ML19178A098

Restoration Project - Final Status Survey Release Record, Switchyard Survey Unit 10205, Final Report - Phase 1, Revision 1

ML19178A098
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	06/20/2019
From:	Yetter R ZionSolutions
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
MML19178A106	List: ML19178A098 ML19178A100 ML19178A101 ML19178A102 ML19178A103 ML19178A104 ML19178A105 ML19178A107 ML19178A108 ZS-2019-0043, Transmittal of Revised Final Status Survey Report - Phase 1
References
ZS-2019-0043
Download: ML19178A098 (154)

Text

ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD SWITCHYARD SURVEY UNIT 10205 Revision 1 June 2019

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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Summary of Changes in this Revision:

• Rev. 1: Revised Release Record. Changes include the following; Added additional acronyms to List of Acronyms and Abbreviations Added clarifying language regarding operation of switchyard Corrected version of NAD.

Spelled out acronyms used 1st time in text Added statement pertaining to subsurface soil sampling during FSS Added clarifying language pertaining to selection of reporting values that are less than MDC Corrected use of MARSSIM 2000 software Added statement clarifying LTP requirement threshold for subsurface sampling.

Corrected sample ID number presentation in Tables 9, 12, 15, 16 and 17 Added text clarifying inference of HTD ROC Corrected title to Table H.1 of NUREG-1757 Clarified that the coordinates listed in Table 9 were designed coordinates Renumbered the Attachments such that the gamma spec and Eberline reports were last.

Removed Cs-137 results from QC worksheet

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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PREPARED BY / DATE:

20 June 2019 R. F. Yetter III, Junior Technical Assistant Date REVIEWED BY / DATE:

20 June 2019 R. Massengill, Radiological Engineer Date APPROVED BY / DATE:

20 June 2019 D. Wojtkowiak, C/LT Manager Date

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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TABLE OF CONTENTS

1.

EXECUTIVE

SUMMARY

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

2.

SURVEY UNIT DESCRIPTION........................................................................................... 8

3.

CLASSIFICATION BASIS.................................................................................................... 8

4.

DATA QUALITY OBJECTIVES (DQO)........................................................................... 10

5.

SURVEY DESIGN................................................................................................................ 14

6.

SURVEY IMPLEMENTATION.......................................................................................... 22

7.

SURVEY RESULTS.............................................................................................................. 23

8.

QUALITY CONTROL......................................................................................................... 27

9.

INVESTIGATIONS AND RESULTS................................................................................. 27

10. REMEDIATION AND RESULTS....................................................................................... 27

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN........................................... 27

12. DATA QUALITY ASSESSMENT (DQA).......................................................................... 27

13. ANOMALIES......................................................................................................................... 28

14. CONCLUSION...................................................................................................................... 28

15. REFERENCES...................................................................................................................... 29

16. ATTACHMENTS.................................................................................................................. 30 ATTACHMENT 1 - FIGURES AND MAPS............................................................................... 31 ATTACHMENT 2 - CONSULTATION TRIGGERS FOR RESIDENTIAL AND COMMERCIAL/INDUSTRIAL SOIL CONTAMINATION............................... 35 ATTACHMENT 3 - QC SAMPLE ASSESSMENT..................................................................... 37 ATTACHMENT 4 - GRAPHICAL PRESENTATIONS................................................................. 39 ATTACHMENT 5 - SAMPLE ANALYTICAL REPORTS............................................................ 45 ATTACHMENT 6 - EBERLINE ANALYTICAL REPORTS.......................................................... 46 151

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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LIST OF ACRONYMS AND ABBREVIATIONS AMCG Average Member of the Critical Group ALARA As Low As Reasonably Achievable BcDCGL Base Case Soil DCGLs CoC Chain of Custody cpm Counts per minute DQO Data Quality Objective DCGL Derived Concentration Guideline Level EMC Elevated Measurement Comparison FSS Final Status Survey GPS Global Positioning System HTD Hard-to-Detect IC Insignificant Dose Contributor ISFSI Independent Spent Fuel Storage Installation LBGR Lower Bound of the Gray Region LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDC Minimum Detectable Concentration MDCR Minimum Detectable Count Rate NAD North American Datum NaI Sodium Iodide OpDCGL Operational Derived Concentration Guideline Level QAPP Quality Assurance Project Plan (for Characterization and FSS)

QC Quality Control RE Radiological Engineer ROC Radionuclides of Concern SOF Sum-of-Fraction TSD Technical Support Documents

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TEDE Total Effective Dose Equivalent UBGR Upper Bound of the Gray Region UCL Upper Confidence Level VSP Visual Sample Plan ZNPS Zion Nuclear Power Station ZSRP Zion Station Restoration Project

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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1.

EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit 10205, Switchyard, has been 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).

A Final Status Survey (FSS) package (L3-10205-F #2) was developed in accordance with ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development (Reference 3), the ZSRP LTP, and with guidance from NUREG-1575, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)

(Reference 4).

This open land survey unit has a MARSSIM classification of 3. A survey 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.

Fourteen (14) randomly located surface soil samples were acquired from the survey unit.

Surface scanning was not performed because of the danger, discovered and documented during characterization, of using electrical hand-held instruments in proximity to high-voltage lines discovered during characterization. The analytical results for all surface soil samples taken in survey unit 10205 indicate that the Sum-of-Fraction (SOF) for each sample, considering the concentration of all applicable Radionuclides of Concern (ROC),

either by direct measurement or by inference, is less than 0.1 when applying the respective Operational Derived Concentration Guideline Levels (OpDCGL). Therefore, the null hypothesis is rejected, and survey unit 10205 is acceptable for unrestricted release.

Picture 1 - Survey Unit 10205

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2.

SURVEY UNIT DESCRIPTION The Switchyard, survey unit 10205, is an impacted Class 3 open land survey unit. It is bounded by Class 2 survey unit 10214A, 10214B, and 10214C to the north, Class 1 survey units 10204A, 10206A, 10207A, 10208A to the east, the Independent Spent Fuel Storage Installation (ISFSI) to the south, and non-impacted survey units 10216 and 10217 to the west. The total area of the survey unit is 54,573 m2.

In 2016, ComEd performed work in the Switchyard to reinforce the outer fence and add new gravel. A previous FSS, under package L3-10205-F #1, was conducted before the ComEd restoration activities took place. As a result of the work performed after the FSS was performed on the area, it was determined that another FSS would be performed, on the survey unit, once the restoration activities were concluded. Package L3-10205-F #1 is superseded by package L3-10205-F #2.

The topography of the survey unit is mainly flat with some small dips and depressions.

The ground consists of a mixture of mostly gravel and loamy soil. No vegetation is present in the survey unit. Solid physical items such as transformer pads, electrical panels, chain-link fencing, small buildings, energized high-voltage lines, and other switchyard support components are present in the area. The Switchyard is and continues to be energized.

The boundary of the survey unit was defined using a Global Positioning System (GPS) based on the Illinois State Plane System North American Datum (NAD) 1983 East. The reference coordinates associated with this survey unit are denoted on Figure 1 located in.

3.

CLASSIFICATION BASIS Survey unit 10205 was classified in accordance with ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 5).

Impacted Class 3 open land survey unit 10205 was originally designated as a Class 3 survey unit by the Historical Site Assessment (HSA) (Reference 6). The HSA does not cite any processes and/or incidents involving the use and/or handling of radioactive material in this open land survey unit and an inspection of the survey unit did not identify any visual indications that there are any subsurface burial sites present in this area.

Characterization surveys were performed in this survey unit from May 23, 2013 through June 27, 2013. The survey design for this survey unit called for the acquisition of twenty-seven (27) surface soil samples taken at random locations. Due to the nature of the equipment in this survey unit, no subsurface soil samples were required.

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The survey design also required the gamma-scan of 25% of the exposed ground surface in the survey unit using a Ludlum Model 2350-1 and a Model 44-10 Sodium Iodide (NaI) detector. During the implementation of the characterization survey, a safety concern was raised regarding the use of electrical hand-held instrumentation in close proximity to live high-voltage lines. It was decided to suspend the remainder of the scan survey and compensate with additional surface samples. Only scan area number three (3), which measures 5,009 square meters was scanned. Of the area scanned, the average observed background was 2,229 counts per minute (cpm), the mean count rate observed was 2,594 cpm and the maximum observed count rate was 5,437 cpm. One (1) scan alarm was observed in this survey unit with the scan alarm set-point set at the Minimum Detectable Count Rate (MDCR) plus background. Five (5) additional surface soil samples were obtained as investigations at biased locations.

Thirty-two (32) surface soil samples and two (2) Quality Control (QC) split samples were acquired and analyzed by the on-site gamma spectroscopy system. No plant-derived radionuclides greater that their respective Minimum Detectable Concentration (MDC) was detected in any sample in this survey unit.

The locations of surface soil samples taken during characterization in survey unit 10205 are illustrated on Figure 2 in Attachment 1. A summary of the analysis results for the surface soil samples taken during site characterization are presented in Table 1.

Table 1 - Statistical Quantities for Cs-137 and Co-60 from the 2013 Characterization Survey Statistical Quantities Cs-137 Co-60 (pCi/g)

(pCi/g)

Minimum Value :

0.050 0.017 Maximum Value :

0.095 0.078 Mean :

0.074 0.052 Median :

0.074 0.055 Standard Deviation :

0.012 0.016 A Radiological Engineer (RE) did not perform a visual inspection and walk-down of the survey unit prior to performing FSS. The reason for this was safety concerns with static electricity. During the implementation of the characterization survey, a safety concern was raised regarding the use of electrical hand-held instrumentation in close proximity to live high-voltage lines after a technician felt a shock in his instrument earpiece (CR-2013-0540, Injury Report 2013-39). It was determined that the use of scanning equipment was unsafe and that additional soil samples would be acquired as recompense. Because of this

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incident, the RE decided to minimize the amount of time spent in the survey unit, which meant forgoing a walk-down and scanning for FSS. A final classification assessment was performed in accordance with procedure ZS-LT-300-001-002, Survey Unit Classification as part of the survey design for FSS.

Based upon completion of Survey Unit Classification Basis for final classification, which included a review of the historical information, the results of the Characterization Survey data and, completion of a final Survey Unit Classification Worksheet, it was concluded that there was a low probability for the presence of residual radioactivity in soils in concentrations greater than 50% of the OpDCGLs, justifying a final survey unit classification of Class 3.

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 objective of the survey is satisfied. The DQO process is described in the ZSRP LTP, which is in accordance with MARSSIM guidance. The appropriate design for a given survey will be 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 unit 10205 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, Potential Radionuclides of Concern during the Decommissioning of Zion Station (Reference 7) 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 describes the results of surveys

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taken of soils. Surface and subsurface soil samples were taken in each impacted open land survey units and analyzed for the presence of plant-derived radionuclides. The results of surface and subsurface soil characterization in the impacted area surrounding ZNPS indicate that there is minimal residual radioactivity in soil. Consequently, due to the absence of any significant source term in soil, the suite of ROC and radionuclide mixture derived for non-activated concrete was considered as a reasonably conservative mixture to apply to soils for FSS planning and implementation.

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. Based upon the analysis of the mixture, it was determined that Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 accounted for 99.5% of all dose in the non-activated contaminated concrete mixes.

Table 2 presents the ROC for the decommissioning of soils at ZNPS and the normalized mixture fractions based on the radionuclide mixture.

Table 2 - Dose Significant Radionuclides and Mixture Radionuclide

% of Total Activity (normalized)(1)(2)

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.

(2) Does not include dose significant radionuclides for activated concrete (H-3, Eu-152, Eu-154).

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 soils.

Surface soil is defined as soil residing in the first 0.15 m layer of soil. A subsurface soil category, which is defined as a layer of soil beginning at the surface but extending to a depth of 1 m, is also assessed to allow for flexibility in compliance demonstration if contamination deeper than 0.15 m is encountered. Site-specific DCGLs for soil were

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calculated for both the 0.15 m and 1 m thicknesses. Based on characterization data and historical information, there are no expectations of encountering a source term geometry that is comprised of a clean surface layer of soil over a contaminated subsurface soil layer.

ZionSolutions TSD 14-011, Soil Area Factors (Reference 8) and LTP Chapter 6, section 6.8, provide the exposure scenarios and modeling parameters that were used to calculate the site-specific DCGLs for soils (referred to a Base Case Soil DCGLs

[BcDCGL] in this Release Record).

At ZNPS, compliance is demonstrated through the summation of dose from four distinct source terms for the end-state (basements, soils, buried pipe and groundwater). Basements are comprised of the summation of four structural source terms (surfaces, embedded pipe, penetrations and fill). When applied to soil, the DCGLs are expressed in units of activity per unit of mass (pCi/g). 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 surface and subsurface soil BcDCGLs for the unrestricted release of open land survey units are provided in Table 3 and Table 4 respectively. The IC dose percentage of 10%

was used to adjust the DCGLs in soils to account for the dose from the eliminated IC radionuclides.

Table 3 - Base Case DCGLs for Surface Soils (BcDCGLSS)

Radionuclide Surface Soil DCGL (pCi/g)

Co-60 4.26 Cs-134 6.77 Cs-137 14.18 Ni-63 3572.10 Sr-90 12.09

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Table 4 - Base Case DCGLs for Subsurface Soils (BcDCGLSB)

Radionuclide Subsurface Soil DCGL (pCi/g)

Co-60 3.44 Cs-134 4.44 Cs-137 7.75 Ni-63 763.02 Sr-90 1.66 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 ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey (Reference 9).

The OpDCGLs for the FSS of surface and subsurface soils are presented in Table 5 and Table 6, respectively.

Table 5 - Operational DCGLs for Surface Soils (OpDCGLSS)

Radionuclide Surface Soil DCGL (pCi/g)

Co-60 1.091 Cs-134 1.733 Cs-137 3.630 Ni-63 914.458 Sr-90 3.095

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Table 6 - Operational DCGLs for Subsurface Soils (OpDCGLSB)

Radionuclide Subsurface Soil DCGL (pCi/g)

Co-60 0.881 Cs-134 1.137 Cs-137 1.984 Ni-63 195.333 Sr-90 0.425 In accordance with NUREG-1757, Appendix G, if the HSA indicates that there is no likelihood of substantial subsurface residual radioactivity, subsurface surveys are not necessary. The HSA as well as the results of the extensive characterization of subsurface soils in the impacted area surrounding the Zion facility have shown that there is minimal residual radioactivity in subsurface soil. Consequently, Zion proposes to perform minimal subsurface sampling during FSS.

Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the OpDCGL. Survey instrument response checks were required prior to issuance and after the instrument had been used. Control and accountability of survey instruments was required to assure the quality and prevent the loss of data.

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 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 percent of the applicable OpDCGL.

5.

SURVEY DESIGN The level of effort associated with planning a survey is based on the complexity of the survey and nature of the hazards. Guidance for preparing FSS plans is provided in

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procedure ZS-LT-300-001-001 Final Status Survey Package Development. The FSS plan uses an integrated sample design that combines scanning surveys and sampling which can be either random or judgmental.

The DQO process determined that Co-60, Ni-63, Sr-90, Cs-134 and Cs-137 would be the ROC in survey unit 10205. During FSS, concentrations for Hard-to-Detect (HTD) ROC Ni-63 and Sr-90 are inferred using a surrogate approach. 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 for concrete core samples taken in the Auxiliary Building basement were calculated in ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms (Reference 10) and are presented in Table 7. The maximum ratios will be used in the surrogate calculations during FSS unless area specific ratios are determined by continuing characterization.

Table 7 - Surrogate Ratios Ratios Auxiliary Building 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 unit 10205, the surrogate OpDCGLs for Co-60 and Cs-137 were computed based on the maximum ratios from Table 7.

The equation for calculating a surrogate DCGL is as follows:

Equation 1

=

1

1

+

2 2+

3 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

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Using the OpDCGLs presented in Table 5 and the maximum ratios from Table 7, the following surrogate calculations were performed:

Equation 2 (137) =

1

1 3.630(137)+

0.002 3.095(90)

= 3.622 /

The surrogate OpDCGL that was used for Cs-137 in this survey unit for direct comparison of sample results to demonstrate compliance is 3.622 pCi/g.

Equation 3 (60) =

1

1 1.091(60)+

180.45 914.458(63)

= 0.898 /

The surrogate OpDCGL that was used for Co-60 in this survey unit for direct comparison of sample results to demonstrate compliance is 0.898 pCi/g.

The action level for investigation in a Class 3 open land survey unit is 50% of the OpDCGL. The surrogate DCGL for Co-60 while inferring Ni-63 is 0.898 pCi/g and the surrogate DCGL for Cs-137 while inferring Sr-90 is 3.622 pCi/g. Using the normalized mixture for gamma emitting ROC from Table 2, the surrogate adjusted gamma DCGL is then calculated as follows:

Equation 4

() =

1

0.012 0.898(60)+ 0.00001 1.733134+

0.988 3.622(137)

= 3.494 /

The surrogate adjusted gamma DCGL equals 3.494 pCi/g. The action levels for survey unit 10205 are based on 50% of the DCGL and are presented in Table 8.

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Table 8 - Action Levels for Survey Unit 10205 ROC DCGL (pCi/g)

Co-60 (1) 0.449 Cs-134 (2) 0.867 Cs-137 (3) 1.811 Gross Gamma (4) 1.747 (1)

Based on 50% of surrogate adjusted DCGL of 0.898 pCi/g for Co-60 while inferring Ni-63 (2)

Based on 50% of OpDCGL (3)

Based on 50% of surrogate adjusted DCGL of 3.622 pCi/g for Cs-137 while inferring Sr-90 (4)

Based on 50% of normalized surrogate adjusted DCGLs for gamma-emitting ROC The Sign Test was selected as the non-parametric statistical test. The use of the Sign Test did not require the selection or use of a background reference area, which simplified survey design and implementation. This approach was conservative since it included background Cs-137 as part of the sample set.

The Elevated Measurement Comparison (EMC) did not apply to this survey unit since it is a Class 3 survey unit and discrete, elevated areas of contamination were not expected.

The number of soil samples for FSS was determined in accordance with procedure ZS-LT-300-001-001 Final Status Survey Package Development. The relative shift (/) for the survey unit data set is defined as shift (), which is the Upper Bound of the Gray Region (UBGR), or the DCGL (SOF of 1) minus the Lower Bound of the Gray Region (LBGR)

(SOF of 0.5), divided by sigma () (0.08), which is the standard deviation of the data set used for survey design. The optimal value for / should range between 1 and 3. The largest value the / can have is 3. If the / exceeds 3, then the value of 3 will be used for /. The / for survey unit 10205 was calculated as follows:

Equation 5

/

=

0.5/0.012

=

41.67 As the calculated relative shift (41.67) was greater than 3, then a value of 3 was used as the adjusted /. Both the Type I error, or value and the Type II error, or value was set at 0.05. The sample size from Table 5.5 of MARSSIM that equates to the Type I and Type II error of 0.05 for use with the Sign Test is an N value of 14.

A Prospective Power Curve was generated using MARSSIM 2000, a software package developed for implementation of the MARSSIM in support of the decommissioning license termination rule (10CFR20, Subpart E). The result of the MARSSIM 2000

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computer run showed adequate power for the survey design. The survey design specified fourteen (14) surface soil samples for non-parametric statistical testing.

As the survey unit was classified as Class 3, sample locations were selected at random.

The random locations of the surface soil samples were selected using Visual Sample Plan (VSP), in accordance with ZS-LT-300-001-001. Input parameters included use of Bing or Google Maps aerial photographs and the random sampling tool set with a predetermined number (14) of sample points. These coordinates were integrated with a GPS to locate sample locations in the field. Sample measurement locations for the surface soil samples taken for random design are listed with the GPS coordinates in Table 9.

In Class 3 open land survey units, no subsurface soil sample(s) will be taken as part of FSS survey design in accordance with LTP Chapter 5, section 5.7.1.6.2. However, if during the performance of FSS, the analysis of a surface soil sample, or the results of a surface gamma scan indicates the potential presence of residual radioactivity at a concentration of 75% of the subsurface Operational DCGL, then biased subsurface soil sample(s) would be taken to the appropriate depth within the area of concern as part of the investigation. This threshold was not encountered during the FSS of survey unit 10205.

ZSRP LTP Chapter 5, section 5.1, states that soil samples will be collected during FSS to confirm the HTD to surrogate radionuclide ratios (Table 7). Ten percent (10%) of the FSS samples collected from open land survey units will be analyzed for HTD ROC. Only HTD radionuclides included as ROC (Ni-63 and Sr-90 for soils) will be analyzed in the FSS confirmatory samples. For soil samples with positive results for both a HTD ROC and the corresponding surrogate radionuclide (Cs-137 or Co-60), the HTD surrogate ratio will be derived and compared against the maximum ratio (see Table 7). The maximum ratios will be used unless survey information supports the use of a surrogate ratio that is specific to the area. In these cases, the survey unit-specific radiological data and the derived surrogate ratios will be submitted to the NRC for approval. If approved, then the survey unit-specific ratios used and the survey data serving as the basis for the surrogate ratios will be documented in the release record for the survey unit.

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Table 9 - Random Sample Measurement Locations MEASUREMENT ID NORTHING (meters)

EASTING (meters)

L3-10205A-FRGC-001-CV 641667.8772 343448.8988 L3-10205A-FRGC-002-CV 641682.492 343412.828 L3-10205A-FRGC-003-CV 641717.4000 343371.6788 L3-10205A-FRGC-004-CV 641783.4303 343358.8087 L3-10205A-FRGC-005-CV 641799.9379 343445.6813 L3-10205A-FRGC-006-CV 641816.4454 343397.4188 L3-10205A-FRGC-007-CV 641858.6315 343455.3338 L3-10205A-FRGC-008-CV 641867.221 343475.873 L3-10205A-FRGC-009-CV 641882.4758 343436.0288 L3-10205A-FRGC-010-CV 641908.1542 343378.1138 L3-10205A-FRGC-011-CV 641931.9985 343461.7688 L3-10205C-FRGC-012-CV 641965.0137 343500.3789 L3-10205S-FRGC-013-CV 642013.396 343422.468 L3-10205A-FQGC-013-CV 642013.396 343422.468 L3-10205A-FRGC-014-CV 642027.128 343533.913 Fourteen (14) surface soil samples were required for the non-parametric statistical test (sample size N = 14). No judgmental or investigational samples were acquired during the performance of FSS. A map of the random surface soil sample locations is provided on Figure 3 located in Attachment 1.

The selection of one (1) surface soil sample met the requirement that 10% of the samples collected for the FSS of survey unit 10205 be analyzed for HTD ROC. Sample L3-10205A-FRGC-011-CV was selected. The selected sample was sent off-site (Eberline Analytical) for analysis of the HTD ROC as specified in LTP Chapter 5, section 5.1.

The implementation of quality control measures as referenced by LTP Chapter 5, section 5.9 and ZionSolutions ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS) (QAPP) (Reference 11) includes the collection of a soil sample for split sample analysis on 5% of the soil samples taken in a survey unit with

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the locations selected at random. One (1) surface soil sample, #L3-10205A-FQGC-013-CV was selected randomly for split sample analysis for the FSS of this survey unit.

LTP Chapter 5, section 5.6.4.4 and Table 5-24 specifies that for Class 3 survey units, judgmental (biased) surface scans will be performed on areas with the greatest potential of contamination. As discussed in section 3 of this Release Record, scanning during characterization was discontinued due to safety concerns. For the design of this FSS, the same concerns that arose during characterization were heeded, and it was decided that scanning would not be performed in order to negate the danger of using electrical hand-held instrumentation in close proximity to live high-voltage lines. The HSA, characterization, and process knowledge show, with confidence, that there is a negligible chance of any residual radioactivity residing in the survey unit and that scanning is not necessary to demonstrate compliance with the release criteria.

For this Class 3 open land survey unit, the Investigation Levels for soil sample measurement results are those levels specified in LTP Chapter 5, Table 5-25, and are reproduced below in Table 10.

Table 10 - Investigation Levels Classification Direct Investigation Levels Class 3

>0.5 Operational DCGL

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Table 11 provides a synopsis of the survey design for survey unit 10205.

Table 11 - Synopsis of Survey Design FEATURE DESIGN CRITERIA BASIS Survey Unit Land Area 54,573 m2 GPS measurements of area Number of Measurements (N) 14 (random)

= 0.012 UBGR = SOF of 1 LBGR = SOF of 0.5 Type I error = 0.05 Type II error = 0.05

/ = 3 (adjusted)

(MARSSIM Table 5.5)

Grid Spacing Random (LTP Chapter 5, section 5.6.4.5.2)

DCGLs Co 1.091 pCi/g Cs-134 - 1.733 pCi/g Cs-137 - 3.630 pCi/g Ni 914.458 pCi/g Sr 3.095 pCi/g Operational DCGLs for Surface

Soils, (LTP Chapter 5, Table 5-7)

HTD ROC Analysis One (1) surface soil samples selected for HTD ROC analysis (LTP Chapter 5, section 5.1)

Soil Investigation Level

>0.5 Operational DCGL (LTP Chapter 5, Table 5-25)

QC One (1) surface soil sample selected randomly for split sample analysis (LTP Chapter 5, section 5.9)

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6.

SURVEY IMPLEMENTATION For survey unit 10205, compliance with the unrestricted release criteria was demonstrated through the sampling of surface soil for isotopic analysis. In accordance with the LTP Chapter 5, section 5.7.1.6.2, no subsurface soil sample(s) will be taken as part of the survey design in Class 3 open land survey units. However, if during the performance of FSS, the analysis of a surface soil sample, or the results of a surface gamma scan indicates the potential presence of residual radioactivity at a concentration of 75% of the subsurface OpDCGL, then a biased subsurface soil sample(s) would have been taken to the appropriate depth within the area of concern as part of the investigation. This threshold was not encountered during the FSS of survey unit 10205. Consequently, no subsurface soil samples were collected during FSS.

In addition, LTP Chapter 5, section 5.1 states that if levels of residual gamma radioactivity in an individual soil sample exceeds a SOF (OpSOF) of 0.1 when compared against the OpDCGL, then the sample(s) will be analyzed for HTD ROC. Again, this threshold was not encountered during the FSS of survey unit 10205. Consequently, no additional surface soil samples in excess of the one surface soil sample designated during survey design were analyzed for HTD ROC.

FSS field activities were conducted under FSS Sample Plan L3-10205-F #2. The Sample Plan included DQOs, survey design, detailed FSS instructions, job safety analysis, and related procedures for reference. A Field Log (ZS-LT-300-001-001 Attachment 14) was used to document field activities and other information pertaining to the performance of the FSS.

FSS field activities were projected to take eight (8) working days to complete. Daily briefings were conducted to discuss the expectations for job performance and to review safety aspects of the job. The survey required field activities were performed on Friday, March 24, 2017.

The fourteen (14) random surface soil sample locations were marked with flags based on GPS coordinates provided by VSP. In accordance with FSS design, fourteen (14) surface soil samples were collected at random locations. Each surface soil sample consisted of 1 liter of soil. The sample media was sifted to remove stones and other media larger than 1 cm in diameter. All collected soil samples were controlled, transported, stored, and transferred to the on-site laboratory using Chain-of-Custody (CoC) process from ZionSolutions procedure ZS-LT-100-001-004, Sample Media Preparation (Reference 12).

One (1) sample (L3-10205A-FRGC-011-CV) was selected for HTD radionuclide analysis.

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The implementation of survey specific QC measures included the collection of one sample (L3-10205A-FQGC-013-CV) for split sample analysis.

7.

SURVEY RESULTS The on-site laboratory analyzed the fourteen (14) surface soil samples taken for non-parametric statistical testing using the on-site gamma spectroscopy system. A summary of the 14 samples collected for non-parametric statistical testing results is provided in Table 12. The results for the gamma emitting ROC (Co-60, Cs-134 and Cs-137) presented in Table 12 are the measured values from gamma spectroscopy analysis. The results for HTD ROC were inferred using the ratios presented in Table 7. Gamma spectroscopy results (summarized in Table 12) revealed no samples above MDC for Cs-137, Co-60, or Cs-134. The concentration for Ni-63 and Sr-90 are inferred based on the maximum ratios as specified in Table 7. The mean of the gamma spectroscopic analysis results for the sample population indicated that Cs-137 was present at levels lower than the concentrations of Cs-137 expected to be found in off-site soil within the vicinity of the ZNPS as presented in ZionSolutions TSD 13-004, Examination of Cs-137 Global Fallout in Soils at Zion Station (Reference 13). The complete gamma spectroscopy reports are presented in Attachment 5. The basic statistics for the random sample population is summarized in Table 13.

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Table 12 - Summary of Gamma Spectroscopy Results for Surface Soil Samples Comprising the Random Sample Population MEASUREMENT ID Co-60(1)

Cs-134(1)

Cs-137(1)

Ni-63(2)

Sr-90(2)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

L3-10205A-FRGC-001-CV 1.47E-02 3.65E-03 0.00E+00 2.65E+00 0.00E+00 L3-10205A-FRGC-002-CV 1.00E-02 0.00E+00 1.16E-02 1.80E+00 2.32E-05 L3-10205A-FRGC-003-CV 5.01E-03 0.00E+00 2.74E-02 9.04E-01 5.48E-05 L3-10205A-FRGC-004-CV 4.39E-03 0.00E+00 1.13E-02 7.92E-01 2.26E-05 L3-10205A-FRGC-005-CV 0.00E+00 3.55E-02 1.51E-03 0.00E+00 3.02E-06 L3-10205A-FRGC-006-CV 8.22E-03 1.53E-02 0.00E+00 1.48E+00 0.00E+00 L3-10205A-FRGC-007-CV 3.57E-03 2.55E-03 2.49E-03 6.44E-01 4.98E-06 L3-10205A-FRGC-008-CV 1.21E-02 7.46E-03 1.47E-02 2.18E+00 2.94E-05 L3-10205A-FRGC-009-CV 0.00E+00 0.00E+00 1.65E-02 0.00E+00 3.30E-05 L3-10205A-FRGC-010-CV 3.84E-03 0.00E+00 8.35E-03 6.93E-01 1.67E-05 L3-10205A-FRGC-011-CV 2.27E-02 6.54E-03 5.41E-03 4.10E+00 1.08E-05 L3-10205C-FRGC-012-CV 7.48E-03 0.00E+00 3.42E-02 1.35E+00 6.84E-05 L3-10205S-FRGC-013-CV 1.74E-02 0.00E+00 2.20E-02 3.14E+00 4.40E-05 L3-10205A-FRGC-014-CV 1.45E-02 0.00E+00 0.00E+00 2.62E+00 0.00E+00 Note:

1. Bold font indicates ROC positively detected at concentration greater than MDC.

2. Ni-63 and Sr-90 are inferred concentrations using the maximum HTD ratio.

Table 13 - Basic Statistical Properties of Random Sample Population ROC Mean Median Max Min Std. Dev.

BcDCGL Avg. SOF Avg. Dose (pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g) per ROC Per ROC Co-60 8.85E-03 7.85E-03 2.27E-02 0.00E+00 6.73E-03 4.26 2.08E-03 5.19E-02 Cs-134 5.07E-03 0.00E+00 3.55E-02 0.00E+00 9.82E-03 6.77 7.49E-04 1.87E-02 Cs-137 1.11E-02 9.83E-03 3.42E-02 0.00E+00 1.09E-02 14.18 7.83E-04 1.96E-02 Ni-63 1.60E+00 1.42E+00 4.10E+00 0.00E+00 1.21E+00 3572.1 4.47E-04 1.12E-02 Sr-90 2.22E-05 1.97E-05 6.84E-05 0.00E+00 2.17E-05 12.09 1.84E-06 4.59E-05 The off-site laboratory, Eberline Analytical, processed the 1 sample selected for HTD ROC analysis as specified in the survey design. Sample # L3-10205A-FRGC-011-CV was selected. Only HTD radionuclides included as ROC (Ni-63 and Sr-90 for soils) were included in the analysis. All analyses met the required MDC.

No ROC were positively detected at a concentration greater than MDC for sample # L3-10205A-FRGC-011-CV. The results are provided in Table 14.

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Table 14 - Off-Site Analysis Results (Eberline Analytical) for Sample ID #L3-10205A-FRGC-011-CV ROC Result Uncertainty MDC

>MDC (pCi/g)

(pCi/g)

(pCi/g)

Co-60

-1.23E-02 3.07E-02 5.30E-02 No Cs-134

-5.44E-02 4.59E-02 4.94E-02 No Cs-137 5.61E-02 3.84E-02 1.46E-01 No Ni-63

-7.58E-02 2.76E-01 4.76E-01 No Sr-90

-4.48E-02 1.61E-01 3.50E-01 No The implementation of survey specific QC measures included the collection of one sample (L3-10205A-FQGC-013-CV) for split sample analysis. The on-site laboratory analyzed the designated QC sample using the on-site gamma spectroscopy system. A summary of the analytical results for the QC sample is provided in Table 15. Gamma spectroscopy results (summarized in Table 15) indicate that the measured concentrations for Co-60, Cs-134 and Cs-137 were less than MDC. The concentration for Ni-63 and Sr-90 are inferred based on the maximum ratios as specified in Table 7.

Table 15 - Summary of Gamma Spectroscopy Results for QC Surface Soil Sample MEASUREMENT ID Co-60(1)

Cs-134(1)

Cs-137(1)

Ni-63(2)

Sr-90(2)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

L3-10205A-FQGC-013-CV 0.00E+00 2.81E-03 4.34E-03 0.00E+00 8.68E-06 Note:

1. Bold font indicates ROC positively detected at concentration greater than MDC.

2. Ni-63 and Sr-90 are inferred concentrations using the maximum HTD ratio.

The SOF or unity rule is the mathematical test used to evaluate compliance with radiological criteria for license termination when more than one radionuclide has been determined to be potentially present. The equation for the unity rule is:

Equation 5 Where:

Cn

= concentration of radionuclide n DCGLn

= DCGL of radionuclide n.

The results of the unity rule calculation for the ROC in the random sample population for survey unit 10205 are provided in Table 16 and the results for the QC sample is provided in Table 17.

1 2

2 1

1

+

+

DCGL C

DCGL C

DCGL C

n n

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Table 16 - Sum-of-Fractions for Individual Surface Soil Samples (Random)

MEASUREMENT ID FRACTION OF OpDCGL OpSOF Co-60 Cs-134 Cs-137 Ni-63 Sr-90 L3-10205A-FRGC-001-CV 0.0135 0.0021 0.0000 0.0029 0.0000 0.0185 L3-10205A-FRGC-002-CV 0.0092 0.0000 0.0032 0.0020 0.0000 0.0143 L3-10205A-FRGC-003-CV 0.0046 0.0000 0.0075 0.0010 0.0000 0.0131 L3-10205A-FRGC-004-CV 0.0040 0.0000 0.0031 0.0009 0.0000 0.0080 L3-10205A-FRGC-005-CV 0.0000 0.0205 0.0004 0.0000 0.0000 0.0209 L3-10205A-FRGC-006-CV 0.0075 0.0088 0.0000 0.0016 0.0000 0.0180 L3-10205A-FRGC-007-CV 0.0033 0.0015 0.0007 0.0007 0.0000 0.0061 L3-10205A-FRGC-008-CV 0.0111 0.0043 0.0040 0.0024 0.0000 0.0218 L3-10205A-FRGC-009-CV 0.0000 0.0000 0.0045 0.0000 0.0000 0.0046 L3-10205A-FRGC-010-CV 0.0035 0.0000 0.0023 0.0008 0.0000 0.0066 L3-10205A-FRGC-011-CV 0.0208 0.0038 0.0015 0.0045 0.0000 0.0306 L3-10205C-FRGC-012-CV 0.0069 0.0000 0.0094 0.0015 0.0000 0.0178 L3-10205S-FRGC-013-CV 0.0159 0.0000 0.0061 0.0034 0.0000 0.0255 L3-10205A-FRGC-014-CV 0.0133 0.0000 0.0000 0.0029 0.0000 0.0162 Random Measurements Number of Random Measurements =

14

1. of Random Measurements with OpSOF > 1 =

0

1. of Random Measurements with OpSOF > 0.1 (HTD Assessment) =

0 Max Individual Random Measurement OpSOF =

0.0306 Mean Random Measurement OpSOF =

0.0159 Table 17 - Sum-of-Fractions for Individual Surface Soil Samples (QC)

MEASUREMENT ID FRACTION OF OpDCGL OpSOF Co-60 Cs-134 Cs-137 Ni-63 Sr-90 L3-10205A-FQGC-013-CV 0.0000 0.0016 0.0012 0.0000 0.0000 0.0028 The mean Base Case SOF (BcSOF) for survey unit 10205 is 0.0041 which equates to a dose of 0.1015 mrem/yr TEDE.

The mean of all identified isotopes are less than the Consultation Triggers for Residential and Commercial/Industrial Soil Contamination depicted in Table H.1 of NUREG 1757, Vol.1, Rev. 2 (MOU Table 1). The full table is included in Attachment 2 of this Release Record.

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8.

QUALITY CONTROL The on-site laboratory processed one split sample, L3-10205A-FQGC-013-CV, using gamma spectroscopy analysis. The data was evaluated using USNRC acceptance criteria specified in Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring (Reference 14). There was acceptable agreement between field split results. Refer to Attachment 3 for data and quality control analysis results.

9.

INVESTIGATIONS AND RESULTS No investigations were performed in survey unit 10205.

10.

REMEDIATION AND RESULTS Historically, no radiological remedial action as described by MARSSIM Section 5.4 was performed in this survey unit prior to or as a result of the FSS. Chapter 4 of the ZSRP LTP determined that remediation beyond that required to meet the release criteria is unnecessary and that the remaining residual radioactivity in soil was ALARA.

11.

CHANGES FROM THE FINAL STATUS SURVEY PLAN ZionSolutions Procedure ZS-LT-300-001-001, Final Status Survey Package Development states, If a selected location is found to be either inaccessible or unsuitable, then the location will be adjusted to the closest adjacent suitable location. In these cases, a notation will be made in Attachment 14, FSS Field Log, and the coordinates of the new location documented. Random sample locations 2, 8, 13 and 14 were relocated due to the presence of physical obstructions. The location coordinates presented in Table 9 are the designed coordinates.

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 15) for completeness and consistency. Documentation was complete and legible. Surveys and sample collection were consistent with the DQOs and were sufficient to ensure that the survey unit was properly designated as Class 3. The sampling design had adequate power as indicated by the Retrospective Power Curve generated by MARSSIM Power 2000.

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The analytical results of all samples were less than a SOF of one. Additionally, the maximum activity for each ROC did not exceed 10% of their respective OpDCGL for surface soils.

Although MARSSIM states that the Sign Test need not be performed in the instance that no measurements surpass the DCGL, the test was conducted to demonstrate coherence to the statistical principles of the DQO process. The Sign Test was performed on the data and compared to the original assumptions of the DQOs. The evaluation of the Sign Test results clearly demonstrates that the survey unit passes the unrestricted release criteria, thus, the null hypothesis is rejected.

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

mean, median, standard deviation). All data was considered valid including negative values, zeros, values reported below the MDC, and values with uncertainties greater than two standard deviations. The mean and median values for each ROC were well below the respective OpDCGLs. Also, the retrospective power curve shows that a sufficient number of samples were collected to achieve the desired power. Therefore, the survey unit meets the unrestricted release criteria with adequate power as required by the DQOs.

The data for Co-60 and Cs-137 is represented graphically through a frequency plot and a quantile plot. All graphical representations are provided in Attachment 4.

13.

ANOMALIES No anomalies were observed during the performance or analyses of the survey.

14.

CONCLUSION Survey unit 10205 has met the DQOs of the FSS plan. The ALARA criteria for soils as specified in Chapter 4 of the LTP were achieved. The EMC for soils was not applicable and remediation was not required.

All identified ROC were used for statistical testing to determine the adequacy of the survey unit for FSS. Evaluation of the data shows that none of the ROC concentration values exceeds the OpDCGL or any investigational levels; therefore, in accordance with the LTP Section 5.10, the survey unit meets the release criterion.

The sample data passed the Sign Test. The null hypothesis was rejected. The Retrospective Power Curve showed that adequate power was achieved. The survey unit is properly classified as Class 3.

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The mean SOF, when the analytical results were compared to the Base Case DCGLs, was 0.0041, which results in a dose contribution from soil in survey unit 10205 of 0.1015 mrem/yr TEDE, based on the average concentration of the ROC in samples used for non-parametric statistical sampling.

Survey unit 10205 is 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, Revision 1, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)

5. ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification

6. Historical Site Assessment (HSA)

7. ZionSolutions TSD 11-001, Potential Radionuclides of Concern during the Decommissioning of Zion Station

8. ZionSolutions TSD 14-011, Soil Area Factors

9. ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey

10. ZionSolutions TSD 14-019, Radionuclides of Concern for Soil and Basement Fill Model Source Terms

11. ZionSolutions ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS) (QAPP)

12. ZionSolutions procedure ZS-LT-100-001-004, Sample Media Preparation

13. ZionSolutions TSD 13-004, Examination of Cs-137 Global Fallout in Soils at Zion Station

14. U.S. NRC Inspection Procedure No. 84750, Radioactive Waste Treatment, and Effluent and Environmental Monitoring

15. ZionSolutions procedure ZS-LT-300-001-004, Final Status Survey Data Assessment

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16.

ATTACHMENTS

- Figures and Maps

- Consultation Triggers for Residential and Commercial/Industrial Soil Contamination

- QC Sample Assessment

- Graphical Presentations

- Sample Analytical Reports

- Eberline Analytical Reports

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ATTACHMENT 1 FIGURES AND MAPS

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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Figure 1 Survey Unit 10205 Boundary

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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Figure 2 Survey Unit 10205 Characterization Survey

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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Figure 3 Survey Unit 10205 Final Status Survey

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ATTACHMENT 2 CONSULTATION TRIGGERS FOR RESIDENTIAL AND COMMERCIAL/INDUSTRIAL SOIL CONTAMINATION

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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ATTACHMENT 3 QC SAMPLE ASSESSMENT

FSS RELEASE RECORD SWITCHYARD SURVEY UNIT 10205, Revision 1

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Duplicate Sample Assessment Survey Unit #

10205 Survey Unit Name Switchyard Sample Plan #

L3-10205A-F Sample

Description:

Comparison of split sample collected from surface soil sample from location

1. 13 and analyzed using gamma spectroscopy by on-site HpGe System. The standard samples was L3-10205A-FRGC-013-CV and the comparison sample was L3-10205A-FRQC-013-CV.

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

K-40 1.52E+00 4.80E-01 3.17 0.4-2.5 2.21E+00 7.15E-02 0.69 Y

Comments/Corrective Actions: There was not an agreement between the two samples when comparing with Cs-137 because Cs-137 was not positively identified in either sample. A further evaluation was performed on the K-40 data. NRC IP 84750 does not specify an agreement range for when the resolution is less than 4 because it is considered not comparable. Consequently, the comparison of the K-40 results is considered to be in agreement.

Table is provided to show acceptance criteria used to assess split samples.

Performed By:

Date:

06/20/2019 Reviewed by:

Date:

06/20/2019 RF Yetter III J. Graham

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ATTACHMENT 4 GRAPHICAL PRESENTATIONS

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Quantile Plot for Co-60 Survey Unit: 10205 Survey Unit Name:

Open Land - Switchyard Mean: 8.85E-03 pCi/g

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Quantile Plot for Cs-137 Survey Unit: 10205 Survey Unit Name:

Open Land - Switchyard Mean: 1.11E-02 pCi/g

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Histogram for Co-60 Survey Unit: 10205 Survey Unit Name: Open Land - Switchyard Mean:

8.85E-03 pCi/g Median:

7.85E-03 pCi/g ST DEV:

0.0067339 Skew: 0.55532981 Upper Value Observation Frequency Observation 3.78E-03 3

21%

7.57E-03 4

29%

1.14E-02 2

14%

1.51E-02 3

21%

1.89E-02 1

7%

2.27E-02 1

7%

TOTAL 14

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Histogram for Cs-137 Survey Unit: 10205 Survey Unit Name: Open Land - Switchyard Mean:

1.11E-02 pCi/g Median:

9.83E-03 pCi/g ST DEV: 0.01087053 Skew: 0.85991809 Upper Value Observation Frequency Observation 5.70E-03 6

43%

1.14E-02 2

14%

1.71E-02 3

21%

2.28E-02 1

7%

2.85E-02 1

7%

3.42E-02 1

7%

TOTAL 14

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Retrospective Power Curve for Survey Unit 10205A

ATTACHMENT 5 SAMPLE ANALYTICAL REPORTS

[45]

[46]

3/29/2017 10:04:13AM

~§'~pex-Gamma Analysis Report for 29-Mar-17-10012 L3-10205A-FRGC-OO 1 CV GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10012

L3-10205A-FRGC-001CV

Sand 1.632E+03 grams

Default

3/24/2017 8:55:00AM

3/29/2017 9:54:04AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.4 seconds

0.06%

3.00

120 - 8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11/16/16

2617

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 10:04:06AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of6

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3/29/2017 10:04: 13AM Page 2 of6 Analysis Report for 29-Mar-17-10012 L3-10205A-FRGC-001 CV Peak Energy ROI No.

(keV) start 1

238.71 949 -

2 250.69 999 -

3 295.21 1177 -

4 352.15 1402 -

5 609.20 2430 -

6 1461.06 5834 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 959 1006 1185 1413 2439 5851 Peak Centroid 954.40 1002.26 1180.11 1407.. 60 2434.85 5842.19 No background subtract performed on this spectrum.

Net Peak Net Area Continuum Area Uncertainty Counts 3.16E+Ol 9.39 2.24E+Ol 8. 00E+OO 4.01 4.00E+OO 1.54E+Ol 5.07 4.57E+OO 3.50E+Ol 7.75 9.98E+OO 1.36E+Ol 5.38 6.36E+OO 7.50E+Ol 9.00 2.00E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{%)

Activity Activity Name Confidence (keV)

(pCi/grams)

Uncertainty K-40 0.99 1460.82 10.66 1.85E+OO 2.36E-01 Pb-212 0,99 115.18 0.60 238.63 43.60 5.26E-02 1.62E-0 2 300.09 3.30 Bi-214 0.99 609. 32 45.49 4.25E-02

1. 69E-02 768.36 4.89 806.18 1.26 934.06 3.11 1120.29 14.92 1155.21

1. 63 1238.12 5.83 FWHM (keV) 0.30 0.27 0.83 0.47 0.34 0.45

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Analysis Report for 29-Mar-17-10012 L3-10205A-FRGC-OO 1 CV Nuclide Id Energy Name Confidence (keV)

Bi-214 0.99 1280.98 1377. 67 1385. 31 1401.52 1407.99 1509. 21 1661. 2 7 1729.59 1764.49 1847.43 2118.51 Pb-214 0.99 241.99 2 95. 22 351.93 785.96

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma 3/29/2017 10:04:13AM Page3 of6 Yield(%)

Activity Activity (pCilgrams)

Uncertainty

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 7.25 18.42 6.96E-02 2.36E-02 35.60 9.36E-02 2.20E-02

1. 06 INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Pb-212 Bi-214 Pb-214 Nuclide Id Confidence 0.991 0.999 0.999 0.996

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis Wt mean Activity (pCi/grams) 1.85E+OO 5.26E-02 4.25E-02 8.24E-02

= nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Comments Activity Uncertainty 2.36E-01 1.62E-02 1.69E-02 1.61E-02

[49]

3/29/2017 10:04:13AM Analysis Report for 29-Mar-17-10012

+

L3-10205A-FRGC-001 CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV) 2 250.69 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

. 3/29/2017 10:04:06AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty 1.33333E-02

~

Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCUgrams)

(pCi!grams)

BE-7 477.60 10.44 1.53E-01 3.33E-01 3.33E-01 K-40 1460.82 10.6 6 1.85E+OO 2.77E-01 2.77E-01 Co-60 1173.23 99.8 5 1.0lE-02 3.58E-02 4.05E-02 133'.::.49 99.98

1. 4 7E-02 3.58E-02 Nb-94 702. 65 99.81

-1.65E-02 2. 2 '7E-0 2 2.71E-0 2 871.09 99.89

-4.12E-02 2.27E-0 2 Ag-108m 79.13 6.60 2.29E-01

2. 71E- 02 6.15E-01 433.94 90.50 8.90E-03

2. 71E-02 614.28 89.80

- 4.18E-02 3.60E-02 722. 94 90.80

- l.58E-03 3.18E-02 Sb-125 176.31 6.84

- 2.37E-01 9.07E-0 2 2.59E-01 380.45

1. 52 5.17E-01 1.47E+OO 427.87 2 9.60 4.19E-02 9.07E-02 463.36 10.49 1.52E-01 2.52E-01 600.60 17.65 2.19E-02 1.56E-01 606.71 4.98 7.2 8E-01 8.55E-01 635.95

11. 22

1. llE-01 2.64E-01 671.44

1. '7 9 7.45E-02 1.77E+OO Page 4 of6 Tolerance Nuclide

[50]

3/29/2017 10:04:13AM Page 5 of6 Analysis Report for 29-Mar-17-10012 L3-10205A-FRGC-001 CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl!grams)

(pCilgrams)

(pCi/grams)

Ba-133 79.61 2.65

-2.64E-01 4.51E-02 l.42E+OO

81. 00 32.90 2.28E-02 l.09E-01 276.40 7.16 l.58E-01 3.44E-01 302. 85 18.34 2.76E-02 l.07E-01 356.01 62.05

-2.61E-02

4. 51E-02 383.85 8.94

-5.66E-02

1. 96E-01 Cs-134 475.36

1. 48 8.65E-03 4.03E-02 2.28E+00 563. 2 5 8.34 7.67E-02 3.36E-01 569. 33

15. 37

-l.08E-01 l.59E-01 604. 72 97.62 3.65E-03 4.03E-02 795.86 85.46

1. 02E-02 4.31E-02 801.95 8.69

-2.07E-01 3.87E-01 1038.61 0.99 l.05E+OO 2.84E+OO 1167.97

1. 79

-l.15E-01 l.83E+OO 1365.19 3.0 2

-4.44E-0 2 l.29E+OO Cs-137 661.66 85.10

-l.77E-02 3.68E-02 3.68E-02 Eu-152 121. 78

28. 67

-2.75E-03 7.22E- 02 7.22E-02 244.70 7. 61

-1.62E-02 3.29E-01 295.94 0. 45 2.05E+OO 5.74E+OO 344. 2 8 26.60 3.34E-0 2 9.45E-02 367.79 0.86 8.22E-01 2.65E+OO 411.12 2.24 1.62E-01

1. 08E+00 443.96 2.83 l.48E-01 9.05E-01 488.68 0.42 2.40E- 02 5.62E+OO 563.99 0.49 2.66E+OO 5.70E+OO 586. 2 6 0.46 5.17E-Ol 6.97E+OO 678.62 0.47 l.87E+OO 6.09E+OO 688.67 0.86

l. llE+OO 3.51E+OO 719.35 0.28

-4.81E+OO 8.36E+OO 778.90 12. 96

-1. 22E-01

1. 90E-01 810.45 0.32

- 9.31E+OO 8.87E+OO 867.37 4.2 6 3.55E-03 4.77E-01 919.33 0.43

-9.08E-01 9.50E+OO 964. 08 14.65

-l.84E-01 2.78E-01 1085.87 10.24 2.49E-01 4.05E-01 1089.74

1. 73

l. 27E+OO 2. 72E+OO 1112.07

13. 69

- 6.57E-0 2 2.72E-01 1212.95

1. 43 1.77E+OO 3.02E+OO 1249.94 0.19

1. 62E+OO 2.03E+Ol 1299.14

1. 63

-4. 16E-02 2.43E+OO 1408.01

21. 07 3.63E-02 1.35E-01 1457.64 0.50 4.00E+Ol 2. 38E+Ol 1528.10

0. 28 l.93E+OO 9.32E+OO Eu-154 123.07 40.40

-2.05E-03 5. 28E-02 5.28E-02 2 47.93 6.89

-l.84E-01 3.33E-01 591.76 4.95 1.25E-01 4.62E-Ol 692.4 2

1. 78 1.78E-01 l.76E+OO 723.30 20.06 2.25E-02 1.50E-01 756.80 4.52 2.12E-01 6.60E-01 873.18 12.08

-l.89E-03 l.88E-01 996. 2 9 10.48

-l.39E-01 2.39E-01

[51]

3/29/2017 10:04:13AM Page 6 of6 Analysis Report for 29-Mar-17-10012 L3-10205A-FRGC-OO 1 CV Nuclide Energy Yield(%)

Activity Nuclide MDA LineMDA Name (keV)

(pCl/grams)

(pCilgrams)

(pCi/grams)

Eu-154 1004.76 18.01 2.32E-02

5. 2 8E-02 1.74E-01 1274.43 34.80

-4.19E-02 9.27E-02 1596.48

1. 80

-3.53E,...01 1.20E+OO Eu-155 45.30

1. 31 6.86E-02 1.05E-01 6.13E+OO 60.01

1. 22 1.70E+00 7.09E+OO 86.55 30.70

-2.63E-02 1. 0SE-01 105.31 21.10

-1.83E-02

1. llE-01 Ra-22 6 186.21 3.64 1.65E-01 5.56E-01 5.56E-Ol Pa-231 27.36 10.30 O.OOE+OO 7.35E-02 7.35E-0 2 2 83.69

1. 70 4.15E-02

1. 33E+OO 300.07 2.47

- 6.82E-02 8.llE-01 302.65 2. 2 0 2.04E-01 8.95E-01 330.06

1. 40

3. 96E-01 1.77E+OO U-235 143.76 10.96 1.16E-01 3.66E-02 2.04E-01 163.33 5.08 1.38E-01 4.07E-01 185.71

57. 2 0 3.06E-02 3.66E-0 2 2 02.11

1. 08

- 8.43E-01 1.70E+OO 2 05. 31 5.01

1. 72E-01 4.00E-01 Am-241 59.54 35.90 7.18E-02 2.48E-01 2.48E-01

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

? = CAUTION: MDA value Is Inconsistent with Currie MDA at 95% confidence level

[52]

60 55 50 45 1000 2000 3000

~

ROI Type: 1 0000002617.CNF 4000 channel 5000 Live Tille :600.000 sec Real Ti11e :600.380 sec start:

1: -0.0(kev) stop : 8192: 2047.8(kev)

Acq. start :wed Mar 29 09: 54: 04 2017 6000 7000 8000

[53]

3/29/2017 10:16:42AM

~~~pex-Gamma Analysis Report for 29-Mar-17-10013 L3-10205A-FRGC-002CV GAMMA SPECTRUM ANAL YS/S Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10013

L3-10205A-FRGC-002CV

Sand 1.594E+03 grams

Default

3/24/2017 9:00:00AM

3/29/2017 10:06:34AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.4 seconds

0.06%

3.00

120 - 8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11 /16/16

2619

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 10:16:36AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Pagel of6

[54]

3/29/2017 10:16:42AM Page 2 of6 Analysis Report for 29-Mar-17-10013 L3-10205A-FRGC-002CV Peak No.

Energy (keV)

ROI start ROI end 1

2 238.53 1461.19 947 -

958 5833 -

5851 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centroid 953.72 5842. 72 No background subtract performed on this spectrum.

Net Peak Net Area Continuum Area Uncertainty Counts 4.36E+01 9.76E+Ol 8.34 10.59 1.04E+Ol 4.45E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 0.97 1460.82 Pb-212 0.99 115.18 238.63 300.09

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30*

Errors quoted at 1.000sigma Yield(%)

10.66 0.60 43.60 3.30 Activity (pCilgrams) 2.46E+OO 7.44E-02 Activity Uncertainty

2. 87E-01 1.54E-02 FWHM (keV) 0.59

0. 71

[55]

3/29/2017 10:16:42AM Analysis Report for 29-Mar-17-10013

+

L3-10205A-FRGC-002CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel PeakN~.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 10:16:36AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCUgrams)

(pCi/grams)

(pCi/grams)

BE-7 477.60 10.44 8.90E-02 3.03E-01

3. 03E-01 K-40 1460.82 10.66 2.46E+OO 3.99E-01 3.99E-01 Co-60 1173. 23 99.85

-1. 72E-03 3.12E-02 4.32E-02 1332.49 99.98 1.00E-0 2 3.12E-02 Nb-94 702. 65 99.81

-1. 21E-03 2.73E-0 2 2.78E-02 871.09 99.89 O.OOE+OO 2.73E-0 2 Ag-108m 79.13 6.60 1.90E-01 2.07E-02 6.54E-01 433.94 90.50

-6. 44E-03 2.07E-02 614.28 89.80

-1.84E-02 3.49E-02 722.94 90.80 8.07E-03 3.25E-02 Sb-125 176.31 6.84

- 1.41E-01 8.19E-02 2.65E-01 380.45

1. 52

-1.13E+OO 1.18E+OO 427.87 29.60 1.05E-02 8.19E-02 463.36 10.49

-3.42E-01 2.38E-01 600.60 17.65

1. 43E-02

1. 54E-01 606.71 4.98 3.14E-01 7.40E-01 635.95

11. 22 2.28E-01 3.03E-01 671. 4 4

1. 79 1.13E+OO 1.76E+00 Ba-133 79.61 2.65 1.37E-01 4.76E-02 1.55E+OO Page4 of6 Tolerance Nuclide

[56]

3/29/2017 10:16:42AM Page 5 of6 Analysis Report for 29-Mar-17-10013 L3-10205A-FRGC-002CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl/grams)

(pCUgrams)

(pCl/grams)

Ba-133

81. 00 32.90

-4.26E-02 4.76E-02 1.04E-01 276.40 7.16

-4.0lE-02 2.47E-01 302.85

18. 34

-8.38E-03 1.1 7E-01 356.01 62.05

-4.94E-0 2 4.76E-02 383.85 8.94

-5.05E-02 2. 27E-01 Cs-134 475.36

1. 48 3.60E-01 3.54E-02

1. 87E+OO 563.25 8.34

-9.83E-02 2.86E-01 569.33 15.37

-8.59E-02 1.56E-01 604. 72 97.62

-2.21E-0 3 3.54E-0 2 795.86 85.46

-9.26E-03 4.54E-0 2 801.95 8.69

1. 06E-01 4.24E-01 1038.61 0.99 6.42E-01 2.39E+OO 1167.97

1. 79

-7.37E-01 l.88E+OO 1365.19 3.02

-3.82E-01 8.19E-01 Cs-137 661.66 85.10 l.16E-0 2 3.40E-02 3.40E-0 2 Eu-152 121.78 28.67

- 4.22E-02 7.65E-0 2 7.65E-02 244.70 7.61 l.60E-01 3.38E-0 1 295.94 0.45 6.54E-01

6. llE+OO 344. 2 8 2 6.60 4.06E-02 8.59E-02 367.79 0.86 4.27E-02 2.36E+OO 411.12 2.24 l.35E-0 1 9.20E-01 443.96 2.83

-7.53E-02 7.68E-01 488.68 0.42

-6.24E-01 5.55E+00 563.99 0.49 l.71E+OO 5.05E+OO 586.26 0.46 8.53E+OO 9.23E+OO 678.62 0.47

-2.18E+OO 5.99E+OO 688.67 0.86

-2.71E+OO 3.84E+OO 719.35 0.28 5.85E+OO 1.06E+Ol 778.90

12. 96

-l.66E-02 2.30E-01 810.45 0.32

-l.15E+Ol 9.97E+OO 867.37 4.26

-2.29E-Ol 5.94E-01 919.33 0.43 2.44E+OO 8.84E+OO 964.08 14.65 2.16E-01 3.68E-01 1085.87

10. 24 l.49E-0 1 3.31E-01 1089.74

1. 73 4.73E-02

1. 84E+OO 1112.07 13.69

-l.67E-01 2.51E-01 1212.95 1.43 O.OOE+OO 2.56E+OO 1249.94 0.19 l.43E+Ol 2.94E+Ol 12 99.14

1. 63

- 7.00E-01 1.46E+OO 1408.01

21. 07

-l.16E-02 l.55E-01 1457.64 0.50 5.65E+Ol 2.79E+Ol 1523.10

0. 2 8 O.OOE+OO 2.84E+OO Eu-154 123.07 40.40 2.lOE-02 5.58E-02 5.58E-02 247.93 6.89

-7.lOE-02 3.42E-01 591.76 4.95 3.31E-0 2 3.91E-01 692.42

1. 78 2. 2 4E-0 2 l.62E+OO 723.30 2 0.06 3.86E-02

1. 4 7E-01 756.80

4. 52 9.57E-02 6. 46E-01 873.18 12.08

3. 2 6E-02 2.41E-01 996.29 10.48

-2.45E-02 3.54E-01 1004.76 18.01 9.17E-0 2

1. 89E-01 1274.43 34.8 0

- 4.07E-0 2 7.BOE-02

[57]

3/29/2017 10:16:42AM Page 6 of6 Analysis Report for 29-Mar-17-10013 L3-10205A-FRGC-002CV Nuclide Energy Yield(%)

Activity Nuclide MDA LineMDA Name (keV)

(pCilgrams)

(pCi/grams)

(pCl/grams)

Eu-154 1596.48

1. 80

-3.25E+OO 5.58E-02 2.00E+OO Eu-155 45.30

1. 31 7.67E-01 1.0lE-01 6.19E+OO 60.01

1. 22 3.28E+OO 6.42E+OO 86.55 30.70 1.54E-02 1.07E-0 1 105.31 21.10

- 7.12E-02 1.0lE-01 Ra-226 186.21 3.64 5.89E-01 5.63E-01 5.63E-01 Pa-23 1 27.36 10.3 0 O.OOE+OO 7.53E-02 7.53E-02 283.69

1. 70 3.72E-01 1.28E+OO 300.07 2.47

-4.86E-01 8. 59E-01 30 2.65 2.20

-1.lOE-01 9.49E-01 330.06

1. 40 4.33E-01 1.62E+OO U-23 5 143.76

10. 96

-1.06E-0 2 3.53E-02

1. 81E-01 163.33 5.08 7.45E-02 3.67E-01 185.71

57. 2 0 2.89E-02 3.53E-02 202. 11

1. 08

-l.57E+OO 1.96E+OO 205.31 5.01 6.39E-02 4.58E-01 Am-241 59.54 35.90

1. 40E-02 2.05E-01 2.05E-01

+

= Nuclide identified during the nuclide identification

= Energy line found in the spectrum

= MDA value not calculated

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

?

= CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[58]

V}

C:

60 55 50 45 40 35 8 30 1000 2000

~

ROI Type: 1 3000 0000002619.CNF 4000 channel 5000 Live Tine :600.000 sec Real Tine :600.350 sec Start:

1: -0.0(kev)

Stop : 8192:2047.8(keV)

Acq. start :wed Mar 29 10:06:34 2017 6000 7000 8000

[59]

3/29/2017 10:29:03AM

~~~pex-Gamma Analysis Report for 29-Mar-17-10016 L3-10205A-FRGC-003CV GAMMA SPECTRUM ANAL YS/S Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10016

L3-10205A-FRGC-003CV

Sand 1.619E+03 grams

Default

3/24/2017 9:05:00AM

3/29/2017 10:18:55AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.3 seconds

0.05%

3.00

120-8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11 /16/16

2620

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 10:28:58AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of6

[60]

3/29/2017 10:29:03AM Page 2 of6 Analysis Report for 29-Mar-17-10016 L3-10205A-FRGC-003CV Peak Energy ROI No.

(keV) start 1

238.51 948 -

2 609.66 2432 -

3 1460.88 5835 -

M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 958 2 441 5849 Peak Centroid 953.63 2436.67 5841. 44 No background subtract performed on this spectrum.

Net Peak Net Area Continuum Area Uncertainty Counts 5.60E+O l 8.67 8.02E+OO 1.70E+Ol 5.80 6.96E+OO 5.42E+Ol

9. 22 l.08E+Ol NUCLIDE /DENT/FICA T/ON REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCi/grams)

Uncertainty K-40

1. 00 1460.82

• 10.66 1.34E+OO 2.36E-01 Pb-212 0.99 115.18 0.60 23 8.63

• 43.60 9.40E-02 1.64E-02 300.09 3.30 Bi-214 0.99 609.32 45.49 5.36E-02

1. 85E-02 768.36 4.89 806.18

1. 2 6 934.06 3.11 1120. 2 9

14. 92 1155.21

1. 63 1238.12 5.83 1280.98

1. 43 1377.67 3.99 1385.31 0.79 FWHM (keV) 0.82

0. 78

1. 26

[61]

Analysis Report for 29-Mar-17-10016 L3-10205A-FRGC-003CV Nuclide Name Bi-214 Id Confidence 0.99 Energy (keV) 1401.52 1407.99 1509.21 1661. 27 1729.59 1764.49 1847.43 2118.51

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma Yield(%)

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 3/29/2017 10:29:03AM Page 3 of6 Activity (pCilgrams)

Activity Uncertainty INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Pb-212 Bi-214 Nuclide Id Confidence

1. 000 0.998 0.993

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCilgrams) l.34E+OO 9.40E-02 5.36E-02

= nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma wt mean Comments Activity Uncertainty 2.36E-01 1.64E-02 l.85E-02

[62]

3/29/2017 10:29:03AM Analysis Report for 29-Mar-17-10016

+

L3-10205A-FRGC-003CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 10:28:58AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl/grams)

(pCi/grams)

(pCi!grams)

BE-7 477.60 10.44 6.61E-02 2.78E-01 2.78E-01 K-40 1460.82 10.66 1.34E+OO 5.39E-01

5. 3 9E-01 Co-60 1173.23 99.85 5.01E-03 2.76E-02

4. 71E-02 1332.49 99. 98

-1.34E-0 2 2.76E-02 Nb-94 702.65 99.8 1

1. 51E-02 2.69E-02 3.30E-02 871.09 99.89 1.10E-02 2.69E-0 2 Ag-108m 79.13 6.60 l.57E-01 2.50E-02 6.14E-0 1 433.94 90.50 4.52E-03 2.50E-02 614. 2 8 89.80

-4.64E-02 4.30E-02 722. 94 90.80

-l.90E-04 3.70E-02 Sb-125 176.31 6.84

-3.82E-0 2 7.33E-02

2. 96E-01 380.45

1. 52

-1.47E-02 1.49E+OO 427.87 2 9.60

-3.46E-02 7.33E-02 463.36 10.49 2.07E-02 2.48E-01 600.60 17.65

-4.42E-02

1. 62E-01 606.71 4.98 9.26E-01 9.75E-01 635.95

11. 22 8.40E-0 2 2.38E-01 671. 44

1. 79 2.14E-0 2

1. 55E+OO Ba-133 79.61 2.65 3.51E-01 4.12E-0 2 1.49E+OO Page 4 of6 Tolerance Nuclide

[63]

3/29/2017 10:29:03AM Page 5 of6 Analysis Report for 29-Mar-17-10016 L3-10205A-FRGC-003CV Nuclide Energy Yield(%)

Activity NuclideMDA LlneMDA Name (keV)

(pCi/grams)

(pCilgrams)

(pC//grams)

Ba-133

81. 00 32.90

-1. 4 7E-01 4.12E-02 9.40E-0 2 276. 40 7.16

-2.30E-0 1 2.50E-01 302.85 18.34

-1.18E-01 1.20E-01 356.01 62.05

-3.85E-03 4.12E-02 383.85 8.94 1.46E-01 2.85E-01 Cs-13 4 475.36

1. 48 3.93E-01 2. 96E-02 1.94E+OO 563. 2 5 8.34

-5.29E-02 2.38E-0 1 569. 33 15.37

3. 96E-0 2 1.61E-01 604. 72 97.62

-2.28E-0 2 4.00E-02 795.86 85.46

-1.60E-02

2. 96E-02 801.95 8.69 1.80E-01 3.46E-01 1038.61 0.99

-6.85E-01 3.47E+OO 1167.97

1. 79 1.21E-01 2.55E+OO 1365. 1 9 3.02

-5.0lE-01 8.07E-01 Cs-137 661.66 85.10 2.74E-0 2 4.87E- 02 4.87E-02 Eu-15 2 121.78 28.67 1.72E-02 8.00E-02 8.00E-02 244.70 7.61

-9.0lE-02 3.14E-01 2 95.94 0.45 3.81E+OO 6.45E+00 344. 28 26.60 3.83E-02 9.20E-0 2 367.79 0.86

-7. 77E-01 2.32E+OO 411.12 2. 24 2.29E-01

9. 72E-01 443. 96 2.83 8.66E-02 9.80E-01 488.68 0.4 2 4.65E+OO 6.42E+OO 563.99 0.49

-3.45E+OO 4.03E+OO 586.26 0.46

5. 30E-01 7.98E+OO 678.62 0.47 4.50E-01

5. 38E+OO 688.67 0.86

-1.54E+OO 2.66E+OO 719. 35 0.28 2.84E+OO

1. 04E+Ol 778.90 12.96

-8.16E-0 2 2.26E-01 810.45

0. 32

-5.27E+OO 6. 78E+OO 867.37

4. 2 6

-5.65E-01 5.85E-01 919.33 0.43

-2.36E+OO 6.95E+OO 964. 08 14.65 1.34E-01 2.89E-01 1085.87 10.24

-2.70E-02 3.06E-01 1089.74

1. 73

1. 49E+00 2.42E+00 1112. 07 13.69

-4.37E-0 2 2.75E-01 1212.95

1. 43 1.18E-01

3. 27E+OO 1249.94 0.19

-3.12E+OO 1. 21E+Ol 1299.14

1. 63 8.94E-01 2.18E+OO 1408.01

21. 07

-8.24E-02

1. 78E-01 1457.64 0.50 3.89E+Ol 2.32E+01 1528. 1 0

0. 2 8

-1.13E+OO 1.09E+Ol Eu-154 123.07 40.40 5.93E-03 5.61E-02 5.61E-02 247.93 6.89 5.24E-02 3.19E-01 591.76 4.95

1. 29E-01

5. llE-01 692.42

1. 78 7.93E-01

1. 52E+OO 723. 30 20.06

-2.87E-03 1.68E-01 756.80 4.52

1. 4 7E- 01 6.06E-01 873. 1 8 12. 08 1.07E- 01 2. 37E-01 996. 2 9 10.48 O.OOE+OO 3.17E-01 1004. 7 6 18.01 2.32E-0 2 1.95E-01 1274.43 34.80 4.12E-0 2 1. 00E-01

[64]

3/29/2017 10:29:03AM Page 6 of6 Analysis Report for 29-Mar-17-10016 L3-10205A-FRGC-003CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCilgrams)

(pCi/grams)

Eu-154 1596.48

1. 80 6.32E-01 5.61E-02 1.97E+OO Eu-155 45.30

1. 31 2.73E+OO 1.13E-01 6.18E+OO 60.01

1. 22 l.34E+OO 5.45E+OO 86.55 30.70 1.02E-02 1.13E-01 105.31

21. 10

- 4.45E-0 3 1.18E-01 Ra-22 6 186. 21 3.64

4. 27E-01 6.50E-01 6.50E-01 Pa-231 27.36 10.3 0 O.OOE+OO 7.41E-02 7.41E-02 283.69

1. 70 4.14E-01 1.46E+OO 300.07

2. 47

-3.03E-01 9.98E-01 302.65 2.20

-4.93E-01 1.0SE+OO 330.06

1. 40 l.09E-01 l.63E+OO U-23 5 143.76

10. 96 7.18E-0 2 4.17E-02

1. 95E-01 163.33 5.08

-1.33E-01 3.34E-01 185.71

57. 2 0 2.26E-02 4.17E-02 202.11

1. 08

-5.0lE-02 l.88E+OO 205.31 5.01

-l.20E-01

4. 2 0E-01 Am-241 59.54 35.90

-4.29E-02 1.75E- 01

1. 75E-01

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[65]

60 55 50 45 40 1000 2000 3000

~

ROI Type: 1 0000002620.CNF 4000 channel 5000 Live Time :600.000 sec Real Time

600.290 sec start:

1: -0.0(kev) stop : 8192: 2047.8(kev)

Acq. start :wed Mar 29 10:18:55 2017 6000 7000 8000

[66]

3/29/2017 10:41 :03AM

~§/fff.~pex-Gamma Analysis Report for 29-Mar-17-10017 L3-10205A-FRGC-004CV GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10017

L3-10205A-FRGC-004CV

Sand 1.820E+03 grams

Default

3/24/2017 9:10:00AM

3/29/2017 10:30:54AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.3 seconds

0.06%

3.00

120 - 8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

ir:,itial 11/16/16

2621

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 10:40:57AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of6

[67]

3/29/2017 10:41 :03AM Page 2 of6 Analysis Report for 29-Mar-17-10017 L3-10205A-FRGC-004CV Peak Energy ROI No.

(keV) start 1

238.72 949 -

2 351.94 1402 -

3 1460.98 5833 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 960 1413 5850 Peak Centroid 954.45 1406.77 5841.86 No background subtract performed on this spectrum.

Net Peak Net Area Continuum Area Uncertainty Counts 4.25E+Ol 10.27 2.45E+Ol 2.27E+Ol 6.97 1.03E+Ol 8.0BE+Ol 9.37 2.15E+OO NUCLIDE /DENT/FICA TIO/\\! REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCilgrams)

Uncertainty K-40 0.99 1460.82 10.66 1.78E+OO 2.21E-01 Bi-211 0.88 351.07 13.02 l.48E-01

4. 72E-02 Pb-212 0.99 115.18 0.60 238.63 43.60 6.35E-02 1.62E-02 300.09 3.3 0 Pb-214

1. 00 241. 99 7.25 295.22 18.42 351.93 35.60 5.43E-02

1. 73E-0 2 785.96

1. 06 FWHM (keV) 0.99 0.44 0.95

[68]

Analysis Report for 29-Mar-17-10017 L3-10205A-FRGC-004CV

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma 3/29/2017 10:41 :03AM INTERFERENCE CORRECTED REPORT

?

?

Nuclide Name K-40 Bi-211 Pb-21 2 Pb-214 Nuclide Id Confidence 0.996 0.886 0.999

1. 000

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis wt mean Activity (pCilgrams) l.78E+OO

1. 48E-01 6.35E-02 5.43E-02

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma wt mean Activity Uncertainty 2.21E-Ol

4. 72E-02 1.62E-02

l. 73E-02 Page 3 of6 Comments

[69]

3/29/2017 10:41:03AM Analysis Report for 29-Mar-17-10017

+

L3-10205A-FRGC-004CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 10:40:57AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl!grams)

(pCi!grams)

(pCi/grams)

BE-7 477.60 10.44 1.84E-01 2.99E-01 2.99E-01 K-40 1460.82 10.66

1. 78E+00 2.59E-Ol 2.59E-01 Co-60 1173. 23 99.85

-1. 2 6E-02 2.12E-0 2 3.63E-02 1332.49 99.98 4.39E-03 2.12E-0 2 Nb-94 70 2.65 99.8 1 1.58E-02 2.69E-02 3.02E-02 871.09 99.89 4.39E-03 2.69E-02 Ag-108m 79.13 6.60 2.28E-01 2.62E-02 6.59E-01 433.94 90.50 1.60E-02 2.62E-02 614.28 89.80 l.98E-02 4.33E-02 72 2. 94 90. 80 7.43E-03 3.08E-02 Sb-1 25 176.31 6.8 4

-8.53E-02 7.38E-02 2.70E-01 380.45

1. 52 7.48E-02 1.42E+OO 427.87 2 9.60

-4.98E-02 7.38E-02 463.36 10.49 5.65E-0 2 2.38E-Ol 600.60 17.65

-4.83E-02 l.34E-01 606.71 4.98

8. 2 6E-01 7.98E-01 635. 95

11. 22 l.08E-01 2.51E-01 671.44

1. 79

-5.57E-01 l.32E+OO Ba-133 79.61 2.65 2.87E-01 4.l:E-02 1.56E+OO Page 4 of6 Tolerance Nuclide

[70]

3/29/2017 10:41 :03AM Page 5 of6 Analysis Report for 29-Mar-17-10017 L3-10205A-FRGC-004CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCVgrams)

(pCi/grams)

(pCi/grams)

Ba-133

81. 00 32.90

-6. 08E-02 4.l:E-02 1.05E-01 276.40 7.16 1.12E-01 2.94E-01 302.35 18.34

- 1.05E-01 8.73E-02 356.01 62.05

- 1.44E-02 4.17E-0 2 383.85 8.94 1.37E-02 2.31E-01 Cs-13 4 47 5.36

1. 48 7.49E-01 2. 71E-02 1.94E+OO 563. 25 8.34 9.31E-02 3.52E-01 569.33 15.37

-1.00E-01 1.60E-01 60 4. 72

97. 62

-9.57E-02 2.71E-02 795.86 85.46

-2.25E-02 2.96E-02 801. 95 8.69 1.78E-01 3.21E-01 1038.61 0.99

-1.56E+OO 3.38E+OO 1167.97

1. 79 7.27E-01

2. llE+OO 1365.19 3.02

-1.76E-01 7.17E-01 Cs-137 661. 66 85.10 1.13E-02 3.50E-02 3.50E-0 2 Eu-152 121. 78 28.67 2.35E-02 7.70E-02 7.70E-02 244.70 7.61 8.60E-02 3.12E-01 295.94 0.45 5.02E-01 5.35E+OO 344.28 2 6.60 1.19E-02 8.79E-0 2 367.79 0.86

1. lOE+OO 2.38E+OO 411.12 2.24 1.95E-02 1.09E+OO 443. 96 2.8 3 3.94E-01 6.73E-01 488.68 0.4 2

-8. 92E-01 5.55E+OO 563.99 0.49

-1.llE+OO 5.70E+OO 586.26 0.46

- 1.28E+OO 6.97E+OO 678.62 0.47

- 2.82E+OO 4.25E+OO 688.67 0.86 3.63E-01 3.15E+OO 719.35 0.28

-8.12E+O O 6.97E+OO 778.90

12. 96 6.64E-02 2.lOE-01 810.45 0.32

-2.26E+OO 9.09E+OO 867.37 4.26

-4.39E-02

5. 2 0E-01 919. 33 0.43 2.45E+OO 8.99E+OO 964.08 14.65

-1.44E-0 1 2.85E-01 1085.87

10. 24 4.19E-02 3.87E-01 10 89.74

1. 73 9.20E-02 2.37E+OO 1112. 07 13.69

-3.25E-01 2.20E-01 1212.95

1. 43

-7.95E-01 2.81E+OO 1249.94 0.19 1.44E+Ol 2.24E+Ol 1299.14

1. 63 9.55E-01 2.67E+OO 1408.01

21. 07

-1.17E-01

1. 05E-01 1457.64 0.50 4.06E+Ol 2.22E+ Ol 1528.10 0.28 8.65E-01 6.63E+00 Eu-154 123.07 40.40

-2.15E-02

5. 18E-02 5.18E-02 247.93 6.89

-7.43E-02 2.79E-01 591.76 4.95 1.13E-01 5.40E-01 692.42

1. 78

4. llE-01 1.68E+OO 723. 30 20.0 6 8.59E-02 1.39E-01 756.8 0 4.5 2 1.56E-01 7.03E-01 873. 1 8 12.0 8 3.61E-02 2.34E-01 996. 2 9 10.48 8.34E-0 2

2. 96E-01 1004.76 18.01

1. 76E-02 2.03E-01 1274.43 34.80 4.27E-02 9.51E-02

[71]

3/29/2017 10:41:03AM Page 6 of6 Analysis Report for 29-Mar-17-10017 L3-10205A-FRGC-004CV Nuclide Energy Yield(%)

Activity Nuclide MDA LineMDA Name (keV)

(pCilgrams)

(pCl/grams)

(pCilgrams)

Eu-154 1596.48

1. 80 1.41E-01

5. 18E-02 l. 08E+OO Eu-155 45.30

1. 31 7.48E-01 1.09E-01

5. 64E+OO

60. 01

1. 22

-4.22E+OO 4.84E+OO 86.55 30.70 5.70E-02 l.12E-01 105.31

21. 10 4.39E-02 l.09E-01 Ra-22 6 186.21 3.64 4.20E-01 6.13E-0 1 6.13E-01 Pa-231 27.36 10.30 O.OOE+OO 6.59E-02 6.59E-02 283.69

1. 70 1.37E-01

1. 2 6E+OO 300.07

2. 47

-2.05E-01

7. 35E-01 302.65 2. 2 0

-6.31E-01 7.70E-Ol 330.06

1. 40

1. 45E+OO 1.67E+OO U-2 35 143.76 10.96 5.13E-02 3.83E-02

1. 96E-Ol 163.33 5.08 1.05E-01 4.llE-01 185.71

57. 2 0 2. 23E-0 2 3.83E-02 2 02.11

1. 08

-1.45E+OO 1.65E+OO 205.31 5.01 2.54E-02 3.97E-01 Am-241 59.54 35.90

-1.53E-01 1.66E-0 1 l.66E-01

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[72]

60 55 50 45 1000 2000 3000

~

ROI Type: 1 0000002621.CNF 4000 channel 5000 Live Time :600.000 sec Real Tire :600.340 sec Start:

1: -0.0(kev) stop : 8192:2047.8(kev)

Acq. start :wed Mar 29 10: 30: 54 2017 6000 7000 8000

[73]

3/29/2017 10:59:05AM Analysis Report for 29-Mar-17-10018 L3-10205A-FRGC-005CV GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10018

L3-10205A-FRGC-005CV

Sand

1. 757E+03 grams

Default

3/24/2017 9:22:00AM

3/29/2017 10:48:56AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.3 seconds

0.05%

3.00

120-8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11/16/16

2623

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 10:58:59AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of6

[74]

3/29/2017 10:59:0SAM Page 2 of6 Analysis Report for 29-Mar-17-10018 L3-10205A-FRGC-005CV Peak Energy ROI No.

(keV) start 1

2 38.72 949 -

2 609.70 2432 -

3 14 61. 02 5832 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 959 2441 5851 Peak Centroid 954.46 2436.83 5842.03 No background subtract performed an this spectrum.

Net Peak Net Area Continuum Area Uncertainty Counts 5.97E+Ol 9.36 l.13E+Ol l.79E+Ol 5.83 6.06E+OO 9.41E+Ol 10.55 4.88E+OO NUCLIDE /DENT/FICA T/ON REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCilgrams)

Uncertainty K-40 0.99 1460.82 10.66 2.15E+OO 2.58E-01 Pb-212 0.99 115.18 0.60 2 38.63 43.60

9. 2 4E-02 l.63E-02 300.09 3.30 Bi-2 14 0.99 609.32 45.49 5.20E-02

1. 72E-02 768.36 4.89 806.18

1. 26 934.06 3.11 1120.29 14.92 1155.21

1. 63 1238.12 5.83 1280.98

1. 43 1377.67 3.99 1385.31 0.79 FWHM (keV) 0.81 0.69 0.87

[75]

Analysis Report for 29-Mar-17-10018 L3-10205A-FRGC-005CV Nuclide Name Bi-214 Id Confidence 0.99 Energy (keV) 1401.52 1407.99 1509.21 1661. 27 1729.59 1764.49 1847.43 2118.51

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma Yield(%)

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 3/29/2017 10:59:05AM Page 3 of6 Activity (pCilgrams)

Activity Uncertainty INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Pb-21 2 Bi-214 Nuclide Id Confidence 0.994 0.999 0.991

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCi!grams) 2.lSE+OO 9.24E-02 5.20E-02

= nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma wt mean Comments Activity Uncertainty 2.58E-01 1.63E-02

1. 72E-02

[76]

3/29/2017 10:59:05AM Analysis Report for 29-Mar-17-10018

+

L3-10205A-FRGC-005CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 10:58:59AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCilgrams)

(pCilgrams)

BE-7 477.60 10.44 2.53E-01 3.58E-01 3.58E-01 K-40 1460.82 10.66 2.15E+OO 3.86E-01 3.86E-01 Co-60 1173.23 99.85

-2.69E-02 2.54E-02 3.05E-02 1332.49 99.98

-2.22E-02 2.54E-02 Nb-94 702.65 99.81

-5.54E-03 1.98E-02 1.98E-02 871.09 99.89 1.86E-02 3.18E-02 Ag-108m 79.13 6.60 6.04E-01 2.45E-02 7.23E-01 433.94 90.50 1.29E-03 2.45E-0 2 614.28 89.80

-2.54E-02 4.23E-0 2 722.94 90.80

-4.09E-04 2.95E-02 Sb-125 176.31 6.84 1.66E-01 8.97E-02 3.16E-01 380.45

1. 52 7.33E-01 1.67E+00 427.87 29.60 4.56E-02 8.97E-02 463.36 10.49 1.59E-02 2.22E- 01 600.60 17.65 1.54E-02 1.44E-01 606. 71 4.98

1. llE+OO 8.99E-01 635.95

11. 22

-5.68E-02 2.19E-01 671.44

1. 79

-8.30E-01 1.36E+OO Ba-133 79.61 2.65 1.12E+OO 3.86E-02 l.73E+OO Page 4 of6 Tolerance Nuclide

[77]

3/29/2017 10:59:05AM Page 5 of6 Analysis Report for 29-Mar-17-10018 L3-10205A-FRGC-005CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl/grams)

(pCilgrams)

(pCilgrams)

Ba-133

81. 00 32.90

-1.48E-01 3.86E-02 1.06E-01 276.40 7.16 5.07E-02 3.22E-01 302.85 18.34 6.12E-02 l.23E-01 356.01 62.05

-4.65E-02 3.86E-02 383.85 8.94

1. llE-01 2.79E-01 Cs-134 4:5.36

1. 48 1.71E+OO 3.81E-02 2.34E+OO 563.25 8.34

- 2.74E-01 3.03E-01 569.33 15.37 l.35E-02 l.95E-01 604. 72 97.62

-1.35E-02 3.81E-02 795.86 85.46 3.55E-02 4.44E-02 801.95 8.69 5.79E-0 2 3.72E-01 1038.61 0.99

-2.43E-01

3. 51E+OO 1167.97

1. 79 3.30E-01 2.27E+OO 1365.19 3.02 l.54E-01 7.43E-'01 Cs-137 6 61. 6 6 85.10 l.51E-03 3.62E-02 3.62E-02 Eu-152 121.78 28.67

2. 64E-02 7.44E-02 7.44E-02 244.70 7.61 4.28E-02 3.13E-01 2 95.94 0.45 4.54E-02 4.79E+OO 344.28 2 6.60 6.77E-03 8.31E-02 367.79 0.86

-4.14E-01 2.69E+OO 411.12 2. 2 4

-5.75E-01 9.25E-01 443.96 2.83

-l.21E- 01 6.97E-01 488.68 0.42 2.36E+OO 5.22E+OO 563.99 0.49

1. 33E+OO 5.61E+OO 586. 2 6 0.46 7.92E+00 8.60E+OO 678.62 0.47 4.04E+OO 7.00E+OO 688.67 0.86

-1. OlE+OO 2.75E+OO 719.35 0.28 5.84E+OO 9. 97E+OO 778.90 12.96

-2. llE-02 2.44E-01 810.45 0.32 3.51E+OO 7.80E+OO 867.37 4.26

-4.95E-Ol 6.51E-01 919.33 0.43 6.46E-0 1 6. 40E+OO 964.08 14.65

-1. 37E-01

2. 51E-01 1085.87

10. 24

-9.16E-02 3.00E-01 1089.74

1. 73 6.86E-01 l.67E+OO 1112. 07

13. 69 l.32E-01 2.53E-01 1212.95

1. 43

-1. llE+OO 2.80E+OO 1249.94 0.19

- 9.36E+OO l.79E+Ol 1299.14

1. 63 3.35E-01 2.37E+OO 1408.01 21.07 3.37E-02 l.26E-01 1457.64 0.50 4.58E+Ol 2.51E+Ol 1528.10

0. 28

-9.18E+OO

1. OOE+Ol Eu-154 123.07 40.40 1.63E-02 5.0lE-02 5.0lE-02 247.93 6.89 8.83E-0 2

3. llE-01 591.76 4.95 2.lOE-01

5. 26E-01 692.42

1. 78

-3. llE-01 l.40E+OO 723.30 2 0.06 3.87E-02 l.34E-01 756.80 4.52

-1.06E-01 5.86E-0 1 873.18 12.08

-1.75E-02 2.53E-01 996. 2 9 10.48

-l.07E-01 2.92E-01 1004.76 1 8.01 l.41E-0 2 l.62E-01 1274.43 34.80

- 6.57E-0 2 1.09E-Ol

[78]

3/29/2017 10:59:05AM Page 6 of6 Analysis Report for 29-Mar-17-10018 L3-10205A-FRGC-005CV Nuclide Energy Yie/d{°/o)

Activity NuclideMDA LineMDA Name (keV)

(pCl/grams)

(pCilgrams)

(pCi/grams)

Eu-154 1596.48

1. 80

-7. 2 8E-01 5.0lE-02 1.41E+OO Eu-155 45.30

1. 31

-8.50E-01 1.lOE-01 5.771;:+00 60.01

1. 22

-1.llE+OO 5.39E+OO 86.55 30.70 7.02E-02 1.llE-01 105.31

21. 10 5.56E-02 1.lOE-01 Ra-22 6 186. 21 3.64 3.0lE-01 5.88E-01 5.88E-01 Pa-23 1 27.36 10.30 O.OOE+OO

6. 83E-02 6.83E-02 283.69

1. 70 9.70E-03

1. 30E+OO 300.07

2. 47

-2.2 7E-01

8. '7 6:E;-01 302.65 2. 2 0 5.37E-01

1. 04E+OO 330.06

1. 40

1. 7 9E-02 1.68E+OO U-235 143.76 10.96

-2.21E-04 3.74E-02 1.86E-01 163.33 5.08 2.26E-0 1 4.lBE-01 185.71 57.2 0 1.lBE-02 3.74E-02 202.11

1. 08 1.14E-01 1.85E+OO 205.31 5.01

-2.91E-01 4.06E-01 Am-241 59.54 35.90

-2.16E-01

1. 69E-01 1.69E-01

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[79]

60 55 50 45 40 35 1000 2000

~

ROI Type: 1 3000 0000002623.CNF 4000 channel 5000 Live Time :600.000 sec Real Time :600.300 sec start:

1: -0.0(kev) stop : 8192:2047.S(kev)

Acq. start :wed Mar 29 10: 48: 56 2017 6000 7000 8000

[80]

3/29/2017 11:10:36AM

.......:!§~~pex-Gamma Analysis Report for 29-Mar-17-10019 L3-10205A-FRGC-006CV GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10019

L3-10205A-FRGC-006CV

Sand 1.688E+03 grams

Default

3/24/2017 9:18:00AM

3/29/2017 11 :00:27 AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.4 seconds

0.06%

3.00

120-8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11 /16/16

2625

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 11 :10:30AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of6

[81]

3/29/2017 11 :10:36AM Page 2 of6 Analysis Report for 29-Mar-17-10019 L3-10205A-FRGC-006CV Peak Energy ROI No.

(keV) start 1

238.62 948 -

2 351.77 1401 -

3 583. 29 232 7 -

4 1460.88 5833 -

M = First peak in a_ multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 960 1412 2336 5851 Peak Centroid 954.07 1406.10 2331. 28 5841.47 No background subtract performed on this spectrum.

Net Peak Net Area Continuum Area Uncertainty Counts 5.04E+Ol 10.76 2.46E+Ol 3.40E+Ol 7.68 9.95E+OO 1.77E+Ol 5.07 3.32E+OO 8.70E+Ol

9. 33 O.OOE+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDE$

Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCi/grams)

Uncertainty K-40 0.99 1460.82 10.66 2.07E+OO 2.39E-Ol Tl-208 0.99 583.19 85.00 2.77E-02 8.09E-03 Bi-211 0.92 351. 07 13.02 2.41E-01 5.76E-02 Pb-21 2

1. 00 115.18 0.60 238.63 43.60 8.12E-02 1.85E-02 300.09 3.30 Pb-214 0.99 241.99 7.25 2 95. 2 2 13.42 351.93 35.60 8.80E-02 2. llE-02 785.96

1. 06 FWHM (keV) 0.94 0.36 0.43

1. 53

[82]

Analysis Report for 29-Mar-17-10019 L3-10205A-FRGC-006CV

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma 3/29/2017 11 :10:36AM INTERFERENCE CORRECTED REPORT

?

?

? =

X =

@ =

Nuclide Name K-40 Tl-208 Bi-211 Pb-21 2 Pb-214 Nuclide Id Confidence 0.999 0.998 0.924 1.000 0.998 nuclide is part of an undetermined solution nuclide rejected by the interference analysis Wt mean Activity (pCilgrams) 2.07E+OO 2.77E-02 2.41E-01 8.12E-02 8.80E-02 nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Activity Uncertainty 2.39E-01 8.09E-03 5.76E-02 l.85E-02 2. llE-02 Page 3 of6 Comments

[83]

3/29/2017 11: 10:36AM Analysis Report for 29-Mar-17-10019

+

L3-10205A-FRGC-006CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/201 7 11:10:30AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCi/grams)

(pCl/grams)

BE-7 477.60 10.44 1.47E-01 3.43E-01 3.43E-01 K-40 1460.82 10.66 2.07E+00 6.84E-02 6.84E-02 Co-60 1173. 23 99.85 l.46E-02 4.23E-02 4.23E-02 1332.49 99.98 8.22E-03 4.44E-02 Nb-94 702.65 99.81 1.13E-02 2.85E-02

2. 85E-02 871. 09 99.89

-3.lOE-02 3.31E-02 Ag-108m 79.13 6.60 1.29E-01 2.82E-02 6.76E-01 433.94 90.50

-3.50E-03 2.82E-0 2 614.28 89.80

-1.77E-02 4.05E-02 722.94 90.80

-7.73E-03 3.32E-02 Sb-125 176.31 6.84

-8.55E-02 8.77E-02 2.91E-01 380.45

1. 52

-3.54E-01 1.57E+OO 427.87 29.60

-2.25E-02 8.77E-02 463. 3 6 10.49

-9.62E-04 2.24E-01 600.60 17.65

-1.74E-01 1.33E-01 606.71 4.98 1.02E+OO 8.83E-01 635.95

11. 22 6.88E-02

3. 14E-01 671. 44

1. 79 2.06E-02 1.48E+OO Ba-13 3 79.61 2.65 3.37E-01 4.23E- 02 1.66E+OO Page 4 of6 Tolerance Nuclide

[84]

3/29/2017 11:10:36AM Page 5 of6 Analysis Report for 29-Mar-17-10019 L3-10205A-FRGC-006CV Nuclide Energy Yield(%)

Activity NuclideMDA LlneMDA Name (keV)

(pCi/grams)

(pCl/grams),

(pCi/grams)

Ba-133

81. 00 32.90

-5. 24E-02 4.23E-02 l.15E-01 276.40 7.16 1.60E-01 3.61E-01 302.85 18.34

-5.53E-0 2 1.0BE-01 356.01 62.05

-3.56E-02 4.23E-02 383.85 8.94 9.63E-02 2.49E-01 Cs-134 475.36

1. 48 6.32E-01 3.56E-02 2.24E+OO 563. 25 8.34 l.50E-01 3.25E-Ol

,569.33 15. 37

-1. 86E-02 1.60E-Ol 604. 72 97.62

- 2.84E-0 2 3.56E-02 795.86 85.46 1.53E-02 4.05E-02 801. 95 8.69

-3.22E-01 3.32E-01 1038.61 0.99

-5.0SE-02 3.80E+OO 1167. 97

1. 79

- 2.24E+00 1.88E+OO 1365.19 3.0 2 6.41E-01

1. 32E+OO Cs-137 661.66 85.10

- 1.. 28E-02 3.33E-02 3.33E-02 Eu-152 121. 78 28.67 2.34E-02 7.45E-02 7.45E-02 244.70 7.61 1.30E-01 3.2GE-01 2 95. 94 0.45

-1.32E+OO 5.23E+OO 344.28 2 6.60

-3.0lE-02 8.47E-02 367.79 0.86 8. 33E-01 2.57E+OO 411.12 2.24

-6.08E-01 9.63E-01 443.96 2.83

- 8.58E-03 8.97E-01 488.68 0.4 2

-1.59E+OO 6.15E+OO 563.99 0.49

-3.36E+OO 4.97E+OO 586.26 0.46 4.42E+OO 8.07E+OO 678.62 0.47

- 2.67E+OO 5.89E+OO 688.67 0.86

-3.05E-01 2. 8oE+OO 719.35 0.28

-3.88E+OO 9. 97E+OO 778.90

12. 96

-7.95E-03 2.85E-01 810.45 0.32

- 1.83E+OO 8.12E+OO 867.37

4. 2 6

-1. llE-01 8.31E-0 1 919. 33 0.43

-3.67E-01 6.66E+OO 964. 08 14.65 1.33E-01 3.00E-01 1085.87

10. 2 4

-6.02E-02 3.12E-01 1089.74

1. 73

-4.38E-01

2. 2 4E+OO 1112. 07 13.69

-1.75E-01 2.97E-01 1212.95

1. 43 3.30E-01 2.55E+OO 1249.94 0.19 5.13E+OO 2.33E+Ol 1299.14

1. 63 1.14E+OO 2. 35E+OO 1408.01 21.07

-l.14E-01 1. 46E-Ol 1457.64 0.50 4.43E+Ol 2.41E+Ol 1528.10 0.28 4.66E+OO 1.27E+Ol Eu-154 123.07 40.40

-5.24E-03

5. llE-02

5. llE-0 2 247.93 6.89 1.15E-01 3.15E-01 591.76 4.95 2.34E-01 5.66E-01 692.42

1. 78 1.06E-01 1.59E+OO 723. 30 2 0.06 2.37E-03 1.56E-01 756.80 4.52 1.77E-01 4.81E - 01 873.18 12.08 1.07E-0 2 3.13E-01 996.29 10.48

-2.37E-01 3.97E-01 1004.76 18.01 9.89E-02 2.18E-01 1274.43 34.80 2.17E-02 1.19E-01

[85]

3/29/2017 11:10:36AM Page 6 of6 Analysis Report for 29-Mar-17-10019 L3-10205A-FRGC-006CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCi!grams)

(pCi!grams)

Eu-154 1596.48

1. 80

-1. 24E+OO

5. llE-02 1.70E+OO Eu-155 45.30

1. 31 2.21E+OO l.12E-01 6.61E+OO 60.0 1

1. 22 2.6 1 E-O l 6. 47E+OO 86.55 30.70

-5.08E-0 2 1.12E-01 105.31 21.10 4.15E-02

1. 19E-01 Ra-2 2 6 186.21 3.64

-8.55E-02 5.45E-01 5.45E-01 Pa-231 27.36 10.30 O.OOE+OO

7. llE-02

7. llE-0 2 283.69

1. 70

-6.99E-01 1.32E+OO 30 0. 07 2.47

-2.98E-01 7.55E-01 302.65 2. 2 0

-4.32E-01 8.75E-01 330. 0 6

1. 40

- 1.07E+OO

1. 80E+OO U-235 143.76 10.96 5.67E-02 3.38E-0 2

1. 95E-01 163.33 5.08 5.20E-02 3.94E-01 185. 71 57.20

-8.27E-03 3.38E-02 20 2.11

1. 08

-2.84E-01 l.90E+OO 205.31 5.01 8.41E-02 4.33E-01 Am-24 1 59.54 35.90

-6.9:3E-02 2.18E-01 2.18E-01

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[86]

60 55 50 45 40 GO

~

I-1000 2000

~

ROI Type: 1 3000 0000002625.CNF 4000 channel 5000 Live Tire :600.000 sec Real Tire :600.390 sec start:

1: -0.0(kev)

Stop : 8192: 2047. B(kev)

Acq. start :wed Mar 29 11:00:27 2017 6000 7000 8000

[87]

3/29/2017 11 :21 :38AM

~pex-Gamma Analysis Report for 29-Mar-17-10020 L3-10205A-FRGC-007CV GAMMA SPECTRUM ANAL YS/S Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10020

L3-10205A-FRGC-007CV

Sand 1.634E+03 grams

Default

3/24/2017 9:27:00AM

3/29/2017 11 :11 :30AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.3 seconds

0.05%

3.00

120-8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11/16/16

2626

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 11 :21 :32AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of6

[88]

3/29/2017 11 :21 :38AM Page 2 of6 Analysis Report for 29-Mar-17-10020 L3-10205A-FRGC-007CV Peak Energy ROI No.

(keV) start 1

238.72 949 -

2 295.16 1176 -

3 351.75 1400 -

4 609.14 2430 -

5 1461.16 5835 -

M = First peak In a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 959 1185 1411 2439 5851 Peak Centroid 954.44 1179.93 1406.03 2434.62 5842.60 No background subtract performed on this spectrum.

Net Peak NetArea Continuum Area Uncertainty Counts 4.20E+Ol

8. 71 1.40E+Ol 2.09E+Ol 5.88 6.07E+OO 3.58E+Ol 7.36 7.24E+OO 1.95E+Ol 6.12 7.50E+00 7.70E+Ol 9.88 7.04E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCilgrams)

Uncertainty K-40 0.98 1460.82 10.66

1. 89E+OO 2.56E-Ol Pb-21 2 0.99 115.18 0.60 238.63 43.60 7.00E-02 1.56E-02 300.09 3.30 Bi-214 0. 99 609. 32 45.49 6.07E-02 1.94E-02 768.36 4.89 806.18

1. 2 6 934.06 3.11 1120.29 14.92 1155.21

1. 63 1238.12 5.83 1280.98

1. 43 FWHM (keV) 0.60

1. 03

0. 96 0.52 0.42

[89]

Analysis Report for 29-Mar-17-10020 L3-10205A-FRGC-007CV Nuclide Id Energy Name Confidence (keV)

Bi-214 0.99 1377. 67 13'85.31 1401.52 1407.99 1509.21 1661. 27 1729.59 1764.49 1847.43 2118.51 Pb-214 0.99 2 41.99 2 95. 22 351.93 785. 96

• "' Energy line found in the spectrum.

"' Manually added nuclide.

? "' Manually edited nuclide.

'~

@ "' Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma 3/29/2017 11:21:38AM Page 3 of6 Yield(%)

Activity Activity (pCilgrams)

Uncertainty 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 7.25 18.42 9.43E-02 2.76E-02 35.60 9.55E-02 2. llE-0 2

1. 06 INTERFERENCE CORRECTED REPORT Nuclide Name K-40 X

Bi-211 Pb-21 2 Bi-214 Pb-214 Nuclide Id Confidence 0.981 0.928 0.999 0.998 0.997

?

= nuclide is part of an undetermined solution X

"' nuclide rejected by the interference analysis Wt mean Activity (pCl/grams) 1.89E+OO 7.00E-02 6.0 7E-02 9.50E-02

"' nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Comments Activity Uncertainty 2.56E-01 1.56E-02

1. 94E-02 1.67E-02

[90]

3/29/2017 11 :21 :38AM Analysis Report for 29-Mar-17-10020

+

L3-10205A-FRGC-007CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 11 :21 :32AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity Nuc/ideMDA LineMDA Name (keV)

(pCUgrams)

(pCl/grams)

(pCilgrams)

BE-7 477. 60 10.44 1.66E-01 3.15E-01 3.15E-01 K-40 1460.82 10.66 1.89E+OO 4.50E-01 4.50E-01 Co-60 1173.23 99.85 3.57E-03 2. 73E-02 3.69E-02 1332. 49 99.98

-2.38E-02 2.73E-02 Nb-94 702.65 99.81 6.47E-03 3.06E-02 3.06E-02 871.09 99.89

1. 05E-02 3.55E-02 Ag-108m

79. 13 6.60 1.50E-01 2.63E-02 6.09E-0 1 433.94 90.50 1.30E-02 2.63E-02 614.28 89.80

-2.04E-02 4.03E-02 722. 94 90.80 4.lOE-03 3.04E-02 Sb-125 176.31 6.84 1.22E-0 2 5.80E-02 2.90E-01 380.45

1. 52

-7.84E-01 1.35E+OO 427.87 29.60 -l. 56E-01 5.80E-02 463.36 10.49

l. 22E- 01 2.09E-01 60 0.60 17.65 7.60E-02 2.06E-01 606. 71 4.98 3.91E-01 9.77E-01 635.95

11. 22

-l.41E-01 1.63E-01 671.44

1. 79

-2.76E-01 1.60E+OO Ba-133 79.61 2.65 2. 19E-01 3.59E-02 1.45E+OO Page4 of6 Tolerance Nuclide

[91]

3/29/2017 11:21 :38AM Page 5 of6 Analysis Report for 29-Mar-17-10020 L3-10205A-FRGC-007CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl/grams)

(pCilgrams)

(pCilgrams)

Ba-133 81.00 32.90

-8.52E-02 3.59E-02 1.04E-01 276.40 7.16 3.82E-02 3.20E-01 302.85 18.34

-2.42E-03 1.37E-01 356.01 62.05

-3.12E- 02 3.59E-02 383.85 8.94

-2.84E-02 2.37E-01 Cs-134 475.36

1. 48

1. 31E+O O 3.77E-0 2 2.17E+OO 563.25 8.34

6. 4 6E-02 3.15E-01 569.33

15. 37

-1. 20E-01 1.59E-01 604. 72 97.62

-1.35E-02 4.53E-0 2 795.86 85.46 2.55E-03 3.77E-02 80 1.95 8.69 1.35E-01 3.73E-01 1038.61 0.99

1. 25E+OO 3.06E+OO 1167. 97

1. 79

-2.31E+OO 1.70E+OO 1365.19 3. 02

-1.70E+OO

9. 2 6E-01 Cs-137 661.66 85.1 0 2.49E-03 3.32E-02 3.32E-02 Eu-152 121. 78 28.67 1.60E-02 6.68E-02 6.68E-02 244.70 7.6 1

-5.33E-02 3.15E-01 2 95. 94 0.45 2.33E+OO 6.52E+OO 344. 28 2 6.60

-1.73E-02 8.56E-02 367.79 0.86 1.23E+OO 2.65E+OO 411. 12 2.24 5.13E-01 l.14E+OO 443. 96 2.83 3.66E-01 8.56E-01 488.68 0.42 2.95E+OO 6.85E+OO 563.99 0.49 2.03E+OO 5.13E+OO 586. 2 6

0. 46 9.60E+OO 9.00E+OO 678.62 0.47 4.7 5E-01 5.04E+OO 688.67 0.86 l.62E+O O 3.63E+OO 71 9.35 0.28 1.84E+OO 9.39E+OO 778. 90

12. 96

-2.92E-02 2.14E-01 810.45 0.32 1.62E+00 6.03E+OO 867.37 4.26

-5.68E-01 6.23E-01 919.33 0.43 3.98E+OO

'.64E+OO 964.08 14.65 2.00E-02 2.69E-01 1085.87 10.24

-1.55E-0 2 3.03E-01 1089.74

1. 73

-2.92E-01 1.53E+OO 1112. 07 13. 69 l.58E-01 2.84E-01 1212.95

1. 43 1.20E-01 3.24E+OO 1249.94 0.19

- 5.87E+OO 2.03E+Ol 1299.14

1. 63 3.62E-01 2.66E+OO 1408.01 21.07 1.21E-02 9.28E-02 1457.64 0.50 4.30E+ 01 2.54E+Ol 1528.10 0.28 2.89E+OO

1. 08E+Ol Eu-15 4 123.07 40.40

-4.27E-02 4.46E-02 4.46E-02 247.93 6.89 1.15E-01 3.24E-01 591.76 4.95

-5.87E-02 5.27E-01 692.42

1. 78

-2.03E+OO

1. 28E+00 723. 30 2 0.06

-1.79E-02 1.31E-0 1 756.80 4.52

-1.34E-01 4.08E-01 873.18 12.08 2. 2 6E-01 3.24E-01 996. 2 9 10.48

1. 72E-01 3.30E-01 1004.76 18.01

-3.64E-0 2 1.84E-01 1274.43 34.80 4.08E-02 9.95E-02

[92]

3/29/2017 11:21:38AM Page 6 of6 Analysis Report for 29-Mar-17-10020 L3-10205A-FRGC-007CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCi/grams)

(pCl/grams)

Eu-154 1596.48

1. 80 O.OOE+OO 4.46E-02 4.50E-01 Eu-155 45.30

1. 31 1.99E+OO 1.13E-0 1 6.04E+OO 60.01

1. 22

-1.20E+00 5.60E+OO 86.55 30.70 6.46E-02 l.16E-01 105.31 21. 10 8.05E-03 1.13E-01 Ra-22 6 186.2 1 3.64 8.67E-02 6.14E-01 6.14E-01 Pa-231

27. 3 6 10.30 O.OOE+OO 7.34E-02 7.34E-02 283.69

1. 70

-1.12E+OO 1.26E+OO 300.07 2.47

-7.49E-01 9.47E-01 302.65 2.20

-4.90E-02 1.14E+OO 330.06

1. 40 5.76E-01 1.70E+OO U-235 143.76

10. 96 l.70E-02 3.82E-02 2.00E-01 163.33 5.08 l.47E-01 3.88E-01 185.7 1

57. 20 2.78E-03 3.82E-02 202. 11

1. 08

1. 73E-01

1. 96E+OO 205.3 1 5.01 2.00E-02 4.37E-01 Am-24 1 59.54 35.90 8.48E-02

2. 03E-01 2.03E-01

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[93]

60 55 50 45 1000 2000 3000

~

ROI Type: 1 0000002626.CNF 4000 channel 5000 Live Time :600.000 sec Real Time : 600.320 sec start:

1: -0.0(kev)

Stop : 8192:2047.B(keV)

Acq. start :wed Mar 29 11:11:30 2017 6000 7000 8000

[94]

3/29/2017 11 :33:00AM

~~~pex-Gamma Analysis Report for 29-Mar-17-10021 L3-10205A-FRGC-008CV GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate.Date

29-Mar-17-10021

L3-10205A-FRGC-008CV

Sand 1.649E+03 grams

Default

3/24/2017 9:30:00AM

3/29/2017 11 :22:52AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.3 seconds

0.06%

3.00

120-8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11/16/16

2627

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 11:32:SSAM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of6

[95]

3/29/2017 11 :33:00AM Page 2 0(6 Analysis Report for 29-Mar-17-10021 L3-10205A-FRGC-008CV Peak Energy ROI No.

(keV) start 1

2 38.64 949 -

2 351.53 1401 -

3 1460.89 5833 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 959 1409 5851 Peak Centroid 954.15 1405.14 5841. 52 No background subtract performed on this spectrum.

NetPeak Net Area Continuum Area Uncertainty Counts 4.73E+O l

10. 32 2.47E+Ol

1. 54E+O l 5.86 7.61E+OO 9.93E+O l 10. 74 4.75E+OO NUCLIDE /DENT/FICA TJON REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\Z!ON LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCi/grams)

Uncertainty K-40 0.99 1460.82 10.66 2.42E+OO 2.82E-01 Bi-211 0.96 351.07 13.02

1. llE-01 4.33E-0 2 Pb-212

1. 00 115. 18 0.60 238.63 43.60 7.79E-02

1. 81E-02 30 0.09 3.30 Pb-214 0.98 2 41.99 7.25 2 95.22 18.42 351.93 35.60 4.07E-02 1. 58E- 02 785.96

1. 06 FWHM (keV) 0.87 0.46 0.93

[96]

Analysis Report for 29-Mar-17-10021 L3-10205A-FRGC-008CV

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma 3/29/2017 11 :33:00AM INTERFERENCE CORRECTED REPORT Nuclide Name K-40

?

Bi-211 Pb-21 2

?

Pb-21 4 Nuclide Id Confidence 0.999

0. 967

1. 000 0.985

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCi/grams) 2.42E+OO l.llE-01 7.79E-02 4.07E-02

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Activity Uncertainty 2.82E-01 4.33E-02 1.81E-02 1.58E-02 Page 3 of6 Comments

[97]

3/29/2017 11 :33:00AM Analysis Report for 29-Mar-17-10021

+

L3-10205A-FRGC-008CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 11 :32:54AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LlneMDA Name (keV)

(pCl/grams)

(pCi/grams)

(pCilgrams)

BE-7 477.60

10. 4 4 3.41E-02 3.30E-01 3.30E-01 K-40 1460.82 1 0.66 2.42E+OO 4. 02E-01 4.02E-01 Co-60 1173.23 99.85

1. 56E-0 2 3.29E-02 3.46E-02 1332.49 99.98 1.21E-02

3. 2 9E-02 Nb-94 702.65 99.8 1

-1.32E-02 2.45E- 02 2.92E-02 871.09 99.89

-2.48E-02 2.45E-0 2 Ag-108m 79.13 6.60

-1.54E-01 3.02E-02

6. 27E-0 1 433.94 90. 50 1.45E-02 3.02E-02 614. 2 8 89. 80

-1.14E-02 4.15E-02 722.94 90.80

-6.03E-04 3.52E-02 Sl.J-125 176.31 6.84 4.39E-0 2 8.36E-02 2.98E-01 380.45

1. 52

-2. 2 9E-01

1. 54E+OO 427.87 29.60 3.45E-0 2 8.36E-02 463.36 10. 49 1.25E-03 2.80E-01 600.60 17.65 6.91E-02

1. 83E-01 606.71 4.98 6.89E-01 7.97E-01 635.95

11. 22 1.16E-01 2.78E-01 671. 44

1. 79

-7.18E-01

1. 45E+OO Ba-13 3 79.61 2.65

-9.74E-01 4.12E-02

1. 48E+OO Page 4 of6 Tolerance Nuclide

[98]

3/29/2017 11:33:00AM Page 5 of6 Analysis Report for 29-Mar-17-10021 L3-10205A-FRGC-OOBCV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl/grams)

(pCilgrams)

(pCi/grams)

Ba-133

81. 00 32.90

-1.07E-01 4.12E-02 1.0lE-01 276.40 7.16 7.09E-02 3.19E-01 302.85 18.34 5.99E-02 1.37E-01 356.0 1 62.05

-3.63E-02 4.12E-02 383.85 8. 94

1. 71E-01 2.68E-01 Cs-134 475.36

1. 48 1.14E+O O 3.42E-02 2.18E+OO 563.25 8.34

-2.18E-02 3.23E-01 569.33 15.37

-4.53E-02 1.36E-01 604. 72 97.62

-3. 23E-02 3.42E-02 795.86 85.46 7.46E-03 4.14E-0 2 801.95 8.69

-2.lOE-01 3.23E-01 1038.61 0.99 2.48E+OO 4.03E+OO 1167.97

1. 79

-8.36E-01 l.69E+OO 1365. 1 9 3.0 2 2.46E-01

9. 17E-01 Cs-137 661. 66 85.10 1.47E-02 3.53E-0 2 3.'j3E-02 Eu-152 121. 7 8 28.67

-::2.23E-02 7.55E-02 7.55E-0 2 244.70 7. 61

-1.64E- 01 2.97E-01 295.94 0. 45 7.44E-01 5.52E+OO 344. 2 8 2 6.60 7.88E-03 9.37E-02 367.79 0.86

-6.74E-01 3.19E+00 411. 12 2. 2 4 1.66E-01 1.15E+OO 443.96 2.8 3 1.49E-01 8.95E-01 488.68

0. 42 1.64E+OO 5.36E+OO 563.99 0.49

1. 02E-01 5.64E+OO 586.26 0.46

-l.49E-01 7.07E+OO 678.62 0.47

-2.30E+OO 6.48E+OO 688.67 0.86

-2.90E-01 3.47E+OO 719.35 0.28

-5.llE+OO 8.27E+OO 778.90

12. 96

-2.93E-01 2.12E-01 810.45 0.32

1. 4 7E+OO 1.08E+Ol 867.37 4.26 5.lOE-02 6.17E-01 919.33 0.43

-7.0lE+OO 7.91E+OO 964.08 14.65 9.92E-03 2.58E-01 1085.87 10.24

-3.25E-01 3. 20E-01 1089. 74

1. 73

-2.02E+OO 1.90E+OO 1112.0:'

13.69 2.65E-01 3.54E-01 1212.95

1. 43

-6.94E-01

3. 2 1E+OO 1249.94 0.19 5.51E+OO 2. llE+Ol 12 99. 1 4

1. 63

-1.16E-01 2.14E+OO 1408. 01

21. 07

-3.14E-02 1.16E-01 1457. 64 0. 50 5.08E+Ol 2. 72E+Ol 1528. 10 0.28 1.91E+OO 9.22E+OO Eu-154 123. 07 40.40

- 9.34E-0 3 5.23E-02 5.23E-02 247.93 6.89

-3.80E-02 2.93E-01 591. 76 4.95 1.85E-01 5.22E-01 692.42

1. 78

-7.35E-01 1.63E+OO 723. 30 20.06

-4.71E-03 1.59E-01 756.80 4.52

-4.52E-03

5. 2 9E-01 873.18 12.08

-1.49E-01 2.19E-01 996.29 10.48

-l.OlE-01 2.77E-01 1004.76 18.01

- 3.60E-0 2 2.00E-01 1274.4 3 34.80

4. 72E-0 2 1.05E-01

[99]

3/29/2017 11:33:00AM Page 6 of6 Analysis Report for 29-Mar-17-10021 L3-10205A-FRGC-008CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi!grams)

(pCilgrams)

(pCl!grams)

Eu-154 1596.48

1. 80 3.lOE-01

5. 23E-02

1. 50E+OO Eu-155 45.30

1. 31

-5.66E-01

1. llE-01 5.63E+00 60.01

1. 22 9.81E-01 6.70E+OO 86.55 30.70

7. 2 4E-03

1. llE-01 105.31 21.10 8.64E-02 1.18E-01 Ra-22 6 186.21 3. 64 6.18E-01 7.19E-0 1 7.19E-01 Pa-231 27.36 10.30 O.OOE+OO

7. 2 7E-02

7. 27E-0 :::'.

283.69

1. 70

-3.29E-01 1.05E+OO 300.07 2.47 3.31E-01 1.07E+OO 302.65 2.20 2.17E-01 1.14E+OO 330. 0 6

1. 40

-7.38E-01 1.66E+OO U-23 5 143.76

10. 96

l. 2 7E-01 4.44E-0 2 2.03E- 01 163.33 5.08 2.00E-01 3.99E-01 185. 71 57: 2 0

2. 22E-02 4.44E-0 2 202.11

1. 08

-8.66E- 01 1.94E+OO 205.31 5.01 8.36E-02 4.48E-01 Arn-241 59.54 35.90

-5.61E-02 2. 2 6E- 01 2.26E-0 1

+

= Nuclide identified during the nuclide identification

= Energy line found in the spectrum

= MDA value not calculated

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

?

= CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[100]

60 55 50 45 40 35 1000

~

ROI Type: 1

..-< 7 H..

2000 3000 0000002627.CNF 4000 channel 5000 Live Time :600.000 sec Real Time :600. 340 sec start:

1: -0.0(kev)

Stop : 8192: 2047. B(keV)

Acq. start :wed Mar 29 11: 22: 52 2017 6000 7000 8000

[101]

3/29/2017 11 :44:14AM

~F~pex-Gamma Analysis Report for 29-Mar-17-10022 L3-10205A-FRGC-009CV GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10022

L3-10205A-FRGC-009CV

Sand 1.618E+03 grams

Default

3/24/2017 9:35:00AM

3/29/2017 11 :34:06AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.3 seconds

0.05%

3.00

120 - 8192

120 - 8192

1.000keV

11/10/2016

3/29/2017

initial 11/16/16

2628

1000.00 gram

Eu 155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 11 :44:08AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of7

[102]

3/29/2017 11:44:14AM Page 2 of?

Analysis Report for 29-Mar-17-10022 L3-10205A-FRGC-009CV Peak Energy ROI No.

(keV) start 1

238.66 949 -

2 338.13 1348 -

3 351.91 1401 -

4 583.00 2325 -

5 609.20 2430 -

6 14 61. 00 5832 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 960 1355 1411 2336 2 440 5850.

Peak Centroid 954. 22 1351.58 1406.64 2330.13 2434.83 5841.92 No background subtract performed on this spectrum.

Net Peak Net Area Continuum Area Uncertainty Counts 6.0lE+Ol 12.76 3.99E+Ol

1. 30E+Ol 5.39 8.00E+OO

1. 60E+Ol

6. 49 1.lOE+Ol 2.43E+Ol 6.67 7.66E+OO 2.33E+Ol 6.12 5.70E+OO 1.37E+02 12.38 4.75E+OO I\\JUCLiDt:. iDENTIF/CA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCilgrams)

Uncertainty K-40 0.99 1460. 82 10.66 3.41E+OO 3.41E-01 Tl-208 0.99 58 3.19 85.00 3.97E-02

1. llE-02 Bi-211 0.89 351.07

13. 02 1.18E-01 4.88E-02 Pb-21 2

1. 00 11 5.18 0.60 238.63 43.60 1.0lE-01 2.2 9E-02 300. 0 9 3.30 Bi-2 14 0.99 609. 32 45.49 7.32E-02 1.97E-02 768. 3 6 4.89 806.18

1. 26 93 4.06 3.11 1120. 2 9 14.92 FWHM (keV) 0.61

0. 72 0.67 1.17

1. 03

1. 24

[103]

Analysis Report for 29-Mar-17-10022 L3-10205A-FRGC-009CV Nuclide Id Energy Name Confidence (keV)

Bi-214 0.99 1155.21 1238.12 1280.98 1377.67 1385.31 1401.52 1407.99 1509.2 1 1661. 27 1729.59 17 64.49 1847.43 2118. 51 Pb-214

1. 00 241. 99 295. 22 351.93 785.96 Ac-228 0.99 129. 07 209.25 270.24 328.00 338.32 40 9.46 463.00 794. 95 911. 2 0 964. 77 968.97 1588.20

• = Energy line found in the spectrum.

• = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma 3/29/2017 11:44:14AM Page 3 of7 Yield(%)

Activity Activity (pCilgrams)

Uncertainty

1. 63 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1-. 1 6 7.25 18.42 35.60 4.31E-02 1. 78E-02

1. 06 2. 42 3.89 3.46 2.95

11. 27

1. 07E-01 4.53E-0 2

1. 92 4.40 4.25 25.80 4.99 15.80

3. 22 INTERFERENCE CORRECTED REPORT

[104]

Analysis Report for 29-Mar-17-10022

?

?

? =

X =

L3-10205A-FRGC-009CV Nuclide Nuclide Name Id Confidence K-40 0.995 Tl-208 0.995 Bi-211 0.894 Pb-21 2

1. 000 Bi-2 1 4 0.999 Pb-21 4

1. 000 Ac-228 0.999 nuclide is part of an undetermined solution nuclide rejected by the interference analysis 3/29/2017 Wt mean Activity (pCilgrams) 3.41E+00 3.97E-02

1. lBE-01

1. OlE-01 7.32E-02 4.31E-02 1.07E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma 11:44:14AM Page 4 of7 Wt mean Comments Activity Uncertainty 3.41E-01

1. llE-02 4.BBE-02 2.2 9E-02 1.97E-02 1.78E-02 4.53E-02

[105]

3/29/2017 11 :44:14AM Analysis Report for 29-Mar-17-10022

+

L3-10205A-FRGC-009CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 11 :44:08AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LlneMDA Name (keV)

(pCl/grams)

(pCl/grams)

(pCl/grams)

BE-7 477.60 10.44 2.21E-01

2. 85E-01 2.85E-01 K-40 1460.82 10.6 6 3.41E+00 4.0SE-01 4.08E-01 Co-60 1173.23 99.85

-1.78E-02 3.36E-02 5.00E-02 1332.49 99.9 8

-3. 23E-02 3.36E-02 Nb-94 702.65 99.8 1 1.16E-02 3.40E-02 3.40E-02 871.09 99.89 1.24E-02 4.16E-02 Ag-108m 79.13 6.60 2.93E-01 2.95E-02 6.56E-01 433.94 90.50

-2.12E-03 2.95E-0 2 614.28 89.80

-2.56E-02 4.67E-02 722. 94 90.80

-4.63E-02 4.60E-02 Sb-125 176.31 6.84 3.06E-03 8.30E-0 2 3.07E-01 380.45

1. 52 l.31E+OO 1.74E+OO 427.87 29.60

-9.52E-03 8.30E-0 2 463.36 10.49 8.53E-02 2.48E-01 600.60 17.65

-6.84E-02 l.45E-01 606.71 4.98 7.55E-01 9.43E-01 635.95

11. 22

-1. 12E-01

2. 48E-01 671.44

1. 79

- 6.44E-02 1. 48E+OO Ba-133 79.61 2.65 2.70E-01

4. 27E-02 1.57E+00 Page 5 of7 Tolerance Nuclide

[106]

3/29/2017 11 :44:14AM Page 6 of7 Analysis Report for 29-Mar-17-10022 L3-10205A-FRGC-009CV Nuclide Energy Yield(%)

Activity Nuc/ideMDA LineMDA Name (keV)

(pCl/grams)

(pCilgrams)

(pCilgrams)

Ba-133 81.00 32.90

-4. 24E-02 4.27E-02 9.69E-02 276.40 7.16

1. 89E-01 3.54E-01 302.85 18.34

-3.39E-02 1.26E-01 356.01 62.05

-1.27E-02 4.27E-02 383.85 8.94

-3.85E-02 2.60E-01 Cs-134 475.36

1. 48 9.16E- 01

4. 00E-02 1.98E+OO 563. 25 8.34

-8.73E-04 3.39E-01 569.33 15.37

-5.65E-03 1.80E-01 604. 72 97.62

-3.39E-0 2

4. 0 0E~02 795.86 85.46

-3.33E-03 4.22E-02 801.95 8.69

-6.17E-02 4.04E-01 1038.61 0.99

-5.75E+OO 3.81E+OO 1167.97

1. 79

-4.04E+OO 2.37E+OO 1365.19 3.02

-5.43E-01 9.34E-01 Cs-13 7 661.66 85.10 1.65E-02 4.24E-02

4. 24E-02 Eu-1 52 121. 78 28.67

- 1.55E-02 8.64E-02 8.74E-02 244.70

7. 61

-4.92E-02 3.80E-01 295.94 0.45 2.13E+00 6.85E+OO 344. 2 8 26.60

-2.20E-02 8.64E-0 2 367.79 0.86

1. OOE+OO 3.09E+OO 411.12 2.24

-5.98E-01

1. 20E+OO 443. 96 2.83 2.07E-01 9.13E-01 488.68 0.4 2 3.55E+OO 6.59E+OO 563.99 0.49 3.17E-01 5.92E+OO 586.26 0.46

-4.94E+OO 1.07E+Ol 678.62 0.47 5.56E- 01 4.45E+OO 688.67 0.86 2.44E-02 3.66E+OO 71 9. 35

0. 2 8

-4.16E+OO 1.24E+Ol 778.9 0 12.96 1.97E-02 2.37E-01 810.45 0.3 2 9.52E-01 1.06E+Ol 867.37 4.26

-4.51E-01 7.76E-01 919.33 0.43

-2.70E+OO 8.39E+OO 964.08 14.65 2.52E-01 3.49E-01 1085.87

10. 2 4

-3.77E-02 2.85E-01 1089.74

1. 73 8.69E-01 1.93E+OO 1112. 07 13.69

-7.56E-02 2.48E-01 1212.95

1. 43

-7.65E-01 2.80E+OO 1249.94 0.19

- 1.63E+Ol 2.90E+Ol 1299.14

1. 63 1.06E-01 2.32E+OO 1408.01

21. 07

-1.84E-0 1 1.6oE-01 1457.64 0.50 7.77E+Ol 3.22E+Ol 1528.10 0.2 8 O.OOE+OO 2.80E+OO Eu-154 123.07 40.40

-4.07E-02 5.88E-02 5.88E-02 247.93 6.89 1.23E-01 3.50E-01 591. 7 6 4.95

2. 32E-01

7. 19E-01 692.42

1. 78

7. 27E-01 2.05E+OO 723.30 20.06

-3.12E-02 2.12E-01 756.80 4.5 2 2.99E-01 7.68E-01 873. 1 8 12.08 7.24E-02 3.36E-0 1 996. 2 9 10.48

-2.80E-01

3. 17E-01 10 04.76 18.01 1.60E-02 2.20E-01 1274.43 34.80

-2.99E-02 l.07E-01

[107]

3/29/2017 11:44:14AM Page 7 of7 Analysis Report for 29-Mar-17-10022 L3-10205A-FRGC-009CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCUgrams)

(pCl/grams)

Eu-154 1596.48

1. 80

-2.02E+OO 5.88E-02

l. 21E+OO Eu-155 45.30

1. 31 l.21E+OO 1.12E-01 6.97E+OO 60.01

1. 22

-8.42E-01 6.49E+OO 86.55 30.70

- 3.31E-02 1.12E-01 105. 31 21.10 6.59E-02 1.25E-01 Ra-2 2 6 186.21 3.64 5.0lE-02 6.38E-01 6.38E-01 Pa-231 27.36 10.30 O.OOE+OO 7.41E-02 7.41E-02 283.69

1. 70

-6.00E-01

1. 2 1E+OO 300.07 2.47

-5.88E-01

1. OlE+OO 302.65 2.20 8.12E-02 1.llE+OO 330.06

1. 40 1.98E+OO 2.12E+OO U-235 143.76 10.96

-3.08£-02 4.05E-02 2.24E-01 163. 33 5.08

4. 2 6E-02 4.86E-01 185.71 57.20 1.23E-02 4.0SE-0 2 202.11

1. 08 5.07E-01 2.17E+OO 205.31 5.01

-4.26E-01 4.14E-01 Am-241 59.54 35.90 2. llE-02 2.33E-01 2.33E-01

+

= Nuclide identified during the nuclide identification

= Energy line found in the spectrum

= MDA value not calculated

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

?

= CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[108]

60 55 50 45 40

~

ROI Type: 1 1000 2000 00~

0""

-' w I-X 3000 0000002628.CNF 4000 Channel 5000 Live Time :600.000 sec Real Time :600.310 sec start:

1: -0.0(kev) stop : 8192: 2047.8(kev)

ACq. start :wed Mar 29 11:34:06 2017 6000 7000 8000

[109]

Analysis Report for 29-M ar-17-10024 L3-10205A-FRGC-010CV 3/29/2017 11 :55:33AM GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10024

L3-10205A-FRGC-010CV

Sand

• 1.604E+03 grams Default

• 3/24/2017 10:10:00AM 3/29/2017 11 :45:25AM 130G_Sand Administrator P11314 130G_Sand 600.0 seconds

• 600.3 seconds

0.06%

3.00

120 - 8192

120- 8192

1.000 keV

11/10/2016

3/29/2017

initial 11/16/16

2630

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 11 :55:27 AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of6

[110]

Analysis Report for 29-Mar-17-10024 L3-10205A-FRGC-010CV Peak Energy ROI ROI No.

(keV) start end 1

238.52 948 -

961 2

351.85 1402 - 1411 3

583.51 2328 -

2337 4

911. 64 3639 -

3649 5

1460.95 5833 -

5850 M "" First peak in a multiplet region m "" Other peak in a multiplet region F ""Fitted singlet Errors quoted at 1.000sigma 3/29/2017 11 :55:33AM Peak Net Peak Net Area Centroid Area Uncertainty 953.67 4.56E+Ol 9.98 1406.40 l.58E+Ol 6.17 2332.15 2.06E+Ol

5. 96 3644.00

1. 48E+Ol 4.21 5841.74 7.85E+Ol 9.65 No background subtract performed on this spectrum.

NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Page 2 of6 Continuum FWHM Counts (keV) l.94E+Ol

0. 92 9.20E+OO 0.55 6.44E+OO 0.40 1.23E+OO 0.36 4.50E+OO 0.90 Activity Name Confidence (keV)

(pCilgrams)

Uncertainty K-40 0.99 1460.82 10.66 l.97E+OO 2.56E-01 Tl-208 0.98 583.19 85.00 3.38E-02 1.00E-02 Bi-211 0.90 351.07

13. 02 1.17E-01 4.68E-02 Pb-212 0.99 115. 18 0.60 238.63 43.60 7.73E-02 l.80E-02 300.09 3.30 Pb-214 0.99 241.99 7.25 295.22 18.42 351.93 35.60 4.30E-02 1. 71E-02 785.96

1. 06 Ac-228 0.99 129.07 2.42 209.25 3.89

[111]

Analysis Report for 29-Mar-17-10024 L3-10205A-FRGC-O 1 DCV Nuclide Id Energy Name Confidence (keV)

Ac-228 0.99 270.24 328.00 338.32 409.46 463.00 794.95 911. 20 964.77 968. 97 1588.20

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma 3/29/2017 11 :55:33AM Page 3 of6 Yield(%)

Activity Activity (pCilgrams)

Uncertainty 3.46 2.95

11. 27

1. 92 4.40 4.25 25.80 1.l OE- 01 3.1 6E-02 4.99 15.80 3.22 INTERFERENCE CORRECTED REPORT

?

?

Nuclide Name K-40 Tl-208 Bi-211 Pb-212 Pb-214 Ac-228 Nuclide Id Confidence 0.997 0.984 0.908 0.998 0.999 0.991

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCi/grams) l.97E+OO 3*. 38E-02

1. 17E-Ol 7.73E-02 4.30E-02 1.lOE-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Comments Activity Uncertainty 2.56E-01 1.00E-02 4.68E-02

1. 80E-02 1. 71E-02 3.16E-02

[112]

3/29/2017 11 :55:33AM Analysis Report for 29-Mar-17-10024

+

L3-10205A-FRGC-01 OCV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M "' First peak in a multiplet region m "' other peak in a multiplet region F "' Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 11:55:27AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity Nuc/ideMDA LineMDA Name (keV)

(pCi!grams)

(pCi/grams)

(pCilgrams)

BE-7 477.60 10.44 8.99E-02 2.74E-01 2.74E-01 K-40 1460.82 10.66

1. 97E+OO 3.97E-01 3.97E-Ol Co-60 1173.23 99.85 3.84E-03 3.39E-02 3.56E-02 1332.49 99.98

-l.93E-02 3.39E-02 Nb-94 702.65

99. 81 9.59E-03 2.34E-02 2.34E-02 871.09 99.89

-4.33E-03

2. 71E-02 Ag-108m 79.13 6.60 3.81E-01 2.25E-02 6.85E-01 433.94 90.50

-2.03E-02 2.25E-02 614.28 89.80

-5.08E-02 3.57E-02 722. 94 90.80 5.46E-03 3.37E-D2 Sb-125 176.31 6.84

-1.45E-02 1.00E-01 2.87E-01 380.45

1. 52

-l.65E-01

1. 58E+OO 427.87 29.60 3.87E-02 1.00E-01 463.36 10.49

-1.61E-Ol 2.82E-01 600.60 17.65 8.84E-02 l.74E-01 606.71 4.98 6.44E-02 8.06E-01 635.95 11.12 1.66E-02 2.50E-01 671.4 4

1. 79

1. 19E+OO

2. llE+OO Ba-133 79.61 2.65 9.64E-01 3.83E-02

1. 68E+OO Page4 of6 Tolerance Nuclide

[113]

3/29/2017 11:55:33AM Page 5 of6 Analysis Report for 29-Mar-17-10024 L3-10205A-FRGC-O 1 OCV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCilgrams)

(pCi/grams)

Ba-133

81. 00 32.90

-8.05E-02 3.83E-02 1.15E-01 276.40 7.16

-1.61E-01 3.02E-Ol 302.85 18.34 5.82E-02 l.39E-01 356.01 62.05

-1. 09E-02 3.83E-02 383.85 8.94

-6.93E-02 2.55E-01 Cs-134 475.36

1. 48 3.38E-02 3, 69E-02 1.86E+OO 563.25 8.34 3.82E-03 3.42E-01 569.33 15.37 5.68E-02 1.62E-01 604.72

97. 62

-1.0lE-02 3.90E-02 795.86 85.46

-5. llE-04 3.69E-02 801.95 8.69 O.OOE+OO 2.75E-01 1038.61 0.99

-7.49E-01 4.29E+OO 1167.97

1. 79

-2.87E-01 1.86E+OO 1365.19 3.02 3.37E-01 1.05E+OO Cs-137 661.66 85.10 8.35E-03 4.47E-02 4.47E-02 Eu-152 121. 78 28.67

-1.SSE-02 7.43E-02 7.43E-02 244.70 7.61

-6.65E-02 2.88E-01 295.94 0.45 2.lOE+OO 5.67E+OO 344.28 26.60

-l.48E-02

9. 28E-02 367.79 0.86

-4.98E-Ol 2.49E+OO 411.12 2.24 2.02E-01

l. lOE+OO 443.96 2.83 2.84E-01 7.64E-01 488.68 0.42 8.80E-01

5. 72E+OO 563.99 0.49

-5.69E+OO 5.43E+OO 586.26 0.46 6.88E+OO 9.67E+OO 678.62 0.47

-5.97E-01 6.66E+OO 688.67 0.86

-9.80E-01 3.70E+OO 719.35 0.28

-5.09E-01 9.56E+OO 778.90

12. 96 l.72E-01 2.67E-01 810.45 0.32 2.20E+OO 6.85E+OO 867.37 4.26

-l.84E-01 6.34E-01 919.33 0.43 9.0lE-01 4.35E+OO 964. 08 14.65 8.75E-02 2.83E-01 1085.87 10.24 4.87E-02 4.26E-01 1089.74

1. 73

1. 25E+OO 2.26E+OO 1112. 07 13.69

1. 44E-01 2.77E-01 1212. 95

1. 43 1.85E+OO 3.61E+OO 1249.94 0.19 1.0lE+Ol 2.07E+Ol 1299. 14

1. 63 9.02E-01 2.20E+OO 1408.01 21.07

-5.23E-02

1. 38E-01 1457.64 0.50 3.79E+Ol 2.56E+01 1528.10 0.28

-9.57E+OO 7.53E+OO Eu-154 123.07 40.40

-6.94E-03 5. 49E-02 5.49E-02 247.93 6.89 5.55E-02 3.12E-01 591. 76 4.95 1.47E-01 5.16E-Ol 692.42

1. 78

-2.30E-01 1.54E+OO 723.30 20.06

-4.BOE-02 1.53E-01 756.80 4.52 2.02E-Ol

6. 71E-01 873.18 12.08

-7.99E-02 2.09E-01 996.29 10.48 6.55E-02 3.66E-01 1004.76

18. 01

1. 14E-01 2.06E-01 1274.43 34.80

1. 17E-02 l.14E-Ol

[114]

3/29/2017 11:55:33AM Page 6 of6 Analysis Report for 29-Mar-17-10024 L3-10205A-FRGC-O 1 OCV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCi!grams)

(pCi!grams)

Eu-154 1596.48

1. 80

-1.25E+OO 5.49E-02 1.78E+OO Eu-155 45.30

1. 31

-1.69E+OO 1.16E-01 6.15E+OO 60.01

1. 22

-1.75E+OO 6.81E+OO

86. 55 30.70 2.61E-02 1.16E-01 105.31

21. 10 6.46E-02

1. 25E-Ol Ra-226 186.21 3.64 2.19E-Ol 6.S2E-01 6.62E-Ol Pa-231 27.36 10.30 O.OOE+OO 7.48E-02 7.48E-02 283.69

1. 70 5.13E-02 1.24E+OO 300.07 2.47

-1.75E-01 9.26E-01 302.65 2.20

-1.90E-01 1.lOE+OO 330.06

1. 40 5.61E-02 1.87E+OO U-235 143.76 10.96 3.74E-02 4.13E-02

1. 78E-01 163.33 5.08

-1.22E-01 4.00E-01 185.71 57.20

-4.lOE-03 4.13E-02 202.11

1. 08

-7.29E-01

1. 84E+OO 205.31

5. 01

-2.91E-02 3.95E-01 Am-241 59.54 35.90

3. 72E-03 2.44E-01 2.44E-01

+

= Nuclide identified during the nuclide identification

= Energy line found in the spectrum

= MDA value not calculated

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

?

= CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[115]

Vl

.f-J C:

60-=

55-45 40 35 8 30 25 20 15 10 5

~

ROI Type: 1 1000 2000 3000 0000002630.CNF 4000 channel 5000 Live Time 600.000 sec Rea 1 Time 600. 340 sec start:

1 -0.0(kev)

Stop : 8192 2047. 8(kev)

Acq. start wed Mar 29 11: 45: 2 S 2017 6000 7000 8000

[116]

3/29/2017 12:06:31PM

~pex-Gamma Analysis Report for 29-Mar-17-10025 L3-10205A-FRGC-O 11 CV GAMMA SPECTRUM ANAL YS/S Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10025

L3-10205A-FRGC-011CV

Sand 1.536E+03 grams

Default

3/24/2017 9:45:00AM

3/29/2017 11 :56:22AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.3 seconds

0.05 %

3.00

120- 8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11 /16/16

2631

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 12:06:25PM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of6

[117]

3/29/2017 12:06:31PM Page 2 of6 Analysis Report for 29-Mar-17-10025 L3-10205A-FRGC-011CV Peak Energy ROI No.

(keV) start 1

238.63 948 -

2 338.28 1349 -

3 583.43 2 327 -

4 1460.94 5831 -

M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 960 1358 2336 5851 Peak Centroid 954.11 1352.20 2331. 8 6 5841.68 No background subtract performed on this spectrum.

NetPeak Net Area Continuum Area Uncertainty Counts 6.63E+Ol 12.07 2.97E+Ol 2.16E+Ol 6.05 6.39E+OO l.12E+Ol 5.58 8.77E+OO

1. 08E+02 12.07

1. 05E+Ol NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCi/grams)

Uncertainty K-40

0. 99 1460.82 10.66 2.81E+OO 3.38E-01 Tl-208

0. 99 583.19 85.00 l.93E-02 9.66E-03 Pb-21 2

1. 00 11 5.18 0.60 238.63 43.60 1.17E-01 2.34E-0 2 300.09 3.30 Ac-228

1. 00 129.07 2.42 209. 25 3.89 270.24 3.46 328.00 2.95 338. 32

11. 27 l. 88E- 01 5.48E-02 409.46

1. 92 463. 00 4.40 7 94.95

4. 2 5 FWHM (keV) 0.80 0.52 0.89

1. 77

[118]

Analysis Report for 29-Mar-17-10025 L3-10205A-FRGC-011 CV Nuclide Name Ac-2 28 Id Confidence

1. 00 Energy (keV) 911. 20 964. 77 968.97 1588. 20

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold= 0.30 Errors quoted at 1.000sigma Yield(%)

25.80 4.99 15.80 3.22 3/29/2017 12:06:31PM Page 3 of6 Activity (pCilgrams)

Activity Uncertainty INTERFERENCE CORRECTED REPORT

?

=

X

=

Nuclide Name K-40 Tl-208 Pb-212 Ac-228 Nuclide Id Confidence 0.998 0.990

1. 000

1. 000 nuclide is part of an undetermined solution nuclide rejected by the interference analysis Wt mean Activity (pCilgrams) 2.81E+OO

1. 93E.,..02 1.1 7E-01 1.88E-01

=

nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Comments Activity Uncertainty 3.38E-01 9.66E-03 2.34E-02 5.48E-02

[119]

3/29/2017 12:06:31PM Analysis Report for 29-Mar-17-10025

+

L3-10205A-FRGC-011 CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (ke V)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 12:06:24PM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCUgrams)

(pCl/grams)

BE-7 477.60 10.44 6.68E-02 3.60E-01 3.60E-01 K-40 1460. 82 10.66 2.81E+OO 6.23E-01 6.23E-01 Co-60 1173. 23 99.85 2. 27E-0 2 3.24E- 02 5.40E-02 1332.49 99.98

-2. llE-0 3 3.24E-02 Nb-94 702.65 99.81 6.lSE-04

3. 34E-02 3.97E-02 871.09 99.89

-1. 20E-02 3.34E-02 Ag-108m 79.13 6.60 3.76E-01 3.44E-0 2 7.03E-01 433.94 90.50 1.SlE-03 3.44E-02 614. 2 8 89.80

-2.40E-02 4.19E-02 722.94 90.80 9.35E-04 4.0lE-02 Sb-125 176.31 6.84

-4.03E-02 9.42E-02 3.34E-01 380.45

1. 52 3.19E-01 1.76E+OO 427.87 2 9.60 1.82E-03 9.42E-0 2 463.36 10.49

-1.98E-01 2.54E-01 600.60 17.65 9.71E-02 1.82E-01 606. 71 4.98 4.62E-01 8.13E-01 635.95

11. 2 2 7.29E-02

3. 23E-01 671. 44

1. 79 9.94E-01 1.70E+OO Ba-133 79.61 2.65 6.46E-01 4.87E-02

1. 66E+OO Page 4 of6 Tolerance Nuclide

[120]

3/29/2017 12:06:31PM Page 5 of6 Analysis Report for 29-Mar-17-10025 L3-10205A-FRGC-011 CV Nuclide Energy Yield(%)

Activity Nuclide MDA LineMDA Name (keV)

(pCi!grams)

(pCilgrams)

(pCilgrams)

Ba-133

81. 00 32.90

-6.62E-02 4.87E-02 1.02E-01 276.40 7.16 1.51E-01 3.68E-01 302.85 18.34

1. 05E-01 1.49E-01 35f;.0 1 62.05

-4.72E-02 4.87E-02 383.85 8.94

-1.49E- 01 2.44E-01 Cs-134 475.36

1. 48

1. 52E+ OO 3.49E-02 2.26E+OO 563.25 8.34 7. 32E-02 3.99E-01 569.33 15.37

-8.77E-0 2 2.0lE-01 604. 72 97.62

-3. 45E-0 2 3.49E-0 2 795.86 85.46 6.54E-0 3 4.58E-0 2 801.95 8.69

1. 23E-01 4.66E-01 1038.61 0.99 2.67E+OO 4.33E+OO 1167.97

1. 79

-2.43E+00 3.0lE+OO 1365.19 3.02 2.64E-01 9.84E-01 Cs-1 37 661.66 85.10 5.41E-03 5.04E-02 5.04E-02 Eu-1 52 121. 78 28.67

2. 17E-02 7.84E-02 7.84E-0 2 244.70 7.61 l.53E-01 4.00E-0 1 295.94 0.45 7.49E-01 6.64E+OO 344.28 26.60 3.84E-02 9.86E-02 367.79 0.86 1.73E+OO 3.08E+OO 411.12 2. 2 4

-7.51E-01 1.31E+OO 443. 96 2.83 2.19E-01 1. 0lE+OO 488.68 0.4 2 3.63E+OO 6.76E+OO 563. 99 0.49

-3.41E+OO

6. 41E+OO 586.26 0.46 4.88E+OO 9.84E+OO 678.62 0.47

-9.48E-01 5.36E+OO 688.67 0.86

-2.00E+OO 2.80E+OO 719.35 0.28 l.19E+OO 1.18E+Ol 778.90

12. 96

-5.37E-02 2.38E-01 810. 45 0.32

-2.56E+OO l.03E+Ol 867. 37 4.26

-8.71E-01 7. 05E-01 919. 33 0.43

-9.14E-01 8. 12E+OO 964. 0 8 14.65

-2.13E-0 2 3.53E-01 1085.87 10.24

-3.86E-0 2 3.98E-01 1089.74

1. 73

-6.02E-01 2.36E+OO 1112.07 13.69 1.51E-01 2.89E-01 1212.95

1. 43

- 1.07E+OO 3.08E+OO 12 49.94 0.19

-3.83E+00

~.82E+Ol 12 99.14

1. 63

-2.90E+OO

1. 96E+OO 1408.01

21. 07 5.14E-0 2 1.60E-01 1457.64 0.50 6.62E+Ol

3. l OE+Ol 1528. 10

0. 28

-1.79E+OO 7.86E+OO Eu-154 123.07 40.40

- 1. llE-02 5.61E-02 5.61E-02 2 47.93 6.89

-4.67E-02 3.20E-01 591. 7 6 4.95

-:.65E-02 5.82E-01 692.42

1. 78

-1.44E+OO

1. 1 6E+OO 723.30 20.06

1. 27E-0 2 1.82E-01 756.80 4.52

-2.81E-01 8.09E-Ol 873.18 12.08

-4. 0lE-03 3.0lE-01 996.2 9 10.4 8

-2.85E-02 3.67E-01 1004. 7 6 18.01

-5.80E-02 l.48E-01 12 74. 43 34.80 9. 72E-03 l.1 9E-01

[121]

3/29/2017 12:06:31PM Page 6 of6 Analysis Report for 29-Mar-17-10025 L3-10205A-FRGC-011 CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl/grams)

(pCUgrams)

(pCilgrams)

Eu-154 1596.48

1. 80 4.99E-01 5.61E-02 1.86E+OO Eu-155 45.30

1. 31

2. 72E-01 1.1 6E-0 1 7.18E+OO

60. 01

1. 22

-1.33E+OO 7.61E+OO 86.55 30.70 7.32E-03 l.18E-01 105.31 21.10

-2. 68E-02 1.16E-01 Ra-226 186. 2 1 3.64

-8.95E-02 6.72E-01

6. 72E-01 Pa-23 1 27.36 10.30 O.OOE+OO 7.BlE-02 7.BlE-02 283.69

1. 70

-2. 34E-01 1.44E+OO 300.07 2.47

-6.28E-01

1. 02E+OO 302. 65 2.20 4.91E-01 1.20E+OO 330. 0 6

1. 40 1.40E+OO 2.12E+OO U-235 143.76 i0.96 1. 22E-0 2 4. 31E-02 2.34E-01 1 63.33 5.08

-3. 0lE-02 4.61E-01 185. 71

57. 2 0 1.BlE-02 4.31E-02 202.11

1. 08

7. 21E-01 2.23E+OO 205.31 5.0 1

-1.61E-01 4.65E-01 Am-241 59.54 35.90 1.75E-02 2. 72E-01 2. 72E-01

+

= Nuclide identified during the nuclide identification

= Energy line found in the spectrum

= MDA value not calculated

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

?

= CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[122]

60 55 50 45 40 35 1000 2000

~

ROI Type: 1 3000 0000002631.CNF 4000 channel 5000 Live Time :600.000 sec Real Tire :600.330 sec Start:

1: -0.0(kev)

Stop : 8192:2047.S(kev)

Acq. start :wed Mar 29 11:56:22 2017 6000 7000 8000

[123]

3/29/2017 12:17:34PM

~pex-Gamma Analysis Report for 29-Mar-17-10026 L3-10205C-FRGC-012CV GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10026

L3-10205C-FRGC-012CV

Sand 1.600E+03 grams

Default

3/24/2017 9:50:00AM

3/29/2017 12:07:25PM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.4 seconds

0.06%

3.00

120 - 8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11/16/16

2633

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 12:17:28PM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of6

[124]

3/29/2017 12:17:34PM Page 2 of6 Analysis Report for 29-Mar-17-10026 L3-10205C-FRGC-O 12CV Peak No.

Energy (keV)

ROI start ROI end 1

2 238.67 1461.22 948-959 5834 -

5850 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centroid 954.24 5842.83 No background subtract performed on this spectrum.

Net Peak Area 4.55E+Ol 7.88E+Ol Net Area Uncertainty 8.90 9.92 Continuum Counts l.35E+Ol 6.20E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 0.97 1460.82 Pb-212

1. 00 115.18 238.63 300.09

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma Yield(%)

10.66 0.60 43.60 3.30 Activity (pCi/grams) 1.98E+OO 7.73E-02 Activity Uncertainty

2. 63E-Ol l.64E-02 FWHM (keV) 0.86 0.54

[125]

3/29/2017 12:17:34PM Analysis-Report for 29-Mar-17-10026 L3-10205C-FRGC-O 12CV INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Pb-212 Nuclide Id Confidence 0.975

1. 000

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCi/grams) l.98E+OO 7.73E-02

= nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Activity Uncertainty 2.63E-01 1.64E-02 Page3 of6 Comments

[126]

3/29/2017 12:17:34PM Analysis Report for 29-Mar-17-10026

+

L3-10205C-FRGC-O 12CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 12:17:28PM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL. NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCl/grams)

(pCi/grams)

BE-7 477.60 10.44

5. 2 0E-02 3.40E-01 3.40E-01 K-40 1460.82 10.6 6 1.98E+OO 4.49E-01 4.49E-01 Co-60 1173. 23 99.85

-7.73E-03 2.79E-02 4.77E-02 1332. 49 99.98 7.48E-0 3 2.79E-02 Nb-94 702.65 99.8 1

-2.00E-0 2 2.49E-02 2.49E-02 871. 09 99.89

1. 73E-02 3.99E-0 2 Ag-1 08m 79.13 6.60 3.85E-01 2.98E-0 2 6.75E-01 433.94 90.50

- 9.33E-03 2.98E-02 614.28 89.80

-1. 72E-03 3.57E-02 722.94 90.80

-1.80E-03 3.74E-02 Sb-125 176.31 6.84 1.02E-01 9.84E- 02 3.14E-01 380.45

1. 52

1. 87E-01

1. 28E+OO 427.87 29.60 3.93E-03 9.84E-02 463.36 10.49

- 4.22E-02 2.37E-01 600.60 17.65 2.51E-02 1.59E-01 606. 71 4.98 3.27E-01

7. 22E-01 635.95

11. 22

-7.42E-02 2.19E-01 671.44

1. 79 3.62E-02

1. 27E+OO Ba-133 79.61 2.65 2.64E-01 4.67E- 02 1.57E+OO Page 4 of6 Tolerance Nuclide

[127]

3/29/2017 12:17:34PM Page 5 of6 Analysis Report for 29-Mar-17-10026 L3-10205C-FRGC-O 12CV Nuclide Energy Yield(%)

Activity Nuc/ide MDA LineMDA Name (keV)

(pCi/grams)

(pCl/grams)

(pCi/grams)

Ba-1 33

81. 00 32.90

-2.0lE-02 4.67E-02 9.95E-0 2 276.40 7.16 l.78E-01 3. 72E-01 30 2.85 18.34 2.28E-02 l.39E-01 356.01 62.05

- 4.35E-0 2 4.67E-02 383.85 8.94

-2.08E-01 2.42E-01 Cs-13 4 475.36

1. 48 1.17E+OO 3.18E-02 2.21E+OO 563.25 8. 34

-3.19E-01 2.97E-Ol 569.33 15.37 5.52E-02 1.99E-01 604. 72 97.62

-3.31E-02 3.18E-02 795.86 85.46

-4.79E-02 3.19E-02 801. 95 8.69 9.63E-0 2 4.35E-01 1038.61 0.99

1. 33E+OO 4.0lE+OO 1167. 97

1. 79

- 1. 73E+OO 2.49E+OO 1365.19 3.02 2.53E-01 9.45E-01 Cs-137 661. 66 85.10 3.42E-02

4. 2 9E-0 2 4.29E-02 Eu-152 121. 78 28.67

-1.31E-02 7.94E-02 7.94E-0 2 244.70 7.61

-9.37E-02 3.lOE-01 295.94 0.45 l.69E+OO

6. 31E+OO 344. 28 2 6.60 l.44E-0 2 9.48E-02 367.79 0.86

- 1.41E+OO 2.64E+OO 411.12 2. 24 6.34E-01 9.84E-01 443.96 2.83

-2.65E-01 7.65E-01 488.68 0.42 3.98E+OO 6.83E+OO 563.99 0.49

-3.65E+OO

5. 2 4E+OO 586.26 0.46 7.50E+OO 9.06E+OO 6?8.62 0.47

-1.57E+OO 4.50E+OO 688.67 0.86

-1.40E+OO 2.86E+OO 719.35

0. 28

-9.74E+OO 1.09E+Ol 778.90 12.96

- 1. 59E-02 1.80E-01 810.45 0.32

-3.47E+OO 9.93E+00 867.37

4. 26

-3.lOE-01

7. 51E-01 919.33 0.43

3. 2 9E+OO 8.80E+OO 964. 08 14.65

-1.15E-01 2.46E-01 10 85.87 10.24 4.76E-02 4.41E-01 1089.74

1. 73 1.63E+OO 2.53E+OO 1112. 07 13.69 3.93E-0 2 2.78E-01 1212.95

1. 43

-1. 3 0E+OO 2.69E+OO 1249.94 0.19 2.79E+OO

1. 85E+Ol 1299.1 4

1. 63 5.65E-02 2.48E+OO 1408.01

21. 07 3.70E-02

1. 38E-01 1457.64 0.50 4.78E+Ol 2.57E+Ol 1528.10 0.28 O.OOE+OO 2.83E+OO Eu-154 123.07 40.40 7.53E-0 3 5.56E-02 5.56E-02 247.93 6.89

-1.88E-01 3.36E-01 591.76 4.95 2.-31E-01 5.38E-01 692.42

1. 78

-3.12E-01 1.61E+OO 723. 30 2 0.06 9.44E-02

1. 80E-01 756.80

4. 52 3.73E-Ol 6.73E-01 873. 1 8 12.08

-4.02E-02

3. 21E-01 996.29 10.48

-3.17E-02 2.43E-01 1004.76 18.01

-4.85E-02 l.78E-01 1274.43 34.80 1.04E-02 1.08E-01

[128]

3/29/2017 12:17:34PM Page 6 of6 Analysis Report for 29-Mar-17-10026 L3-10205C-FRGC-O 12CV Nuclide Energy Yield(%)

Activity Nuc/ideMDA LineMDA Name (keV)

(pCi!grams)

(pCi/grams)

(pCl/grams)

Eu-154 1596.48

1. 80 3. 2 0E-01 5.56E-02

1. 54E+OO Eu-155 45.30

1. 31 4.06E-01 9.57E-02 6.25E+OO 60.01

1. 22 2.89E+OO 6.66E+OO 86.55 30.70

6. 2 5E-0 3 9.57E-02 105.31

21. 10 4.93E-03 1.16E-01 Ra-226 186.21 3.64 3.94E-01 6.51E-01 6.51E-01 Pa-231 27.36 10.30 O.OOE+OO 7.50E-02 7.50E-0 2 283.69

1. 70

-7.73E-01 1.30E+OO 300.07 2.47

-5.45E-01

9. 28E-01 302.65 2.20

- 7.54E-01 1.07E+OO 330.06

1. 40

-1.66E-02 L 72E+OO U-2 35 143.76 10.96

-3. 20E-02 3.98E-02 2.00E-01 163.33 5.08 2.21E-01 4.42E-01 185.71

57. 2 0 6.49E-03 3.98E-0 2 202.11

1. 08

-7.34E-01 1.88E+OO 205.31 5.01

-7.59E-02 4.36E-01 Am-2 41 59.54 35.90 4.27E-02 2. 30E-01 2.30E-01

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[129]

60 55 50 45 1000 2000 3000

~

ROI Type: 1 0000002633.CNF 4000 channel 5000 Live Time :600.000 sec Real Tire :600.350 sec Start:

1: -0.0(kev) stop : 8192: 2047. S(kev)

Acq. start :wed Mar 29 12:07:25 2017 6000 7000 8000

[130]

3/29/2017 12:33:49PM Analysis Report for 29-Mar-17-10029 L3-10205S-FRGC-013CV GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10029

L3-10205S-FRGC-013CV

Sand 1.606E+03 grams

Default

3/24/2017 10:02:00AM

3/29/2017 12:23:41PM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.4 seconds

0.06 %

3.00

120 - 8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11/16/16

2635

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 12:33:43PM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of6

[131]

3/29/2017 12:33:49PM Page 2 of6 Analysis Report for 29-Mar-17-10029 L3-10205S-FRGC-O 13CV Peak Energy ROI No.

(keV) start 1

238.56 949 -

2 910.87 3636 -

3 1461.01 5835 -

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma ROI end 959 3645 5849 Peak Centroid 953.81 3640.93 5841.97 No background subtract performed on this spectrum.

NetPeak Net Area Continuum Area Uncertainty Counts 4.86E+Ol 8.8 2 1.14E+Ol

1. 35E+Ol 4.43 2.50E+OO 6.09E+Ol 9.17 8. 13E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Defau!t\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCi/grams)

Uncertainty K-40 0.99 1460.8 2 10.66

1. 52E+OO

2. 39E-01 Pb-21 2 0.99 115.18 0.60 238.63 43.60 8.23E-0 2

1. 63E-0 2 300.09 3.30 Ac-228 0.99 129.07 2.4 2 209.25 3.89 210. 24 3.46 328.00 2.95 338.3 2 11.27 409.46

1. 92 463.0 0 4.40 794.95

4. 2 5 911. 20 25.80 1.00E-01

3. 31E-02 964. 77 4.99 FWHM (keV) 0.69 0.97 0.50

[132]

Analysis Report for 29-Mar-17-10029 L3-10205S-FRGC-O 13CV Nuclide Name Ac-228 Id Confidence 0.99 Energy (keV) 968. 97 1588.20

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma Yield(%)

15.80 3.22 3/29/2017 12:33:49PM Page 3 of6 Activity (pCilgrams)

Activity Uncertainty INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Pb-212 Ac-228 Nuclide Id Confidence 0.995 0.999 0.995

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCl/grams) 1.52E+OO 8.23E-02 1.00E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma wt mean Comments Activity Uncertainty 2.39E-01 1.63E-02 3.31E-02

[133]

3/29/2017 12:33:49PM Analysis Report for 29-Mar-17-10029

+

L3-10205S-FRGC-013CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 12:33:43PM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl!grams)

(pCilgrams)

(pCl/grams)

BE-7 477.60 10.44 1.56E-01 2.81E-01 2.81E-01 K-40 1460.82 10.66

1. 52E+OO 4.80E-01 4.80E-01 Co-60 1173.23 99.85 4.37E-03 3.34E-02 3.34E-02 1332.49 99. 98 1.74E-02 3.87E-02 Nb-94 702.65 99.81 1.02E-02 2.88E-02 3.00E-02 871.09 99.89

-1.96E-02 2.88E-0 2 Ag-108m 79.13 6.60

1. 62E-01 2.97E-02 6.61E-01 433.94 90. 50 1.59E-03 2.97E-02 614.28 89.80

-7.28E-0 2 4.0lE-02 722.94 90.80 l.35E-0 2 3.61E-02 Sb-125 176.31 6.84

-1.30E-01 9.22E-02 2.83E-01 380.45

1. 52 8.51E-01

1. 50E+OO 427.87 29.60 2.47E-02 9.22E-0 2 463.36 10.49

-5.66E-03 2.57E-01 600.60 17.65

-4.35E-02 1.40E-01 606.71 4.98 7.90E-01 8.93E-01 635.95

11. 22 4.86E-0 2 2.93E-01 671.44

1. '7 9 5.40E-01 1.91E+OO Ba-133 79.61 2.65

-2.14E-02 4.52E-02 1.61E+OO Page 4 of6 Tolerance Nuclide

[134]

3/29/2017 12:33:49PM Page 5 of6 Analysis Report for 29-Mar-17-10029 L3-10205S-FRGC-013CV Nuclide Energy Yield(%)

Activity Nucllde MDA LineMDA Name (keV)

(pCilgrams)

(pCilgrams)

(pCi/grams)

Ba-13 3

81. 00 32.90

-2. 60E-02 4.52E-0 2 1.15E-01 276.40 7.16

-1. 70E-01 3.07E-01 302.85 18.34

-8. 63E-02 1.18E-01 356.01

62. 05

-5.69E-02 4.52E-02 383.85 8.94 7.14E-02 2.09E-01 Cs-134 475. 3 6

1. 48

-2.87E-01 3.74E-02

1. 71E+OO 563.25 8.34

-6.28E-0 2 2. 96E-01 569.33 15.37

-3.59E-03 l.93E-01 604.72 97.62

-2.75E-02 3.74E-02 795. 86 85.46

-4.79E-03 4.12E-02 801.95 8.69

-1.87E-01 3.32E-01 1038.61 0.99 5.05E-01

3. llE+OO 1167.97

1. 79 2.15E-01 2.09E+OO 1365.19 3.0 2 5.05E-01 l.23E+OO Cs-137 661. 66

85. 10 2. 20E-02 4.99E-0 2 4.99E-02 Eu-152 121. 78 28.67

3. 91E-03 7.59E-02 7.59E-02 244.70 7.61 1.21E-02

3. 17E-01 295.94 0.45 1.57E+00 6.14E+OO 344. 28 2 6.60 2.08E-0 2 8.12E-0 2 367.79 0.86 1.77E+00 3.00E+OO 411. 12 2.2 4

-7.07E-02 9.13E-01 44 3. 96

2. 83 6.90E-01 9.19E-01 488.68 0.42

-7.33E-02 5.91E+OO 563.99 0.49 2.03E+OO 5.42E+OO 586. 2 6 0.46

-2.58E-01 8.34E+OO 678. 62 0.47

- 6.32E+OO 6.19E+OO 688.67 0.86 l.06E+OO 3.30E+OO 719.35 0.28

-l. 2 0E+Ol 7.90E+OO 778.90 12.96

7. 72E-02 2.48E-Ol 810.45 0.32 3.84E+OO 8. 54E+OO 867.37 4.2 6

-4.62E-01 7.12E-01 919.33 0.4 3 2.09E+00 7.77E+OO 964. 08 14.65

-2.04E-02 2.65E-01 1085.87

10. 2 4 3.34E-02 3.08E-01 1089.74

1. 73

-1.93E+OO 1.56E+OO 1112.07 13.69 1.54E-01 3.54E-01 1212.95

1. 43

-1.44E+OO 3.29E+OO 1249.94 0.19 3.37E+OO 2.62E+Ol 12 99.14

1. 63 1.05E+OO 2.34E+OO 1408.01 21.07

-2.77E-02 1.67E-01 1457.64 0.50 4.13E+Ol 2.39E+Ol 1528.10

0. 28 4.90E+OO

1. 33E+Ol Eu-154 123.07 40. 40 1.42E-02 5.48E-0 2 5.48E-0 2 2 47. 93 6.89 6.74E-03 3.16E-01 591. 76 4.95 2.60E-01 5.76E-0 1 692.42

1. 78 8.88E-0 1 1.60E+00 723. 30 20.06 9.lOE-02

1. 69E-01 756.80 4.5 2 4.46E-01 7.24E-01 873.18 12.08

1. 54E-01 2.77E-01 996.2 9 10.48

-1.51E-02 3.36E-01 1004. 76 18.01

-l.88E-02 1. 55E-01 1274.4 3 34.80

-2.08E-03 9. 42E-02

[135]

3/29/2017 12:33:49PM Page 6 of6 Analysis Report for 29-Mar-17 -10029 L3-10205S-FRGC-013CV Nuclide Energy Yield(%)

Activity Nuclide MDA LineMDA Name (keV)

(pCi/grams)

(pCi/grams)

(pCi/grams)

Eu-154 1596.48

1. 80 3.18E-01 5.48E-02

1. 54E+OO Eu-155 45.30

1. 31

-2.20E+OO

1. llE-01 5.49E+OO 60.01

1. 22

-2.29E+OO 6.80E+OO 86.55 30.70 5.41E-02

1. llE-01 105.31 21.10

-3.87E-02 1.19E-01 Ra-226 186. 2 1 3.64 3.56E-01 6.61E-01 6.61E-01 Pa-23 1 27.36 10.30 O.OOE+OO 7.47E-02 7. 47E- 02 2 83.69

1. 70

l. 67E-01

1. 38E+00 300.07 2.47

-9.06E-01 9.41E-01 30 2.65 2.20

-2.38E-01 l.OOE+OO 330.06

1. 40

-3.50E-01 1.74E+OO U-235 143.76 10.96

-5.96E-02 4.16E-02

l. 89E-01 163.33 5.08

-1. 27E-01 4.05E-01 185.71

57. 2 0 2.56E-0 2 4.16E-02 2 02.11

1. 08

-1.48E-01 1.87E+OO 205.31 5.01

1. 33E-01 4.29E-01 Am-2 41 59.54 35.90

-1.18E-01 2.41E-01 2.41E-01

+

= Nuclide identified during the nuclide identification

= Energy line found in the spectrum

= MDA value not calculated

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

?

= CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[136]

60 55 50 45 1000 2000 3000

~

ROI Type: 1 0000002635.CNF 4000 channel 5000 Live Time :600.000 sec Real Tille :600.350 sec start:

1: -0.0(kev) stop : 8192: 2047.8(kev)

Acq. start :wed Mar 29 12:23:41 2017 6000 7000 8000

[137]

3/29/2017 1:01 :14PM

~pex-Gamma Analysis Report for 29-Mar-17-10031 L3-10205A-FRGC 014CV GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live lime Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10031

L3-10205A-FRGC 014CV

Sand 1.652E+03 grams

Default

3/24/2017 10:10:00AM

3/29/2017 12:51:03PM

130G_Sand

Administrator

P11314

130G_Sand

60.0.0 seconds

600.3 seconds

0.04 %

3.00

120 - 8192

120 - 8192

1.000 keV

11/10/2016

3/29/2017

initial 11/16/16

2637

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 1:01 :06PM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of6

[138]

3/29/2017 1:01:14PM Page 2 of6 Analysis Report for 29-Mar-17-10031 L3-10205A-FRGC 014CV Peak Energy ROI No.

(keV) start 1

2 38.83 949 -

2 351.95 1402 -

3 609.27 2431 -

4 1460.92 5834 -

M a: First peak in a multiplet region m a: Other peak in a multiplet region F a: Fitted singlet Errors quoted at 1.000sigma ROI end 959 1410 2441 5849 Peak Centroid 954.90 1406.80 2435.12 5841.61 No background subtract performed on this spectrum.

Net Peak Net Area Continuum Area Uncertainty Counts 3.08E+Ol 9.65 2.62E+Ol 2.17E+Ol 6.78 1.13E+Ol 1.94E+Ol 5.93 6.56E+OO 6.92E+Ol 8.62

1. 81E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCi/grams)

Uncertainty K-40 0.99 1460.8 2 10. 66 1.68E+OO 2. 22E-01 Bi-211 0.88 351.07

13. 02 1.57E-01

5. 0 6E-02 Pb-212 0.99 115.18 0.60 238.63 43.60 5.07E-02 1.64E-02 300.09 3.30 Bi-2 1 4

1. 00 609.32 45.49 5.98E-02

1. 8 6E-02 768.36 4.89 80 6.18

1. 2 6 934.06

3. 11 112 0.29 14.92 1155.2 1

1. 63 1238.12 5.83 128 0. 98

1. 43 FWHM (keV) 0.37 0.69 0.29 0.31

[139]

Analysis Report for 29-Mar-17-10031 L3-10205A-FRGC 014CV Nuclide Id Energy Name Confidence (keV)

Bi-214

1. 00 1377. 67 1385.31 1401.52 1407.99 1509. 21 1661. 2 7 1729.59 1764.49 1847.43 2118.51 Pb-214

1. 00 241.99 295. 22 351. 93 785. 96

• = Energy line found in the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma 3/29/2017 1:01 :14PM Page3 of6 Yield(%)

Activity Activity (pCi/grams)

Uncertainty 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16

7. 2 5 18.42 35.60 5.73E-02

1. 85E-02

1. 06 INTERFERENCE CORRECTED REPORT Nuclide Name K-40

?

Bi-211 Pb-212 Bi-214

?

Pb-214 Nuclide Id Confidence 0.999 0.884 0.994

1. 000 1.000

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCilgrams) 1.68E+OO 1.57E-01 5.0 ':'E-02 5.98E-02 5.73E-02

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Comments Activity Uncertainty 2.22E-01 5.06E-02 1.64E-02 1.86E-02

1. 85E-02

[140]

3/29/2017 1 :01: 14PM Analysis Report for 29-Mar-17-10031

+

L3-10205A-FRGC 014CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 1 :01 :06PM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide

• Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCl/grams)

(pCi/grams)

BE-7 477.60 10.44 1.97E-01 2.99E-01 2.99E-01 K-40 1460.82 10.6 6 l.68E+00 2.5":'E-01 2.57E-01 Co-60 1173. 23 99.85 5.61E-03 3.53E-02 3.83E-02 1332. 49 99.98 1.45E-02 3.53E-02 Nb-94 702.65 99.81 l.70E-02 2.45E-02 3.42E-02 871.09 99.89 2. 25E-03 2.45E-0 2 Ag-108m 79.13 6.60

-4. 20E-02 2.68E-0 2 6.37E-01 433.94 90.50 8.79E-03 2.68E-02 614.28 89.80 8.02E-03

3. 98E....:02 722.94 90.80 8.18E-03 3.27E-02 Sb-125 176.31 6.84

- 9. 71E-03 7.90E- 02 2.79E-01 380.45

1. 52

-3.33E-01 1.46E+OO 427.87 29.60 2. 30E-02 7.90E-02 463. 36 10.49

- 2.0lE-01 2.49E-01 600.60 17.65

-1.63E-02 1.54E-01 606.71 4.98 7.39E-Ol 8.91E-01 635.95

11. 22

-2.65E-02 2.23E-01 671. 44

1. 79

-3. 96E-01 l.75E+OO Ba-133 79.61 2.65

- 9.56E-02 4.46E- 02 l.56E+OO Page 4 of6 Tolerance Nuclide

[141]

3/29/2017 1:01:14PM Page 5 of6 Analysis Report for 29-Mar-17-10031 L3-10205A-FRGC 014CV Nuclide Energy Yield(%)

Activity Nuclide MDA LineMDA Name (keV)

(pCl/grams)

(pCi!grams)

(pCilgrams)

Ba -1 33

81. 00 32.90 2.45E-03 4.46E-02 1.07E-01 276.40 7.16

-5. llE-02 3.14E-01 302.85 18.34

4. 1 6E-02 1. 15E-01 356.01 62. 05

-4. 43E-02 4. 46E-02 383.85 8.94

-2.0 0E-02 2.48E-01 Cs-134 475.36

1. 48 7.18E-01 3. 43E-02 1.98E+OO 563.25 8.34 2. 23E- 01 3.32E-01 569.33 15.37

-4.82E-02

1. 51E-01 604.72 97.62

-2.97E-02 4.24E-02 795.86 85.46

-1.15E-0 2 3.43E-02 801.95 8.69

-2.45E-0 2 3.39E-01 1038.61 0.99

-5.16E-02 3.22E+OO 1167. 97

1. 79 5.57E-01 2.23E+OO 1365.19 3.0 2 1.64E-01 7.91E-01 Cs - 137 661.66 85.10

-2.55E-03 4. 15E-02 4.15E-02 Eu-15 2 121. 78 28.67 5. 45E-0 2

8. 06E-02 8.06E-02 244.70

7. 61

-9.5 6E-02 3.12E-01 295.94 0.45

2. 81E-01 5.82E+OO 344. 2 8 2 6.60 2. 5 6E-02 8.66E-02 367.79 0.86

-6.49E-01 2.49E+OO 411.12

2. 24 9.92E-01

1. 17E+OO 443. 96 2.83

-5.05E-01

7. 96E-01 488.68 0.4 2 4.48E-0 1 5.93E+OO 563.99 0.49 1.llE+OO 5.27E+OO 586.26 0.46 4.92E+OO 8.38E+OO 678.62 0.47 3.42E+OO 7.07E+OO 688.67 0.86

-1.16E+OO 3.59E+OO 719.35 0.28

-8.18E-01

1. 02E+Ol 778. 90 12. 96 1.05E-01 2.50E-01 810. 45 0.32

4. 2 6E+OO 8.76E+OO 867.37 4.26 3.58E-02 5.73E-01 919. 33 0.43

-1.06E+OO 6.81E+OO 964. 08 14.65

-1.12E-01 2.75E-01 1085. 87 10.24 8.88E-02 3.54E-01 1089. 74

1. 73 6.95E-02 1.89E+OO 1112. 07

13. 69 3.90E-0 3 3.04E-01 1212.95

1. 43

-3. 40E+OO 2. 86E+OO 1249.94 0.19

-5. 1 9E+OO 2.0lE+Ol 1299.14

1. 63 8.76E-01 2.13E+OO 1408.01 21.07

-1. 2 9E-01 1.15E-01 1457.64 0.50 3.81E+Ol 2. 2 7E+Ol 1528. 1 0

0. 28

-7.15E+OO 9.20E+OO Eu-154 123. 07 40. 40

-2.91E-03 5.44E-02 5.44E-02 247.93 6.89

-l.96E-0 1 3.07E-01 591.76 4.95

-6.94E-03 4.79E-01 692.42

1. 78

-6.48E-02 1.49E+OO 72 3.30 2 0.06 3.51E-02 l.48E-Ol 756.80 4.52 1.75E-01

6. 23E-01 873. 1 8 12.08

-l.18E-01 2.03E-01 996. 2 9 10.48

-2.46E-02 2.57E-01 1004.76 18.01 8.85E-0 2 1.82E-01 1274.43 34.80

-1. llE-01 1.16E-01

[142]

3/29/2017 1 :01 :14PM Page 6 of6 Analysis Report for 29-Mar-17-10031 L3-10205A-FRGC 014CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCilgrams)

(pCi/grams)

(pCi!grams)

Eu-154 1596.48

1. 80 1.55E-0 1 5.44E-02 l.19E+OO Eu-155 45.30

1. 31 6.08E-01 9.38E-02 6.53E+OO 60.01

1. 22

- 8.70E-01 5.34E+OO 86.55 30.70

-l. 72E-02 9.38E-02 105.31 21.10 3.39E-03

l. lOE-01 Ra-226 186.21 3.64 2.38E-01 5.00E-01 5.00E-01 Pa-231 27.36 10.30 O.OOE+OO

7. 2 6E-02

7. 2 6E-02 283.69

1. 70

-5. 40E-01

l. 2 3E+00 300.07 2.47

-3.85E-0 1 9.47E-01 302.65 2. 2 0 3.76E-O:

9.56E-01 330.06

1. 40

-5.30E- 01 1.38E+OO U-235 143.76 10.96

1. 42E-02 3.08E-02 l.77E-01 163.33 5.08

-7.78E-0 2 3.54E-01 185. 71

57. 2 0

-7.08E-0 3 3. 08E-0 2 2 02. 11

1. 08

-4.76E-01 1.94E+OO 205.31 5.01

-1.40E-01 4.06E....:01 Am-241 59.54 35.90

-7.61E-02 1. 80E-01

• 1.80E-01

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

? = CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level

[143]

60 55 50 45 40 35 1000 2000 3000

~

ROI Type: 1 0000002637.CNF 4000 channel 5000 Live Time

600.000 sec Real Tire :600.260 sec start:

1: -0.0(kev)

Stop : 8192:2047.S(keV)

Acq, Start :wed Mar 29 12: 51: 03 2017 6000 7000 8000

[144]

3/29/2017 12:49:59PM

~pex Gamma Analysis Report for 29-Mar-17-10030 L3-10205A-FRQC-O 13CV GAMMA SPECTRUM ANAL YS/S Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

29-Mar-17-10030

L3-10205A-FRQC-013CV

Sand 1.614E+03 grams

Default

3/24/2017 10:02:00AM

3/29/2017 12:39:SOPM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.4 seconds

0.06%

3.00

120 - 8192

120- 8192

1.000 keV

11/10/2016

3/29/2017

initial 11 /16/16

2636

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/29/2017 12:49:53PM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page 1 of6

[145]

3/29/2017 12:49:59PM Page 2 of6 Analysis Report for 29-Mar-17-10030 L3-10205A-FRQC-013CV Peak No.

Energy (keV)

ROI start ROI end 1

2 238.60 1460.71 948 -

960 5832 -

5850 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centroid 953.97 5840.76 No background subtract performed on this spectrum.

Net Peak Area 5.93E+O l 8.90E+O l Net Area Continuum Uncertainty Counts 9.91 9.43

1. 4 7E+Ol O.OOE+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Name Confidence (keV)

K-40 0.99 1460.82 Pb-212

1. 00 115.18 238.63 300.09

• = Energy line found In the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma Yield(%)

10.66 0.60 43.60 3.30 Activity (pCilgrams) 2. 21E+OO 9.99E-02 Activity Uncertainty

2. 54E-01 1.85E-02 FWHM (keV) 0.94 0.80

[146]

3/29/2017 12:49:59PM Analysis Report for 29-Mar-17-10030 L3-10205A-FRQC-013CV INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Pb-212 Nuclide Id Confidence 0.998

1. 000

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wt mean Activity (pCl!grams) 2.21E+OO 9.99E-02

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Activity Uncertainty 2.54E-01 1.85E-02 Page 3 of6 Comments

[147]

3/29/2017 12:49:59PM Analysis Report for 29-M_ar-17-10030

+

L3-10205A-FRQC-O 13CV Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks were identified.

M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS

3/29/2017 12:49:53PM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE MDA REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCl/grams)

(pCilgrams)

(pCl/grams)

BE-7 477.60 10.44 4.31E-02 3.06E-01 3.06E-01 K-40 1460.8 2 10.66 2.21E+OO

7. 15E-02 7.15E-0 2 Co-60 1173. 23 99.85

-1.42E-04 3.73E-02 3.73E-02 1332.49 99.98

-1.68E-0 2 3.85E-02 Nb-94 702.65 99.81

-l.61E-02 2.87E-02 2.87E-02 871.09 99.89

- 1.13E-02 3.46E-02 Ag-108m 79.13 6.60 2.73E-03 2.50E-0 2 6.46E-01 433.94 90.50

-l.67E-04 2.50E-0 2 614. 2 8 89.80

-5.73E-02 4.24E-02 722.94 90.80

-1.09E-02 3.82E-02 Sb-125 176..?l 6. 84

9. 2 6E-02 7.85E- 02 2.89E-01 380.45

1. 52 3.19E-01 1.68E+OO 427.87 2 9.60 8. 75E-04 7.85E-02 463.36 10.49 l.97E-02 2.42E-01 600.60 17.65

-4.44E-02 l.63E-01 606.71 4.98

9. llE-01 9.00E-01 635.95

11. 22

- 2.53E-0 2 2. 28E-01 671.44

1. 79 1.53E-Ol l.90E+OO Ba-133 79.61 2.65

4. 0SE-01 3.72E- 02 1.60E+OO Page 4 of6 Tolerance Nuclide

[148]

3/29/2017 12:49:59PM Page 5 of6 Analysis Report for 29-Mar-17-10030 L3-10205A-FRQC~013CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCUgrams)

(pCilgrams)

(pCi/grams)

Ba-133

81. 00 32.90

-5.38E-02

3. 72E-02 1.08E-01 276.40 7.16 3.07E-03 3.05E-01 302.85 18.34

- 1.0lE-02 1.13E-01 356. 01 62.05

-3.66E-02

3. 72E-0 2 383.85 8.94

1. 4 9E-01 2.92E-01 Cs - 134 475.36

1. 48 5.25E-01 3.82E-02 2.19E+OO 563.25 8.34

-6.60E-03 3.30E-01 569.33 15.37

-l.44E-02 1.54E-01 604. 72 97.62 2.81E-03 3.87E-02 795.86 85.46

-6.46E-04 3.82E-02 801.95 8.69 2.41E-01 3.92E-0 1 1038.61 0.99 2. llE+OO 3.82E+OO 1167.97

1. 79

-2.53E+OO

1. 58E+OO 1365.19 3.02

-9.00E-01 8.09E-01 Cs-137 661.66 85.10 4.34E-03 4.15E-02 4.15E-02 Eu-15 2 121. 78 28.67 4.lOE-02 8.33E-02 8.33E-02 244.70 7.61 1.14E-01 3.48E-01 295.94 0.45 3.75E+OO 6.40E+OO 344.28 26.60

-5.77E-02 8.67E-0 2 367.79 0.86

-1.07E+OO 2.41E+OO 411.12 2.24

-5.05E-0 2 1.lOE+OO 443. 96 2.83 2.90E-01 9.83E-01 488.68 0.42

-2.08E+OO 6.61E+OO 563. 99 0.49 2.46E+OO 5.58E+OO 586. 26 0.46 4.lOE+OO 9.llE+OO 678.62 0.47

-7.JBE-01 6.83E+OO 688.67 0.86

-2.59E+OO 3.14E+OO 71 9. 35 0.28 4.33E-01 1.09E+Ol 778.90 12.96

-8.22E-02 1.64E-01 810.45

0. 32

-2. 32E+OO 7.98E+OO 867.37

4. 2 6

-2.37E-01 8.97E-01 919.33 0.43

-7.09E-01 6.55E+OO 964. 08 14.65 9.13E-02 2.82E-01 1085.87 10.24

1. 89E- 01 3.62E-01 1089.74

1. 73

-9.86E-01 2.15E+OO 1112.07

13. 69 8.90E-0 2 3.22E-01 1212.95

1. 43 5.54E-01 3.05E+00 1249.94 0.19 3.34E+OO 2.16E+Ol 1299.14

1. 63

8. 96E-01 2.19E+OO 1408.01 21.07 3.67E-02

1. 37E-01 1457.64 0.50 3.75E+Ol 2.55E+Ol 1528.10 0.28

-5.61E+OO 9.42E+OO Eu-154 123.07 40.40

-7.02E-03 5.68E-02 5.68E-02 247.93 6.89

-5.75E-0 2 3.24E-01 591. 7 6 4.95

-9.94E-0 2 6.lOE-01 692.4 2

1. 78

-3.65E-0 1

1. 72E+OO 723. 30 20.06 1.16E-02 1.73E-01 756.8 0 4.52

-3.47E-01 6.67E-01 873. 1 8 12.08

-1.76E-01 2.87E-0 1 996.29 10.48 9.67E-02 2.63E-01 1004.76 18.01 2.83E-03 1.66E-01 1274.43 34.80 7.58E-0 2

1. 2 9E-01

[149]

3/29/2017 12:49:59PM Page 6 of6 Analysis Report for 29-Mar-17-10030 L3-10205A-FRQC-013CV Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCi/grams)

(pCUgrams)

(pCi/grams)

Eu-154 1596.48

1. 80 4.75E-01 5.68E-02 1.77E+OO Eu-155 45.30

1. 31

-2. 14E+OO 1.04E-0 1 6.52E+OO 60.01

1. 22

-4.89E-01 6.15E+OO 86.55 30.70

-2.91E-02 1.04E-01 105.31 21.10

-2.00E-02 1.23E-01 Ra-226 186. 21 3.64

-3.55E-01

6. 15E-01 6.15E-01 Pa-231 27.36 10.30 O.OOE+OO 7.43E-02 7.43E-02 283.69

1. '7 0

-2.78E-0 2

1. 31E+OO 300.07 2.47

-8.85E-01 9.20E-01 302.65 2.20 4.14E-01 9.79E-01 330.06

1. 40

-6.21E-01 1.80E+OO U-235 143.76 10. 96

1. 27E-02

3. 99E-02 2.00E-01 163.33 5.08

- 8.62E-0 2 3.57E-01 185. 71 57.20 4.99E-03 3.99E-02 202.11

1. 08 5.42E-02 1.81E+OO 205.31 5.01

-3.59E-01 4.21E-01 Am-2 41 59.54 35.90

-2.83E-02 2.06E-0 1 2.06E-01

+

= Nuclide identified during the nuclide identification

~

= Energy line found in the spectrum

= MDA value not calculated

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

?

= CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level *

[150]

60 55 50 45 40 35 1000 2000

~

ROI Type: 1 3000 0000002636.CNF 4000 channel 5000 Live Time :600.000 sec Real Ti11e : 600.390 sec Start:

1: -0.0(keV)

Stop : 8192:2047.S(keV)

Acq. start :wed Mar 29 12: 39: 50 2017 6000 7000 8000

ATTACHMENT 6 EBERLINE ANALYTICAL REPORTS

[151]

Printed: 6/11/2018 3:27 PM Page 1 of 3 SDG:

Purchase Order:

Analysis Category:

Sample Matrix:

Lab ID Sample Type Client ID Sample Date Receipt Date Analysis Date Batch ID Analyte Method Result CU CSU MDA Qualifier Report Units 17-05091-01 LCS KNOWN 05/17/17 00:00 5/15/2017 5/30/2017 17-05091 Nickel-63 ASTM 3500-Ni Modified 1.58E+03 4.74E+01 pCi/g 17-05091-01 LCS SPIKE 05/17/17 00:00 5/15/2017 5/30/2017 17-05091 Nickel-63 ASTM 3500-Ni Modified 1.47E+03 9.92E+00 8.69E+01 2.56E+00 pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/30/2017 17-05091 Nickel-63 ASTM 3500-Ni Modified

-2.31E-01 3.03E-01 3.04E-01 5.28E-01 U

pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/30/2017 17-05091 Nickel-63 ASTM 3500-Ni Modified 0.00E+00 2.75E-01 2.75E-01 4.71E-01 U

pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/30/2017 17-05091 Nickel-63 ASTM 3500-Ni Modified

-3.70E-01 2.77E-01 2.78E-01 4.89E-01 U

pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/30/2017 17-05091 Nickel-63 ASTM 3500-Ni Modified

-2.03E-02 2.97E-01 2.97E-01 5.09E-01 U

pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/30/2017 17-05091 Nickel-63 ASTM 3500-Ni Modified

-2.08E-01 3.00E-01 3.00E-01 5.21E-01 U

pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/31/2017 17-05091 Nickel-63 ASTM 3500-Ni Modified

-7.58E-02 2.76E-01 2.76E-01 4.76E-01 U

pCi/g 17-05091-01 LCS KNOWN 05/17/17 00:00 5/15/2017 6/16/2017 17-05091 Strontium-90 EIChroM SRW01 Modified 5.43E+01 3.04E-01 pCi/g 17-05091-01 LCS SPIKE 05/17/17 00:00 5/15/2017 6/16/2017 17-05091 Strontium-90 EIChroM SRW01 Modified 6.74E+01 1.59E+00 9.30E+00 6.91E-01 pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 6/16/2017 17-05091 Strontium-90 EIChroM SRW01 Modified 2.68E-01 1.48E-01 1.52E-01 2.82E-01 U

pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 6/16/2017 17-05091 Strontium-90 EIChroM SRW01 Modified 1.37E-01 1.66E-01 1.67E-01 3.39E-01 U

pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 6/16/2017 17-05091 Strontium-90 EIChroM SRW01 Modified 2.82E-01 1.54E-01 1.59E-01 2.95E-01 U

pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 6/16/2017 17-05091 Strontium-90 EIChroM SRW01 Modified

-1.80E-02 1.55E-01 1.55E-01 3.34E-01 U

pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 6/16/2017 17-05091 Strontium-90 EIChroM SRW01 Modified 3.30E-02 1.94E-01 1.94E-01 4.10E-01 U

pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 6/16/2017 17-05091 Strontium-90 EIChroM SRW01 Modified

-4.48E-02 1.61E-01 1.62E-01 3.50E-01 U

pCi/g 17-05091-01 LCS KNOWN 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Cobalt-60 EPA 901.1 Modified 1.35E+02 5.27E+00 pCi/g 17-05091-01 LCS KNOWN 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Cesium-137 EPA 901.1 Modified 8.44E+01 3.38E+00 pCi/g 17-05091-01 LCS SPIKE 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Cobalt-60 EPA 901.1 Modified 1.26E+02 7.53E+00 9.93E+00 1.04E+00 pCi/g 17-05091-01 LCS SPIKE 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Cesium-137 EPA 901.1 Modified 8.25E+01 7.49E+00 8.61E+00 1.30E+00 pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Actinium-228 EPA 901.1 Modified 1.67E-02 4.38E-02 4.38E-02 7.49E-02 U

pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Bismuth-214 EPA 901.1 Modified 1.11E-02 3.16E-02 3.16E-02 4.55E-02 U

pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Cobalt-60 EPA 901.1 Modified 3.11E-03 1.24E-02 1.24E-02 2.02E-02 U

pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Cesium-134 EPA 901.1 Modified

-4.51E-03 1.41E-02 1.41E-02 1.80E-02 U

pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Cesium-137 EPA 901.1 Modified 5.29E-04 1.26E-02 1.26E-02 2.11E-02 U

pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Potassium-40 EPA 901.1 Modified 1.74E-01 1.29E-01 1.29E-01 1.90E-01 U

pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Lead-212 EPA 901.1 Modified 1.51E-02 2.21E-02 2.21E-02 3.15E-02 U

pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Lead-214 EPA 901.1 Modified 7.01E-03 3.46E-02 3.46E-02 4.67E-02 U

pCi/g 17-05091-02 MBL BLANK 05/17/17 00:00 5/15/2017 5/19/2017 17-05091 Thallium-208 EPA 901.1 Modified 9.11E-03 4.15E-02 4.15E-02 5.91E-02 U

pCi/g Zion, IL 60099 Work Order Details:

671498 17-05091 SO ENVIRONMENTAL Eberline Analytical Final Report of Analysis Report To:

Patricia Giza Zion Solutions 101 Shiloh Blvd CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (2-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample; MBL=Blank; DUP=Duplicate; TRG=Normal Sample; DO=Duplicate Original

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Printed: 6/11/2018 3:27 PM Page 2 of 3 SDG:

Purchase Order:

Analysis Category:

Sample Matrix:

Lab ID Sample Type Client ID Sample Date Receipt Date Analysis Date Batch ID Analyte Method Result CU CSU MDA Qualifier Report Units Zion, IL 60099 Work Order Details:

671498 17-05091 SO ENVIRONMENTAL Eberline Analytical Final Report of Analysis Report To:

Patricia Giza Zion Solutions 101 Shiloh Blvd 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Actinium-228 EPA 901.1 Modified 2.89E-01 8.11E-02 8.25E-02 1.63E-01 pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Bismuth-214 EPA 901.1 Modified 2.56E-01 6.80E-02 6.92E-02 9.25E-02 pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Cobalt-60 EPA 901.1 Modified 3.85E-02 1.97E-02 1.98E-02 3.39E-02 U

pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Cesium-134 EPA 901.1 Modified 1.15E-03 1.08E-02 1.08E-02 3.12E-02 U

pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Cesium-137 EPA 901.1 Modified 9.95E-03 2.01E-02 2.01E-02 3.15E-02 U

pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Potassium-40 EPA 901.1 Modified 7.85E+00 9.34E-01 1.02E+00 6.57E-01 pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Lead-212 EPA 901.1 Modified 4.14E-01 7.66E-02 7.95E-02 1.06E-01 pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Lead-214 EPA 901.1 Modified 3.12E-01 5.91E-02 6.13E-02 1.04E-01 pCi/g 17-05091-03 DUP L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Thallium-208 EPA 901.1 Modified 2.77E-01 6.02E-02 6.18E-02 7.50E-02 pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Actinium-228 EPA 901.1 Modified 4.24E-01 9.56E-02 9.80E-02 1.84E-01 pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Bismuth-214 EPA 901.1 Modified 3.06E-01 5.59E-02 5.80E-02 8.40E-02 pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Cobalt-60 EPA 901.1 Modified 1.02E-02 2.21E-02 2.21E-02 2.64E-02 U

pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Cesium-134 EPA 901.1 Modified

-6.12E-04 1.14E-02 1.14E-02 3.32E-02 U

pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Cesium-137 EPA 901.1 Modified 1.63E-02 2.08E-02 2.08E-02 3.34E-02 U

pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Potassium-40 EPA 901.1 Modified 8.43E+00 9.35E-01 1.03E+00 4.18E-01 pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Lead-212 EPA 901.1 Modified 3.67E-01 5.10E-02 5.44E-02 8.94E-02 pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Lead-214 EPA 901.1 Modified 3.20E-01 5.20E-02 5.45E-02 7.02E-02 pCi/g 17-05091-04 DO L310222AFRGS001SS-B 02/27/17 13:05 5/15/2017 5/19/2017 17-05091 Thallium-208 EPA 901.1 Modified 3.23E-01 6.22E-02 6.43E-02 6.65E-02 pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/19/2017 17-05091 Actinium-228 EPA 901.1 Modified 3.20E-01 7.05E-02 7.24E-02 1.36E-01 pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/19/2017 17-05091 Bismuth-214 EPA 901.1 Modified 2.97E-01 6.07E-02 6.26E-02 8.22E-02 pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/19/2017 17-05091 Cobalt-60 EPA 901.1 Modified

-6.99E-04 2.58E-02 2.58E-02 2.90E-02 U

pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/19/2017 17-05091 Cesium-134 EPA 901.1 Modified

-4.44E-03 9.41E-03 9.41E-03 2.36E-02 U

pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/19/2017 17-05091 Cesium-137 EPA 901.1 Modified

-6.65E-03 2.01E-02 2.01E-02 3.18E-02 U

pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/19/2017 17-05091 Potassium-40 EPA 901.1 Modified 8.26E+00 9.79E-01 1.07E+00 3.18E-01 pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/19/2017 17-05091 Lead-212 EPA 901.1 Modified 2.72E-01 6.07E-02 6.22E-02 8.70E-02 pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/19/2017 17-05091 Lead-214 EPA 901.1 Modified 3.34E-01 5.60E-02 5.86E-02 8.83E-02 pCi/g 17-05091-05 TRG L310222AFRGS004SS-B 02/27/17 12:45 5/15/2017 5/19/2017 17-05091 Thallium-208 EPA 901.1 Modified 2.07E-01 5.15E-02 5.26E-02 5.30E-02 pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (2-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample; MBL=Blank; DUP=Duplicate; TRG=Normal Sample; DO=Duplicate Original

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Printed: 6/11/2018 3:27 PM Page 3 of 3 SDG:

Purchase Order:

Analysis Category:

Sample Matrix:

Lab ID Sample Type Client ID Sample Date Receipt Date Analysis Date Batch ID Analyte Method Result CU CSU MDA Qualifier Report Units Zion, IL 60099 Work Order Details:

671498 17-05091 SO ENVIRONMENTAL Eberline Analytical Final Report of Analysis Report To:

Patricia Giza Zion Solutions 101 Shiloh Blvd 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/19/2017 17-05091 Actinium-228 EPA 901.1 Modified 3.78E-01 1.49E-01 1.51E-01 2.58E-01 pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/19/2017 17-05091 Bismuth-214 EPA 901.1 Modified 6.26E-01 1.16E-01 1.21E-01 1.56E-01 pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/19/2017 17-05091 Cobalt-60 EPA 901.1 Modified 1.36E-02 4.80E-02 4.80E-02 6.56E-02 U

pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/19/2017 17-05091 Cesium-134 EPA 901.1 Modified

-3.10E-01 9.64E-02 9.77E-02 7.98E-02 U

pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/19/2017 17-05091 Cesium-137 EPA 901.1 Modified 3.90E-02 4.03E-02 4.04E-02 6.69E-02 U

pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/19/2017 17-05091 Potassium-40 EPA 901.1 Modified 1.17E+01 1.38E+00 1.51E+00 7.26E-01 pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/19/2017 17-05091 Lead-212 EPA 901.1 Modified 4.96E-01 1.04E-01 1.07E-01 1.49E-01 pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/19/2017 17-05091 Lead-214 EPA 901.1 Modified 5.23E-01 9.23E-02 9.61E-02 1.47E-01 pCi/g 17-05091-06 TRG L310205AFRGS004SS-B 04/13/16 13:20 5/15/2017 5/19/2017 17-05091 Thallium-208 EPA 901.1 Modified 4.11E-01 1.10E-01 1.12E-01 2.00E-01 U

pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/19/2017 17-05091 Actinium-228 EPA 901.1 Modified 2.84E-01 1.12E-01 1.13E-01 2.09E-01 pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/19/2017 17-05091 Bismuth-214 EPA 901.1 Modified 1.30E-01 6.35E-02 6.39E-02 1.16E-01 U

pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/19/2017 17-05091 Cobalt-60 EPA 901.1 Modified

-1.23E-02 3.07E-02 3.07E-02 5.30E-02 U

pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/19/2017 17-05091 Cesium-134 EPA 901.1 Modified

-5.44E-02 4.59E-02 4.60E-02 4.94E-02 U

pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/19/2017 17-05091 Cesium-137 EPA 901.1 Modified 5.61E-02 3.84E-02 3.85E-02 1.46E-01 U

pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/19/2017 17-05091 Potassium-40 EPA 901.1 Modified 5.54E+00 8.85E-01 9.29E-01 4.62E-01 pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/19/2017 17-05091 Lead-212 EPA 901.1 Modified 2.01E-01 6.30E-02 6.38E-02 1.49E-01 pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/19/2017 17-05091 Lead-214 EPA 901.1 Modified 1.56E-01 7.81E-02 7.85E-02 1.22E-01 pCi/g 17-05091-07 TRG L310205AFRGC011CV-B 03/24/17 09:45 5/15/2017 5/19/2017 17-05091 Thallium-208 EPA 901.1 Modified 3.15E-01 9.67E-02 9.80E-02 1.09E-01 pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (2-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample; MBL=Blank; DUP=Duplicate; TRG=Normal Sample; DO=Duplicate Original

[154]