 3 7 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC012GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"'2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 3.798E+004 3.80E+004 9.966E+00 5 O.OOOE+OOO Co-60 1173.23 99.85 4.137E+004 3.27E+004v'3.572E+004 1.888E+004 1332 .49 99.98 3.265E+004 7.551E+003 V1.440E+004 Nb - 94 702.65 99.81 3.550E+004 3.39E+004 4.663E+003 1.635E+004 8 71. 09 99.89 3.386E+004 1.011E+003 1.537E+004 Ag - 1 08m 433.90 90.50 3.990E+004 3 . 99E+004 - 2.759E+004 1.875E+004 6 14 .30 89.80 4.648E+004 6.479E+004 2 .179E+004 722 '. 90 90 . 80 4.074E+004 - 3.188E+003 1.881E+004 Cs - 134 604.72 97. 62 4.318E+004 4. 27E+004,v"3. 026E+004 v2. 027E+004 795.86 85.46 4.273E+004 o/. 272E+004 J... 962E+004 Cs - 137 661.66 8 5 .10 4.738E+004 4 . 74E+004 t.'4 .463E+003V"2.210E+004 Eu- 152 121.78 28.67 1.902E+005 1.35E+005 -8. 3 79E+004 9 .277E+004 344.28 26.60 1. 704E+005 6.917E+003 8.164E+004 1408.01 21.07 1. 351E+005 9.016E+004 5.817E+004 Eu-154 123.07 40.40 1.330E+005 9.79E+004 -9. 29 0E+004 6.486E+004 723.30 20.06 1 . 810E+005 - 7.788E+004 8.340E+004 1274.43 34.80 9.789E+004 3.705E+004 4.355E+004 Eu-155 86.55 30.70 2.369E+005 2 .3 7E+005 1 . 488E+005 1.1 61E+005 105.31 21.10 2.859E+005 1.025E+005 1.397E+OOS

+ Tl-208 583 . 19* 85.00 2.696E+004 2.70E+004 2.641E+004 1. 1 98E+004 Bi-212 727.33 6.67 5.403E+005 5.40E+005 - 2.240E+005 2.488E+005 Pb-212 238.63 43.60 1. 062E+005 1 . 06E+OOS 1.055E+005 5.129E+004

+ Bi-214 609.32* 45.49 4.810E+004 2 . 98 E+004 7.534E+004 2.119E+004 1120.29 14.92 2.532E+005 - 2 .726E+002 l.148E+005 1764.49* 15.30 2.980E+004 1.872E+00 5 O.OOOE+OOO

+ Pb-214 295.22* 18.42 1.274E+005 6 . 52E+004 7.914E+004 5.896E+004 351.93* 35 . 60 6.516E+004 8.414E+004 2 .987E+004 Ra-226 1 86.21 3.64 1 .164E+006 1.16E+006 - 1.665E+00 6 5.627E+005 Ac-228 338.32 11. 2 7 3.559E+005 1.56E+005 - 1 . 045E+005 l . 696E+OOS 911.20 25.80 l .560E+005 1.602E+OOS 7.183E+004 968.97 15.80 2.54SE+00 5 - 7.416E+004 1.169E+OOS Am-241 59.54 35.90 2. 509E+005 2 .51E+005 1.929E+004 l.224E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[136]

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

Filename: 6279 Report Generated On 4/24/2018 1:29:01 PM Sample Title B306 2 15AFSWC013GD Sample Description East U2 Valve House Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2 IN Peak Locate Threshold 3 .00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10 .000 keV Sample Size 2.830E+001 MA2 Sample Taken On 4/24/2018 1:18:00 PM Acquisition Started 4/24/2018 1:19:00 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07  %

v Energy Calibration Used Done On 12/28/2 017 V Efficiency Calibration Used Done On 2/1/2018 v Efficiency ID 3M90D CP 2 IN V

'7)/tptPrV.At/t L\~J 1/z.:;/ir O -+lxr e___) ~

[137]

Peak Analysis Report 4/24 /2 018 1 :29 :01 PM Page 2

          • PE AK A N A L Y S I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306215AFSWC013GD Peak Analysis Performed on: 4/24/2018 1:29:01 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 121- 136 128.67 32.09 0.61 3 . 3 3E+001 2 7.47 5.17E+001 2 286 - 306 298.33 74.55 0.58 9.07E+001 72.64 3.36E+002 3 946- 963 954.02 23 8.63 0.32 2.llE+OOl 32.77 7.49E+001 4 1173- 1190 1181.76 2 95.61 0.96 4 . 24E+001 23.9 5 3.06E+001 5 1398 - 1416 1407.42 352.05 0.33 4.68E+001 25.73 3.52E+001 6 2325 - 2342 2333.15 583.57 0.57 2.15E+001 16.23 1.35E+001 7 2429- 2447 2437.96 609.78 1. 01 3.65E+001 19.21 1.65E+001 8 2639 - 2656 2647.18 662.09 0.75 5.15E+001 19.58 1.35E+001 9 4474 - 4493 4483.95 1121.09 0.73 2.34E+001 1 1.46 2.56E+OOO 10 5838 - 5857 5847.64 1461. 63 0.46 7.60E+001 17.44 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted* at 2.000 sigma

[138]

Interference Corrected Activity Report 4/24/2018 1: 2 9 : 01 PM Page 3

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

Sample

Title:

B306215AFSWC013GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) ( %) (pCi/MA 2 ) Uncertainty K-40 0.999 1460.82* 10.66 l.06663E+006 2 .61644E+005 Cs-137 1. 000 661.66* 8 5 .10 6.06650E+004 2 .41959E+004 Tl-208 1.000 583.19* 85.00 2.37579E + 004 1 .81555E+004 Pb-212 1.000 238.63* 4 3.6 0 2.80030E+004 4.38072E+004 Bi-214 0.735 609.32* 45.49 7.70433E+004 4.16145E+004 1120.29* 14.92 2.04581E+005 1.01322E+005 1764.49 15.3 0 Pb- 2 14 1.000 295.22* 18.42 l .48709E+005 8.73780E+004 351.93* 35.60 9.37430E+004 5.33726E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2 .000 s i gma

[139]

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          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 1.066628E+006 2.616437E+005 /

Cs- 137 1 . 000 6.066502E+004 \1"'2 . 419590E+004 Tl-208 1. 000 2 . 375788E+004 l.815553E+004 Pb-212 1. 000 2 .800296E+004 4.380724E+004 Bi-214 0 . 735 9.545179E+004 3 . 849429E+004 Pb-214 1 . 000 1.086787E+005 4.554767E+004

? = Nucl ide is part of an undetermined solution X = Nuclide rejected by the interference analysis

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 s igma

[140]

Interference Corrected Activity Report 4/24 /2 018 1: 2 9:01 PM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/24/20 1 8 1: 2 9:01 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.09 5.5500E - 002 82.49 2 74.55 1. 5125E - 0 01 80.04 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[141]

Nuclide MDA Report 4 /24/ 2 018 1: 29 : 01 PM Page 6

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

Detector Name: 6 2 79 Sample Geometry: 3M90D CP 2IN Sample Title : B306215AFSWC013GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 3.798E+004 3.80E+004 /1.067E+00 6 O.OOOE+OOO Co-6 0 1173.23 99 . 85 3.981E+004 3.55E+004N' 1 . 634E+004 fi..810E+004 1332.49 99.98 3.554E+004 1.766E+004/1.585E+004 Nb- 94 702.65 99.81 3.091E+004 3.09E+004 -5 .866E+003 1 . 406E+004 871.09 99.89 3.567E+004 - 2 .894E+004 1. 62 8E+004 Ag-108 rn 433.90 90.50 4.294E+004 4.00E+004 2 .436E+004 2 .027E+004 614.30 89.80 5.213E+004 6.991E+004 2.461E+004 722.90 90.80 3.997E+004 l.804E+004 J.842E+004 Cs - 134 604.72 97.62 4.567E+004 3.79E+oo4 *v "5.290E+oo4 *v "2 .1s1E+oo4 795.86 85.46 3.786E+004 -i . 093E+004 1.719E+004

+ Cs - 137 661.66* 85.10 2.901E+004 2 .90E+004 ./'6 . 067E+004 1. 29 1E+004 Eu- 1 52 121. 78 28.67 2.084E+005 1.31E+005 -2 .145E+00 5 1.019E+005 344.28 26.60 l.704E+005 - 1.399E+00 5 8.164E+004 1408. 01 21. 07 l. 3 05E+005 8.322E+00 4 5.589E+004 Eu-154 123. 0 7 40.40 1.486E+005 1.09E+00 5 3.428E+003 7.267E+004 723.30 20 . 06 1. 792E+005 1 . 887E+004 8.251E+004 1274.43 34.80 1.091E+005 1.117E+005 4.913E+004 Eu-155 86.55 30.70 2.572E+005 2.57E+005 - 7.615E+004 1.262E+005 105 . 31 21.10 3 . 088E+005 8 . 264E+004 1.512E+005 Tl-208 583.19* oi:: nn 2.719E+004 2.72E+004 2. 3 76E+004 1 . 210E+004

+ u-i.vv Bi-212 727.33 6.67 5.457E+005 5.46E+005 4.140E+005 2.515E+005

+ Pb-212 238.63* 43.60 7.241E+004 7.24E+004 2.800E+004 3 .440E+004

+ Bi-2 14 609.32* 45 . 49 5.761E+004 5.76E+004 7.704E+004 2 .594E+004 1120.29* 14.92 1. 1 15E+005 2.046E+005 4.396E+004 1764.49 15.30 2.282E+005 1 . 486E+004 9.920E+004

+ Pb-214 295.22* 18.42 1. 2 56E+005 7.71E+004 1.487E+00 5 5.804E+004 351.93* 35.60 7 . 715E+004 9. 374E+004 3 . 587E+004 Ra-226 186.21 3 .64 1 . 32 9E+006 1.33E+006 1.378E+00 6 6.452E+005 Ac-228 338.32 11. 2 7 3. 422E+005 1.43E+005 -2 .567E+00 5 1.627E+00 5 911. 20 25 .80 1.429E+005 - 1. 593E+004 6 . 529E+004 968.97 15.80 2 .625E+005 1.896E+005 1.209E+005 Am-241 59.54 35.90 2 .566E+005 2 .57E+005 1 .907E+005 l.253E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[142]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/24/ 2 018 1 :0 5 :57 PM Sample Title B306215AFSWC014GD Sample Description East U2 Valve House Wall Sample Identification Sample Sample Type Geometry Gamma Direct 3M90D CP 2IN v Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 M"2 v Sample Taken On Acquisition Started 4/24/2018 4/24/2018 12:55:00 PM 12:55:55 PM v

V Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0.08 % v Energy Calibration Used Done On 12/28/2017 v Efficiency Calibration Used Done On 2/1/2018 v Efficiency ID 3M90D CP 2IN v

[143]

Peak Analysis Report 4/24/2018 1:0 5:57 PM Page 2

          • P E A K ANALYSIS R E P O R T *****

Detector Name: 6279 Sample

Title:

B306215AFSWC014GD Peak Analysis Performed on: 4/24/2018 1: 0 5:56 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 292 - 348 300.76 75.16 1.13 - 2 . 2 9E+001 180.38 9.99E+00 2 2 946 - 963 954.40 238.72 0.63 1. 2 8E+001 35. 03 9.02E+001 3 1174 - 11 91 1182.25 295.73 1. 04 4.46E+001 22.28 2.44E+001 4 1399 - 1416 1407.38 352.05 1. 08 3 .41E+001 21.51 2.49E+001 5 2325 - 2342 2333 .0 7 583.55 0.31 1.13E+001 18.28 2.17E+001 6 2429 - 2446 2437.64 609.7 0 1. 55 3.78E+001 1 6.60 9.23 E+OOO 7 2640 - 2657 2648.14 662.33 0.73 1.40E+001 14.11 1.lO E+OOl 8 3637 - 3654 3645.81 911. 69 0.88 1.92E+001 12.89 6.78E+OOO 9 44 73- 4492 4482.94 1120.84 0.33 1.26E+001 9.21 2 .40E+OOO 10 5839- 5858 5848.29 1461. 79 1. 58 8.04E+001 18.98 2.64E+OOO 11 7056- 7075 7065.10 1765.46 0. 3 1 1.80E+001 8.49 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[144]

Interference Corrected Activity Report 4/24/2018 1:05:57 PM Page 3

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

Sample

Title:

B306215AFSWC014GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) ( %) (pCi/MA 2 ) Uncertainty K-40 0.999 1460.82* 10.66 l.12788E+006 2.83842E+005 Cs- 137 0.999 661.66* 85.10 1 .64902E+004 1.67525E+004 Tl-208 1.000 58 3 .19* 85.00 1. 254 01E+004 2 .02501E+004 Pb- 2 12 1. 000 238.63* 43.60 1 .70742E+004 4.66594E+004 Bi - 2 14 0.999 609.32* 45.49 7. 9 7719E+004 3.635 0 0E+004 112 0 .29* 14.92 1.09947E+005 8.08060E+004 1764.49* 15.30 1.98251E+005 9.47959E+004 Pb- 2 14 1 .000 2 95.22* 18.42 1.56549E+ 005 8.21468E+004 351.93* 35.60 6.82631E + 004 4.4 23 68E+004

  • =Energy l ine found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2 .000 sigma

[145]

Interference Corrected Activity Report 4/24/2018 1:05:57 PM Page 4

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

Nuclide Wt mean Wt mean Nuc lide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 Cs-137 0.999 0.999

l. 12 7875E+006 .2 . 838419E+005 l.649018E+004 Vl . 675249E+004 ./

Tl-208 1. 000 l . 2 54006E+004 2 .025010E+004 Pb-212 1. 000 l.707425E+004 4 . 665937E+004 Bi-214 0.999 9 .720729E+004 3.129211E+004 Pb-214 1. 000 8.810988E+004 3.894842E+004

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

@ = Nuclide contains energy lines not used i n Weighted Mean Activity Errors quoted at 2. 000 sigma

[146]

Interference Corrected Act i vity Report 4/24/2018 1:05:57 PM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/24/2018 1:05:56 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts pe r Second  % Uncertainty Type Nuclide 1 75.16 -3.8088E-002 - 789. 32 8 911.69 3.2035E-002 67.06 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[147]

Nuclide MDA Report 4/24/ 2 018 1:05:57 PM Page 6

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2 IN Sample

Title:

B306215AFSWC014GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 1 .819E+005 1. 82 E+005 1.128E+00 6 7.195E+004 Co-60 1173.23 99.8 5 4.188E+004 3.03E+004v.:'.°2.081E+004 1.913E+004 1332.49 99.98 3.028E+004 8.457E+003v"'°l.322E+004 Nb-94 702.65 99.81 3.983E+004 3.98E+004 -3.640E+003 1.852E+004 871. 09 99.89 3.980E+004 -3.044E+004 1. 834E+004 Ag-108m 433.90 90.50 4.079E+004 4.08E+004 4.203E+004 1. 92 0E+004 614.30 89.80 5.111E+004 3 .464E+004 2 .410E+004 722.90 90 . 80 4.112E+004 - 1.825E+003 1.900E+004 Cs-134 6 0 4.72 97.62 4.825E+004 3 . 68E+0 04v' 7. 548E+004 \1"2. 280E+004 795.86 85.46 3 .680E+004 ,/"1.351E+004 1.666E+004

+ Cs-137 661.66* 85.10 2 .639E+004 2 . 64E+004* 1. 649E+004 1 .160E+004 Eu -1 52 12 1 .78 2 8 . 67 2 .054E+005 1.5 9 E+005 - 5.811E+004 1.004E+005 344.28 26.60 1.604E+005 4.028E+004 7 . 661E+004 1408.01 2 1 .07 1.594E+005 - 2.254E+004 7.033E+004 Eu - 154 123.07 40.40 1.462E+005 9.38E+004 -4.597E+004 7.145E+004 723.30 2 0.06 1 .827E+005 - 1 .323E+005 8.428E+004 1274.43 34.80 9.384E+004 3.512E+004 4.152E+004 Eu-155 86.55 30.70 2 . 637E+005 2.64E+005 1.452E+005 1. 29 5E+005 105.31 21.10 3 . 112E+005 1.976E+005 1.524E+005

+ Tl-208 583.19* 85.00 3.387E+004 3.39E+004 1.254E+004 1.544E+004 Bi-212 727.33 6.67 5.563E+005 5.56E+005 6.038E+005 2.568E+005

+ Pb-212 23 8.63* 43.60 7.860E+004 7.86E+004 1 .707E+004 3.750E+004

+ Bi -2 14 609.32* 45.49 4.448E+004 2.98E+004 7 .9 77E+004 1.938E+004 1120.29* 14.92 1.077E+005 1.099E+005 4.206E+004 1764.49* 15.30 2.980E+004 1.983E+005 O.OOOE+OOO

+ Pb-214 295.22* 18.42 1.125E+005 6.49E+004 1.565E+005 5.151E+004 351.93* 35.60 6.487E+004 6.826E+004 2 .973E+004 Ra- 22 6 186.21 3 .64 1.293E+006 1. 2 9E+006 5.179E+004 6.272E+005 Ac- 22 8 338.32 11. 27 3.631E+005 l .78E+005 - 1 . 310E+005 1. 732E+005 911.20 25.80 1 .778E+005 5.758E+004 8.272E+004 968.97 1 5.80 2.286E+005 -6.873E+003 1.039E+005 Am- 2 41 59.54 35.90 2.698E+005 2.70E+00 5 1. 95 0E+005 1. 3 19E+005

+=Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[148]

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

Filename: 6279 Report Generated On 4/24/2018 9:53:26 AM Sample Title B306215AFSWC015GD Sample Description East U2 Valve House Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels ) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 4/24/2018 9:43:00 AM Acquisition Started 4/24/2018 9:43:24 AM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0. 08 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2 IN

>>~ *A-- V /rC-1 D~]J y/z s/ ;r I 0P-z5

. ~

[149]

Peak .Analysis Report 4/24/ 2 018 9 :5 3 :26 AM Page 2

          • PE AK ANALYS I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306215AFSWC015GD Peak Analysis Performed on: 4/24/2018 9:53:26 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 2 93- 350 300.98 75.21 0.87 - 5.98E+001 182.64 l.02E+003 2 737- 752 744.14 186.11 1. 03 3.21E+001 26.61 4.69E+001 3 945- 962 953.21 238.43 0.72 4.60E+001 27.86 4.30E+001 4 1173- 1190 1181.46 295.53 1.19 2.17E+001 22 . 22 3.13E+001 5 1402 - 1419 1410.07 352.72 0.51 4.52E+001 20.12 l.68E+001 6 2325 - 2342 2333.90 583.76 0.35 2.96E+001 13.30 4.37E+OOO 7 2430 - 2447 2438.38 6 0 9.89 0.40 2.85E+001 2 0 .18 2 .25E+00 1 8 5840- 5859 5849.44 1462.07 0.90 5.12E +001 1 6.49 4.78E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 0 00 s igma

[150]

Interference Corrected Activity Report 4/24/2018 9:53 : 26 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306 21 5AFSWC015GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. . . . . . . . . - . .. . . .. . ... IDENTIFIED NUCLIDES . . . . . .......... - ... .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.997 1460.82* 10.66 7.19035E+005 2.39687E+005 Tl - 208 0.999 583 . 19* 85. 0 0 3.27498E+004 1.52196E+004 Pb-212 1.0 00 238.63* 43.60 6.11352E+004 3.83257E+004 Bi-214 0.442 609.32* 45.49 6.02092E+004 4.32434E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.999 295.22* 18.4 2 7.63238E+004 7.89471E+004 351.93* 35.60 9.05728E+004 4.25265E+004 Ra-226 1 .000 186.21* 3.64 4.57160E+005 3.86677E+005

  • =Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0. 3 0 Errors quoted at 2 .000 sigma N

[151]

Interference Corrected Activity Report 4/24/2018 9:53:26 AM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M2 ) Uncertainty K-40 0.997 7.190346E+005 2.396865E+005 Tl-208 0.999 3.274977E+004 l.521965E+004 Pb-212 1.000 6.1 1 3518E+004 3.832572E+004 Bi-214 0.442 6.0209 1 9E+004 4.324 3 40E+004 Pb-214 0.999 8.736807E+004 3.744011E+004 Ra-226 1. 000 4.571601E+005 3.86 6 775E+005

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/24/2018 9:53:26 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75. 21 -9.9663E-002 -3 0 5.43 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[152]

Nucl ide MDA Report 4/24/2018 9:53:26 AM Page 5

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

Detector Name: 62 79 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC015GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 2 . 2 68E+005 2.27E+005 7.190E+OO S 9.442E+004 Co-60 1173.23 99.85 4.034E+004 3.75E+004~1 . 782E+004 1.836E+004 1332.49 99.98 3 .755E+004 3.693E+004 .Jl .685E+004 Nb- 94 7 0 2.65 99.8 1 3.757E+004 3.70E+004 2 . 163E+004 1.738E+004 8 71. 09 99.89 3.696E+004 - l . 725E+003 1 .692E+004 Ag-10 8m 433 . 90 90.50 3.559E+004 3.56E+004 -2 . 476E+004 1.660E+004 614.30 89.80 5.436E+004 6.159E+004 2.573E+004 722.90 90.80 3.753E+004 -p.775E+002 /l.720E+004 Cs-134 604 . 72 97.62 4.82SE+004 4.13E+004\/5.037E+004 V 2.280E+004 795.86 85.46 4.133E+004 .,/5 . 531E+004 1.893E+004 Cs-137 661.66 85.10 4.529E+004 4 . 53E+004 -2 . 3 66E+003 2 . 10 5E+004 Eu-152 121. 78 28.67 1.939E+005 1.59E+005 -2 .516E+00 5 9.465E+004 344.28 26.60 1.667E+OOS l.193E+OO S 7.976E+004 1408.01 21. 07 1 .594E+005 6.762E+004 7.033E+004 Eu-1 54 123.07 40.40 1. 379E+005 1.07E+005 1.447E+005 6 . 729E+004 723.30 2 0.06 1 .661E+005 - l .749E+OOS 7.597E+004 1274.43 34.80 1. 073E+OOS 6 . 781E+004 4.824E+004 Eu- 155 86.55 30.70 2 .549E+OOS 2 .55E+OO S 6.417E+003 1 .251E+005 105.3 1 21.10 2 . 975E+005 - 2 . 950E+OOS l . 455E+005

+ Tl-208 583.19* 85.00 1 . 689E+004 1 . 69E+004 3 . 275E+004 6 . 948E+003 Bi-212 727 . 33 6.67 S.563E+005 5.56E+OOS 1 . 010E+005 2 . 568E+OOS

+ Pb-212 238.63* 43.60 5.680E+004 S.68E+004 6.114E+004 2 .660E+004

+ Bi-214 609 . 32* 45.49 6.523E+004 6.52E+004 6.021E+004 2.976E+004 1120.29 14 .92 2.70SE+OOS 4.097E+004 1.234E+005 1764.49 15.30 2.073E+005 -6.652E+003 8.873E+004

+ Pb-214 295.22* 18.42 1.260E+005 5.48E+004 7.632E+004 5.823E+004 351.93* 35.60 5.475E+004 9.057E+004 2.467E+004

+ Ra- 22 6 186.21* 3.64 6.019E+005 6.02E+005 4.572E+005 2.817E+005 Ac-228 338.3 2 11.27 3 . 607E+005 1.59E+OOS 4.572E+004 l .720E+OOS 911.20 25.80 l.591E+005 1.241E+005 7.338E+004 968.97 15.80 2.286E+005 l . 915E+004 1.039E+005 Am-241 59 . 54 35.90 2.787E+OOS 2 .79E+OOS 6.796E+004 1.363E+OO S

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[153]

          • GAMMA S P E C T R U M A N A L Y S I S *****

Filename: 6279 Report Generated On 4/24/2018 10: 1 1:12 AM Sample Title B306215AFSWC016GD Sample Description East U2 Valve House Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN V Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA 2 V Sample Taken On 4/24/2018 10:01:00 AM Acquisition Started 4/24/2018 10:01:11 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

'-:J)c:+s Lfev f, c,{c.~ /

'!/z-- F/, ~ ocf5 Y

'I..

[154]

Peak Analysis Report 4/24/2018 10:11:12 AM Page 2

          • P E A K ANALYSIS R E P O R T *****

Detector Name: 6279 Sample

Title:

B3062l5AFSWC016GD Peak Analysis Performed on: 4/24/2 018 10:11:12 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 292 - 309 299.39 74 . 82 0.85 1.70E+002 60.03 2 . 23 E+002 2 946 - 963 954.62 238.78 0.36 2 .82E+001 31.04 6.28E+001 3 1400 - 1417 1408.22 352.26 0.86 5.25E + 001 19 . 64 1.35E+001 4 2038 - 2055 2046.83 511.98 0.54 3. 2 7E+001 16.67 1.13E+001 5 243 1 - 2448 2439.53 610.17 0.83 4.llE+OOl 16.03 6.93E+OOO 6 5842- 5861 5851.77 1462.66 0.5 0 7.00E+OOl 16.73 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2.000 sigma

[155]

Interference Corrected Activity Report 4/ 2 4 /2 018 10:11:12 AM Page 3

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

Sample

Title:

B306215AFSWC016GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) (%) (pCi/M" 2 ) Uncertainty K-40 0.995 1460.82* 10.66 9.82856E+005 2 .49969E+005 Pb- 212 1.000 23 8.63* 43.60 3.75015E+004 4.17260E+004 Bi- 2 14 0.441 609.32* 45.49 8.67920E+004 3.54369E+004 1120.29 14.92 1 764.49 15.30 Pb- 2 14 0.437 295. 22 18.42 351. 93

  • 35.60 l .05101E+005 4.23444E+004
  • =Energy line found in the spectrum.

@ = Energy line not used f or Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2.000 sigma

[156]

Interference Corrected Activity Report 4/24/2018 10:11:12 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0. 9 95 9.828560E+00 5 2.499690E+005 Pb-212 1.000 3.750148E+004 4.172600E+004 Bi-214 0.441 8.679204E+004 3.543694E+004 Pb-214 0.437 1.051010E+005 4.234438E+004

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

@=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/24/ 2 018 10:11:12 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS. Peak Tol.

No. (keV) Counts per Second  % *uncertainty Type Nucl ide 1 74.82 2 .8376E-001 35. 2 6 4 5 11. 98 5.4574E-002 50 . 91 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[157]

Nuclide MDA Report 4/24/ 2 018 10:11:12 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC016GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuc li de MDA Activity Dec . Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10 .66 3.799E+004 3.80E+004 j.829E+00 5 O.OOOE+OOO Co-60 1173.23 99.85 3.704E+004 2.67E+004 V9.673E+003 1.671E+004 1332.49 99.98 2.674E+004 1.705E+004 ../1.145E+004 Nb-94 702.65 99.81 3.252E+004 3.09E+004 1.787E+004 1.486E+004 871. 09 99.89 3. 0 92E+004 6.688E+003 1 .390E+004 Ag-1 08m 433.90 90.50 3. 659E+004 3.66E+004 -2 .789E+004 1.710E+004 614.30 89.80 4.899E+004 2 .734E+004 2.304E+004 722.90 90.80 3 .997E+004 .,.J.032E+004 1 .842E+004 Cs-134 604.72 97.6 2 4.470E+004 4.36E+004'\f-4.122E+002 2.102E+004 795.86 85.46 4.363E+004 ~. 770E+004 -./2. 007E+004 Cs-137 661. 66 85.10 3.955E+004 3.95E+004/-5.185E+004 1.818E+004 Eu-152 12 1. 78 28.67 1 .953E+005 1.56E+005 1.484E+00 5 9.532E+004 344.28 26.60 1.662E+00 5 -4.061E+004 7.952E+004 1408.01 21.07 1.557E+005 -9 .122E+00 4 6.845E+004 Eu-154 123.07 40.40 1.379E+005 9.98E+004 1.685E+005 6.729E+004 723.30 2 0.06 1. 810E+005 1.884E+005 8.340E+004 1274.43 34.80 9.985E+004 4.988E+00 3 4.453E+004 Eu-155 86.55 30.70 2 .498E+005 2 .50E+005 1.858E+005 1.225E+005 105.31 21.10 2.778E+005 -8.017E+004 1 .357E+005 Tl-208 583 . 1 9 85.00 4 . 213E+004 4.21E+004 - 3.304E+003 l . 957E+004 Bi-212 727.33 6.67 5.125E+005 5.12E+005 -8.093E+005 2.349E+005

+ Pb- 2 12 238.63* 43.60 6.741E+004 6.74E+004 3.750E+004 3.191E+004

+ Bi-214 609.32* 45.49 3.916E+004 3.92E+004 8.679E+004 1.672E+004 1120.29 14.92 2 .496E+005 8.070E+004 1.130E+005 1764.49 15.30 2 .347E+005 1.762E+005 1.025E+005

+ Pb-214 295.22 18.42 2 .114E+005 4.91E+004 1 . 302E+005 1 .009E+005 351.93* 3 5.60 4.907E+004 1 . 051E+005 2.183E+004 Ra- 22 6 186.21 3.64 1.176E+006 1.18E+006 5.620E+005 5.685E+005 Ac-22 8 338.32 11. 2 7 3 .485E+005 1.53E+005 - 1.879E+005 1.659E+005 911.20 25.80 1.528E+005 1.472E+005 7.0 2 5E+004 968.97 15.80 2.376E+005 1.436E+005 l.084E+005 Am-241 59.54 35.90 2.583E+005 2.5 8E+005 2.267E+005 1. 2 61E+005

+ = Nuclide identified during the nuclide identification

  • =Energy line found in the spectrum

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

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

[158]

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

Filename: 6279 Report Generated On 4/24/2018 9:24:10 AM Sample Title B306215AFSWC017GD Sample Description East U2 Valve House Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 4/24/2018 9:14:00 AM v Acquisition Started 4/24/2018 9:14:09 AM v Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 % V Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

[159]

Peak Analysis Report 4/24/2018 9:2 4:10 AM Page 2

          • PE AK A N A L Y S I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306215AFSWC017GD Peak Analysis Performed on: 4/24/2018 9:24:10 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 286- 346 300.27 75.04 0.63 1.65E+OOO 186.38 9.78E+002 2 946 - 963 954.11 2 38.65 0.50 3 . l OE+OOl 33.75 7.70E+001 3 1173 - 1190 1181.90 295.64 0.33 1.08E+00 1 25.63 4 .72E+001 4 1399 - 1416 1407.68 352.12 0.42 4. 9 8E+001 22.07 2 .22E+001 5 2324 - 234 1 2332.89 583.51 1. 09 2 .89E+001 15.98 1.0lE+OOl 6 2429 - 2446 2437.63 609.70 0.67 4.30E+ 001 20.16 1.80E+001 7 3639 - 3656 3647.08 912.01 0. 32 2 .09E +001 13.43 7.05E+OOO 8 5838 - 5857 5847 . 10 1 461.49 1. 59 9.13E +001 20.13 2 .69E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[160]

Interference Corrected Activity Report 4/24/ 2 018 9 :24: 10 AM Page 3

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

Sample

Title:

B306215AFSWC017GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. . ..... .. . . .. .. ... . . IDENTIFIED NUCLIDES . .. .. ... . ... . ... ... .

Nuclide Id Energy Yield Activity Activity Name Confidence {keV) {%) {pCi/MA2 ) Uncertainty K-40 0.999 1460.82* 10 .66 1 . 2 8140E+006 3.03655E+005 Tl- 2 08 1. 000 583.19* 85.00 3.19020E+004 1.80684E+004 Pb-212 1.000 238.63* 43.60 4.11801E+004 4.53655E+004 Bi-214 0.442 6 0 9.32* 45 . 49 9.08274E+004 4.39652E+004 112 0 .29 14.92 1764.49 15.30 Pb-214 1.000 295.22* 18.42 3.78899E+004 9.01891E+004 351.93* 35.60 9.97270E+004 4.66266E+004

  • = Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

[161]

Interference Corrected Activity Report 4/24/2 01 8 9:24: 10 AM Page 4

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

Nucl ide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0. 999 1.281401E+006 3.036549E+005 Tl-208 1.000 3 .190200E+004 1.806842E+004 Pb-212 1. 000 4.118009E+004 4.536546E+004 Bi -2 14 0.44 2 9.082735E+004 4.396522E+004 Pb-214 1. 000 8.668523E+004 4.141890E+004

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

@ Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D P E A K S ** ********

Peak Locate Performed on: 4/24/20 1 8 9:24 :10 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts pe r Second  % Uncertainty Type Nuclide 1 75. 04 2 .7466E-003 11309.7 7 9 12.01 3.4911E-002 64. 11 Sum M = First peak in a mult iplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[162]

Nuclide MDA Report 4/24/2018 9:24:11 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2 IN Sample

Title:

B306215AFSWC017GD Nuclide Library Used: C:\GENIE2K\CAMFILES \ Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 1.841E+005 1. 84E+005.../1.281E+00 6 7.308E+004 Co-60 1173.23 99.85 4 . 336E+004 3.48E+004/-2 . 758E+003 1.987E+004 1332.49 99.98 3.484E+004 6. :wl3,.. v V -l.409E+004 1.550E+004 Nb- 94 702.65 99.81 4.167E+004 3.74E+004 2 .670E+004 1.943E+004 871.09 99.89 3 .738E+004 1.181E+004 1.713E+004 Ag-108m 433.9 0 90.50 4.397E+004 4.37E+004 - 4.086E+00 3 2.079E+004 614.30 89.80 5.580E+004 5.505E+004 2.645E+004 722.90 90.80 4. 3 70E+004 _/-1.721E+004 2.029E+004 Cs - 1 3 4 604.72 97.62 4.960E+004 4.41E+004 -1.061E+004 J..348E+004 795.86 85.46 4.407E+004 Jl. 677E+004 y2.030E+004 Cs - 137 661. 66 85.10 5. 12 9E+004 5 .13E+O 04 V 7. 943E+004 V2. 405E+004 Eu-152 121. 78 28 . 67 2 .081E+OOS 1.59E+005 -2.390E+00 5 1.017E+005 344.28 26.60 1.623E+OOS -2.634E+004 7.759E+004 1408.01 21. 07 1.594E+005 l.318E+005 7.033E+004 Eu-154 123.07 40.40 1.475E+005 8.03E+004 4.362E+Q04 7.212E+004 723.30 20.06 1.978E+005 -8.624E+004 9.185E+004 1274.4 3 34.80 8.028E+004 -3 . 093E+004 3.474E+004 Eu-155 86.55 30.70 2.526E+OOS 2.53E+005 3 .734E+003 1.239E+005 105.3 1 21.10 3.012E+005 l .978E+005 1.474E+005

+ Tl-208 583.19* 85.00 2.449E+004 2.45E+004 3. 1 90E+004 1. 075E+004 Bi-212 727.33 6.67 6.063E+OOS 6.06E+005 - 2.160E+005 2 .818E+005

+ Pb-212 238.63* 43.60 7.329E+004 7.33E+004 4.118E+004 3 .484E+004

+ Bi -2 14 609.32* 45.49 5.893E+004 5.89E+004 9.083E+004 2.661E+004 1120.29 14.92 2.496E+005 8.070E+004 1.130E+005 1764.49 15.30 2 .410E+005 5.473E+004 1.056E+005

+ Pb- 2 14 295.22* 18.42 1.526E+005 6.13E+004 3.789E+004 7.154E+004 351.93* 35.60 6.127E+004 9.973E+004 2.793E+004 Ra - 226 186.21 3.64 1.344E+006 1.34E+006 - 1. 053E+004 6.528E+005 Ac-228 338.32 11. 2 7 3.239E+005 1.72E+005 -4.084E+005 1 .536E+005 911. 2 0 25.80 1.722E+005 1.650E+005 7.996E+004 968.97 15.80 2 .991E+005 1.395E+005 1.392E+005 Am-24 1 59.54 35.90 2 .705E+005 2. 70E+005 1. 2 63E+005 1.322E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[163]

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

Filename: 6279 Report Generated On 4/23/2018 2:37:37 PM V""

Sample Title B306215AFSWC018GD ~

Sample Description East U2 Valve House Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 v Sample Taken On 4/23/2018 2:27:00 PM v Acquisition Started 4/23/2018 2:27:36 PM V Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

[164]

Peak Analysis Report 4/23/2018 2: 37: 37 PM Page 2

          • PE AK A N A L Y S I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306215AFSWC018GD Peak Analysis Performed on: 4/23/2018 2:37:36 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 122- 137 129.25 32.23 0.25 l .39E+001 24.73 4.61E+001 2 292- 346 299.95 74.96 0.84 4.04E+001 163.71 8.47E+002 3 945- 962 953.71 238.55 0.29 2.70E+001 29.89 6.00E+OOl 4 1172 - 1189 1 180.19 295.21 0.38 2.06E+001 25.14 4.14E+001 5 1399 - 1416 1407.02 35 1. 96 1 .03 5.55E +001 23.26 2.45E+001 6 2428- 2446 2436.72 609.47 0.70 5.48E+001 19.21 l.12E+001 7 5835- 5854 5844.59 1460.86 0.56 7.40E+001 19.13 5.00E+OOO 8 7051- 7070 7060 . 66 1764.36 0.50 l.80E+001 8.49 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[165]

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Sample

Title:

B3062 1 5AFSWC018GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 146 0 .82* 10.66 1.03822E+006 2.83179E+005 Pb-212 1.000 238.63* 43.60 3 .59370E+004 4.01568E+004 Bi-214 0.706 609.32* 45.49 1.15744E+005 4.28838E+004 1120.29 14.92 1764.49* 15.30 1.98173E+005 9.47585E+004 Pb-214 1.000 295.22* 18.42 7.22811E +004 8.89457E+004 351.93* 35.60 1.10 960E +005 4.94250E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2.000 sigma

[166]

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1.038217E+006 2.831793E+005 Pb-212 1. 000 3.593696E+004 4. 01 5680E+004 Bi-214 0.706 1.297563E+005 3.906915E+004 Pb-214 1.000 1.018346E+005 4.320302E+004

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

@ = Nuc l ide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 . 000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/23/2018 2 : 37: 36 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.23 2.3139E-002 178.11 2 74 . 96 6.7270£ - 002 405.60 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[167]

Nucli d e MDA Report 4 /23 / 2 018 2 : 3 7: 3 7 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC018GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 2 . 3 12E+OOS 2. 31E+005 /l.0 3 8E+00 6 9.662E+004 Co-60 1173. 23 99.85 3.873E+004 3.87E+004v'-1.722E+004 /1.756E+004 1332.49 99.98 3.944E+004 2 .033E+003v 1.780E+004 Nb-94 702.65 99 . 81 3.585E+004 3.59E+004 2 .863E+004 l.653E+004 871. 09 99.89 3.821E+004 1.632E+004 1.755E+004 Ag-108m 433.90 90.50 4.231E+004 4.04E+004 - 5.384E+003 1.996E+004 614.30 89.80 5 .264E+004 4.166E+004 2 .486E+004 722.90 90.80 4 . 036E+004 ~ . 9 69E+004 ;L . 862E+004 Cs-134 604.72 97.6 2 5.134E+004 3.99E+004 8.049E+004~2 . 435E+004 795 . 86 85.46 3.989E+004 -4.509E+004 )- .820E+004 Cs-137 661.66 85.10 4.565E+004 4.56E+004~9.621E+003 vf 2 .123E+004 Eu-152 121. 78 28.67 2 .079E+005 1 .44E+005 - 3.598E+004 1.016E+005 344 . 28 26.60 1 .799E+005 - 2.567E+004 8.637E+004 1408.01 21.07 1. 437E+005 -2.248E+005 6.249E+004 Eu-154 123.07 40.40 1 .470E+005 l . 02E+005 1.792E+005 7.184E+004 723.30 20.06 1.827E+005 3.655E+004 8.428E+004 1274.43 34.80 1 .018E+005 5.138E+004 4. 54 8E+004 Eu - 155 86 . 55 30.70 2.544E+005 2.54E+005 1.642E+004 1. 248E+005 105 . 3 1 21.10 2.999E+005 -2 .969E+005 l.468E+ 0 05 Tl - 2 08 583 .1 9 85 . 00 4 . 953E+004 4.95E+004 2 . 347E+004 2 .327E+004 Bi-212 727.33 6.67 5.067E+005 5.07E+005 l.406E+005 2 .320E+005

+ Pb- 2 12 238.63* 43.60 6.488E+004 6.49E+004 3.594E+004 3 . 064E+004

+ Bi- 2 14 6 0 9.32* 45.49 4 . 822E+004 2.98E+004 1.157E+005 2 .125E+004 1120.29 14.92 3.135E+005 2.552E+005 1.449E+005 1764 . 49* 15.30 2.979E+004 l.982E+005 O.OOOE+OOO

+ Pb- 2 14 295. 22

  • 18.42 l.448E+005 6.42E+004 7.228E+004 6.764E+004 351.93* 35.60 6.424E+004 1.llOE+OOS 2.941E+004 Ra-226 186.21 3.64 1. 315E+006 l. 32 E+006 -2.812E+005 6.384E+005 Ac-228 338.32 11 .27 3.690E+005 1.64E+005 2.183E+005 1.762E+005 911. 2 0 25.80 1.636E+005 -5 . 088E+003 7.564E+004 968 . 97 15. 80 2 .677E+005 4. 2 14E+004 l. 2 35E+005 Am-241 59.54 35.90 2 .564E+005 2.56E+005 4.070E+004 1 . 2 52E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[168]

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

Filename: 6279 Report Generated On 4/24/2018 8:38:51 AM Sample Title B306215AFSWC019GD v

Sample Description East U2 Valve House Wall V Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 4/24/2018 8:28:00 AM Acquisition Started 4/24/2018 8: 2 8:50 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

v Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

[169]

Peak Analysis Report 4/24/2 018 8:38:51 AM Page 2

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

Detector Name: 6279 Sample

Title:

B306215AFSWC019GD Peak Analysis Performed on: 4/24/2018 8:38:51 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start e nd centroid (keV) (keV) Area Uncert. Counts 1 291- 3 10 3 00.11 74.99 1. 03 1.99E+002 69.52 2.87E+002 2 945- 962 953.4 0 238.47 0.56 7.76E+OOO 2 8.68 5.92E+001 3 1171 - 11 88 1179.49 295.04 0.87 1.75E+001 25.03 4.25E+001 4 1398- 1417 1406.97 351.94 0.34 4.67E+001 25.04 3.13E+001 5 2034 - 2 0 51 2 042.23 510.83 0.33 2.85E +001 16.73 1.25E+001 6 2323 - 2 340 2331.73 583.22 1.17 2.58E+001 15.78 1. 12E+001 7 2428- 2445 2436 . 25 609.35 0.59 4.40E+001 17.1 2 9.00E+OOO 8 5834- 5853 5843.56 14 60.6 1 0.79 5.44E+001 16 . 01 2.64E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[170]

Interference Corrected Activity Report 4/24/ 2 018 8:38:51 AM Page 3

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Sample

Title:

B306215AFSWC019GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nucl ide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertainty K-40 1.000 1460.82* 10.66 7.62641E+005 2.34158E+005 Tl-208 1.000 583.19* 85.00 2.85049E+004 1. 77640E+004 Pb-212 1.000 238.63* 43.60 1.03152E+004 3.81593E+004 Bi -2 14 0.442 609.32* 45.49 9.29124E+004 3.78448E+004 1120.29 14.9 2 1764.49 15.30 Pb-214 1.000 295.22* 18.42 6.15170E+004 8.83240E+004 351.93* 35.60 9.33828E+004 5.20123E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold 0. 3 0 Errors quoted at 2 .000 sigma

[171]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 7.626408E+005 2 .341579E+005 Tl-208 1.000 2.850494E+004 1.77 639 9E+004 Pb-212 1. 000 1.031523E+004 3.81 593 0E+004 Bi-214 0. 442 9. 29 1241E+004 3.784483E+00 4 Pb- 2 14 1. 000 8.517775E+004 4.481853E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/24/2018 8: 3 8:51 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Si z*e in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 74.99 3. 3 170E-001 34.93 5 510.83 4.7500E-002 58.68 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 s igma

[172]

Nuclide MDA Report 4/24/2018 8:38:51 AM Page 5

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

Detector Name: 62 79 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC019GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pC i /MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 l .818E+005 1.82E+005 j7.626E+00 5 7.194E+004 Co-6 0 1173.23 99.85 3.646E+004 3 . 48E+004 v'8. 339E+003./1. 642E+004 1332.49 99.98 3.484E+004 2 .034E+003 1.550E+004 Nb-94 702.65 99.81 3.367E+004 3.37E+004 -2 .171E+004 1.543E+004 871.09 99.89 3.386E+004 2 .893E+003 1. 53 7E+004 Ag-Hl8m 433.90 90.50 3.781E+004 3.58E+004 1. 2 03E+004 1.771E+004 614.30 89.80 4.926E+004 1 . 5 84E+004 2 .317E+004 722.90 90.80 3.581E+004 - 6.496E+004 1.634E+004 Cs-134 604.72 97.62 4.470E+004 4. 23 E+004 /5. 096E+004 /2 .102E+004 795.86 85.46 4.227E+004 -4.057E+004 J_. 9 39E+004 Cs-137 661.66 85.10 4.704E+004 4. 70E+004v('6. 295E+003 ~2 . 193E+004 Eu-152 12 1 .78 28.67 2 .059E+005 1.52E+005 3 .539E+004 6) '"1.006E+005 344.28 26 . 60 1 .700E+005 1.472E+005 8.141E+004 1408.01 21.07 1.518E+005 1.179E+005 6.652E+004 Eu-154 123.07 40.40 1.456E+005 8. 2 7E+004 2 .707E+004 7.116E+004 723.30 20.06 1.621E+005 - 8.063E+004 7.400E+004 1274.43 34.80 8. 2 71E+004 5.986E+004 3.596E+004 Eu-155 86.55 30.70 2 .493E+005 2.49E+005 -2 .411E+005 1.223E+005 105.31 21.10 3.030E+005 1. 1 05E+005 1.483E+005

+ Tl- 2 0 8 583.19* 85.00 2 .493E+004 2.49E+004 2.850E+004 1. 0 97E+004 Bi-212 727.33 6.67 4.950E+005 4.95E+005 2.720E+005 2.262E+005

+ Pb- 2 12 2 38.63* 43.60 6.511E+004 6.51E+004 1 .032E+004 3.076E+004

+ Bi-214 609.32* 45.49 4.332E+004 4.33E+004 9. 2 91E+004 1.880E+004 1120.29 14.92 2.835E+005 1.679E+00 5 1.300E+005 1764.49 15.30 2 .589E+005 2.202E+005 l.145E+005

+ Pb-214 295. 22

  • 18.42 1.456E+005 7.45E+004 6.152E+004 6.803E+004 351.93* 35.60 7.448E+004 9.338E+004 3.453E+004 Ra-226 186.21 3 .64 1.265E+006 1. 2 6E+006 6.170E+005 6.130E+005 Ac-228 338.32 11. 2 7 3 .371E+005 l.58E+005 - 1.946E+005 1.602E+005 911.20 25.80 1.575E+005 2.504E+004 7.261E+004 968.97 15.80 2 .346E+005 2 .825E+004 1.069E+005 Am- 24 1 59.54 35.90 2.909E+005 2 . 9 1 E+005 1.526E+004 1.424E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[173]

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

Filename: 6279 Report Generated On 4/24/2018 9:40:00 AM Sample Title B306215AFSWC020GD V

\_.../" .

Sample Description East U2 Valve House Wall Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M" 2 Sample Taken On 4/24/2018 9:29:00 AM Acquisition Started 4/24/2018 9:29:59 AM Live Time 600.0 seconds v*

Real Time 600.4 seconds V

Dead Time 0.06 %

Energy Calibration Used Done On 12/28/20 1 7 v

V Efficiency Calibration Used Done On Efficiency ID 2/1/2018 3M90D CP 2IN v

[174]

Peak Analysis Report 4/24/2 018 9:4 0 : 00 AM Page 2

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

Detector Name: 6279 Sample

Title:

B306215AFSWC020GD Peak Analysis Performed on: 4/24/2018 9:40:00 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 2 93 - 348 300.91 75.20 0.83 -5.95E+001 170.18 9.15E+00 2 2 1173- 1190 1 18 1. 70 295.59 0.49 2.82E+001 2 1. 58 2.68E+001 3 1400- 1417 1408.94 352.43 0.80 3.82E+001 2 1. 84 2.48E+001 4 2431 - 2448 2439.63 610.20 0.63 4.lOE+OOl 16.77 9.00E+OOO 5 5842 - 5862 5852.03 1462.72 1. 63 6.66E +001 17.32 2.43E+OOO 6 7061- 7080 7070 . 06 1766.70 0.34 1 .9 0E +001 8.72 O.OOE+OOO M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 s igma

[175]

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Sample

Title:

B306215AFSWC020GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M ... 2 ) Uncertainty K-40 0.994 1460.82* 10.66 9.34706E+ 005 2 .56443E+005 Bi -2 14 0.704 609.32* 45.49 8.66397E +004 3.69293E+004 1120.29 14.92 1764.49* 15.30 2.09358E+005 9.75125E+004 Pb -2 14 1.000 295.22* 18.42 9.91172E+004 7.74024E+004 351.93* 35.60 7.64204E+004 4.52057E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0.30 Errors quoted at 2.000 sigma

[176]

Interference Corrected Activity Report 4/24/2018 9:40:00 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.994 9.347064E+005 2.564427E+005 Bi-214 0.704 1.0 2 0327E+005 3.453566E+004 Pb-214 1. 000 8.2 1 9318E+004 3.903583E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

                    • U N I D E N T I F I E D PE AK S **********

Peak Locate Performed on: 4/24/2018 9:40:00 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.20 -9.9225E-002 - 2 85.85 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2.000 sigma

[177]

Nuclide MDA Report 4/24/ 2 018 9:40:00 AM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN Sample

Title:

B306215AFSWC020GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/M ... 2 ) (pCi/M ... 2 )

+ K-40 1460.82* 10.66 1 .724E+005 1.72E+005 9.347E+005 /6.721E+004 Co-60 1173. 23 99.85 3.761E+004 3. 27E+004 V4. 003E+oo4J 1. 700E+004 1332.49 99.98 3.265E+004 -3.172E+004 1.440E+004 Nb- 94 702.65 99.81 3.367E+004 3. 24 E+004 -5.181E+002 1.543E+004 8 71. 09 99.89 3.243E+004 3.451E+004 l.466E+004 Ag-108m 433.90 90.50 3.757E+004 3.63E+004 1.642E+003 1.759E+004 614.30 89.80 5.388E+004 8.684E+004 2 .548E+004 722.90 90.80 3.625E+004 7'1.468E+003 /1.656E+004 Cs- 1 34 604.72 97.6 2 4.757E+004 3.99E+004'V 3.553E+004V2.246E+004 795.86 85.46 3.989E+004 ..): . 759E+004 J: . 820E+004 Cs-137 661.66 85.10 3.996E+004 4.00E+004 2 .857E+004 V°l .839E+004 Eu-152 121. 78 28.67 1.963E+005 1.21E+005 - 7.115E+004 9.582E+004 344.28 26.60 1.599E+005 4.365E+004 7.637E+004 1408.01 21.07 1. 2 08E+005 6.935E+004 5.102E+004 Eu-154 123.07 40.40 1. 3 86E+005 8.51E+004 8.778E+004 6.764E+004 723.30 20.06 1.601E+005 - 8.443E+004 7. 2 99E+004 1274.43 34.80 8.507E+004 - 1.160E+004 3.714E+004 Eu-1 55 86.55 30.70 2.553E+005 2 .55E+005 9.811E+004 1.253E+005 105.31 21.10 3.072E+005 3.453E+005 1.504E+OOS Tl- 2 08 583.19 85.00 4.378E+004 4.38E+004 -7.877E+003 2.040E+004 Bi-212 727.33 6.67 4.890E+005 4.89E+OOS 2.557E+005 2.232E+005 Pb-212 238.63 43.60 9.618E+004 9.62E+004 6.828E+004 4.629E+004

+ Bi -2 14 609.32* 45.49 4.334E+004 2 .98E+004 8.664E+004 1.881E+004 1120.29 14.92 2 .603E+00 5 2.113E+005 1.183E+005 1764.49* 15.30 2.982E+004 2.094E+005 O.OOOE+OOO

+ Pb-214 295.22* 18.4 2 1.180E+005 6.47E+004 9.912E+004 5.423E+004 351.93* 35.60 6.475E+004 7.642E+004 2 .966E+004 Ra-226 186.21 3.64 1.200E+006 1.20E+006 9.000E+004 5.809E+005 Ac-228 338.32 11. 27 3.305E+005 l.38E+005 1.809E+005 1.569E+005 911.20 25.80 1.376E+005 1.434E+004 6.266E+004 968.97 15.80 2.127E+OOS -2 .511E+005 9.598E+004 Am- 24 1 59.54 35.90 2.911E+005 2 .91E+00 5 4.522E+005 1.425E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[178]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/23/2018 2:48:40 PM Sample Title B3062l5AFQWC018GD V Sample Description East U2 Valve House Wall QC V Sample Identification QC v Sample Type Gamma Direct Sample Geometry 3M90D CP 2IN ~

Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 4/23/2018 2:38 : 00 PM Acquisition Started 4/23/2018 2:38:39 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 % V Energy Calib"ration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

>>~ v~l,k+c4 1fa11/ff (]ODO

~?JI

[179]

Peak Analysis Report 4 / 2 3/2 018 2 :48: 40 PM Page 2

          • PE AK ANALYSIS R E P O R T *****

Detector Name: 6279 Sample

Title:

B306215AFQWC018GD Peak Analysis Performed on: 4/23/2018 2:48:40 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert . Counts 1 293 - 347 3 01. 62 75.37 0.41 -2.16E+00 2 184.1 3 1.10E+003 2 945- 963 954.34 238.71 0.95 3.33E+001 35.01 8.08E+001 3 1399 - 1416 1407 . 30 352 . 02 0 . 58 5.45E+001 19.84 1.35E+001 4 2428 - 2445 2436.79 609.49 1.15 3.73E+001 18.81 1.57E+001 5 3636- 3653 3644. 22 911.29 0.38 1. 49E+001 12.57 7.lOE+OOO 6 5833 - 5854 5844.06 1460.73 1.09 9.44E+001 21.54 5 . 61E+OOO 7 7049 - 7068 7058.94 1763 . 93 0. 42 1.30E+001 7. 2 1 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[180]

Interference Corrected Activity Report 4 /23 /2018 2 :48: 40 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306215AFQWC018GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

.................... IDENTIFIED NUCLIDES .....................

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10.66 1 .32428E+006 3.23369E+005 Pb-212 1.000 238.63* 43.60 4.42141E+004 4.70987E+004 Bi-214 0.706 609.32* 45.49 7.87076E+004 4.08377E+004 1120.29 14.92 1764.49* 15.30 1.43103E+005 8.02025E+004 Pb-214 0.437 295.22 18.42 351.93* 35.60 1.09065E+00 5 4. 2 9324E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2.000 sigma

[181]

Interference Corrected Activity Report 4/23/2018 2:48: 4 0 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 l.324282E+006 3.233692E+005 Pb-212 1.000 4.421413E+004 4.709869E+004 Bi-214 0.706 9.196576E+004 3.639168E+004 Pb-214 0.437 l.090646E+005 4.293244E+004

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

@=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2. 000 sigma

                    • UN I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/23/2018 2 :48:40 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts pe r Second  % Uncertainty Type Nuclide 1 75.37 - 3.6050E-001 - 85.13 5 911.29 2.4830E-002 84.36 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[182]

Nuclide MDA Report 4/23 /2018 2 :48:40 PM Page 5

          • NUCLIDE MD A REPORT *****

Detector Name: 6279 Sample Geometry: 3M90D CP 2IN sample

Title:

B306215AFQWC018GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460 . 82* 10. 66 2.526E+005 2 .53E+005 1.324E+006 /1 .073E+005 Co-6 0 1173.23 99.85 3.526E+004 3 .48E+004 / 3 .469E+004 V 1 .583E+004 1332.49 99.98 3.484E+004 - 6.667E+003 1.550E+004 Nb- 94 7 0 2 . 65 99.81 3.478E+004 3. 48E+004 -2 .938E+004 1.599E+004 87 1. 0 9 99.89 3 .941E+004 3 .114E+004 1.815E+004 Ag-108m 433.90 90.50 4.397E+004 4.19E+004 - l.262E+004 2 .079E+004 614.30 89.80 5.461E+004 7.543E+004 2 .585E+004 722 . 90 90.80 4.188E+004 -5 . 119E+004 Jl.938E+004 Cs-134 604 . 72 97.62 5 .004E+004 4.83E+004 \/ 5 . 765E+004./2.370E+004 795.86 85.46 4.827E+004 3.193E+004 2.239E+004 Cs-137 661.66 85.10 4.704E+004 4.70E+004 3.845E+004\/"2.193E+OD4 Eu-152 121. 78 28.67 2 .027E+005 1.63E+005 -2.884E+004 9.901E+004 344.28 26.60 1.633E+005 3.377E+004 7.808E+004 1408.01 21. 07 1.666E+005 - 9.685E+004 7.394E+004 Eu- 154 123.07 40. 40 1.428E+005 1.11E+005 - 2.873E+004 6.974E+004 723.30 20. 06 1.896E+005 - 1 .847E+005 8.773E+004 1274.43 34.80 1 . 1 08E+005 2 .893E+004 5.000E+004 Eu-155 86.55 30.70 2 .640E+005 2 .64E+005 3 .669E+004 1 . 2 96E+005 105.31 21.10 3.002E+005 -1.159E+005 1 .469E+005 Tl-208 583 . 19 85 . 00 4 . 474E+004 4. 4 7E+004 1.612E+004 2.088E+004 Bi- 212 727.33 6.67 5 . 868E+005 5.87E+005 4.014E+003 2.721E+005

+ Pb- 2 12 2 38.63* 43.60 7.590E+004 7 . 59E+004 4.421E+004 3. 615E+004

+ Bi-214 609.32* 45.49 5.543E+004 2.98E+004 7.871E+004 2 .486E+004 112 0 .29 14.92 2.568E+005 - l .810E+005 l.166E+005 1764.49* 15.30 2.979E+OD4 1.431E+005 O.OOOE+OOO

+ Pb-214 295.22 18.42 2.351E+005 4.91E+004 1.381E+005 1.128E+00 5 351.93* 35 .60 4.906E+004 l .091E+005 2 .182E+004 Ra-226 186.21 3.64 1. 332E+006 1.33E+006 - 2 .004E+006 6.469E+005 Ac-228 338.32 11. 27 3.447E+005 1 . 67E+005 2.623E+005 l .640E+005 911. 20 25.80 1 .665E+005 4.624E+004 7.711E+004 968 . 97 15.80 2.651E+005 3.717E+004 1.222E+005 Am-24 1 59.54 35.90 2.632E+005 2 .63E+005 -4.191E+004 1. 2 86E+00 5

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[183]

          • G AMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated on 4/ 2 0/2018 1: 4 5: 11 PM Sample Title B306216AFSFC001GD v Sample Description U2 WEST VALVE HOUSE V Sample Identification 001 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 4/20/2018 1 : 35 :00 PM Acquisition Started 4/20/ 2 018 1:35:09 PM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0 . 08 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

~~ v~t:cbie/

1/21/; 8' t) 1- '-/)

(__) --~;;/t1

[184]

Peak Analysis Report 4/20/2018 1:45:11 PM Page 2

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

Detector Name: 6279 Sample

Title:

B306216AFSFC001GD Peak Analysis Performed on: 4/20/2018 1:45:10 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start e nd centroid (keV) (keV) Area Uncert. Counts 1 121- 136 128.64 32.08 0.88 4.33E+001 27.34 4.77E+001 2 286 - 346 300.01 74.97 0.78 l.43E+002 177.27 8.83E+002 3 736- 751 743.45 185.94 1. 07 2.89E+001 29.38 6.21E+001 4 945- 962 953.03 238.38 0.61 3.87E+001 28.95 4.93E+001 5 1399 - 1416 1407.62 352.11 0.40 5.lOE+OOl 25.75 3 . 50E+001 6 1801- 1818 1809.48 452.62 0.72 1.80E+001 15.23 l.lOE+OOl 7 2034- 2051 2042.77 510.96 0.40 2.88E+001 16 . 95 1. 32 E+001 8 2325 - 2342 2333.26 583.60 1.21 l .50E+001 16.96 l.70E+001 9 2428 - 2446 2436.73 609.47 1. 28 4.81E +001 19.08 1.19E+001 10 2638- 2655 2646.82 662.00 0.75 6.65E+001 21. 02 l . 3 5E+00 1 11 3638 - 3655 3646.96 911.98 0.81 2.09E+001 15 . 08 l.llE+OOl 12 4474 - 4493 4483.2 1 1120.91 1.25 2.04E+001 10.96 2.59E+OOO 13 5836- 5855 5845.73 1461.15 1. 33 8. 2 0E+001 18.11 O.OOE+OOO 14 7053 - 7072 7062.56 1764.83 0.25 l.06E+001 8.80 2 .40E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[185]

Interference Corrected Activity Report 4/ 2 0/ 2 018 1:4 5 :11 PM Page 3

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

Sample

Title:

B306216AFSFC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

........ . ......... .. IDENTIFIED NUCLIDES . ...................

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pci/MA2 ) Uncertainty K-40 1 . 000 1460.82* 10.66 l.15060E+006 2.73061E+005 Cs-137 1.000 661.66* 85.10 7.83640E+004 2 .64 93 5E+004 Tl-208 1 .000 583.19* 85.00 1.65757E+004 l.88507E+004 Pb- 2 12 1.000 238.63* 43 . 60 5.13746E+004 3.93573E+004 Bi- 2 14 1. 000 609.32* 45.49 l.01545E+005 4.21035E+004 1120.29* 14.92 l.78129E+005 9.66683E+004 1764.49* 15. 30 l . 1 6 679E+005 9.73178E+004 Pb-214 0.437 295.22 18.4 2 351.93* 35.60 1.01992E+ 005 5.37507E+004 Ra- 22 6 1.000 186.21* 3.64 4.11019E +00 5 4.23772E+005

  • = Energy line found in the spectrum .

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

[186]

Interference Corrected Activity Report 4/ 2 0/2018 1:45: 1 1 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1.150598E+006 2.730605E+005 . /

Cs-137 1.000 7. 836398E+004 .,/ 2.649348E+004 Tl-208 1.000 l .657569E+004 1.885072E+004 Pb-212 1. 000 5.137458E+004 3.935727E+004 Bi-214 1. 000 1.141540E+OO S 3.588153E+004 Pb-214 0.437 1.019922E+OOS 5.37 5 073E+004 Ra-226 1. 000 4.110189E+OOS 4.237717E+OOS

? = 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

[187]

Interference Corrected Activity Report 4/20/2018 1:45:11 PM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/20/2018 1: 45 :10 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.08 7. 2 088E-002 63.20 2 74.97 2 . 3792E-001 124.18 6 452.62 2.9943E-00 2 84.80 7 510.96 4.7976E - 002 58.88 11 911. 98 3.4896E-002 72.02 Tol. Ac -22 8 M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[188]

Nuclide MDA Report 4/20/2018 1:4 5 :11 PM Page 6

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B306216AFSFC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M ... 2 ) (pCi/MA2 ) (pCi/M ... 2 ) (pCi/M ... 2 )

+ K-40 1460.82* 10.66 3.797E+004 3 .80E+004 1.151E+006 O.OOOE+OOO Co-6 0 1173. 23 99.85 4.188E+004 3 .41E+004 2 .019E+004 v"° l.913E+004 1332.49 99.98 3.413E+004 -1.776E+003 1.514E+004 Nb -94 702.65 99.81 3.133E+004 3 .13E+004 - 1. 2 81E+004 l . 426E+004 871. 09 99.8 9 3.339E+004 - 2 .235E+004 l.514E+004 Ag - 108m 433.90 90.50 4.315E+004 4. 31E+004 2 . 2 84E+004 2 .038E+004 614.30 89.80 5.388E+004 6.821E+004 2 .548E+004 72 2 .90 90.80 4.544E+004 -2.3 76E+004 2 .116E+004 Cs-134 604.72 97 . 62 4.780E+004 3.57E+004 2 . 2 96E+004 v"' 2 . 2 57E+004 795.86 85.46 3.571E+004 - 2.693E+004 1.611E+004

+ Cs-137 661.66* 85 . 10 2.888E+004 2.89E+004 7.836E+004 l.285E+004 Eu-152 121. 78 28.67 l.968E+005 1 .31E+005 -9.291E+004 9.607E+004 344.28 26.60 1.795E+005 -6 .154E+004 B.615E+004 1408.01 21. 07 1.305E+005 1.011E+003 5.589E+004 Eu-154 123.07 40.40 l.387E+005 B.96E+004 -5 .101E+004 6.770E+004 723.30 20.06 2.057E+005 - 5.354E+004 9.579E+004 1274.43 34.80 8.958E+004 - 1.497E+004 3.939E+004 Eu-155 86.55 30.70 2.618E+005 2.62E+005 8. 91BE+004 1.285E+005 1 05.31 21.10 3.030E+OOS l.140E+00 5 1.483E+005

+ Tl-208 583.19* 85.00 3 . 042E+004 3.04E+004 1.658E+004 1 .372E+004 Bi-212 727.33 6 . 67 6. 2 04E+OOS 6.20E+005 - 3. 942E+003 2 .889E+OOS

+ Pb-212 238.63* 43.60 6.075E+004 6.07E+004 5.137E+004 2 .857E+004

+ Bi - 214 609.32* 45.49 5 . 124E+004 5.12E+004 l.015E+005 2.276E+004 1120.29* 14.92 1.126E+005 1.781E+005 4.447E+004 1764.49* 15.30 1.370E+OOS l.167E+005 5 .35BE+004

+ Pb - 214 295.22 18.42 2.397E+005 7.60E+004 2 .879E+005 l.151E+OOS 351.93* 35.60 7.597E+004 1.020E+005 3.528E+004

+ Ra-226 186.21* 3.64 6.781E+OOS 6.78E+OOS 4.110E+005 3.19BE+005 Ac-228 338.32 11. 27 3.534E+005 1.78E+005 1.351E+005 l.684E+OOS 9 11. 20 25.80 1.778E+005 2 .777E+005 8. 2 72E+004 968.97 15.80 2 .462E+005 -9 .835E+004 1.127E+OOS Am- 24 1 59.54 35.90 2 .667E+005 2.67E+005 - l.835E+OOS l.304E+OO S

+ = Nuclide identified during the nuclide identification

  • = Energy l ine found in the spectrum

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

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

[189]

          • GAMM A S P E C T R U M ANAL YS I S *****

Filename: 6279 Report Generated On 4/21/2018 8:03:59 AM Sample Title B306216AFSFC002GD ~/

Sample Description U2 West Valve House /

Sample Identification 002 Sample Type Gamma Direct Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 81 92 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 /

Sample Taken On 4/21/2018 7:50:00 AM V Acquisition Started 4/21/2018 7:53:58 AM V Live Time 600. 0 seconds Real Time 600.5 seconds Dead Time 0.08 %

Energy Calibration Used Done On 12/28/2017 V Efficiency Calibration Used Done On 2/1/2018 v Efficiency ID 3M90D CP 2 IN v

  • DG1-~ V~1ui--+c/

'-/ /z?)1 i

[190] ~

Peak Analysis Report 4/ 2 1/2018 8: 0 3:59 AM Page 2

          • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B306216AFSFC002GD Peak Analysis Performed on: 4/21/2018 8:03:59 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start e nd centroid (keV) (keV) Area Uncert. Counts 1 121- 137 128.78 32.11 0.98 2.60E+001 3 6 . 67 9.90E+001 2 291- 3 48 298.32 74.55 0.38 5.63E+001 180.0 2 9.63E+002 3 944- 961 952.65 238.28 0.27 3.0lE+OOl 33.59 7.69E+001 4 1171- 1 1 88 1179.72 2 95.09 0.33 3.97E+001 23.24 2.93E+001 5 1397- 1414 14 05.26 351.51 0.87 4.95E+001 24.20 2.95E+001 6 2030- 2047 2038.04 509.78 0.3 1 1.60E+001 21. 64 3.lOE+OOl 7 2321- 2338 2329.19 582.58 0.38 1.65E+001 16 . 36 1 .55E+001 8 2426- 2443 2434.08 608.81 0.65 5.52E +001 16.95 4.78E+OOO 9 2631- 2653 2642.62 660.95 1. 30 3.09E+002 39.40 2 .02E+001 10 4464 - 4483 4473.61 1118.51 1. 37 1.14E+001 15.28 1 .26E+001 11 5827 - 5848 5837.14 1459.01 2 . 54 7.75E+001 19.82 5.50E+OOO M = First peak in a mul tiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[191]

Interference Corrected Activity Report 4/21/2018 8: 03:59 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.995 1460.82* 10.66 1.08645E+006 2.93456E+005 Cs - 137 0.999 661.66* 85.10 3.63576E+005 6.37049E+004 Tl-208 0.999 583.19* 85.00 l . 82512E+004 1.81994E+004 Pb - 212 1.000 238.63* 43.60 4.00238E+004 4.50875E+004 Bi - 214 0.734 609.32* 45.49 l .16544E+005 3.84292E+004 112 0 .29* 14.92 9.94267E+004 1.33425E+005 1764.49 15 . 3 0 Pb - 214 1.000 295.22* 18.42 1 .39299E+005 8.45125E+004 351.93* 35.60 9.90607E+004 5.06112E+004

  • =Energy line found in the spectrum .

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.3 0 Errors quoted at 2.000 sigma

[192]

Interference Corrected Activity Report 4/ 2 1/2018 8:03:59 AM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.995 1. 086450E+ 0 06 / 2.934563E+005 Cs-137 0.999 3. 635757E+005 v 6 .370494E+004 V Tl -2 08 0.999 1.825122E+004 1 .819936E+004 Pb-212 1. 000 4.002383E+004 4.508753E+004 Bi -2 14 0.734 1.152328E+005 3.692802E+004 Pb -2 14 1. 000 1 .096823E+005 4.342056E+004

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

@ : Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

[193]

Interference Corrected Activity Report 4/21/2018 8:03:59 AM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 8:03:59 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32. 11 4.3300E-002 141.14 2 74.55 9.3841E-002 319.72 6 5 0 9.78 2.6720E-002 134.98 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[194]

Nuclide MDA Report 4/2 1 /2018 8:03: 59 AM Page 6

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B3062 1 6AFSFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 2.479E+005 2 .48E+005 1.086E+00 6 1.050E+005 Co-60 1173.23 99.85 3.927E+004 3.34E+004 /' 2 .891E+004 \1"'1 .783E+004 1332.49 99.98 3.340E+004 2.841E+004 1.478E+004 Nb - 94 702.65 99.81 3.213E+004 3.21E+004 6.035E+003 1.4 6 6E+004 871. 09 99.89 3.780E+004 - 2.346E+004 1.734E+004 Ag - 108m 433.90 90.50 4.861E+004 4.07E+004 -3.653E+004 2.311E+004 614.30 89.80 5.213E+004 3.894E+004 2.461E+004 72 2 .90 90.80 4.074E+004 - 3.834E+004 1.881E+004 Cs - 134 604.72 97.62 4.960E+004 4.09E+004/'7.568E+004'-'2 .348E+004 795.86 85.46 4.086E+004 )2. 3 48E+004 1.869E+004

+ Cs - 137 661.66* 85.10 3.767E+004 3.77E+00411'3.636E+005 1. 724E+004 Eu-1 52 121. 78 28.67 2 . 2 26E+005 l. 48 E+005 -l. 3 09E+005 l.090E+005 344.28 26.60 1.803E+005 - 3.637E+00 4 8.659E+004 1408.01 21.07 1.478E+005 1. 1 10E+005 6.454E+004 Eu-154 123.07 40.40 1.580E+005 9 . 59 E+004 - 4.303E+004 7.737E+004 723.30 20.06 1.896E+005 1.634E+00 5 8.773E+004 1274.43 34.80 9.589E+004 8.381E+004 4.255E+004 Eu-155 86.55 30.70 2.632E+005 2.63E+005 1 .228E+004 1.292E+005 105.31 21.10 3 . 232E+005 - 1.534E+004 1.584E+005

+ Tl-208 583.19* 85.00 2.878E+004 2 .88E+004 1.825E+004 1.290E+004 Bi-212 727.33 6.67 5.615E+005 5.62E+005 - 3 .577E+005 2 .594E+005

+ Pb-212 238.63* 43.60 7.297E+004 7.30E+004 4.002E+004 3 .469E+004

+ Bi-214 609.32* 45.49 3.404E+004 3.40E+004 l.165E+005 l.417E+004 1120.29* 14. 92 2.201E+005 9.943E+004 9.826E+004 1764.49 15.30 2 .410E+005 1.872E+005 1.056E+005

+ Pb-214 295.22* 18.42 1. 222E+0 05 7.02E+004 l.393E+005 5.633E+004 3 51.93* 35.60 7.016E+004 9.906E+004 3.237E+004 Ra-226 186.21 3.64 1.501E+006 1.50E+006 1.116E+006 7.312E+005 Ac-2 2 8 338.32 11. 27 3 .840E+005 1 .51E+005 2.818E+005 1.836E+005 911. 20 25.80 1.512E+005 - 3.557E+004 6.945E+004 968.97 15.80 2 .517E+005 7. 1 09E+004 1 .155E+005 Am-241 59.54 35.90 2 .777E+005 2 .78E+005 l.080E+005 1. 3 58E+OOS

+ = Nucl i de identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[195]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/20/2018 1:58:32 PM Sample Title B306216AFSFC003GD ./'

Sample Description U2 WEST VALVE HOUSE ../

Sample Identification 003 ../

Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.0 0 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 4/20/2018 1: 48: 00 PM Acquisition Started 4/20/2018 1: 48: 3 1 PM Live Time 600.0 seconds Real Time 600.6 seconds Dead Time 0.09 %

Energy Calibration Used Done On 12/28/2017 v--

Efficiency Calibration Used Done On 2/1/2018 \....o"""

Efficiency ID 3M90D CP 2IN L,..,--

D~Vull~cl y/i, /, 6 015~

-~

' ~//

[196]

Peak Analysis Report 4/20/ 2 018 1:58: 32 PM Page 2

          • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B306216AFSFC003GD Peak Analysis Performed on: 4/20/2018 1:58:32 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start e nd centroid (keV) (keV) Area Uncert. Counts 1 122- 137 129.17 32.21 0.98 2.71E+001 35 .0 3 9.29E+001 2 284 - 308 298.04 74.48 0.83 1. 42E+002 87. 0 9 4.23E+00 2 3 468- 483 475.96 119.00 0. 2 7 1. 41E+OOO 45.72 1.73E+002 4 946- 963 954.73 238.80 0.30 - 8.45E+OOO 39 . 68 l.23E+002 5 1279 - 1296 1287.77 322. 1 3 0.63 6. 2 6E+OOO 25.81 4.87E+001 6 1345- 1362 1 353.18 338.49 0.63 8.31E+OOO 23.00 3.67E+001 7 1399- 1 417 1407.40 352.05 0.94 6.64E+001 24.70 2 . 56E+001 8 1753 - 1 770 1 76 1. 61 440.65 0.39 l.31E+001 18.11 l .89E+001 9 2035 - 2 0 52 2043.05 511.03 0.63 2.04E+001 18.38 l.96E+001 10 24 2 8- 2446 2 436 . 13 609.32 1. 35 4.50E+001 20. 41 1.70E+001 11 2634 - 2656 2645. 2 7 661. 61 1. 36 2.46E +002 36.65 2 .31E+001 12 3636 - 3653 3644. 1 6 911.28 1. 61 l.23E+001 12.83 8.69E+OOO 13 5834- 5853 5843.35 1460.55 0.95 8.04E+001 18.98 2.64E+OOO 14 7051- 7070 7060.75 1764.38 0.3 1 1.70E+001 8.25 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[197]

Interference Corrected Activity Report 4/2 0 / 2 018 1: 58: 32 PM Page 3

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

Sample

Title:

B306216AFSFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. ............ . ...... IDENTIFIED NUCLIDES . . . ................

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.12732E+006 2.83670E+005 Ag-108m 0.459 433.90* 90.50 1 . 16582E+004 1 .62370E+004 614.30* 89.80 4.81653E+004 2. 2 5802E+004 722.90 90.80 Cs-137 1.000 661.66* 85.10 2.89700E+005 5.54461E+004 Pb-212 1.000 238.63* 43.60 -l.12329E+004 5.28019E+004 Bi - 214 0.706 609.32* 45.49 9.50812E+004 4.45797E+004 112 0 .29 14.92 1764.49* 15.30 1.87165E+005 9.20176E+004 Pb -2 14 0.437 295.22 18.4 2 351.93* 35.60 1.32959E+005 5.32769E+004 Ac-228 0.555 338 . 32* 11.27 5.13644E+004 1.42455E+005 911.20* 25.80 5.60436E+004 5.86771E+004 968.97 15.80

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2. 000 sigma

[198]

Interference Corrected Activity Report 4/20/2018 1:58:3 2 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 1.127317E+006 2.836697E+005 Ag-lOBm 0.459 6.440716E+003 1.549349E+004 Cs-137 1. 000 2. 897000E+005 ./ 5. 544612E+004 ./

X Eu-152 0.667 Pb- 212 1.000 - 1.123290E+004 5.2 80193E+004 Bi-214 0.706 1.022857E+005 4.714761E+004 Pb-214 0.437 1.329594E+005 5.327689E+004 Ac-228 0.555 5.536486E+004 5.425483E+004

? = Nuclide i s 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

[199]

Interference Corrected Activity Report 4/2 0 /2018 1: 58: 32 PM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/20/2018 1 :58:32 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.21 4.5205E - 002 129.17 2 74.48 2.3638E - 001 61.41 3 119.00 2.3563E-003 3233.86 Tol. Eu-154 5 322.13 1. 0439E-002 412.13 9 511. 03 3.4073E-002 89 . 9 0 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 00 0 sigma

[200]

Nuclide MDA Report 4/20/ 2 018 1:58: 32 PM Page 6

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

Detector Name: 62 79 Sample Geometry:

Sample

Title:

B3062 1 6AFSFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/M"'2 )

+ K-40 1460.82* 1 0.66 1 .816E+005 1. 82E+005 ,/ 1.127E+006 7 .184E+004 Co-60 1173. 23 99.85 4.432E+004 3 .55E+004 4.234E+004 2.035E+004 1332.49 99.98 3.554E+004 1 . 065E+003 / ' 1.585E+004 Nb-94 702.65 99.81 3.823E+004 3.61E+004 -8.548E+003 l.771E+004 871.09 99.89 3.610E+004 - 3.946E+004 1.650E+004

+ Ag-108m 4 33 .90* 90.50 2 .680E+004 2.68E+004 l.166E+004 1.219E+004 614.3 0

  • 89.80 2.994E+004 4.817E+004 1.352E+004 72 2 .90 90.80 4.150E+004 3.494E+004 1.919E+004 Cs - 1 34 604.72 97.62 4.982E+004 4. 32 E+004./' 5.383E+004 v'2.359E+004 795.86 85.46 4. 3 18E+004 - 6.415E+004 1.985E+004

+ Cs-137 661.66* 85.10 3.993E+004 3.99E+004 /' 2 . 897E+00 5 l.837E+0 0 4 Eu- 152 121.78* 2 8.67 1.338E+005 1 .03E+005 2.431E+003 6.457E+004 344.28* 26.60 1.031E+005 2.176E+004 4.798E+004 1408.01 21. 07 1.666E+005 4.624E+003 7. 3 94E+004 Eu-154 123 . 07 40.40 1.645E+005 9.98E+004 5. 2 86E+004 8.062E+004 723.30 2 0.06 1. 879E+005 9.733E+004 8.688E+004 1274.43 34.80 9 .985E+004 -4. 3 60E+004 4.453E+004 Eu- 155 86.55 30.70 2 .795E+005 2 .79E+005 - 4 . 2 07E+005 1 .374E+005 105.31 21.10 3.306E+005 -1 . 321E+005 l.621E+005 Tl- 208 583.19 85. 0 0 4.953E+004 4.95E+004 2.182E+003 2.327E+004 Bi-212 727 . 33 6.67 5 .615E+005 5.62E+005 4.613E+005 2.594E+00 5

+ Pb-212 238 . 63* 43.60 9.133E+004 9.13E+004 -1.123E+004 4.387E+004

+ Bi-214 609.32* 45.49 5.911E+004 2.98E+004 9.508E+004 2.670E+004 112 0 .29 14.92 3 .191E+005 2.726E+005 l.477E+005 1764.49* 15.30 2.979E+004 l.872E+005 O.OOOE+OOO

+ Pb-214 295.22 18.42 2. 494E+005 6.65E+004 2 .839E+005 l.199E+005 35 1 .93* 35.60 6 .649E+004 l.330E+005 3.053E+004 Ra-226 186. 2 1 3.64 1. 496E+006 l.50E+006 3.760E+005 7.290E+005

+ Ac-228 338.32* 11. 27 2.432E+005 9. 2 8E+004 5.136E+004 l.132E+005 911.20* 25.80 9.279E+004 5.604E+004 4.023E+004 968.97 1 5.80 2.545E+005 - 7.759E+004 l .169E+005 Am- 241 59.54 35.90 2.930E+005 2.93E+005 3 .182E+005 l.435E+005

+ = Nuclide identified during the nuclide ident i fication

  • =Energy line found in the spectrum

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

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

[201]

          • GAMMA S P E C T R U M A N A L Y S I S *****

Filename: 6279 Report Generated On 4 /20/2018 2:24:28 PM Sample Title B306216AFSFC004GD v Sample Sample Description Identification U2 WEST VALVE HOUSE 004 vv Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 4/20/2018 2 :14:00 PM Acquisition Started 4/20/2018 2 :14:27 PM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0. 07 % /

Energy Calibration-Used Done On i2/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN 7)vv~ v~/1~

'-If {Ii 8" 0 li"'"'

[202]

Peak Analysis Report 4/20/2018 2:24:28 PM Page 2

          • PE AK A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B306216AFSFC004GD Peak Analysis Performed on: 4/20/2018 2:24:27 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 281 - 309 297.04 74.23 1.10 2.10E+002 86.08 3.55E+002 2 946 - 963 954.78 238.82 0.54 1 .21E+001 37.53 1.04E+002 3 1174 - 1191 1182 . 64 295.83 0.74 3.90E+001 25.08 3.60E+001 4 1345 - 1362 1353.32 338.52 0.77 1.54E+001 18.94 2.26E+001 5 1399- 1417 1408.16 352.24 1.19 6.34E+001 27 .11 3 . 56E+001 6 2034 - 2051 2042.89 510.99 0.36 3. 70E+001 16. 29 9.00E+OOO 7 2324 - 2341 2332.87 583.50 0.96 2 .57E+001 15.87 1.13E+001 8 2 429- 2447 2438.23 609.85 1.40 6.90E+001 21.56 1.40E+001 9 2 636 - 2657 2646 . 85 662.01 1. 57 8.88E+001 24.50 1.62E+001 10 3637 - 3654 3645.10 911.51 0. 3 1 1.19E+ 001 12.91 8.05E+OOO 11 5838- 5858 5848.35 1461.80 0.9 5 1.01E+002 20.10 O.OOE+OOO 12 7056- 7075 7065.33 1765.52 1 .09 2 .63E+001 12.09 2.70E+OOO M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[203]

Interference Corrected Activity Report 4/20/2018 2 :24:28 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSFC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

....... . .. . . .. .. . .. . . IDENTIFIED NUCLIDES . ...................

Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) ( %) (pCi/M 2 ) Uncertainty K-40 0.998 1460.82* 10.66 1.41760E+006 3.07800E+005 Cs-137 1.000 661.66* 85.10 1.04649E+005 3.14875E+004 Tl-2 08 1.000 583.19* 85.00 2.83479E+004 1 .78612E+004 Pb-212 1. 000 238 . 63* 43.60 1.60753E+004 4.99810E+004 Bi- 2 14 0.706 609.32* 45.49 1.45701E+005 4.87960E+004 1 12 0.29 14.92 1 764 . 49* 15.30 2.89692E+005 1.351 91E+005 Pb-2 14 1.000 295.22* 18.4 2 1.36956E+005 9.07692E+004 351.93* 35.60 1.26846E+00 5 5 .74916E+004 Ac-228 0.555 338.32* 11. 2 7 9.52929E+004 1.18074E+005 911.20* 25.80 5.44136E+004 5.90077E+004 968.97 15.80

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0. 3 0 Errors quoted at 2 .000 sigma

[204]

Interference Corrected Activity Report 4/20/2018 2 :24:28 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.998 1.417600E+006 3.078003E+005 Cs-137 1.000 1. 046488E+005 / 3 .148748E+004 /

Tl-208 1. 000 2.834789E+004 1 .786125E+004 Pb-212 1. 000 1 .607535E+004 4.998104E+004 Bi-214 0.706 1.622980E+005 4.589775E+004 Pb-214 1. 000 1.2 ~ 7406E+00 5 4.856892E+004 Ac-228 0.555 6.258295E+004 5.278331E+004

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

@ = Nucl ide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

[205]

Interference Corrected Activity Report 4/2 0 /2 0 18 2:24 : 28 PM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/20/2018 2 :24:27 PM Peak Locate From Channel: 85 Peak Locate To Channel: 81 92 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts p er Second  % Uncertainty Type Nuclide 1 74.23 3.5029E-001 40.96 6 5 10 .99 6.1667E-002 44 . 02 M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted* at 2 .000 sigma

[206]

Nuclide MDA Report 4 /2 0/2018 2 :24: 2 8 PM Page 6

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

Detector Name: 62 79 Sample Geometry:

Sample

Title:

B306216AFSFC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 3 .798E+004 3.80E+004/ l.418E+00 6 O.OOOE+OOO Co-60 1173.23 99.85 3.981E+004 3.03E+004 3.210E+004 1.810E+004 1332.49 99.98 3.028E+004 2 .273E+004 /' 1.322E+004 Nb- 94 702.65 99.81 3.723E+004 3.72E+004 3 .134E+004 1.721E+004 871. 09 99.89 3.821E+004 1.434E+004 1.755E+004 Ag-108m 433.90 90.50 4 . 418E+004 3.96E+004 -3 . 9 56E+003 2 .089E+004 614.30 89.80 6 . 076E+004 l.222E+00 5 2 .893E+004 722.90 90.80 3.957E+004 - 3 .134E+004 l.822E+004 Cs-134 604.72 97.62 5.425E+004 3.8 9E+004V 7.094E+004 J' 2. 580E+004 795.86 85.46 3.889E+004 4.327E+003 1.770E+004

+ Cs - 137 661.66* 85.10 3 . 353E+004 3.35E+004 1 .046E+00 5 l.517E+004 Eu- 152 121. 78 28.67 2. 1 38E+005 1.52E+005 -9.414E+004 1.046E+00 5 344.28 26.60 1.847E+005 6.515E+004 8.875E+004 1408.01 2 1. 07 1.518E+005 4.304E+004 6.652E+004 Eu-154 123.07 40.40 1.509E+005 9.17E+004 2 . 749E+004 7.382E+004 723. 3 0 20.06 1.810E+005 - 7.975E+004 8.340E+004 1274.43 34.80 9.174E+004 -1.097E+004 4.047E+004 Eu-1 55 86.55 30 . 70 2 .658E+005 2.66E+005 2.098E+005 1.305E+005 105.3 1 21.10 3.040E+005 l.428E+005 1.488E+005

+ Tl- 2 0 8 583. 1 9* 85.00 2.519E+004 2 .52E+004 2.835E+004 1.110E+004 Bi-212 727.33 6.67 5.403E+005 5.40E+005 7.096E+004 2.488E+005

+ Pb-212 238.63* 43.60 8. 42 9E+004 8.43E+004 l.608E+00 4 4.034E+004

+ Bi-214 609.32* 45.49 5.348E+004 5.35E+004 1.457E+005 2 .388E+004 1 120. 2 9 14.92 2.671E+005 2 .044E+005 1.218E+005 1764.49* 15.30 1.458E+005 2 .897E+005 5.802E+004

+ Pb-214 295.22* 18.42 l.352E+005 7.77E+004 1.370E+005 6.283E+004 351.93* 35.60 7.767E+004 1.268E+005 3.613E+004 Ra-226 186.21 3.64 1 .341E+006 l. 34 E+006 -1.264E+006 6.512E+005

+ Ac-228 338.32* 11. 2 7 1.921E+005 9.40E+004 9.529E+004 8.768E+004 911.20* 25.80 9.396E+004 5.441E+004 4.082E+004 968.97 15.80 2.677E+005 4. 2 14E+004 l .235E+005 Am-24 1 59.54 35.90 2.820E+005 2.82E+005 2 .827E+005 1. 3 80E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[207]

    • ~**********************************************************************
          • GAMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/ 2 0 /2 018 2 :4 9 : 24 PM Sample Title B3 06216AFSWC005GD /

Sample Description U2 WEST VALVE HOUSE v"° Sample Identification 005 ,./"'

Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 v Sample Taken On 4/20/2018 2:39:00 PM Acquisition Started 4/20/2018 2:39: 2 3 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07 9.-

0

/'.

Energy -Calibration Used Done On 12/28/2017 v Efficiency Calibration Used Done On 2/1/2018 V Efficiency ID 3M90D CP 2 IN V D~V~,l ,'~

cf/z,(t~

( _____/ '

[208]

Peak Analysis Report 4/20/2018 2 :49:24 PM Page 2

          • PE AK A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B306216AFSWC005GD Peak Analysis Performed on: 4/20/2018 2:49:24 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert . Counts 1 286 - 308 300.21 75.02 0.73 8.60E+001 75.85 3.46E+002 2 946- 964 954.90 238.85 0.41 3.68E+001 31.56 6.22E+001 3 1172 - 1189 1180.9 0 295.39 0.30 1.93E+001 23.95 3.77E+001 4 1399 - 1417 1407.79 352.15 0.99 4.57E+001 23 . 27 2.63E+001 5 2324- 2341 2332.71 583.46 0.36 2.03E +001 17.68 1.77E+001 6 2430- 2447 2438.05 609.80 0.56 5.0lE+OOl 16.43 4.90E+OOO 7 2639- 2656 2647.94 662.28 0 . 97 2 .95E+001 13 . 29 4.50E+OOO 8 4475- 4494 4484.61 1121. 26 0.43 9.00E+OOO 13 . 37 1 .00E+OOl 9 5836- 5857 5847.21 1461. 52 0.48 l. 08E+002 20.78 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2.000 sigma

[209]

Interference Corrected Activity Report 4 /20/2018 2 :4 9: 2 4 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. . . . .... . . . . . . . . . . . . IDENTIFIED NUCLIDES .. . ......... . . . ... ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.999 1460.82* 10.66 l.51 5 66E+00 6 3 .20008E+005 Cs- 137 0.999 661.66* 85.10 3.47706E+004 l.62065E+004 Tl-208 1.000 583.19* 85.00 2.23890E+004 1. 97154E+004 Pb-212 1. 000 238.63* 43.60 4.89903E+004 4.27212E+004 Bi- 2 14 0.735 609. 32

  • 45.49 l.05834E+005 3.69657E+004 1120.29* 14.92 7.85486E+004 1.16827E+005 1764.49 15.30 Pb-214 1.000 295.22* 18.42 6.77955E+004 8. 47474E+004 351.93* 35.60 9.14472E+004 4.85534E+004
  • = Energy line found in the spectrum.

@ = Energy line not used f or Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2 .000 sigma

[210]

Interference Corrected Activity Report 4/20/2018 2 :49: 24 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 0.999 1 .5 1 5663E+006 3 .200079E+005 Cs-137 0.999 3. 477064E+004 .,/ 1. 620645E+004 Tl-208 1.000 2.238899E+004 1.971543E+004 Pb-212 1.000 4.899029E+004 4.272121E+004 Bi-214 0.735 1.033508E+005 3.524350E+004 Pb-214 1. 000 8.560238E+004 4.212905E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

[211]

Interference Corrected Activity Report 4/ 2 0/2018 2 :49: 24 PM Page 5

                    • UN I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/20/2018 2 : 49:24 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.02 1.4336E - 001 88.18 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[212]

Nuclide MDA Report 4/20/2018 2: 49: 24 PM Page 6

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B3062 1 6AFSWC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 3.798E+004 3.80E+OD4 ,jl. 5 16E+006 0.000E+OOO Co-60 1173 . 23 99.85 3.761E+004 3.03E+004 l .101E+004 _)..700E+004 13 32 .49 99.98 3.028E+004 9.633E+003 ~ 1.322E+OD4 Nb-94 702.65 99.81 3.367E+004 3.37E+004 l.029E+004 l.543E+004 87 1. 09 99.89 3.610E+004 -4.026E+003 l.6SOE+004 Ag-108m 433.90 90.50 4.418E+004 4.00E+004 2 .973E+004 2.089E+004 614.30 89.80 5.412E+004 1.003E+005 2.561E+OD4 722.90 90.80 3.997E+004 1 .501E+004 l.842E+004 Cs-134 604.72 97.62 4.916E+004 4.45E+004 ./: 2.950E+D03 2.325E+004 795.86 85.46 4.451E+004 o ,ao eo / -6 .178E+OD4 2 .052E+004

+ Cs-137 661.66* 85.10 1. 802E+004 1. 80E+004 rf 3. 477E+004 7.415E+003 Eu-152 121.78 28.67 2.079E+005 1.4DE+005 l.115E+005 1.016E+00 5 344.28 2 6.60 1. 700E+005 9.922E+004 8.141E+004 1408.01 2 1. 07 l.395E+005 9.660E+003 6.037E+004 Eu-154 123.07 40.40 l.461E+005 1.13E+D05 5.291E+Q04 7.139E+004 723. 3 0 2 0.06 l.792E+OD5 -3.442E+004 8.251E+004 1274.43 34.80 l.125E+005 7.326E+004 5.085E+004 Eu-155 86.55 30.70 2.455E+005 2.46E+005 l.120E+005 1 . 204E+005 105.3 1 21.10 3 . 020E+005 3.740E+005 1. 478E+005

+ Tl-208 583.19* 85.00 3.064E+004 3.06E+004 2.239E+004 l . 382E+004 Bi-212 727.33 6.67 5.349E+005 5.35E+OD5 3 .906E+005 2.461E+005

+ Pb-212 238.63* 43.60 6.735E+004 6.73E+004 4.899E+004 3.187E+004

+ Bi- 2 14 609.32* 45.49 3.47DE+004 3.47E+004 l.058E+D05 l. 449E+004 1120.29* 14.92 l.951E+005 7.855E+004 8.574E+004 1764.49 15.30 2 .347E+005 5.419E+004 1.025E+005

+ Pb-214 295.22* 18.42 l.381E+005 6.78E+004 6.780E+004 6.431E+004 351.93* 35.60 6.78DE+004 9.145E+004 3.119E+004 Ra - 226 186.21 3.64 l.310E+006 1.31E+006 - 1. 509E+006 6.358E+005 Ac-228 338.32 11. 27 3.583E+005 l.79E+005 - 1. 678E+004 l.708E+005 911.20 25.80 1.791E+005 l.473E+D05 8.340E+004 968.97 15.80 2.651E+OD5 2.789E+005 l. 2 22E+005 Am-241 59.54 35.90 2.596E+005 2 .60E+D05 l.843E+005 l.268E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[213]

          • GAMMA S P E C T R U M ANALY S I S *****

Filename: 6279 Report Generated On 4 /2 1/2018 1: 41: 14 PM Sample Title B306216AFSWC006GD Sample Description U2 West Valve House Sample Identification 006 Sample Type Gamma Direct Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 MA2 Sample Taken On 4/21/2018 1:30:00 PM Acquisition Started 4/21/2018 1:31:13 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 ~

0 /

Energy Calibration Used Done On 12/28/2017 V Efficiency Calibration Used Done On 2/1/2018 t(" /

Efficiency ID 3M90D CP 2 IN V

'T)~-~ ~ V0i/,J*I

'-II(; 3/1 ~ os-oo 0

[214]

Peak Analysis Report 4/21/2018 1: 4 1 : 14 PM Page 2

          • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B306216AFSWC0 0 6GD Peak Analysis Performed on: 4/21/2 018 1: 4 1 :14 PM Peak Analysis From Channe l : 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 120 - 1 35 127.26 31.73 0.38 2.40E+001 28.30 5.70E+001 2 283 - 346 297.97 74.46 0.95 1.87E+002 182 . 14 8.78E+002 3 736 - 751 743.14 185.86 0.31 2 .77E+001 31. 36 7.23E+001 4 1171 - 1188 1179.72 295.09 0.87 1.79E+001 24.70 3.91E+001 5 1397- 1415 1405.28 351.52 0.79 5.68E+001 22.66 2.12E+001 6 2322- 2339 2330.00 582.79 0.50 2 .21E+001 13.46 6.92E+OOO 7 2425 - 2442 2433.69 608.71 0.73 5.16E+001 16.24 4.36E+OOO 8 2634 - 2652 2642.86 661.01 1. 00 5.73E+001 22.12 1 .77E+001 9 4467 - 4486 4476.57 1119.25 1. 02 1.64E+001 13.24 7.64E+OOO 10 5829- 5849 5838.77 1459.41 0.44 9.52E+001 20.6 0 2.82E+OOO 11 7046- 7065 7055.63 1763.10 0.38 1.40E+001 7 . 48 O.OOE+OOO M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[215]

Interference Corrected Activity Report 4/21/2018 1 :41: 14 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC006GD Nuc l ide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB

.................... IDENTIFIED NUCLIDES . . . . . .......... .. ...

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.997 1460.82* 10.66 1.33448E+006 3 .11181E+005 Cs-137 0.999 661.66* 85.10 6.74899E+004 2 .72727E+004 Tl -2 08 1.000 583.19* 85.00 2.43790E+004 1.51465E+004 Bi -2 14 0.999 609.32* 45.49 1.08992E+005 3.66892E+004 1120.29* 14.92 l.42695E + 005 1.15981E+005 1764.49* 15.30 1.54065E+005 8 . 32708E+004 Pb- 2 14 1 . 000 295.22* 18.4 2 6.27461E+004 8.72137E+004 351.93* 35.60 1.13534E+005 4.83900E+004 Ra-226 1.000 186.21* 3.64 3.94526E+005 4.51057E+005

  • =Energy line found in the spectrum .

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2 .000 sigma

[216]

Interference Corrected Activity Report 4/21/2018 1 :41: 14 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.997 1. 334479E+006 ~.111812E+OOS j '

Cs-137 0.999 6.748988E+004 .727268E+004 Tl-208 1. 000 2.437904E+004 1.514652E+004 Bi-214 0.999 1.183588E+OOS 3 . 225062E+004 Pb-214 1. 000 1 . 01 5791E+OOS 4.231327E+004 Ra-226 1.000 3.945261E+OOS 4.510572E+OOS

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

@ = Nuclide contains energy lines not used i n Weighted Mean Activity Errors quoted at 2 .000 sigma

[217]

Interference Corrected Activity Report 4/21/2018 1 :41: 14 PM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 1 :41: 14 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts P,er Second  % Uncertainty Type Nuclide 1 31. 73 3.9969E-00 2 118.01 2 74.46 3.1220E-001 97.24 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[218]

Nuclide MDA Report 4/21/2 018 1: 41: 14 PM Page 6

          • N U C L I D E MD A REPORT *****

Detector Name: 6279 Sample Geometry:

Sample

Title:

B306216AFSWC006GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nucl ide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10 .66 1 . 902E+005 1.90E+005 /l.334E+00 6 7.610E+004 Co - 6 0 1173.23 99.85 4.034E+004 3 .4 1 E+004./ 4.222E+003 1.836E+004 1332.49 99.98 3.413E+004 2. 983E+004/ 1. 514E+004 Nb - 94 702.65 99.81 4 . 107E+004 2.93E+004 1. 224E +004 l.913E+004 871. 09 99.89 2 . 933E+004 - 7.908E+00 2 1 . 311E+004 Ag - 108m 433.90 90.50 4.101E+004 3 .75E+004 - 2 .521E+004 1.931E+004 614.30 89.80 5.363E+004 8.889E+004 2.536E+004 722.90 90.80 3.753E+004 2. 3 39E+004/l.720E+004 Cs-134 604.72 97.62 4.733E+004 4. 23 E+004/2. 2 52E+004 2.234E+004 795.86 85.46 4.227E+004 -} . 544E+O 04 l.939E+004

+ Cs - 137 661.66* 85.10 3.441E+004 3.44E+004\f6.749E+004 1.561E+004 Eu-152 121.78 28.67 2.065E+005 1.56E+005 l.116E+005 1.009E+005 344.28 26.60 1. 727E+005 4 .629E+003 8.279E+004 1408.01 21. 07 1. 5 57E+005 -2 .948E+004 6.845E+004 Eu-154 123.07 40. 40 1.4 6 1E+005 8.74E+004 -2 .428E+004 7.139E+004 723.3 0 20.06 l.641E+005 -l.810E+005 7.499E+004 1274.4 3 34.80 8 . 736E+004 - 6 .890E+004 3 . 828E+004 Eu-155 86.55 30.70 2.532E+005 2.53E+OOS -3. 2 90E+004 1.242E+005 105.31 21.10 3.004E+005 -1. 3 16E+0 05 1.470E+005

+ Tl - 208 583. 1 9* 85.00 2.049E+004 2 .05E+004 2.438E+004 8.749E+003 Bi-212 727.33 6.67 5.238E+005 S .24E+OOS - l .486E+005 2.406E+005 Pb-212 23 8.63 43.60 l.141E+005 l.14E+005 5.624E+004 5.524E+004

+ Bi-214 609.32* 45.49 3.195E+004 2 .98E+004 1.090E+005 l.312E+004 1120.29* 14.92 1. 739E+005 1.427E+005 7.513E+004 1764.49* 15.30 2.978E+004 1. 541E+005 O.OOOE+OOO

+ Pb-214 295.22* 18.42 1.434E+005 6 .11E+004 6 . 27 5E+004 6.695E+004 3 51. 93* 35.60 6.106E+004 l.135E+005 2.783E+004

+ Ra-226 186.21* 3.64 7.293E+005 7.29E+005 3.945E+005 3 . 454E+005 Ac - 228 338.32 11.27 3 .460E+005 1.65E+005 9.656E+004 1 .646E+005 911.20 25.80 1.651E+005 l. 423E+005 7.637E+004 968.97 15.80 2 .405E+005 2 .035E+005 l.099E+005 Am-241 59.54 35.90 2 . 674E+005 2 .67E+00 5 l.060E+005 1.307E+005

+= Nucli de identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[219]

    • ~**********************************************************************
          • GAMMA S P E C T R U M ANALY SIS *****

Filename: 6279 Report Generated On 4/21/2018 8 :53 :17 AM Sample Title B306216AFSWC007GD ,......--

Sample Description U2 West Valve House Sample Identification 007 Sample Type Gamma Direct Sample Geometry Peak Locate Threshold 3 .00 Peak Locate Range (in channels) 85 - 8 1 92 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 4/21/2018 8:42:00 AM Acquisition Started 4/21/2018 8:43:16 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06  %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2 IN

[220]

Peak Analysis Report 4/21/20 1 8 8:53:17 AM Page 2

          • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B3062l6AFSWC007GD Peak Analysis Performed on: 4/21/2018 8:53:16 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 291 - 308 300.13 75.00 0.69 l.09E+002 61.11 2.53E+002 2 545 - 560 552.27 138. 1 0 0.68 4.47E+001 33.33 7.73E+001 3 1397 - 1414 1405. 2 5 351. 51 0.65 2.74E+001 22.4 1 2.96E+001 4 2 034- 2051 2042.58 510.92 0.42 9.00E+OOO 17.99 2 .20E+001 5 2425- 2442 2 433 . 86 608 . 75 0.93 2.64E+001 16.88 l.36E+001 6 2634 - 2651 2 642.45 66 0 .90 0.52 2 .54E+001 16.15 l.16E+001 7 3631- 3648 3639.50 910.12 0.38 9.50E+OOO 11.08 6.50E+OOO 8 5827- 5846 5836.35 1458.81 1.11 7.37E+001 18.07 2.35E+OOO 9 7043 - 7062 7052.99 1762.44 0.37 8.08E+OOO 10.45 4.92E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[221]

Inberference Corrected Activity Report 4/ 2 1/2018 8 :53: 17 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC007GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.994 1460.82* 10.66 l.03245E+006 2 .68653E+005 Cs-137 0.999 661.66* 85.10 2 .99599E+004 l.93544E+004 Bi- 2 14 0.705 609.32* 45.49 5.57981E+004 3 .62464E+ 0 04 1120.29 14.92 1 764.49* 15.30 8.88629E+004 l . 1518 3E+005 Pb- 2 14 0.437 295.22 18.42 351.93* 35.60 5.47773E+004 4 . 55582E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 .3 0 Errors quoted at 2.000 sigma

[222]

Interference Corrected Activity Report 4/21/2018 8 :53: 17 AM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.994 1.032455E+006 ,J.. 686527E+005 Cs-137 0.999 2.995994E+004 Vl. 935439E+004 Bi-214 0.705 5.877741E+004 3.457489E+004 Pb-214 0.437 5.477726E+004 4.555825E+004

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

@ = Nuclide contains energy lines not used i n Weighted Mean Activity Errors quoted at 2.000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 8:53:16 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.00 1.8152E-001 56.11 2 138.10 7.4471E-002 74.59 4 510.92 1. SOOOE-002 199.86 7 910.12 1.5833E - 002 116.61 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 s i gma

[223]

Nuclide MDA Report 4/21/ 2 018 8:53 :17 AM Page 5

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

Detector Name: 62 79 Sample Geometry:

Sample

Title:

B306216AFSWC007GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 l.679E+005 1.68E+005 )..032E+006 6.501E+004 Co-60 1173. 23 99.85 3.817E+004 3. 34E+004 V4. 136E+004 ,1""1. 728E+004 1332.49 99.98 3.340E+004 - 1.953E+004 1.478E+004 Nb-94 702.65 99.81 3.367E+004 2.99E+004 l.018E+004 1.543E+004 871.09 99.89 2.987E+004 -l .701E+004 1.338E+004 Ag- 108m 433.90 90.50 3.708E+004 3.71E+004 1.891E+0 04 1.7 3 4E+004 614.30 89.80 5.058E+004 6.378E+004 2.384E+004 722.90 90.80 3.711E+004 -1.308E+004 ~.699E+004 Cs-134 604.72 97.62 4.369E+004 3 . 94E+004 ./2. 812E+004 V2 . 052E+004 795.86 85.46 3.939E+004 3.209E+004 ,..J..795E+004

+ Cs-137 661.66* 85.10 2.762E+004 2 . 76E+004 ./ 2. 996E+004*/ 1. 221E+004 Eu-152 121. 78 2 8.67 1.941E+.00 5 1 .44E+005 - 6.317E+002 9.473E+004 344.28 2 6.60 1.559E+005 4.265E+004 7.436E+004 1408.01 2 1.07 1. 437E+005 1.040E+005 6.249E+004 Eu-154 123.07 40.40 1.366E+005 9.17E+004 6 . 435E+004 6.663E+004 723.30 2 0.06 1.699E+005 5.303E+004 7.790E+004 1274.43 34.80 9.174E+004 -4.626E+004 4.047E+004 Eu-155 86.55 30.70 2.448E+005 2.45E+005 1. 926E+004 1.200E+005 105 .31 21.10 2.884E+005 5.210E+004 1.410E+005 Tl- 208 583.19 85.00 3.822E+004 3.82E+004 7.180E+003 1.762E+004 Bi-212 727.33 6.67 5.182E+005 5.18E+005 -3.193E+005 2.378E+005 Pb-212 238.63 43.60 1.020E+005 1.02E+005 5.451E+004 4.920E+004

+ Bi-214 609.32* 45.49 5.217E+004 5.22E+004 5.580E+004 2 .323E+004 11 20 . 29 14.92 2 .637E+005 2.216E+005 1.201E+005 1764.49* 15.30 1.885E+005 8.886E+004 7.934E+004

+ Pb-214 295.22 18.4 2 1.977E+005 7.06E+004 1.249E+005 9.412E+004 351.93* 35.60 7.059E+004 5.478E+004 3.259E+004 Ra-226 186.21 3.64 1 .212E+006 1. 2 1E+006 5.095E+004 5.865E+005 Ac-228 338.32 11. 2 7 3.345E+005 1. 3 9E+005 1.708E+005 1.589E+005 911. 20 25.80 1. 3 94E+005 1.639E+005 6.355E+004 968.97 15.80 2 . 2 86E+005 1. 3 26E+005 1. 039E+005 Am- 24 1 59.54 35.90 2.840E+005 2 .84E+005 - 1.434E+005 1.390E+005

+=Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[224]

          • GAMM A S P E C T R U M ANALY S IS *****

Filename: 6279 Report Generated On 4/ 2 1/2018 1:26:25 PM Sample Title B306216AFSWC008GD ~ /

Sample Description U2 West Valve House Sample Identification 008 J Sample Type Gamma Direct Sample Geometry Peak Locate Threshold 3 . 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 MA 2

/

Sample Taken On 4/21/2018 1:15 :00 PM /

Acquisition Started 4/21/2018 1 :16 : 24 PM J Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06 % /

Energy Calibration Used Done On 12/ 2 8/2017 \/

R-f-Fi,-,i<=:>nf'"'y /"'::ilihr::it-inn TTc<:>rl non<=> On 2/1/2018 \./

Efficiency I D 3M90D CP 2 IN 'I/"'

t/-2J-tcf

~ )

[225]

Peak Analysis Report 4/ 2 1 /2018 1:26:25 PM Page 2

          • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B306216AFSWC008GD Peak Analysis Performed on: 4/21/2018 1: 2 6: 2 5 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start e nd centroid (keV) (keV) Area Uncert. Counts 1 293- 346 300.69 75.14 0.41 -2 .34E+00 2 169.94 9.60E+002 2 945- 962 953.49 238.49 0.39 - 1.14E+OOO 32.25 7.81E+001 3 1398 - 1415 1406.71 351.88 0.56 1.89E+001 21.93 3.llE+OOl 4 2426- 2443 2434.50 608.92 0.59 3.03E+001 17.07 1.17E+001 5 583 2 - 5851 5841.08 1459.99 1. 3 6 6.88E+001 17.45 2.23E+OOO 6 7047 - 7066 7056.35 1763.28 0.81 1.lOE+OOl 6.63 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[226]

Interference Corrected Activity Report 4/ 2 1/2018 1 :26: 25 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC008GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.999 1460.82* 10.66 9.64491E+005 2.58604E+005 Pb-212 1.000 238.63* 43.60 -1.51902E +003 4. 2 8637E+004 Bi-214 0.706 609.32* 45.49 6.40293E+004 3.68365E+004 1120.29 14.92 1764.49* 15.30 1.21059E+005 7.36426E+004 Pb-214 0.437 295.22 18.42 3 51.93* 35.60 3.77136E+004 4.42404E+004

  • = Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0.30 Errors quoted at 2 .000 sigma

[227]

Interference Corrected Activity Report 4/21/2018 1:26: 25 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity .Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 9.644915E+005 2.586040E+005 Pb-212 1. 000 - 1.519022E+003 4.286371E+004 Bi -2 14 0.706 7.544283E+004 3.294482E+004 Pb-214 0.437 3 . 771359E+004 4.424042E+004

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

@=Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

                    • U N I D E N T I F I E D PE AK S **********

Peak Locate Performed on: 4/21/2018 1: 26 : 25 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak *Tol.

No. (keV) Counts per Second  % Uricertainty Type Nuclide 1 75.14 -3.8943E - 001 - 72.73 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[228]

Nuclide MDA Report 4/21/2018 1: 2 6: 25 PM Page 5

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B3062 1 6AFSWC008GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib - BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2) (pCi/M"2) (pCi/M"2 )

+ K-40 1460.82* 10.66 l.627E+005 l.63E+005/"9.645E+00 5 6.240E+004 Co-6 0 1173.23 99.85 3.873E+004 3.69E+004 -l.541E+004 ~.756E+004 1332.49 99.98 3.689E+004 3.551E+004'./'l.652E+004 Nb- 94 702.65 99.81 3.550E+004 3.09E+004 3.736E+004 l.635E+004 871. 09 99.89 3.092E+004 7.189E+003 l.390E+004 Ag - 1 08m 433.90 90.50 3.455E+004 3.45E+004 -2.280E+004 l.608E+004 614.30 89.80 4.733E+004 2.591E+004 2.221E+004 722.90 90.80 3.795E+004 72.339E+004 l.741E+004 Cs - 134 604.72 97.62 4.293E+004 4.29E+004V 5.563E+003\/"2.014E+004 795.86 85.46 4.407E+004 -9.542E+003 /.2.030E+004 Cs - 137 661.66 85.10 4.156E+004 4.16E+004 8.734E+oo3./1.918E+004 Eu-152 121.78 28.67 l.948E+005 l.35E+005 3.363E+004 9.507E+004 344.28 26.60 l.538E+005 4.432E+004 7.333E+004 1408.01 21. 07 l.351E+005 l.560E+004 5.817E+004 Eu-154 123.07 40. 40 l.368E+005 l.02E+005 4.263E+004 6.675E+004 723.30 20.06 l.699E+005 - 2 .735E+005 7.790E+004 1274.43 34.80 l .018E+005 - 3.542E+004 4.548E+004 Eu-155 86.55 30.70 2.301E+005 2.30E+005 l. 915E+004 l.127E+005 1 05 . 3 1 21.10 2 . 795E+005 -l.476E+005 l.366E+005 Tl - 208 583.19 85.00 4.720E+004 4.72E+004 2.606E+004 2.211E+004 Bi-212 727.33 6.67 5.294E+005 5.29E+005 5.573E+004 2.434E+005

+ Pb-212 238.63* 43.60 7.426E+004 7.43E+004 -l.519E+003 3.533E+004

+ Bi-214 609.32* 45.49 5.097E+004 2.98E+004 6.403E+004 2.263E+004 1120.29 14.92 2.568E+005 2.879E+005 l .166E+005 1764.49* 15.30 2.978E+004 l. 2 11E+005 O.OOOE+OOO

+ Pb- 2 14 295.22 18.42 l.942E+005 7.17E+004 - 2.393E+004 9.233E+004 351.93* 35.60 7.170E+004 3.771E+004 3.314E+004 Ra-226 186.21 3.64 l.162E+006 l.16E+006 9.135E+005 5 . 617E+ ,0 05 Ac-228 338.32 11. 2 7 3.157E+005 l.32E+005 - l.776E+005 l.495E+005 911.20 25.80 l.321E+005 2.447E+004 5.991E+004 968.97 15.80 2.094E+005 - 1. 675E+005 9.431E+004 Am-241 59.54 35.90 2.713E+005 2.71E+005 9.859E+004 l. 326E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[229]

          • GAMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/ 2 0 /2 018 3 :04:04 PM Sample Title B306216AFSWC009GD Sample Description U2 WEST VALVE HOUSE Sample Identification 00 9 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3 .00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 4/20/2018 2:53:00 PM Acquisition Started 4/20/2018 2:54:02 PM Live Time 600.0 seconds Real Time 600 . 4 seconds Dead Time 0 .07 % / '

Energy Calibration Used Done On 12/28/2017 V Efficiency Calibration Used Done On 2/1/2018 \./

Efficiency ID 3M90D CP 2IN \./'°"

"iy,,~ \l1{,'~

yf /1; 1 C) ~ 3o

[230]

Peak Analysis Report 4/20/2018 3: 04 : 04 PM Page 2

          • P E A K ANALYSIS REPORT *****

Detector Name: 62 79 Sample

Title:

B306216AFSWC009GD Peak Analysis Performed on: 4/20/2018 3 :04:03 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 291 - 346 300.52 75 . 10 1. 09 l.06E+002 164.44 8.10E+002 2 947 - 964 955.49 238.99 0. 3 0 l.63E+001 31 . 75 7.07E+001 M 3 1128- 1189 1136.92 284.39 0.66 7.0lE+OOO 2 8.60 1.85E+001 m 4 1128 - 11 89 1181. 28 295.48 0.66 l.OlE+OOl 41. 39 2.17E+001 5 1400 - 1 417 14 0 8.67 352.37 0.81 3.87E+001 19.49 1.73E+001 6 2034 - 2051 2042 . 76 510.96 0.35 4.22E+001 16 . 07 6.80E+OOO 7 2325 - 2342 2333.52 583.67 0.77 l.28E+001 19.45 2.42E+001 8 2429 - 2446 2437.74 609.72 0.38 3.90E+001 17 . 2 9 1.lOE+OOl 9 2638 - 2655 2646.09 661. 82 0.38 2.70E+001 13.43 4.95E+OOO 10 3639- 3656 3647.41 912.09 0.31 1.16E+001 11.40 6 .44E+OOO 11 3868 - 3885 3876 . 95 969.45 0.35 l .74E +001 11. 63 4.64E+OOO 12 5838- 5857 5847.61 1461. 62 1. 54 9.54E +001 20.46 2 .57E+OOO 13 7 0 54- 7073 7063.86 1765.15 0.63 2.lOE+ OOl 9 .17 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[231]

Interference Corrected Activity Report 4 /20/2018 3 : 04: 04 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC009GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB

....... . ...... . ... . . IDENTIFIED NUCLIDES . . ... ...............

Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) ( %) (pCi/M ... 2 ) Uncertainty K-40 0.999 1460.82* 10.66 l .33926E+006 3.09862E+005 Cs- 1 37 1. 000 661.66* 85.10 3 .18677E+004 1.62833E+004 Tl-208 1.000 583.19* 85.00 l.41350E+004 2.15573E+004 Pb-212 1.000 238.63* 4 3 .60 2 .17478E+004 4.23944E+004 Bi-214 0.706 609.32* 45.49 8. 23 168E+004 3.78298E+004 112 0 .29 14.92 1764.49* 15.30 2.31268E+005 1. 02619E+005 Pb- 2 14 1. 000 295 . 22* 18. 4 2 3.56212E+ 004 1.45384E+005 351.93* 35.60 7.74094E +004 4 . 06973E+004 Ac-228 0.581 338.32 11. 27 911.20* 25.80 5.26338E+004 5.21755E+004 968.97* 15.80 1.33060E+005 8.99846E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = o* . 3 0 Errors quoted at 2 .000 sigma

[232]

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          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 1. 339259E+006 _/ 3. 098622E+005 Cs-137 1. 000 3.186766E+004 V 1 .628329E+004 Tl-208 1.000 1.413495E+004 2.155731E+004 Pb-212 1.000 2.174781E+004 4.239443E+004 Bi-214 0.706 1.001372E+005 3 . 549480E+004 Pb-214 1. 000 7.4 3 7285E+004 3.919077E+004 Ac-228 0.581 7 . 286970E+004 4 .513683E+004

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

@ = Nuclide contains energy lines not used i n Weighted Mean Activity Errors quoted at 2.000 sigma

[233]

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                    • UN I D E N T I F I E D PE AK S **********

Peak Locate Performed on: 4/20/2018 3 :04:03 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. {keV) Counts per Second  % Uncertainty Type Nuclide 1 75.1 0 1.7712E-001 154.73 M 3 284.39 1. 1686E-002 407.92 6 510.96 7.0332E-002 38.07 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[234]

Nuclide MDA Report 4/20/2018 3:04:04 PM Page 6

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B306216AFSWC009GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA 2 ) (pCi/M"2 ) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 1.786E+005 1. 79E+005 / 1 .339E+006 7.030E+004 Co-60 1173 . 23 99.85 3.761E+004 3.55E+004 V- 6.026E+004 1.700E+004 1332.49 99.98 3.554E+004 a.-oo e,o / - 1. 847E+004 1. 5 85E+004 Nb - 94 702.65 99.81 3.478E+004 3.48E+004 4.559E+004 1.599E+004 871. 09 99.89 3.738E+004 2. 329E+004 1.713E+004 Ag-108rn 433.90 90.50 4.013E+004 4.01E+004 2 .605E+004 1.887E+004 614.30 89.80 4 .899E+004 - 1.410E+004 2 . 304E+004 722.90 90.80 4.298E+004 1.419E+00 4 1.993E+004 Cs-134 604.72 97 . 6 2 4.567E+004 4 . 32 E+00 4 .j 3. 6 05E+O 04 ./ 2 . 151E+004 795.86 85.46 4.318E+004 - 2.356E+004 1.985E+004

+ Cs-137 661.66* 85.10 1.966E+004 1.97E+004 / 3.187E+004 8.238E+003 Eu-152 1 21.78 28.67 1.999E+005 1. 52 E+005 1.01SE+00 5 9.763E+004 344.28 26.60 1.672E+OOS - 3 .233E+004 8.000E+004 1408.01 21. 07 1 .5 18E+005 - 8.771E+003 6.652E+004 Eu - 154 123.07 40.40 1.420E+005 9.98E+004 1 .512E+005 6.934E+004 723.30 20.06 1. 929E+005 6.319E+003 8.940E+004 1274.43 34.80 9.985E+004 4.819E+004 4.453E+004 Eu-155 86.55 30.70 2.577E+005 2.58E+OOS 1.391E+005 1.265E+005 1 0 5 .31 21.10 3.028E+005 1 . 2 7 6E+005 1 .482E+005

+ Tl-208 583.19* 85.00 3.586E+004 3.59E+004 l.413E+004 1.644Et004 Bi-212 727.33 6 . 67 5.718E+005 5.72E+OOS -3. 3 48E+005 2 .646E+005

+ Pb-212 23 8.63* 43.60 7.081E+004 7.08E+004 2.175E+004 3 .360E+004

+ Bi-214 609.32* 45.49 4.726E+004 2.98E+004 8.232E+004 2 . 077E+004 1120.29 1 4.92 2.705E+005 1.396E+005 1.234E+005 1764.49* 15.30 2 .980E+004 2.313E+005 O.OOOE+OOO

+ Pb- 2 14 295.22* 18.42 8.556E+004 5.48E+004 3.562E+004 3.803E+004 351.93* 35.60 5.483E+004 7.741E+004 2.471E+004 Ra-226 186.21 3.64 1.307E+006 1.31E+00 6 6.737E+005 6.341E+005

+ Ac-228 338 . 32 11. 27 3.522E+005 8.09E+004 1.177E+005 1.677E+005 9 11 .20* 25 .80 8.089E+004 5.263E+004 3 .428E+004 968.97* 15.80 1 .230E+005 1.331E+005 5.115E+004 Am- 241 59.54 35.90 2 .702E+005 2 .70E+OOS 2 .197E+005 1. 32 1E+OOS

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[235]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/ 2 1/2018 1:10:53 PM Sample Title B306216AFSWC010GD v Sample Description U2 West Valve House v Sample Sample Identification Type 010 Gamma Direct v

Sample Geometry Peak Locate Threshold 3 .00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M;.. 2 Sample Taken On 4/21/2018 12:59: 00 PM V Acquisition Started 4/21/ 2 018 1:00:52 PM v Live Time 6 00.0 seconds Real Time 60 0. 4 seconds Dead Time 0.06 %

Energy Calibration Used Done On 12/28/2 017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2 IN 1> c.tJ-,- Vt.DMd 1 /i7/ii

[236]

Peak Analysis Report 4/ 2 1/ 2 018 1:10:53 PM Page 2

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

Detector Name: 6279 Sample

Title:

B306216AFSWC010GD Peak Analysis Performed on: 4/21/2018 1:10: 53 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts M 1 2 85- 351 298.52 74.60 4.13 1.82E+002 46.51 4.06E+002 m 2 2 85- 351 338.89 84.70 4.14 1.65E+002 41.16 3.86E+002 3 736- 751 743 . 19 185.88 0. 39 1. 43E+001 30.33 7.17E+001 4 945- 962 953 . 32 2 38.45 0 .59 3.72E+001 28.55 4.98E+001 5 1170- 1187 1 178.34 2 94.75 0 .67 2.46E+001 22.28 3.04E+001 6 1397- 1414 1405.80 3 51. 65 0. 45 3.44E+001 18.52 1.56E+001 7 4465- 4484 4474.53 1118.74 0. 33 7.60E+OOO 14. 31 1.24E+001 8 5827 - 5846 5836.63 1458.88 2 .0 5 7. 3 0E+001 17.09 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma

[237]

Interference Corrected Activity Report 4/21/2018 1:10:53 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC010GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

. . . .. .. . .. . . . .. . . . . . IDENTIFIED NUCLIDES .................. ..

Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) (%) (pCi/MA 2 ) Uncertainty K-40 0.994 1460.82* 10.66 1.02331E+006 2 .55489E+005 Eu-155 0.330 86.55* 30.70 2.92065E+005 9.35545E+004 105.31 21.10 Pb-212 1. 000 238.63* 43.60 4.95022E+004 3.87788E+004 Pb -2 14 1.000 295.22* 18.42 8.60677E+004 7.93082E+004 351. 93* 35.60 6.88299E+004 3.845 2 8E+004 Ra-226 1.000 1 86.21* 3.64 2.02718E+005 4.32745E+005

  • =Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2.000 sigma

[238]

Interference Corrected Activity Report 4/21/2018 1:10:53 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.994 1. 023309E+006 2 .554894E+005 Eu-155 0.330 2 .920648E+005 9.355447E+004 Pb-212 1 .000 4.950219E+004 3.877876E+004 Pb-214 1. 000 7.211092E+004 3.460030E+004 Ra-226 1. 000 2.027179E+005 4.327447E+005

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D PE AK S **********

Peak Locate Performed on: 4/21/2018 1:10:5 3 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide M 1 74.60 3.0313E-001 25.58 7 1118.74 1.2667E-002 188.25 Tol. Bi-214 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[239]

Nuclide MDA Report 4/21/2018 1: 1 0:53 PM Page 5

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B306216AFSWC010GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M ... 2 ) (pCi/M ... 2 ) (pCi/M ... 2 ) (pCi/M ... 2 )

+ K-40 1460.82* 10.66 3.793E+004 3.79E+004 1.023E+00 6 O.OOOE+OOO Co-60 1173.23 99.85 3.927E+004 3.27E+004 V!.501E+004 / l.783E+004 133 2 .49 99.98 3.265E+004 1.419E+004 1.440E+004 Nb - 94 702.65 99.81 3.550E+004 3 .14E+004 3 .685E+004 1.635E+004 871.09 99.89 3.143E+004 - 3 .685E+004 1.416E+004 Ag - 108m 433.90 90.50 4.167E+004 3 .75E+004 3 .664E+004 1.964E+004 614.30 89.80 3 .7 53 E+004 2.694E+004 1.731E+004 722.90 90.80 4.074E+004 -).667E+003/:i.881E+004 Cs - 134 604.72 97.62 3.708E+004 3.71E+004v'3.602E+004 1. 72 1E+004 795.86 85.46 4.273E+004 - l.608E+003 J. 96 2E+004 Cs - 137 661.66 85.10 4.077E+004 4.08E+004 8. 3 16E+003.../1.879E+004 Eu-152 121.78 28.67 1.946E+005 1. 40E+OOS -4.458E+004 9.498E+004 344.28 26.60 1.431E+005 - 4.868E+003 6.797E+004 1408.01 21.07 1. 3 95E+OOS - 8.843E+004 6.037E+004 Eu-154 123 .0 7 40.40 1. 372E+005 8.74E+004 3.919E+004 6.693E+004 723.30 20.06 1.862E+005 - l.425E+004 8.602E+004 1274.43 34.80 8.736E+004 l .479E+004 3 . 828E+004

+ Eu-155 86 . 55* 30 . 70 1 .671E+005 1.67E+005 2.921E+005 8.115E+004 105.31 21.10 2 .865E+005 -1 .308E+OOS 1.401E+005 Tl-208 583.19 85.00 4 .313E+004 4.31E+004 l.068E+004 2.007E+004 Bi-212 727.33 6.67 5.667E+OOS 5.67E+005 l.498E+005 2.620E+005

+ Pb-212 238.63* 43.60 6.002E+004 6.00E+004 4.950E+004 2.821E+004 Bi-214 609.32 45.49 7.924E+004 7. 92 E+004 -2 .867E+004 3.676E+004 1120.29 14.92 2.989E+005 2 .116E+OOS l.376E+OOS 1764.49 15. 3 0 2. 471E+005 l.982E+005 1 .087E+OOS

+ Pb - 214 295.22* 18.42 1. 2 46E+005 5.26E+004 8.607E+004 5.754E+004 351.93* 35.60 5. 2 57E+004 6.883E+004 2.358E+004

+ Ra-226 186.21* 3.64 7. 2 57E+005 7.26E+00 5 2 .027E+005 3.436E+005 Ac-228 338.32 11. 27 2 . 896E+005 1.50E+005 -1.079E+005 1.365E+005 911. 20 25.80 1.496E+OOS 5.436E+004 6.864E+004 968.97 15.80 1. 990E+005 l.200E+005 8.912E+004 Am-241 59.54 35.90 2.850E+005 2 .85E+OOS 3.850E+005 l.395E+OOS

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[240]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/21/2018 10:34:31 AM Sample Title B306216AFSWC011GD Sample Description U2 West Valve House Sample Identification 011 Sample Type Gamma Direct Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 4/21/2018 10:24:00 AM Acquisition Started 4/21/2018 10:24:30 AM Live Time 600.0 seconds Real Time 600.3 seconds Dead Time 0 .06 %

Energy Calibration Used Done* On 12/28/2 017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN LM~Jl;i 7 JJJ y /,~ /1<,3 (~:;

(__) ,l l

[241]

Peak Analysis Report 4/21/2018 10:34: 3 1 AM Page 2

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

Detector Name: 62 79 Sample

Title:

B306216AFSWC011GD Peak Analysis Performed on: 4/21/2018 10:34:31 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 284- 318 300.13 75.00 1. 34 2.11E+002 97.07 4.00E+002 2 945- 962 953.9 0 238.60 0.49 2.47E+001 29.28 5 .83E+001 3 1122 - 1139 1130.59 282.80 0.31 1.62E+001 20.36 2 .68E+001 4 1398 - 1415 1406 . 7 0 351.87 1. 00 4.14E+001 18.59 1.36E+001 5 2323 - 234 0 233 1. 12 583.07 1.13 2.05E+ 001 11.86 4.50E+OOO 6 2427 - 2 444 2 435.54 609.18 0.59 3.13E+001 14.59 6.72E+OOO 7 3635 - 3652 3643.17 911. 0 3 0.36 1.35E+001 11.75 6.47E+OOO 8 583 3- 5852 5842.84 1460.43 1. 22 6.21E+001 17.81 4.87E+OOO M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[242]

Interference Corrected Activity Report 4/21/2018 10:34:31 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC011GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. .. . . . . . . . . . . .. . . . .. IDENTIFIED NUCLIDES .....................

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1. 000 1460.82* 10.66 8.71578E+OOS 2 .60994E+OOS Tl- 2 08 1.000 583.19* 85.00 2 . 2 6426E+004 1. 33757E+004 Pb-212 1.000 238.63* 43.60 3 . 2 8033E+004 3.92851E+004 Bi-214 0.442 609.32* 45.49 6.60345E+004 3.18120E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.437 295.22 18.4 2 351.93* 35.60 8 . 27748E +004 3 .92037E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2 .000 sigma

[243]

Interference Corrected Activity Report 4/21/2018 10:34 : 31 AM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 8.715779E+OOS 2 .609940E+005 Tl - 2 08 1. 000 2.264263E+004 1.337574E+004 Pb-212 1. 000 3.280329E+004 3.928509E+004 Bi-214 0.44 2 6.603449E+004 3.181205E+004 Pb-214 0.4 3 7 8.277479E+004 3.920374E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

                    • U N I D E N T I F I E D P EAKS **********

Peak Locate Performed on: 4/21/2018 10:34:31 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75 .00 3.5241E-001 45.91 3 2 82.80 2.6938E - 002 125 . 98 7 911.03 2.2542E-002 86.89 Tol. Ac-22 8 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[244]

Nuclide MDA Report 4/21/2018 10:34:3 1 AM Page 5

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B3062 1 6AFSWC011GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 2 . 290E+005 2.29E+005 8 . 716E+005 fa .552E+004 Co-60 1173.23 99.85 3.646E+004 3.27E+0041/"2.170E+004 'Vl .642E+004 1332.49 99.98 3 .265E+004 -9.346E+002 l.440E+004 Nb-94 702.65 99.81 3.888E+004 3.52E+004 4.863E+004 1.804E+004 871.09 99.89 3.522E+004 2.864E+004 1.606E+004 Ag- 1 08m 433.90 90.50 4.188E+004 3 .00E+004 - 3.190E+004 l.974E+004 614.30 89.80 4 . 289E+004 3.327E+004 1.999E+004 722.90 90.80 2.999E+004 -3.041E+004 .,.a_.343E+004 Cs - 134 604.72 97.6 2 4.053E+004 3.79E+004./ 4.194E+004Vl.894E+004 795.86 85.46 3.786E+004 -9.092E+003 1.719E+004 Cs - 137 661.66 85.10 3.562E+004 3.56E+oo4v"' 4.123E+004~1.621E+004 Eu-152 12 1. 78 28.67 1.991E+005 1 .SlE+OOS 6.505E+004 9.722E+004 344.28 26.60 1.507E+OOS 7.670E+004 7.176E+004 1408 . 01 2 1. 07 l.557E+OOS 1. 2 48E+OOS 6.845E+004 Eu- 154 123.07 40.40 1.410E+OOS 8.27E+004 -4.645E+00 4 6.888E+004 723.30 20.06 1. 3 58E+OO S -1.925E+OOS 6.083E+004 1274.43 34.80 8.271E+004 5.986E+004 3.596E+004 Eu- 155 86 . 55 30.70 2.460E+005 2.46E+005 3.553E+OOS 1.206E+OOS 10 5.3 1 21.10 2.950E+OOS -2.521E+005 1.443E+005

+ Tl -208 583. 1 9* 85.00 l.690E+004 l.69E+004 2.264E+004 6.953E+00 3 Bi-212 727.33 6.67 4.446E+005 4.45E+OOS 3.201E+005 2.009E+OOS

+ Pb-212 238.63* 43.60 6.383E+004 6. 3 8E+004 3.280E+004 3.012E+004

+ Bi-214 609.3 2

  • 45.49 3.825E+004 3.83E+004 6.603E+004 1 .627E+004 1120 . 29 14. 92 2 .266E+005 -1.519E+005 1 .015E+OOS 1764.49 15.30 2 .215E+005 1.541E+005 9.584E+004

+ Pb-214 295.22 1 8.42 l .998E+OOS 4.96E+004 5. 365E+003 9.517E+004 351.93* 35.60 4.958E+004 8.277E+004 2.209E+004 Ra-226 1 86.2 1 3.64 1.152E+006 1.15E+006 1.278E+OOS S.568E+005 Ac-228 338.32 11. 2 7 3 .143E+OOS l.41E+005 -1.550E+005 1.488E+005 91 1. 20 25.80 1. 412E+005 1.198E+005 6.442E+004 968.97 15.80 2 .462E+OOS 1.436E+005 1.127E+005 Am-241 59.54 35.90 2 . 765E+005 2 .77E+005 6.017E+004 1.352E+005

+=Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[245]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 62 79 Report Generated On 4/21/2018 12:55:00 PM Sample Title B306216AFSWC012GD Sample Description U2 West Valve House Sample Identification 012 Sample Type Gamma Direct Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 M" 2 Sample Taken On 4/21/2018 12: 4 3:00 PM Acquisition Started 4/21/2018 12:44:59 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 06 %

Energy Calibration Used Done On 12/28/2011 v Efficiency Calibration Used Done On Eff i c i enc y ID 2111201s 3M90D CP 2 IN v/

V

~Vc~,dtfd

~ / 2:/t'i5 aqtf 1////J

[246]

Peak Analysis Report 4 / 2 1/2018 12:55:00 PM Page 2

          • P E A K A N A L Y S I S REPORT *****

Detector Name: 62 7 9 Sample

Title:

B3 0 6216AFSWC012GD Peak Analysis Performed on: 4/21/2018 12:55:00 PM Peak Analysis From Channel : 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 121 - 136 128 . 65 32.08 0. 3 9 l.22E+001 27.70 5 .98E+001 2 2 92- 347 299 . 84 74.93 0.70 -2.26E+002 183 . 73 l.08E+00 3 3 944 - 961 952.67 238.29 0.53 -l.32E+001 34.59 9.02E+001 4 1171- 1188 1180.00 295.16 0.77 l.80E+001 23.55 3.60E+001 5 1309- 1326 13 1 7 . 84 329 . 65 1.42 2.59E+001 15.73 l.llE+OOl 6 1397 - 1414 1405.29 351 . 52 1.13 3.53E+00 1 22 .10 2 .67E+001 7 203 0 - 2047 2038.61 509.92 0.98 3.17E+001 17.46 l.33E+001 8 2321 - 2338 2329.26 582.60 0.66 4.12E+OOO 18.67 2.49E+001 9 2425 - 2442 2433 . 01 608.54 1. 07 3.76E+001 18.75 l.54E+001 10 2635 - 2652 2643.56 661.18 0 . 63 2 .60E+001 15.85 l.lOE+OOl 11 3542 - 3559 3550.78 887.95 0.25 7.79E +OOO 9.58 4. 2 1E+OOO 12 4467- 4486 4476. 32 111 9.19 0.62 2.05E +001 13.68 7.46E+OOO 13 5827- 5846 5836.71 1458.90 0.65 6. 2 0E+001 17.83 5.00E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma

[247]

Interference Corrected Activity Report 4/21/2018 12:55:00 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC012GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

.. .... . . .. . . . . . . . . . . IDENTIFIED NUCLIDES . ... ........... ... . .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) uncertainty K-40 0.994 1460.82* 10.66 8.69120E+00 5 2 . 61131E+005 Cs-137 1. 000 661.66* 85.10 3.05872E+004 1. 90218E+004 Tl-208 0.999 58 3 .19* 85.00 4.54949E+003 2 .06150E+004 Pb- 2 12 1.000 238.63* 43.60 -1.74783E+004 4.60373E+004 Bi - 2 14 0.734 609.32* 45.49 7.93709E+004 4.06951E+004 112 0 .29* 14.92 1.79061E+005 1. 2 0178E+005 1764.49 15.30 Pb-214 1.000 295.22* 18 .4 2 6.32357E +004 8.32 2 05E+004 351.93* 35.60 7.05663E +004 4.54373E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0. 3 0 Errors quoted at 2. 000 sigma

[248]

Interference Corrected Activity Report 4/21/2018 12:55:00 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.994 8.691195E+005 _/2. 611315E+005 Cs-137 1. 000 3.058716E+004 V 1.902185E+004 Tl-208 0.999 4.549488E+003 2.061502E+004 Pb-212 1. 000 - 1 .747833E+004 4.603731E+004 Bi -2 14 0.734 8.962603E+004 3.854514E+004 Pb-214 1.000 6.888287E+004 3.988031E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

[249]

  • Interference Corrected Activity Report 4 /21/2018 12:55:00 PM Page 5
                    • U N I D E N T I F I E D PE AK S **********

Peak Locate Performed on: 4/21/2018 12:55:00 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.08 2 .0289E - 00 2 22 7.53 2 74.93 -3.7673E-001 -81.28 5 32 9.65 4.3209E-002 60.67 Tol. Ac-228 7 509.92 5.2907E-002 55.00 11 887.95 1. 2986E-002 123.02 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[250]

Nuclide MDA Report 4 /2 1/2 018 12:55 :00 PM Page 6

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B3062 1 6AFSWC012GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nucl ide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/M"' 2 ) (pCi/M"'2 )

+ K-4 0 1460.82* 10 .-66 2.309E+005 2.31E+005 /9.691E+005 9.648E+004 Co-60 1173.23 99.85 3.704E+004 3.11E+004V9.661E+003 )..671E+004 1332.49 99.98 3.110E+004 3.969E+003./1.363E+004 Nb- 94 702.65 99.81 3.050E+004 3.05E+004 - 5.738E+003 1.385E+004 871. 09 99.89 3.477E+004 3.138E+003 1.583E+004 Ag- 1 08m 433.90 90.50 4.315E+004 3.88E+004 5.284E+004 2 .0 3 8E+004 614.30 89.80 5.111E+004 3.464E+004 2.410E+004 722.90 90.80 3.877E+004 2.885E+004 ~.782E+004 Cs-134 604 . 72 97.62 4 . 803E+004 4.18E+Oo4v"3 . 749E+004~2.269E+004 795.86 85.46 4.180E+004 p2.605E+004 l.916E+004

+ Cs-137 661.66* 85.10 2.670E+004 2.67E+004'{ 3 .059E+004 l.175E+004 Eu-152 121. 78 28.67 l.916E+005 l.48E+005 1.770E+004 9.346E+004 344. 2 8 26.60 1.584E+005 - 1.626E+004 7 . 562E+004 1408.0 1 21.07 l.478E+005 l.110E+005 6.454E+004 Eu-154 123.07 40 .40 1.349E+005 l.05E+005 2.488E+00 4 6.578E+004 723.30 20.06 1.774E+005 1.841E+005 8 . 161E+004 1274.43 34.80 1.055E+005 l . 696E+004 4.734E+004 Eu-155 86.55 30.70 2 .570E+OOS 2.57E+005 8.690E+004 l.261E+005 105.31 2 1 .10 2.830E+005 -2 .996E+005 1 . 383E+005

+ Tl- 2 0 8 583.19* 85.00 3 . 608E+004 3 .61E+004 4.549E+003 1. 654E+004 Bi-212 727.33 6.67 5. 23 8E+005 5.24E+005 3 .691E+005 2.406E+005

+ Pb-212 238.63* 43.60 8.083E+004 8.08E+004 -1.748E+004 3.862E+004

+ Bi-2 14 609.32* 45 .49 5.493E+004 5 . 49E+004 7.937E+004 2.461E+004 1120.29* 14.92 1.707E+005 l.791E+005 7.353E+004 1764.49 15.30 2.410E+005 l.872E+005 1.056E+005

+ Pb-214 295.22* 18.42 1.362E+005 6.67E+004 6. 3 24E+004 6.337E+004 351.93* 35.60 6.671E+004 7 . 057E+004 3.065E+004 Ra-226 186.21 3.64 1.230E+006 l.23E+006 - 8.236E+005 5.958E+005 Ac-228 338.32 11. 27 3.371E+005 1.48E+005 2.331E+005 l.602E+005 911.20 25.80 1. 480E+005 - 5.000E+004 6.782E+004 968.97 15.80 2.625E+00 5 l.204E+005 1 .209E+005 Am-24 1 59.54 35.90 2.630E+005 2.63E+005 1.905E+005 l.285E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[251]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/ 2 0/2018 3: 20: 31 PM Sample Title B306216AFSWC013GD ./

Sample Description U2 WEST VALVE HOUSE Sample Identification 013 Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 1 0.000 keV Sample Size 2 .830E+001 M" 2 /

Sample Taken On 4/20/2018 3 :00:00 PM Acquisition Started 4/20/2018 3:1 0:30 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06 % ./

Energy Calibration Used Done On 12/28/2017 v Efficiency Calibration Used Done On 2/1/2018 ./

Efficiency ID 3M90D CP 2IN .,/

[252]

Peak Analysis Report 4/20/2018 3: 20: 31 PM Page 2

          • PE AK A N A L Y S I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306216AFSWC013GD Peak Analysis Performed on: 4/20/2018 3:20:31 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 292- 308 300.70 75.14 0.74 6.06E+001 57.52 2.44E+002 2 946- 963 954.64 238.78 0.63 1.70E+001 31. 55 7.00E+OOl 3 1172- 1189 1180.42 295.27 0.53 2.16E+001 23.39 3 .44E+001 4 1399- 1416 1407.34 352.03 0.77 5.03E+001 22.36 2 .27E+001 5 2324 - 2341 2332.17 583.33 1. 91 1.91E+001 12.99 6.90E+OOO 6 2430- 2447 2438.02 6 0 9.80 0.37 3.57E+001 15.74 7.26E+OOO 7 2637 - 2654 2645.57 661.68 0.53 1.26E+001 14.93 1.14E+001 8 4474 - 4493 4483 . 05 1120.87 0.33 2 .40E+001 9.80 O.OOE+OOO 9 5838 - 5857 5847.38 1461.56 1. 85 6.30E+001 17.95 5.00E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 00 0 sigma

[253]

Interference Corrected Activity Report 4/20/2018 3 : 2 0 : 31 PM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC013GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (% ) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 1 0.66 8.84153E+005 2 .63418E+005 Cs-137 1.000 661.66* 85.10 l.48983E+004 1.76832E+004 Tl-208 1.000 583.19* 85.00 2.10970E+004 1.45753E+004 Pb-212 1. 000 238.63* 43.60 2 . 26246E+004 4 . 21195E+004 Bi -2 14 0.735 609.32* 45.49 7 . 55075E +004 3 .44568E+004 1120.29* 14.92 2 . 09426E +005 8.71282E+004 1 764.49 15.30 Pb- 2 14 1.000 295.22* 18.42 7.57107E+004 8.29518E+004 351.93* 35.60 1.00650E+005 4.72138E+004

  • = Energy l ine found in t he spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

[254]

Interference Corrected Activity Report 4/20/2018 3 :20: 31 PM Page 4

          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 8.841531E+OOS 2.634184E+OOS Cs-137 1. 000 1. 489827E+004 / 1. 768321E+004 ._/

Tl-208 1. 000 2.109697E+004 l.457526E+004 Pb-212 1. 000 2.262461E+004 4.211951E+004 Bi-214 0 . 735 9.361958E+004 3.204213E+004 Pb-214 1. 000 9.454782E+004 4. 1 03288E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

[255]

Interference Corrected Activity Report 4/20/2018 3 :20: 3 1 PM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/20/2018 3 : 2 0: 31 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.14 l.0107E-001 94.84 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[256]

Nucl ide MDA Report 4/20/2018 3 : 2 0:31 PM Page 6

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B3 062 1 6AFSWC013GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) {%) {pCi/M"'2 ) (pCi/M"'2) (pCi/M"'2) (pCi/M"'2 )

+ K-40 1460. 82

  • 10.66 2.316E+005 2.3 2E+OOS ~ .842E+00 5 9.684E+004 Co-6 0 1173. 23 99.85 3.761E+004 3.4 1 E+004 - 5 . 848E+003 / 1.700E+004 1332.49 99 . 98 3.413E+004 2 . 9 83E+004v l.514E+004 Nb - 94 702.65 99.8 1 3.823E+004 3.52E+004 1.104E+004 l.771E+004 871. 09 99.89 3.522E+004 - l. 5 82E+004 1.606E+004 Ag-108m 4 33 .90 90.50 3 .990E+004 3.96E+004 l. 9 51E+004 l.875E+004 614.3 0 89.80 4.871E+004 5 .457E+004 2.290E+004 722.90 90.80 3.957E+004 1.675E+004 1.822E+004 Cs-134 604.72 97.62 4.108E+004 4.11E+004 ./2.067E+003 ,/' 1.921E+004 795.86 85.46 4.180E+004 -2 .408E+003 l.916E+004

+ Cs-137 661.66* 85.10 2 . 863E+004 2 .86E+004 ./ l.490E+004 1.272E+004 Eu-152 121.78 28.67 1. 878E+005 l.44E+005 8.037E+00 4 9.156E+004 344.28 26.60 1.599E+005 l.636E+004 7.637E+004 1408.01 21. 07 l .437E+005 4 . 103E+004 6.249E+004 Eu-154 123.07 40 . 40 1. 311E+OOS 9.59E+004 3 .676E+00 4 6.393E+004 723.30 20.06 1.774E+005 -1.475E+OOS 8 . 161E+004 1274.43 34.80 9.589E+004 3 .349E+004 4.255E+004 Eu-155 86.55 30.70 2.299E+OOS 2 . 3 0E+005 2 . 861E+004 1.126E+005 105.31 2 1 .10 2.660E+005 2 .130E+003 l.298E+005

+ Tl- 2 08 583.19* 85.00 2.046E+004 2.05E+004 2 . 110E+004 8.735E+003 Bi- 2 12 727.33 6.67 5.349E+005 5.35E+005 6 . 3 87E+004 2 . 461E+OOS

+ Pb-212 238.63* 43.60 7.022E+004 7.02E+004 2 . 2 62E+004 3.331E+004

+ Bi-214 609.32* 45.49 4.126E+004 2.36E+004 7. 5 51E+00 4 1 . 777E+004 1120.29* 14.92 2.361E+004 2.094E+005 O.OOOE+OOO 1764.49 15.30 2.471E+005 8.166E+004 1.087E+OOS

+ Pb-214 295.22* 18.42 l.334E+OOS 6.23E+004 7.571E+004 6.194E+004 351.93* 35.60 6.232E+004 l . 007E+OOS 2. 845E+004 Ra-226 186.21 3.64 l.239E+006 1.24E+006 6.772E+005 6.004E+005 Ac-228 338.32 11. 2 7 3.318E+OOS l.50E+OOS 5.788E+004 l.576E+OOS 911.20 25 . 80 1 . 496E+005 1.424E+005 6.864E+004 968.97 15.80 2.433E+005 - 3 .227E+004 1.113E+005 Am-241 59.54 35 . 90 2.333E+005 2.33E+005 7 . 654E+004 l.136E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[257]

          • GAMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/21/2018 10:18:45 AM v

Sample Title B306216AFSWC014GD Sample Description U2 West Valve House Sample Identification 014 Sample Type Gamma Direct Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 v Sample Taken On 4/21/2018 10:09:00 AM v

Acquisition Started 4/21/2018 10:08:43 AM v Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06 % /

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN 1)~ v~t r'Jq-cJ 1/z/;2 0 <ii)

J{l

[258]

Peak Analysis Report 4/2 1 /2018 1 0 :18:45 AM Page 2

          • P E A K A N A L Y S I S REPORT *****

Detector Name : 6279 Sample

Title:

B306216AFSWC014GD Peak Analysis Performed on: 4/21/2018 10:18:44 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start e nd centroid (keV) (keV) Area Uncert. Counts 1 121- 136 128.12 31. 95 0.48 l.95E+001 23.55 3.95E+001 2 284 - 347 298.39 74.57 0 . 93 2.25E+002 161.79 6.99E+002 3 1170 - 1 187 1178.88 294.88 0.52 3.13E+001 23.73 3.37E+001 4 1398- 1415 1406.52 351.83 0.57 3.58E+001 22.01 2.52E+001 5 2 0 33- 2050 2041.70 510.69 0.28 2.46E +001 16.78 1.34E+001 6 2322 - 2339 2330.52 582.92 0.51 1.16E+001 14. 94 1 .34E+001 7 2426- 2443 2434.73 608.97 1.13 3.83E+001 18.34 1.38E+001 8 3634- 3651 3642.98 910.98 0.27 1 .59E+001 9.57 2 .14E+OOO 9 5832 - 5853 5841.86 1460.18 0.86 9.50E+001 19.49 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma

[259]

Interference Corrected Activity Report 4/21/2018 10:18:45 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306 2 16AFSWC014GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) ( %) {pCi/MA 2 ) Uncertainty K-40 0.999 1460.82* 10.66 1. 3 3245E+006 2.96888E+005 Tl -2 08 1.000 583.19* 85.00 1. 2 8107E+004 1.65712E+004 Bi -2 14 0.442 609.32* 45 . 49 8.07443E+004 3.99097E+004 112 0 .29 14.92 1764.49 15.30 Pb- 2 14 1.000 295 . 22* 18.42 1 . 098 3 2E +005 8. 5 0322E+004 351.93* 35.6 0 7.17006E +004 4.53151E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0. 3 0 Errors quoted at 2 .000 sigma

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          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.999 1.332454E+006 2.968885E+005 Tl -208 1. 000 1.281071E+004 l .657123E+004 Bi-214 0 . 442 8.074426E+004 3.990966E+004 Pb-214 1. 000 8.013450E+004 3.999079E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 10:18:44 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 31. 95 3.2556E-002 120.57 2 74.57 3.7569E-001 71. 78 5 510.69 4.0965E - 002 68.25 8 910.98 2.6435E-002 60.36 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[261]

Nucl ide MDA Report 4 /2 1/2 018 10:18:45 AM Page 5

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B3062 1 6AFSWC014GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 3 . 795E+004 3.80E+004 /1. 332E+00 6 O.OOOE+OOO Co-60 1 1 73.23 99.85 4.086E+004 2.77E+004 V- l.001E+004 /l.862E+004 1332.49 99.98 2.767E+004 6.802E+003 V 1.192E+004 Nb-94 7 0 2.65 99.81 3.550E+004 3.48E+004 - 6.301E+003 1.635E+004 87 1 .09 99.89 3.477E+004 - 7.476E+003 1.583E+004 Ag- 1 08m 433.90 9 0 .50 3 . 733E+004 3.35E+004 1.337E+004 1.747E+004 614.30 89.80 4 . 926E+004 1.954E+004 2 . 317E+004 722.90 90.80 3.352E+004 -1.541E+004 jl. 52 0E+004 Cs-134 604.72 97.62 4.639E+004 4.04E+004../3.851E+004y'2.187E+004 795.86 85.46 4.037E+004 77.298E+004 )-.845E+004 Cs-137 661.66 85.10 3 .955E+004 3.95E+004V 2.521E+004\/'1.818E+004 Eu-152 12 1 .78 28.67 1.921E+005 l.52E+005 -2 . 33 1E+004 9.371E+004 344.28 26.60 1.638E+005 5 .125E+004 7.832E+004 1408.01 21. 07 1.518E+005 1.179E+005 6.652E+004 Eu - 154 123.07 40.40 1.346E+005 8.74E+004 -3 .349E+004 6.566E+004 723.30 2 0.06 1.539E+005 1.387E+004 6.988E+004 1274.43 34.80 8.736E+004 6.784E+004 3.828E+004 Eu-1 55 86 . 55 30.70 2 .374E+005 2.37E+005 9.860E+004 l.163E+005 105.31 21.10 2.793E+005 1.406E+005 1.365E+005

+ Tl- 2 0 8 583.19* 85.00 2.714E+004 2.71E+004 l.281E+004 1.208E+004 Bi- 212 727.33 6.67 4.446E+005 4.45E+005 - 8.981E+005 2.009E+005 Pb-212 2 38.63 43.60 9.823E+004 9.82E+004 8.058E+004 4.731E+004

+ Bi-214 609.32* 45.49 5.273E+004 5.27E+004 8.074E+004 2.351E+004 1120.29 14.92 3.163E+005 3.578E+005 1 .463E+005 1764.49 15.30 2.145E+005 1.431E+005 9.235E+004

+ Pb-214 295.22* 18.42 1.302E+005 6.6 2E+004 1.098E+005 6.034E+004 351 . 93* 35.60 6.618E+004 7.170E+004 3.038E+004 Ra-226 186.21 3.64 1. 138E+006 1.14E+006 8.095E+005 5.499E+005 Ac-228 338.32 1 1. 27 3.497E+005 l .46E+OO S -1.859E+005 1.665E+OOS 911.20 25.80 1 .463E+005 1.365E+OOS 6.699E+004 968.97 15.80 2.255E+005 7.348E+004 1.024E+005 Am-241 59.54 35.90 2.449E+005 2 .45E+005 2 .743E+005 1.194E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[262]

          • GAMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/21/2018 9:08:24 AM Sample Title B306216AFSWC015GD Sample Description U2 West Valve House Sample Identification 015 Sample Type Gamma Direct Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.83 0E+001 M... 2

/

Sample Taken on 4/21/2018 8:58:00 AM v Acquisition Started 4/21/2018 8:58:23 AM v Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06 %

Energy Calibration Used Done on 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Effic i ency ID 3M90D CP 2IN

~c~+z-~ffaJl~M/

Y/t1/r 0°17"

~ -J/h

[263]

Peak Analysis Report 4/21/2018 9:08:24 AM Page 2

          • PE AK A N A L Y S I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306216AFSWC0 1 5GD Peak Analysis Performed on: 4/21/2018 9:08:23 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Cont inuum No. start end centroid (keV) (keV) Area Uncert. Counts M 1 292 - 347 299.67 74.89 0.88 4 . 00E+OOl 115.30 l.70E+002 m 2 292 - 347 339.88 84.95 0.90 l.46E+001 42.35 1.47E+002 3 944- 961 952.46 238.24 0.26 l.03E+ 001 30.56 6.77E+001 4 1170 - 1187 1178.09 294.69 0.54 4.26E+001 22.13 2.44E+001 5 1397 - 1414 1405.27 351. 52 1. 06 3.73E+001 21. 78 2 .47E+001 6 2 030 - 2047 2038.41 509.87 0 . 42 3.25E+ 001 17.49 l.35E+001 7 2321 - 2338 2329.01 582.54 0.89 l.87E+001 13.88 8 . 33E+OOO 8 2424 - 2441 2432.80 6 0 8.49 1. 32 5.67E+001 19.35 1.13E+001 9 2634- 2651 2642.70 660.97 0.93 l . 53E+001 12.21 6.72E+OOO 10 4466 - 448 5 4475.55 1119.00 0.43 9.04E+OOO 15.68 l.40E+001 11 5826 - 5845 5835.06 1458.49 1. 03 4.63E+001 17.49 8.71E+OOO 12 7041- 7060 7050.24 1761.76 0.56 1 . 30E+001 7. 2 1 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[264]

Interference Corrected Activity Report 4/21/2018 9:08:24 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B3 06216AFSWC015GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

.... . ................. IDENTIFIED NUCLIDES . ....... . .......... .

Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) ( %) (pCi/MA 2 ) Uncertainty K-40 0.991 1460.8 2

  • 10.66 6.48793E+005 2 .51539E+00 5 Cs-137 0.999 661.66* 85.10 1.79963E+004 1.45439E+004 Eu-155 0.33 0 86.55* 30 . 70 2.58877E+004 7.52490E+004 105.31 21.10 Tl-208 0.999 583.19* 85.00 2 .06080E+004 1.55251E+004 Pb-212 1. 000 238.63* 43.60 1.36928E+004 4.06528E+004 Bi-214 0.996 609.32* 45.49 l.19647E+ 005 4.32932E+004 1120.29* 14.92 7 . 88479E+004 1.36865E+005 1764.49* 15.30 l .42992E+005 8.01403E+004 Pb- 2 14 1.000 295.22* 18.42 1.49162E+005 8.11589E+004 351. 93
  • 35.60 7.45809E+004 4.49571E+004
  • = Energy line found in the spectrum.

@ = Energy line not used f or Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2 .000 sigma

[265]

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          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.991 6. 487932E+005 / 2. 515391E+005 j Cs-137 0.999 1.799632E+004 1.454391E+004 Eu-155 0.330 2.588766E+004 7.524896E+004 Tl-208 0.999 2.060801E+004 1.552506E+004 Pb-212 1. 000 1.369279E+004 4.065284E+004 Bi-214 0.996 1.216086E+005 3.669585E+004 Pb-214 1. 000 9.209266E+004 3.932652E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

[266]

Interference Corrected Activity Report 4/21/20 1 8 9:08: 2 4 AM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 9:08:23 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide M 1 74 . 89 6.6682E-002 2 88.18 6 5 0 9 .87 5.4167E-002 53.81 M = First peak in a multiplet region rn = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[267]

Nuclide MDA Report 4/21/2018 9:08: 2 4 AM Page 6

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B306216AFSWC015GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M ... 2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/M ... 2 )

+ K-40 1460.82* 10.66 2 .913E+005 2 . 9 1 E+OOS j6.488E+00 5 1.267E+005 Co-6 0 1173. 23 99.85 4.034E+004 3.69E+004v'l.768E+004 1.836E+004 1332.49 99.98 3.689E+004 3. 551E+004 ./1. 652E+004 Nb-94 702.65 99.81 2.831E+004 2.83E+004 -1.304E+004 1. 2 76E+004 871.09 99.89 3.291E+004 6.753E+003 1.490E+004 Ag-108m 433.90 90.50 3.922E+004 3.67E+004 2 .697E+004 1.841E+004 614.30 89.80 5.533E+004 1.029E+00 5 2.621E+004 722.90 90.80 3.668E+004 4.265E+003 1.678E+004 Cs-134 604.72 97.62 5.048E+004 4. 3 6E+004 ../5. 612E+Oo4/ 2 . 391E+004 795.86 85.46 4.363E+004 -).702E+004 2 .007E+004

+ Cs - 137 661.66* 85.10 2.136E+004 2 .14E+004v'°'l.800E+004 9.088E+003 Eu- 152 121. 78 28.67 1 .909E+005 1.21E+005 1.349E+005 9.312E+004 344.28 26.60 l.604E+005 2.531E+004 7.661E+004 1408.01 21.07 1.208E+005 - 3.156E+004 5.102E+004 Eu-154 123.07 40.40 1.357E+005 1.05E+005 2.090E+004 6 . 621E+004 723.3 0 20.06 1.661E+005 3. 406E+00 4 7.597E+004 1274.43 34.80 1.055E+005 3 .016E+004 4.734E+004

+ Eu - 155 86.55* 30.70 1 . 046E+005 1 .0SE+OOS 2 .589E+004 4.992E+004 105.31 21.10 2 . 655E+005 8.289E+004 1.296E+005

+ Tl-208 583.19* 85.00 2 .272E+004 2.27E+004 2.061E+004 9.866E+003 Bi- 212 727.33 6.67 4.829E+005 4.83E+005 4.062E+005 2.201E+005

+ Pb-2 12 238.63* 43.60 6 . 888E+004 6.89E+004 1 . 369E+004 3.264E+004

+ Bi- 2 14 609.32* 45.49 4.789E+004 2 .98E+004 1.196E+005 2.109E+004 1120.29* 14.92 2.313E+005 7.885E+004 1.039E+005 1764.49* 15.30 2.976E+004 1.430E+005 O.OOOE+OOO

+ Pb-214 295.22* 18.42 1.126E+005 6.47E+004 1.492E+005 5.153E+004 351.93* 35.60 6.472E+004 7.458E+004 2. 965E+004 Ra-226 186.21 3.64 1.223E+006 1 .22E+006 -8.706E+004 5 .921E+005 Ac-228 338.32 11. 2 7 3.225E+005 1.59E+005 - 1 . 973E+005 1.529E+005 911.20 25.80 1.591E+005 7.998E+004 7.338E+004 968.97 15.80 2 .677E+005 2.131E+005 1.235E+005 Am- 24 1 59. 54. 35.90 2 .518E+005 2.52E+005 1 .188E+005 1.229E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[268]

          • GAMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/21/2 0 18 9:53:37 AM Sample Title B306216AFSWC016GD vv Sample Description U2 West Valve House Sample Identification 016 V Sample Type Gamma Direct v' Sample Geometry Peak Locate Threshold 3 . 00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M" 2 v*

Sample Taken On 4/21/2018 9:44 : 00 AM V

Acquisition Started 4/21/2018 9:43:36 AM V Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0.07 % v Energy Calibration Used Done On 12/28/2017 ~ / "

Efficiency Calibration Used Done On 2/1/2018 ~

  • Efficiency ID 3M90D CP 2 IN ~

[269]

Peak Analysis Report 4/21/2018 9:53:37 AM Page 2

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

Detector Name: 6279 Sample

Title:

B306216AFSWC016GD Peak Analysis Performed on: 4/21/2018 9:53: 3 6 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 284 - 345 2 99.77 74.91 0.91 l .29E+002 169.38 7.86E+002 2 944 - 961 952 . 56 238.26 1. 00 1.88E+001 31.17 6.72E+001 3 1397- 1414 14 05.78 351. 64 0.40 2.40E+001 24.88 4.00E+OOl 4 2425- 2442 2433 . 79 608 . 74 0.44 3.90E+001 16.53 9.00E+OOO 5 2634 - 2651 2642.70 660.97 0.70 5.77E+001 19.66 1.13E+001 6 5829- 5848 5838.36 1459. 3 1 2 .04 6.74E+001 19.45 7.64E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2. 000 sigma

[270]

Interference Corrected Activity Report 4/21/2018 9:53:37 AM Page 3

          • N U C L I D E I D E N T I F I C A T I O N REPORT *****

Sample

Title:

B306216AFSWC016GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB

................. . .. IDENTIFIED NUCLIDES . . . .. ....... . . .. . ...

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.996 1460.82* 10.66 9.44425E+005 2.84813E+005 Cs- 1 37 0.999 661 . 66* 85.10 6 . 79340E+004 2.45427E+004 Pb-212 1.000 238.63* 43.60 2.50016E+004 4.16002E+004 Bi-214 0.442 609.32* 45.49 8.23109E+004 3.62569E+004 1120.29 14.92 1764 . 49 15.30 Pb-2 14 0 .437 2 95. 22 18.42 3 51. 93* 35.60 4 .79682E+004 5.02766E+004

  • = Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.3 0 Errors quoted at 2.000 sigma

[271]

Interference Corrected Activity Report 4 /2 1/2018 9:53:37 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2) Uncertainty K-40 0.996 9.444247E+005 2.848127E+005 /

Cs-137 0.999 6.793404E+004 ./°" 2.454269E+OQ4 \/

Pb-212 1. 000 2 .500162E+004 4.160022E+004 Bi-214 0.442 8.231088E+004 3.625690E+004 Pb-214 0.437 4.796824E+004 5.027659E+004

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

@=Nuclide contains energy lines not used i n Weighted Mean Activity Errors quoted at 2 .000 sigma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 9:53:36 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 74.91 2.1481E-00 1 13 l . 42 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[272]

Nuclide MDA Report 4 /2 1/2018 9:53 : 37 AM Page 5

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

Detector Name: 62 79 Sample Geometry:

Sample

Title:

B306216AFSWC016GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 2 . 787E+005 2 .79E+005,j'9.444E+005/1.204E+005 Co - 6 0 1173.23 99.85 3.761E+004 2 . OOE+004" 2 . 681E+004 1. 700E+004 1332.49 99.98 2.003E+004 -2. 308E+004 8.095E+003 Nb-94 702.65 99.81 3.050E+004 3 .05E+004 2 .190E+003 1. 3 85E+004 871. 09 99.89 3.738E+004 1.066E+00 4 1.713E+004 Ag-108m 433.90 9 0 .50 3 .990E+004 3.99E+004 - l.234E+004 1.875E+004 614.3 0 89.80 4.502E+004 1.784E+004 2.106E+004 722.90 90.80 3 .997E+004 4.239E+003 1.842E+004 Cs - 134 604.72 97. 62 4.267E+004 4.27E+004/ 3.862E+004 2.001E+004 795.86 85.46 4.273E+004 _;2.445E+004 1.962E+004

+ Cs - 137 661.66* 85.10 2.735E+004 2.74E+004 6.793E+004 1.208E+004 Eu- 152 121. 78 28.67 1.895E+005 1 .56E+005 l.674E+005 9 .243E+004 344.28 26.60 l.628E+005 -9.721E+004 7.784E+004 1408.0 1 21.07 l.557E+005 - 5.433E+004 6.845E+004 Eu-154 123.07 40.40 1 .3 3 5E+005 8.96E+004 - 1.141E+005 6.511E+004 723.30 20.06 1. 792E+00 5 -3.433E+004 8.251E+004 1274.43 34.80 8.958E+004 2.827E+004 3.939E+004 Eu-155 86 . 55 30 . 70 2.391E+005 2.39E+005 5.616E+004 1. 172E+005 10 5.3 1 21. 10 2 . 791E+005 -9.164E+004 1.364E+005 Tl -2 08 583.19 85.00 4.005E+004 4.01E+004 - 9.666E+003 1.853E+004 Bi -2 12 727.33 6.67 5.457E+005 5.46E+005 4.140E+005 2.515E+005

+ Pb -2 12 238.63* 43.60 6.901E+004 6 . 90E+004 2 .500E+004 3.271E+004

+ Bi- 2 14 609.32* 45.49 4.329E+004 4. 33 E+004 8.231E+004 1 .879E+004 1120. 2 9 14.92 2.532E+005 6.747E+003 1 .148E+005 1764.49 15.30 2.145E+005 1.431E+005 9.235E+004

+ Pb-214 295 . 22 18.42 2.026E+005 8.07E+004 -2 .162E+005 9.656E+004 351.93* 35.60 8.066E+004 4.797E+004 3.762E+004 Ra-226 186.2 1 3.64 1.265E+006 1.26E+006 1.261E+006 6.130E+005 Ac-228 338.32 11. 27 3.266E+005 1.39E+005 -3.147E+005 1.549E+005 911.20 25.80 1 .394E+005 2.393E+004 6.355E+004 968.97 15.80 2.025E+005 3.639E+004 9 . 088E+004 Am- 241 59.54 35.90 2. 525E+005 2.52E+005 1.161E+005 1. 23 2E+005

+ = Nuc l ide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[273]

          • GAMMA S P E C T R U M A N A L Y S I S *****

Filename: 6279 Report Generated On 4/21/2018 9:37:42 AM

\,../"'

Sample Title B306216AFSWC017GD Sample Description U2 West Valve House V Sample Sample Sample Identification Type Geometry 017 Gamma Direct v Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA 2 V Sample Taken On 4/21/2018 9: 2 8:00 AM V

Acquisition Started 4/21/2018 9: 2 7:40 AM V Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 %

v Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

[274]

Peak Analysis Report 4/21/2 01 8 9:37:42 AM Page 2

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

Detector Name: 6279 Sample

Title:

B3062l6AFSWC017GD Peak Analysis Performed on: 4/21/20 1 8 9:37:4 1 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 12 2- 138 129.28 32.24 1.17 3.85E+001 35.38 8.35E+001 2 293 - 314 300.32 75.0 5 0.69 5.86E+ 001 78.2 0 3.81E+002 3 944- 961 952.23 238.18 0.69 4.04E+001 33.83 7.46E+001 4 1397- 1 414 1405.98 351.70 0.79 3.31E+001 27.26 4.69E+001 5 2 032 - 2049 2040.70 510.44 0.45 3.32E+001 1 8.52 1.58E+001 6 23 21 - 2338 2329.6 1 582.69 0.73 2.12E+001 17.05 l .58E+001 7 2424 - 2442 2432.8 0 608.49 0.48 5.45E+001 18.61 9.50E+OOO 8 2632 - 2654 2642.58 660.94 1. 54 2.77E+002 35.70 l.lOE+OOl 9 5828- 5848 5838.00 1 459.22 1.14 7.06E + 001 1 7 . 75 2.38E+OOO M = First peak in a multiplet region m = Other peak in a mul tiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[275]

Interference Corrected Activity Report 4/21/2018 9: 3 7:42 AM Page 3

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

Sample

Title:

B306216AFSWC017GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.996 1460.82* 10.66 9.90091E+005 2.6 3 321E+005 Cs-137 0.999 66 1 .66* 85.10 3.26129E+005 5.74543E+004 Tl-208 1.000 583.19* 85.00 2.34482E+004 l .90327E+004 Pb-212 1. 000 238.63* 43 . 60 5.36812E+004 4.57662E+004 Bi-214 0.441 609.32* 45.49 l.15000E+00 5 4.16390E+004 1120.29 14.92 1764.49 15.30 Pb- 2 14 0.437 295.22 18.42 351.93* 35.6 0 6.61234E+004 5.54233E+004

  • =Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2 .000 sigma

[276]

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          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.996 9.900913E+005 J{.633212E+005 Cs-137 0.999 3 . 2 61287E+005 5.745430E+004 /

Tl - 208 1.000 2 .344821E+004 1 . 903270E+004 Pb -212 1. 000 5.368116E+004 4.576615E+004 Bi-214 0.44 1 1. 14 9999E+005 4.163904E+004 Pb-214 0.437 6.612337E+004 5.542327E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

[277]

Interference Corrected Activity Report 4/21/2018 9:37:42 AM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 9: 37:41 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.24 6.4242E-002 91.79 2 75.05 9.7691E-002 1 33.41 5 510.44 5.5315E-002 55.81 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[278]

Nuclide MDA Report 4/21/2018 9:37:42 AM Page 6

          • N U C L I D E MDA R E P O R T *****

Detector Name: 6279 Sample Geometry:

Sample

Title:

B306216AFSWC017GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82

  • 10.66 1.698E+005 1.70E+005 ~.901E+00 5 6.591E+004 Co-60 1173 . 23 99.85 4.034E+004 2.94E+004~3.791E+004 1.836E+004 1332.49 99.98 2 .944E+004 o,OOf:D V-2.798E+004 1.280E+004 Nb-94 702.65 99.81 3 .478E+004 3.3 9E+004 4.559E+004 1.599E+004 8 71. 09 99.89 3.386E+004 - 1.172E+004 1.537E+004 Ag-108m 433 . 90 90.50 4.730E+004 4.00E+004 3.703E+004 2 .245E+004 614.30 89.80 5. 3 88E+004 7.494E+004 2 .548E+004 722.90 90 . 80 3.997E+004 3 . 032E+00 4 / l .842E+004 Cs - 134 604.72 97.62 5.156E+004 3. 89E+004 \/7. 904E+00 4 2 . 445E+004 795.86 8 5. 46 3.889E+004 ft. 542E+003 1.770E+004

+ Cs-137 661.66* 85.10 2.819E+004 2.82E+004 \1" 3.261E+005 1.250E+004 Eu - 152 12 1. 78 28.67 2.198E+005 1.16E+005 l.184E+005 1.076E+005 344.28 26.60 1.829E+005 -5.334E+001 8.789E+004 1408.01 21. 07 1.156E+005 - 9.189E+004 4.840E+004 Eu-154 123.07 40.40 1 .558E+005 1.07E+005 l.427E+005 7.627E+004 723.30 20.06 1.792E+005 1 .320E+005 8.251E+004 1274.43 34.80 1.073E+005 2.343E+004 4.824E+004 Eu-155 86.55 30.70 2.614E+005 2.61E+005 2.939E+004 1 .283E+005 105 . 3 1 2 1. 10 3.068E+005 - 2 . 794E+005 1.502E+005

+ Tl-208 583.19* 85.00 2.904E+004 2 . 90E+004 2.345E+004 1. 302E+004 Bi-212 727.33 6.67 5.510E+005 5.51E+005 4.297E+005 2.542E+005

+ Pb-212 238.63* 43.60 7.210E+004 7.21E+004 5.368E+004 3.425E+004

+ Bi-214 609.32* 45.49 4.506E+004 4.51E+004 1.150E+005 1.967E+004 1120.29 14.92 2.959E+005 2 .274E+005 1.361E+005 1764 . 49 15.30 2.755E+005 1.568E+005 1 .228E+005

+ Pb-214 295. 22 18.42 2.443E+005 8.67E+004 -2 .167E+004 1.174E+005 351.93* 35. 60 8.675E+004 6.612E+004 4.067E+004 Ra-226 186.2 1 3.64 1.410E+006 l .41E+006 -3 .426E+005 6.856E+005 Ac-228 338.32 11. 27 3.760E+005 1.39E+005 -3 .992E+005 1.796E+005 9 11 .20 25.80 1.394E+005 2.691E+004 6.355E+004 968.97 1 5.80 2.346E+005 2.085E+005 1.069E+005 Am-241 59.54 35.90 2.725E+005 2.72E+00 5 - 2.162E+005 1.332E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[279]

          • GAMM A S P E C T R U M ANALYSIS *****
    • ~**********************************************************************

Filename: 6279 Report Generated On 4/21/2018 9:23:05 AM ,/

Sample Title B306216AFSWC018GD v-Sample Description U2 West Valve House \,../'

Sample Identification 018 v Sample Type Gamma Direct v"'

Sample Geometry Peak Locate Threshold 3 .00 Peak Locate Range (in channels ) 85 - 8 1 92 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 M... 2 ~

~

Sample Taken On 4/21/2018 9:13:00 AM Acquisition Started 4/21/2018 9:13:04 AM Live Time 600.0 seconds Real Time 600 . 4 seconds Dead Time 0.06 % v Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

',1)~TC>- Ve~ /,;L.h,/

'!/'()1~ /1 q ,f.,

[280]

Peak Analysis Report 4/21/2018 9 : 23 :0 5 AM Page 2

          • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B306216AFSWC018GD Peak Analysis Performed on: 4/21/20 1 8 9:2 3 :05 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 293- 346 300.27 75.04 0.79 -1.25E+002 164.90 8.93E+002 2 944- 961 952.36 238 . 2 1 0.38 2.54E+001 25.86 4.16E+001 3 1171- 1 188 1179.26 294.98 0.28 4.91E+OOO 23.29 4.0lE+OOl 4 1397 - 1414 1405.78 351.64 1. 04 3.96E+001 18.66 l.44E+001 5 1526 - 1543 1534.68 383.89 0.51 1.14E+001 15.76 1.56E+001 6 1997- 2014 2005.92 501.75 0.43 1 .65E+001 11.16 4.50E+OOO 7 2320 - 2337 2328.13 582.32 0.48 1.25E+001 15.94 1.45E+001 8 2424 - 2441 2432 . 34 608.37 1.48 4.75E+001 1 5.78 4.50E+OOO 9 2634- 2651 2642.83 661. 00 0.51 1.45E+001 15.39 1.35E+001 10 4465- 4484 4474.74 1118.79 0.97 l.15E+00 1 9.13 2.52E+OOO 11 5826- 5845 5835.96 1458.71 1. 70 7.60E +001 17.44 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[281]

Interference Corrected Activity Report 4/21/2018 9 : 23 :0 5 AM Page 3

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Sample

Title:

B306216AFSWC018GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertainty K-40 0.993 1460.82* 10 .66 1.06529E+006 2 .61315E+005 Cs-137 0.999 661.66* 85.10 1 . 70735E+004 1.82319E+004 Tl- 2 0 8 0.999 583.19* 85.00 1.38484E+004 1.76680E+004 Pb-212 1. 000 238.63* 43.60 3.37437E+004 3 .47796E+004 Bi-214 0.734 609.32* 45.49 1.00219E+005 3.54024E+004 1120.29* 14.92 1.00101E+005 7.99944E+004 1764.49 15 . 30 Pb- 2 14 1. 000 295.22* 18.42 1. 72211E+004 8.17203E+004 351.93* 35.60 7.92307E+004 3.91605E+004

  • =Energy line found in the spectrum.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0. 3 0 Errors quoted at 2.000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.993 1.065286E+006 .,2.613146E+OOS _/

Cs-137 0.999 1.707350E+004 -./1.823185E+004 V Tl-208 0.999 1.384839E+004 1.766800E+004 Pb-212 1. 000 3.374372E+004 3.477962E+004 Bi-214 0.734 1.002001E+OOS 3 . 237373E+004 Pb-214 1. 000 6.765037E+004 3.531510E+004

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

@ = Nucl ide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

[283]

Interference Corrected Activity Report 4/21/2018 9:23:05 AM Page 5

                    • UN I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 9:23:05 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 75.04 -2 .0895E-001 -131.53 5 383.89 l.9059E-002 137.81 6 501. 75 2 .7500E-002 67.63 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[284]

Nuclide MDA Report 4/21/2018 9 : 23 :0 5 AM Page 6

          • N U C L I D E MD A REPORT *****

Detector Name: 62 79 Sample Geometry:

Sample

Title:

B306216AFSWC018GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2) (pCi/MA2) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 3.793E+004 3.79E+004 .1.065E+006 O.OOOE+OOO Co-60 1173.23 99.85 3.646E+004 3.03E+00~8. 33 9E+003 1.642E+004 1332.49 99.98 3.028E+004 2. 273E+004 Vl. 322E+004 Nb- 94 702.65 99.81 3.173E+004 2.99E+004 -4.171E+004 l.446E+004 871.09 99.89 2.987E+004 -5 .855E+003 1 .338E+004 Ag - 108m 433.90 90.50 3.659E+004 3.66E+004 2.558E+004 1.710E+004 614.30 89.80 4.952E+004 4.188E+004 2 . 331E+004 722 .90 90.80 4 .036E+004 4. 620E+003 ;L . 862E+004 Cs - 134 604 . 72 97.62 4.470E+004 4.47E+004.J'7.483E+004 \/' 2.102E+004 795.86 85.46 4.537E+004  ?. 2 33E+004 2.095E+004

+ Cs - 137 661. 66* 85.10 2 .908E+004 2 .91E+004.Jl..707E+004 1 .295E+004 Eu-152 121. 78 2 8.67 1.953E+005 1. 3 1E+005 1.930E+00 5 9.532E+004 344.28 2 6.60 l.453E+005 - 1.002E+00 5 6.907E+004 1408.01 21.07 1.305E+00 5 8.322E+004 5.589E+004 Eu-154 123.07 40.40 1.364E+00 5 1.04E+005 -3.239E+004 6.657E+004 723.30 2 0.06 l . 827E+005 8.133E+004 8.428E+004 1274.43 34.80 1.036E+005 l. 2 97E+004 4.642E+004 Eu - 155 86.55 30.70 2 .397E+005 2 .40E+005 4. 6 10E+004 l.175E+005 105.31 21.10 2 .724E+005 -1.871E+005 l. 330E+005

+ Tl-208 583.19* 85.00 2.891E+004 2.89E+004 1.385E+00 4 1.296E+004 Bi-212 727.33 6.67 5.009E+005 5.0lE+OOS - 3. 1 70E+005 2 .291E+005

+ Pb-212 238.63* 43.60 5.563E+004 5.56E+004 3.374E+004 2.602E+004

+ Bi- 2 14 609.32* 45.49 3.236E+004 3 .24E+004 l.002E+005 1.332E+004 1120.29* 14.92 1.113E+005 l.001E+005 4.386E+004 1764.49 15.30 2 .215E+005 1 .541E+005 9.584E+004

+ Pb-214 295.22* 18.42 1.414E+005 5.07E+004 1.722E+004 6.595E+004 351.93* 35.60 5.073E+004 7.923E+004 2 . 2 66E+004 Ra-226 186.2 1 3.64 1.219E+006 l.22E+006 1.149E+006 5.903E+005 Ac-228 3 38.32 11.27 3 .015E+005 l.43E+005 2 .303E+004 1.424E+005 9 11 .2 0 25.80 l.429E+005 2.995E+00 4 6.529E+004 968.97 15.80 2.224E+005 1.161E+005 1.008E+005 Am-241 59.54 35.90 2.478E+005 2 .48E+005 l.984E+005 l . 209E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[285]

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

Fi lename: 62 79 Report Generated On 4/21/2018 8:39:17 AM v Sample Title B306216AFSWC019GD V Sample Description U2 West Valve House V

~

Sample Identification 019 Sample Type Gamma Direct Sample Geometry Peak Locate Threshold 3. 00 Peak Locate Range (in channels ) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.83 0E+ 001 MA 2 ~

Sample Taken On 4/21/2018 8:29:00 AM v' Acquisition Started 4/21/2018 8:29:15 AM v

Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.06 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

<-.~ V~'t, c-1JJ tJ/n/o I hr

[286]

Peak Analysis Report 4/2 1 /2018 8: 3 9:17 AM Page 2

          • P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B306216AFSWC019GD Peak Analysis Performed on: 4/21/2018 8:39:17 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start e nd centroid (keV) (keV) Area Uncert. Counts 1 293- 347 300.57 75.11 0. 5 7 - 2.39E+00 2 173. 2 8 9.84E+002 2 888- 905 896.40 224 . 21 0.71 2.45E+001 25.01 4.05E+001 3 945- 962 953.40 238.47 1. 01 2.91E+001 28.73 5.39E+001 4 1170 - 1187 1178.20 294.71 0.75 3.28E+001 23.76 3.22E+00 1 5 1397 - 1414 1405.04 351. 46 0.86 3.03E+001 2 0 .14 2 .07E+001 6 2 635- 2652 2643.12 661.07 0.84 2.25E+001 1 9.03 2.05E+001 7 5828 - 5847 5837.62 1 459.13 1. 37 6.54E+001 17.32 2.62E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[287]

Interference Corrected Activity Repo rt 4/21/ 2 018 8:39:17 AM Page 3

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Sample

Title:

B306216AFSWC019GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. . ..... . . . .... ........ IDENTIFIED NUCLIDES . ... . . ... . ....... . . - ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (% ) (pCi/M"2 ) Uncertainty K-40 0.995 1460.82* 10.66 9.16572E+005 2.55507E+005 Cs-137 0.999 661 . 66* 85.10 2.64812E+004 2.26311E+004 Pb-212 1.000 238.63* 43.60 3.87115E+004 3.86924E+004 Pb-214 1 .000 295.22* 18.42 1.14881E+005 8.52995E+004 351.93* 35 .60 6.06482E +004 4.12891E+004

  • = Energy l ine found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold 0.30 Errors quoted at 2.000 sigma

[288]

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          • I N T E R F E R E N C E C O R R E C T E D REPORT *****

Nuclide wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.995 9.165719E+005 2.555073E+005 Cs-137 0.999 2 . 648123E+004 V2. 263114E+004 .J Pb-212 1. 000 3 . 871147E+004 3.869236E+004 Pb-214 1.000 7.094309E+004 3.716414E+004

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

@ = Nuclide contains energy lines not used i n Weighted Mean Act i vity Errors quoted at 2.000 s i gma

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 8:39:17 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . ( keV) Counts per Second  % Uncertainty Type Nuclide 1 75.11 -3.9762E-001 -72.63 2 224.21 4.0833E - 002 102 .0 8 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.0 00 sigma

[289]

Nuclide MDA Report 4/21/2 018 8:39:17 AM Page 5

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

Detector Name: 6279 Sample Geometry:

Sample

Title:

B306216AFSWC019GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 1 0 .66 1.809E+005 l.81E+005.J'9.166E+00 5 7.147E+004 Co-60 1173.23 99.85 3.704E+004 3.48E+004 -2 . 196E+004 1.671E+004 1332.49 99.98 3 .484E+004 ...:,,oo -F-c /.:"s.908E+003 1.550E+004 Nb-94 702.65 99.81 3.008E+004 3. 01E+004 - 1 .060E+003 l.364E+004 871. 09 99.89 3.696E+004 3.464E+004 l.692E+004 Ag-108m 433.90 90.50 4.013E+004 3 .21E+004 4.114E+004 l.887E+004 614.30 89.80 4.226E+004 -2.398E+004 l.968E+004 722.90 90.80 3.206E+004 A.998E+003 l.447E+004 Cs-134 604.72 97.6 2 3.768E+004 3.77E+Oo4v'3.378E+OD 4v 1.751E+004 795.86 85.46 3.989E+004 -ji*. 004E+004 1. 820E+004

+ Cs-137 661.66* 85.10 3.514E+004 3. 5 1E+OD4'Y"2.648E+004 l.598E+004 Eu-152 121.78 28.67 1.865E+005 l. 35E+005 -7.292E+004 9 .095E+004 344.28 26.60 1.574E+005 -6 .544E+004 7 . 512E+004 1408.01 2 1.07 1.351E+005 -3 .894E+004 5.817E+004 Eu-154 123.07 40.40 l.326E+005 9.17E+004 l . 261E+00 5 6.468E+004 723.30 20.06 l .496E+005 1.193E+005 6.773E+004 1274.43 34.80 9.174E+004 4.526E+004 4.047E+004 Eu-155 86.55 30.70 2 . 3 99E+005 2.40E+005 5 .822E+004 l.176E+005 105.31 21.10 2 . 813E+005 -1.284E+005 1 . 375E+005 Tl-208 583.19 85.00 3.860E+004 3.86E+004 5.302E+004 1.780E+004 Bi-212 727.33 6.67 4.577E+005 4.58E+005 3.601E+005 2.075E+005

+ Pb-212 238.63* 43.60 6.181E+004 6.18E+004 3 .871E+004 2.910E+004 Bi-214 609.32 45.49 8.118E+004 8.12E+004 5.940E+004 3.773E+004 1120.29 14.92 2.266E+005 4.222E+004 l.015E+005 1 764.49 15.30 2.145E+005 l.431E+005 9 .235E+004

+ Pb-214 295.22* 18.42 1.296E+005 6.09E+004 1.149E+005 6 .003E+004 351.93* 35 . 60 6.089E+004 6.065E+004 2 .774E+004 Ra-226 186.21 3.64 l.237E+006 1.24E+006 1. 53 6E+006 5 . 995E+005 Ac-228 338.32 11. 27 3.510E+005 1.43E+00 5 3 . 59 3E+005 1.671E+005 911.20 25.80 1.429E+005 1.264E+005 6.529E+004 968.97 15.80 2.376E+005 -4.214E+004 1.084E+005 Am-24 1 59.54 35.90 2.717E+005 2.72E+005 1.528E+005 l. 32 8E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[290]

          • GAMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On ~

4/21/2018 8:24 :01 AM Sample Title B306216AFSWC020GD v--

Sample Description U2 West Valve House v Sample Sample Identification Type 020 Gamma Direct v Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 v"'

Sample Taken On 4/21/2 0 18 8:10:00 AM v Acquisition Started 4/21/2 0 18 8:14:00 AM V Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0.0 8 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 2/1/2018 Efficiency ID 3M90D CP 2IN

[291]

Peak Analysis Report 4/ 2 1 /2018 8: 2 4:01 AM Page 2

          • PE AK A N A L Y S I S R E P O R T *****

Detector Name: 6279 Sample

Title:

B306216AFSWC020GD Peak Analysis Performed on: 4/21/2018 8:24:00 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start e nd centroid (keV) (keV) Area Uncert. Counts 1 120- 138 129.03 32.18 0.74 9.62E+001 32.92 5. 1 8E+001 2 293- 345 300.54 75.10 0.60 - l .84E+002 186.27 l.16E+003 3 945- 962 953.22 238.43 0.53 3.96E+001 35.14 8.24E+001 4 1170- 1187 1178.35 294.75 0.77 3.25E+001 29.15 5.45E+001 5 1397- 1414 1406. 00 351.70 1.44 3.04E+001 27.72 4.96E+001 6 1751- 1768 1759.85 440.21 0.37 6.00E+OOO 19. 3 7 2.70E+001 7 2031- 2048 2039.97 510.26 1.10 3.09E+001 18.47 l.61E+001 8 2321- 2338 2329.7 0 582 . 7 1 0.61 2.39E+001 17.14 l.51E+001 9 2425 - 2442 2433.69 608.71 1. 03 4.75E+001 19.12 l.35E+001 10 2632 - 2654 2642.80 66 0 .99 1. 33 3.42E+002 40.94 l.99E+001 11 5828- 5847 5837.21 1 459.02 1. 05 9.00E+OOl 18.97 O.OOE+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 .000 sigma

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Interference Corrected Activity Report 4/ 2 1/2018 8: 24 :01 AM Page 3

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Sample

Title:

B306216AFSWC020GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

  • * *. * * * * *****Io I I *
  • I IDENTIFIED NUCLIDES .....................

Nuclide Id Energy Yield Activi ty Activity Name Confidence (keV) (%) (pCi/MA 2 ) Uncertainty K-40 0.995 1460.82* 10.66 l. 26169E+00 6 2 .87668E+005 Ag -108m 0.458 433.90* 90.50 5.35196E+003 1 .72884E+004 614.30* 89.80 5.07828E+004 2 .13303E+004 722.90 90.80 Cs - 137 0.999 66 1 .66* 85.10 4.02765E +005 6.82909E+004 Tl - 2 08 1.000 583.19* 85.00 2 .63726E +004 1. 91879E+004 Pb-212 1.000 238.63* 43.60 5 .25643E +004 4.74632E+004 Bi - 214 0.441 609.32* 45.49 1 .00248E+005 4.21 1 32E+004 1120.29 14.92 1764.49 15.30 Pb-214 1.000 295.22* 18.42 l.13959E+005 1.037 9 5E+005 351.93* 35.60 6.08546E+004 5.61784E+004

  • = Energy line found in the spectrum.

@=Energy l ine not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 0 . 995 1. 2 61693E+006 2 .876685E+005 Ag - 108m 0.458 5.351961E+ 0 03 1.728838E+004 /

Cs-137 0.999 4. 02765 1E+0 05 . / 6. 829088E+004 .

Tl-208 1. 000 2.637264E+004 1.918790E+004 Pb-212 1. 000 5.256432E+004 4.746318E+004 Bi-214 0.441 8.968325E+004 5.420113E+004 Pb-214 1. 000 7.288654E+004 4.940590E+004

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

@ = Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2 .000 sigma

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Interference Corrected Activity Report 4/21/2018 8:24:01 AM Page 5

                    • U N I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 4/21/2018 8:24:00 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second  % Uncertainty Type Nuclide 1 32.18 l.6033E-001 34.23 2 75.10 -3.0584E-001 - 101.51 7 510.26 5.1498E-002 59.78 M = First peak in a multiplet region rn = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[295]

Nuclide MDA Report 4/21/2018 8:24:01 AM Page 6

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Detector Name: 6279 Sample Geometry:

Sample

Title:

B306216AFSWC020GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) {pCi/M"2 )

+ K-40 1460.82* 10.66 3.794E+004 3.79E+004~1. 2 62E+00 6 O.OOOE+OOO Co-6 0 1173.23 99.85 4.432E+004 3.69E+004 -l.493E+004 /2.035E+004 1332.49 99.98 3.689E+004 3 . 906E+003"""1.652E+004 Nb - 94 702.65 99.81 3.405E+004 3 .40E+004 - 6.168E+00 2 1.562E+004 871. 09 99.89 3.432E+004 1 .864E+004 1.560E+004

+ Ag - 108m 433.90* 90.50 2.991E+004 2.62E+004 5.352E+003 1.375E+004 614.30* 89.80 2.620E+004 5.078E+004 1.165E+004 722.90 90.80 4.074E+004 fi . 662E+003 1 . 881E+004 Cs - 134 604.72 97.62 4 . 982E+004 4. 62E+004 'V 6 . 2 16E+004 /2. 359E+004 795.86 8 5 .46 4 . 622E+004 5 . 135E+004 2.137E+004

+ Cs - 137 661.66* 85.10 3 . 718E+004 3.72E+004v'4.028E+005 1.700E+004 Eu-152 121. 78 28.67 2 . 2 40E+005 1.48E+005 - 1.794E+004 1.097E+005 344.28 26.60 1.885E+005 4.603E+004 9.065E+004 1408.01 21.07 1 .478E+005 3. 240E+004 6.454E+004 Eu-154 123.07 40.40 1.596E+005 1.02E+005 1.SOOE+005 7.814E+004 723.30 20.06 1.862E+005 2.067E+005 8.602E+004 1274.43 34.80 1. 018E+005 9.578E+004 4.548E+004 Eu-155 86.55 30.70 2.766E+00.5 2 . 77E+OOS 2.743E+005 1.359E+005 105.31 2 1 .10 3.200E+005 -7 . 440E+004 1.568E+005

+ Tl- 208 583.19

  • 85.00 2 . 856E+004 2 .86E+004 2.637E+004 l.279E+004 Bi-212 727.33 6.67 5.182E+005 5.18E+005 7.885E+003 2.378E+OOS

+ Pb-212 238.63* 43.60 7.532E+004 7.53E+004 5.256E+004 3.586E+004

+ Bi -2 14 609.32* 45.49 5.171E+004 5.17E+004 1.002E+005 2.300E+004 1120.29 14.92 2.867E+005 2.793E+005 1.315E+005 1764.49 15.30 2.347E+005 1.762E+005 1 .025E+005

+ Pb-214 2 95.22* 18.42 1.642E+005 8.91E+004 1.140E+005 7.734E+004 351 . 93* 35.60 8.907E+004 6.085E+004 4.183E+004 Ra-226 186 . 2 1 3.64 l .429E+006 1. 43 E+006 1.054E+006 6.951E+005 Ac-228 338. 32 11. 2 7 4.080E+005 1.59E+OOS 3 . 107E+005 1.956E+005 911.20 25.80 1.591E+005 1 . 241E+005 7.338E+004 968.97 1 5.80 2.405E+005 4.723E+004 1.0 9 9E+005 Am-241 59.54 35.90 2. 809E+005 2.81E+OOS -9.779E+004 1.374E+005

+ = Nucl ide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[296]

          • G AMM A S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 4/ 2 0/2018 2 :0 9 : 28 PM Sample Title B306216AFQFC003GD ~

Sample Description U2 WEST VALVE HOUSE Sample Identification 003 QC V Sample Type GAMMA DIRECT Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 .830E+001 M"2 Sample Taken On 4/2 0 /2018 1:59:00 PM Acquisition Started 4/2 0 / 2 018 1:59:27 PM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time o. 09 %V

..)

Energy Calibration Used Done On Efficiency Calibration Used Done On 12/28/2017 2/1/2018 v Efficiency ID 3M90D CP 2 IN v

~~VAhlU i/'n /I 'fr I ? t/1

[297]

Peak Analysis Report 4/20/2018 2 :09:28 PM Page 2

          • P E A K ANALYSIS R E P O R T *****

Detector Name: 6279 Sample

Title:

B306216AFQFC003GD Peak Analysis Performed on: 4/20/2018 2:09:28 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 121 - 1 37 128.61 32.07 1. 32 5.78E+001 3 5 . 11 7.92E+001 2 286- 347 297.70 74.39 0.93 2.10E+002 190.23 9.76E+002 3 737- 752 744.83 186.29 0.56 2.90E+001 34 . 95 8.80E+001 4 946 - 963 954.24 238.68 0.60 1.74E+001 34.96 8.66E+001 5 1172 - 1189 1180.08 295. 1 8 0.40 2.61E+001 25.84 4.29E+00 1 6 1398- 1415 1406.67 351. 87 0.41 5.09E+001 26.45 3.81E+001 7 2325 - 2342 2333.12 583.57 1.17 2.05E+001 16.06 1.35E+001 8 2427 - 2444 2435.69 609.21 0.45 6.24E+001 21.27 1.56E+001 9 2635- 2656 2645.92 661.77 1.29 2.43E+002 34.89 1.65E+001 10 3634- 3651 3642.28 910.81 0.64 1.86E+001 1 3 . 66 7.41E+OOO 11 5835 - 5854 5844 . 27 1460.79 1. 09 7.76E+001 20.33 7.40E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Sample

Title:

B306216AFQFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

........ . ......... .. . IDENTIFIED NUCLIDES . ............. .. .. . .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1 .08873E+006 3 .00515E+005 Cs-137 1.000 661.66* 85.10 2 .85713E+005 5 . 3 5479E+004 Tl-208 1.000 583.19* 85.00 2 . 2 6527E+004 1.79557E+004 Pb-212 1.000 238.63* 43.60 2 . 3 1031E+004 4.66333E+004 Bi-214 0.442 609.32* 45.49 1 .31705E+00 5 4 . 76092E+004 1120.29 14.92 1764 . 49 15 .3 0 Pb- 2 14 1.000 295.22* 18.42 9 . 13936E+004 9.18137E+004 351.93* 35.60 1.01788E+005 5 . 50582E+004 Ra-226 1. 000 186.21* 3.64 4.13063E+005 5.02380E+005

  • =Energy line found in the spectrum.

@= Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 2.000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 1. 088729E+006 j 3 . 005153E+OOS Cs-137 1. 000 2.857129E+OOS 5 .354789E+004 Tl-208 1. 000 2.265273E+004 1.795570E+004 Pb-212 1 . 000 2.310306E+004 4 . 663328E+004 Bi- 2 14 0.442 1.3 1 7047E+OO S 4.760924E+004 Pb- 2 14 1. 000 9.903851E+004 4.721882E+004 Ra-226 1. 000 4.130625E+OOS 5.023802E+OOS

? = 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

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Interference Corrected Act i vity Report 4/20/2018 2 :0 9: 2 9 PM Page 5

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Peak Locate Performed on: 4/20/2018 2 :09:28 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second  % Uncertainty Type Nuclide 1 32 . 07 9.633 8E-002 60.75 2 74.39 3 .5043E-001 90.47 10 910.81 3 .0978E-002 73.49 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 s i gma

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Detector Name: 6279 Sample Geometry:

Sample

Title:

B306216AFQFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 2 .722E+005 2.72E+005/ l.089E+00 6 1 .171E+005 Co-60 1173.23 99.85 3.646E+004 3. 27E+004 8. 767E+003 / 1. 642E+004 1332.49 99.98 3 . 2 65E+004 - 3. 718E+004 1.440E+004 Nb-94 702.65 99.81 3 .550E+004 3.43E+004 - 8.068E+004 1 .635E+004 871.09 99.89 3.432E+004 1.524E+004 1.560E+004 Ag-108m 433.90 90.50 5.076E+004 3.71E+004 3 .486E+004 2.418E+004 614.30 89.80 5.923E+004 2.766E+004 2.816E+004 7 22 .90 90.80 3.711E+004 - 2.265E+004 1.699E+004 Cs-134 604.72 97.62 5.240E+004 4. 32 E+004V 1. 740E+004 J 2 .487E+004 795.86 85.46 4.318E+004 -2.640E+004 1.985E+004

+ Cs - 137 661.66* 85.10 3.368E+004 3.37E+004 2 . 857E+005 1.525E+004 Eu-152 121. 78 28.67 2.370E+005 1.48E+005 2.481E+005 1.162E+005 344.28 26.60 1.864E+005 -8.562E+004 8.960E+004 1408.01 21. 07 1.478E+005 3.251E+004 6.454E+004 Eu-154 123.07 40.40 1.669E+005 1.04E+005 5.152E+004 8.180E+004 723.30 20.06 1.699E+005 -2.615E+003 7.790E+004 1274.43 34.80 1.036E+005 -3.815E+004 4.642E+004 Eu-155 86.55 30.70 2.828E+005 2.83E+005 1.888E+005 1.390E+005 105.31 21.10 3.346E+005 1.949E+005 1.641E+005

+ Tl-208 583.19* 85.00 2.710E+004 2.71E+004 2.265E+004 1. 206E+004 Bi-212 727.33 6.67 5.009E+005 5.01E+005 1.164E+005 2.291E+005

+ Pb-212 238.63* 43.60 7.786E+004 7.79E+004 2.310E+004 3.713E+004

+ Bi-214 609.32* 45.49 5.516E+004 5.52E+004 1 .317E+005 2.473E+004 1120.29 14.92 3.077E+005 4.275E+005 1.421E+005 1764.49 15.30 2.145E+005 1.431E+005 9.235E+004

+ Pb-214 295.22* 18.42 1. 465E+005 7.87E+004 9.139E+004 6.849E+004 3 51.93* 35.60 7.870E+004 1.018E+005 3.664E+004

+ Ra-226 186.21* 3.64 8.167E+005 8.17E+005 4.131E+005 3.891E+005 Ac-228 338.32 11. 27 3.951E+005 1.58E+005 - 2.181E+005 l.892E+005 911.20 25.80 1.575E+005 -3.061E+004 7.261E+004 968.97 15.80 2.405E+005 -1. 2 90E+004 l .099E+005 Am-241 59.54 35.90 2.969E+005 2 .97E+005 3.068E+005 1.454E+005

+ = Nuclide identified during the nuclide identification

  • = Energy line found in the spectrum

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

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

[302]

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