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Restoration Project, FSS Final Report - Phase 1. FSS Release Record, North Beach Area Survey Unit 10222
	ML18331A010
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	06/18/2018
From:	Yetter R; ZionSolutions
To:	; Office of Nuclear Material Safety and Safeguards
Shared Package
ML18331A015	List: ML18331A003; ML18331A004; ML18331A005; ML18331A006; ML18331A007; ML18331A008; ML18331A009; ML18331A010; ML18331A011; ML18331A012; ML18331A013; ZS-2018-0093, Submittal of Final Status Survey (FSS) Final Report - Phase 1;
References
	ZS-2018-0093
	Download: ML18331A010 (199)
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ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

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FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222 PREPARED BY/ DATE:

REVIEWED BY/ DATE:

APPROVED BY/ DATE:

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ZIONSOLllTIONS;:;;

M!~.,,."'.',.,:,o,*

R. F. Yett II, Junior Technical Assistant

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raham,Radiological Engineer 6/B'jfl

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Co,9h8 C/L T Manager

[1]

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

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TABLE OF CONTENTS

1.

EXECUTIVE

SUMMARY

..................................................................................................... 4

2.

SURVEY UNIT DESCRIPTION........................................................................................... 4

3.

CLASSIFICATION BASIS.................................................................................................... 5

4.

DATA QUALITY OBJECTIVES (DQO)............................................................................. 7

5.

SURVEY DESIGN................................................................................................................ 11

6.

SURVEY IMPLEMENTATION.......................................................................................... 18

7.

SURVEY RESULTS.............................................................................................................. 19

8.

QUALITY CONTROL......................................................................................................... 24

9.

INVESTIGATIONS AND RESULTS................................................................................. 24

10.

REMEDIATION AND RESULTS................................................................................... 24

11.

CHANGES FROM THE FINAL STATUS SURVEY PLAN........................................ 24

12.

DATA QUALITY ASSESSMENT (DQA)...................................................................... 24

13.

ANOMALIES..................................................................................................................... 25

14.

CONCLUSION.................................................................................................................. 25

15.

REFERENCES................................................................................................................... 26

16.

ATTACHMENTS.............................................................................................................. 27 ATTACHMENT 1 - FIGURES AND MAPS................................................................................... 28 ATTACHMENT 2 - SCAN DATA................................................................................................ 33 ATTACHMENT 3 - SAMPLE ANALYTICAL REPORTS.................................................................. 58 ATTACHMENT 4 - CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATION..... 185 ATTACHMENT 5 - QC SAMPLE ASSESSMENT........................................................................ 187 ATTACHMENT 6 - GRAPHICAL PRESENTATIONS.................................................................... 189 ATTACHMENT 7 - EBERLINE ANALYTICAL REPORTS............................................................. 195

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

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LIST OF ACRONYMS AND ABBREVIATIONS DQO Data Quality Objective DCGL Derived Concentration Guideline Level FSS Final Status Survey GPS Global Positioning System LTP License Termination Plan MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual MDCR Minimal Detectable Count Rate NAD North American Datum NaI Sodium Iodide OpDCGL Operational Derived Concentration Guideline Level QC Quality Control RE Radiological Engineer ROC Radionuclides of Concern SOF Sum-of-Fraction VCC Vertical Concrete Cask ZSRP Zion Station Restoration Project

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

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1.

EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit 10222, North Beach Area, 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 (L3-10222A-F) 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. As a systematic sample population, fifteen (15) randomly located surface soil samples were acquired from the survey unit. In addition, surface scanning was performed on 5% of the total surface area in the survey unit. The analytical results for all soil samples taken in survey unit 10222 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 0.0596 when applying the respective Operational Derived Concentration Guideline Levels (OpDCGL). Therefore, the null hypothesis is rejected and survey unit 10222 is acceptable for unrestricted release.

2.

SURVEY UNIT DESCRIPTION North Beach Area, survey unit 10222, is an impacted Class 3 open land survey unit. It is bounded to the west by Class 3 survey units 10212B and 10212A and Class 1 survey units 10201A, 10201B, 10201C, and 10201D; Class 3 survey unit 10223 to the south; Lake Michigan to the east; and to the north by Hosah Park. The area of the survey unit is 21,778 m2.

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

The soil is loam and beach sand. The terrain consists of thick underbrush, beach sand, beach grass, and small trees. Solid physical items such as rocks, driftwood, and chain-link fencing are present in the area.

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) 1927. The

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reference coordinates associated with this survey unit are denoted on Figure 1 located in.

Picture 1 - SU10222

3.

CLASSIFICATION BASIS Survey unit 10222 was classified in accordance with ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 5).

Impacted Class 3 open land survey unit 10222 was originally identified as non-impacted by the Historical Site Assessment (HSA) (Reference 6). Because of the survey units proximity to impacted survey units, it was deemed a Class 3 survey unit. 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 July 24, 2013, through August 12, 2013. The survey design for this survey unit called for the acquisition of eleven (11) surface soil samples taken at random locations and eighteen (18) surface soil samples taken at judgmental locations. The survey design also required the acquisition of subsurface soil samples at three (3) random locations and seven (7) subsurface soil samples taken at judgmental locations to a depth of three meters.

Twelve-thousand one-hundred and twelve (12,112) square meters or approximately 56%

of the total surface area in the survey unit was scanned using a Ludlum Model 2350-1 and a Model 44-10 NaI detector. For the area scanned, the average observed background in the survey unit was 1,806 cpm. The average observed scan measurement was 2,139 cpm with a maximum observed measurement of 4,316 cpm. One-hundred and two (102) scan

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alarms were observed in this survey unit with the scan alarm set-point set at the MDCR plus background. The area where the elevated activity was observed was investigated by additional scans. A majority of the scan alarms occurred at the location of black sand deposits observed on the beach which appeared to be grit blasting media. The area was investigated by additional scans and one (1) investigative surface soil sample and five (5) investigative subsurface soil samples were acquired at the location were the scan alarms were observed.

Thirty (30) surface soil samples and two (2) QC split samples were acquired and analyzed by the on-site gamma spectroscopy system. Fifteen (15) subsurface samples were taken to a depth of three-meters. Subsurface soil samples were composited and analyzed in one-meter intervals, resulting in forty-five (45) subsurface soil samples. All subsurface soil samples were analyzed by the on-site gamma spectroscopy system. No plant-derived radionuclides greater that the respective MDC of the instrument was detected in any sample in this survey unit. The samples taken around the black sand deposits exhibited natural radioactive material in the Uranium and Thorium decay chains, confirming that the material is most likely grit blasting media.

The locations of scan areas and surface soil samples taken during characterization in survey unit 10222 are illustrated on Figure 2 in Attachment 1. A summary of the analyses 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 :

< 3.00E-02

< 2.00E-02 Maximum Value :

< 9.00E-02

< 8.00E-02 Mean :

< 6.00E-02

< 5.00E-02 Median :

< 6.00E-02

< 5.00E-02 Standard Deviation :

N/A N/A A Radiological Engineer (RE) performed a visual inspection and walk-down of the survey unit on 02/08/2017 prior to performing FSS. The purpose of the walk-down was to assess the physical condition of the survey unit, evaluate access points and travel paths and identify potentially hazardous conditions. A final classification assessment was performed

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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 Operational DCGLs, 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 in accordance with MARSSIM. The appropriate design for a given survey will be developed using the DQO process as outlined in Appendix D of MARSSIM. A summary of seven steps of the DQO process are outlined as follows.

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 10222 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 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

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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 calculated for both the 0.15 m and 1 m thicknesses. Based on characterization data and

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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 provides the exposure scenarios and modeling parameters that were used to calculate the site-specific DCGLs for soils (referred to as Base Case Soil DCGLs 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 Base Case DCGLs 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 3,572.10 Sr-90 12.09 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

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Radionuclide Subsurface Soil DCGL (pCi/g)

Ni-63 763.02 Sr-90 1.66 Each radionuclide-specific Base Case DCGL 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/year or less after all FSS is completed, the Base Case DCGLs 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 Base Case DCGLs 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 Operational DCGL is then used as the DCGL for the FSS design of the survey unit (calculation of surrogate DCGLs, investigations levels, etc.). Details of the Operational DCGLs 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 Operational DCGLs 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 Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the Operational DCGL. 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. 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 Operational DCGL were preferable while MDCs up to 50% of the Operational DCGL were acceptable. The minimum acceptable MDC for measurements obtained using field instruments was 50 percent of the applicable Operational DCGL.

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 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 10222. 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

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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 10222, the surrogate Operational DCGLs 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

Where:

DCGLSur

= Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn

= Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the Operational DCGLs presented in Table 5 and the maximum ratios from Table 7, the following surrogate calculations were performed:

Equation 2

!

"#$%&

1

'(

1 3.630!

"#$%&- (

0.002 3.095!#12&-3

3.622 45/

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The surrogate Operational DCGL 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

!

7#82&

1

'(

1 1.091!

7#82&- (

180.45 914.458!;<#8&-3

0.898 45/

The surrogate Operational DCGL 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 Operational DCGL. 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:

!=>??>&

1

'(

0.012 0.898!

7#82&- 0.00001 1.733

"#$A (

0.988 3.622!;<#8&-3

3.494 45/

The surrogate adjusted gamma DCGL equals 3.494 pCi/g. The action levels for survey unit 10224 are based on 50% of the DCGL and are presented in Table 8.

Table 8 -

Action Levels for Survey Unit 10222 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 Operational DCGL (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 of 3.494 pCi/g 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

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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 Boundary 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 (), 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 /. In accordance with MARSSIM, because the standard deviation was not recorded for characterization data (all data below MDC), a coefficient of variation on the order of 30% was used to calculate /. The / for survey unit 10222 was calculated as follows:

Equation 4

/

=

0.5/0.02

=

25 As the calculated relative shift (25) 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. One (1) sample location was added to the systematic sample population (N = 15) as a measure to ensure enough survey coverage as a large portion of the survey unit was inaccessible due to the changing water level.

A Prospective Power Curve was generated using COMPASS, a software package developed under the sponsorship of the United States Nuclear Regulatory Commission (USNRC) for implementation of the MARSSIM in support of the decommissioning license termination rule (10CFR20, Subpart E). The result of the COMPASS computer run showed adequate power for the survey design. The survey design specified fifteen (15) surface soil samples for non-parametric statistical testing.

As the survey unit was classified as Class 3, systematic sample locations were selected at random. The random locations of the systematic 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 (15) of sample points. These coordinates were integrated with a GPS to locate sample locations in the field. Sample measurement locations for the

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surface soil samples taken for systematic design are listed with the GPS coordinates in Table 9.

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). If the derived ratio from the confirmatory samples exceeds the maximum ratios (see Table 7), then the area-specific ratios as determined by actual survey data will be used in lieu of the maximum ratios.

Table 9 - Systematic and QC Sample Measurement Locations MEASUREMENT ID NORTHING EASTING L3-10222A-FRGS-001SS 641889.0990 343828.8030 L3-10222A-FRGS-002SS 641916.3860 343832.9420 L3-10222A-FRGS-003SS 642054.0295 343833.0504 L3-10222A-FRGS-004SS 641945.5180 343837.7630 L3-10222A-FRGS-005SS 642018.5290 343830.2145 L3-10222A-FRGS-006SS 642063.1801 343848.3206 L3-10222A-FRGS-007SS 642080.5815 343852.4818 L3-10222A-FRGS-008SS 642095.3349 343858.1562 L3-10222A-FRGS-009SS 642110.5747 343846.5962 L3-10222A-FRGS-010SS 642141.2566 343840.1118 L3-10222A-FRGS-011SS 642168.8497 343858.8707 L3-10222A-FRGS-012SS 642212.8477 343856.4934 L3-10222A-FRGS-013SS 642234.9248 343863.4103 L3-10222A-FRGS-014SS 642258.8706 343872.8751 L3-10222A-FRGS-015SS 642046.6317 343843.8107 L3-10222A-FQGS-007SS 642080.5815 343852.4818 Fourteen (14) surface soil samples were originally required for the non-parametric statistical test (sample size N = 14). One (1) sample was added to the systematic sample

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population. In total, fifteen (15) surface soil samples were collected for the FSS of this survey unit. A map of the surface soil sample locations is provided in Figure 4 in.

The selection of two (2) soil sample met the requirement that 10% of the samples collected for the FSS of survey unit 10222 be analyzed for HTD ROC. Sample numbers L3-10222A-FRGS-001-SS-A and L3-10222A-FRGS-004-SS-A were selected based on exhibiting the highest concentration of Cs-137. Each 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 the locations selected at random. One (1) surface soil sample, L3-10222A-FQGS-007-SS 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. For open land areas, this may include surface drainage areas and collection points. The fraction of scanning coverage required for survey unit 10222 was determined during the DQO process with the total amount and location(s) based on the likelihood of finding elevated activity during FSS. Based on the HSA, the results of the characterization survey, and the operational use of this survey unit, fifteen (15) different scan areas representing 1,205 m2, or approximately 5% of the survey unit, of surface area was chosen at random. A map of the scan grid locations are provided in Figure 3.

For this Class 3 open land survey unit, the Investigation Levels for area scanning and 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 Scan Investigation Levels Direct Investigation Levels Class 3

>Operational DCGL or >MDCscan if MDCscan is greater than Operational DCGL

>0.5 Operational DCGL Table 11 provides a synopsis of the survey design for survey unit 10222.

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Table 11 - Synopsis of Survey Design FEATURE DESIGN CRITERIA BASIS Survey Unit Land Area 21,778 m2 GPS measurements of area Number of Measurements (N) 15 (systematic)

= 0.08

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 Two (2) 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)

Scan Survey Area Coverage 1,200 m2 or ~5% areal coverage (LTP Chapter 5, Table 5-24)

Scan Investigation Level 1.747 pCi/g (Based on 50% of normalized surrogate adjusted DCGLs for gamma emitting ROC)

(LTP Chapter 5, Table 5-25)

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

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[18]

6.

SURVEY IMPLEMENTATION For survey unit 10222, compliance with the unrestricted release criteria was demonstrated through a combination of surface scanning with a Ludlum Model 44-10 gamma detector and 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 Operational DCGL, 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 10222. 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 exceed a SOF of 0.1, then the sample(s) will be analyzed for HTD ROC. This threshold was not encountered during the FSS of survey unit 10222.

FSS field activities were conducted under FSS Sample Plan L3-10222A-F. FSS Sample Plan L3-10222A-F included DQOs, survey design, detailed FSS instructions, job safety analysis, and related procedures for reference. A Field Log (ZS-LT-300-001-001 4) 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 during normal working hours starting on February 21, 2017 and concluding on February 28, 2017.

The fifteen (15) systematic surface soil sample locations were marked with flags based on GPS coordinates provided by VSP. Around each surface soil sample location, an approximately 80 m2 scan area was marked out. A total of fifteen (15) different scan areas were established, constituting an areal scan coverage of 1,200 m2, or approximately 5% of the surface area in survey unit 10222. Background was assessed in the survey unit and it was determined that, using an Ludlum 2350-1 paired with a Model 44-10 (2x 2) sodium iodide (NaI) detector, background ranged from 1,595 counts per minute (cpm) up to 1,959 cpm.

All designated scan areas as denoted on Figure 3 in Attachment 1 were scanned using a Ludlum 2350-1 paired with a Model 44-10 2x 2 NaI detector operated in the rate-meter

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[19]

mode and using audio response. The probe was positioned as close to the ground as possible and was moved at a scan speed of approximately 0.25 meters per second. In accordance with ZionSolutions TSD 11-004, Ludlum Model 44-10 Detector Sensitivity (Reference 12), scan MDC was sufficient to detect residual radioactivity at the action level (adjusted gross gamma DCGL of 1.747 pCi/g, which was based on 50% of the normalized surrogate adjusted Operational DCGLs for gamma emitting ROC). Complete scan results are provided in Attachment 2.

In accordance with FSS design, fifteen (15) surface soil samples were collected at random locations for the systematic sample population. Each surface soil sample consisted of 1 liter of soil. The sample media was sifted to remove stones and other media larger than 1 centimeter 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 13).

Two (2) samples (L3-10222A-FRGS-001-SS-A and L3-10222A-FRGS-004-SS-A) were selected for HTD radionuclide analysis.

The implementation of survey specific QC measures included the collection of one (1) sample (L3-10222A-FQGS-007-SS) for split sample analysis.

7.

SURVEY RESULTS The scan areas identified in the FSS plan were scanned for elevated radiation levels.

Several alarms were noted during the scanning of the survey unit, but no areas alarmed upon rescan. Table 12 provides an overview of the scan results. Complete scan results are provided in Attachment 2.

Table 12 - Synopsis of Scan Results Scan Area Highest Logged Reading Action Level(1) # of Scan Alarms Investigation Samples (cpm)

(cpm)

GS001 2140 2080 1

None GS002 2270 2250 2

None GS003 2060 2080 None None GS004 2500 2250 1

None GS004 2690 2327 1

None GS005 2430 2433 None None

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[20]

Scan Area Highest Logged Reading Action Level(1) # of Scan Alarms Investigation Samples (cpm)

(cpm)

GS006 2380 2433 None None GS007 2210 2433 None None GS008 2240 2433 None None GS009 2070 2080 None None GS010 2100 2127 None None GS011 2250 2433 None None GS012 2070 2069 1

None GS013 2350 2433 None None GS014 2060 2069 None None GS015 2240 2080 1

None

1)

The action level is based on the measurement Minimum Detectable Count Rate (MDCR) plus background in accordance with the FSS plan The on-site laboratory analyzed the fifteen (15) soil samples taken for non-parametric statistical testing using the on-site gamma spectroscopy system. A summary of the fifteen (15) samples collected for non-parametric statistical testing results is provided in Table 13.

Gamma spectroscopy results (summarized in Table 13) revealed no samples above MDC for any ROC. 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 at 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 14). The complete gamma spectroscopy reports are presented in Attachment 3. The basic statistics for the systematic sample population is summarized in Table 14.

Table 13 -

Summary of Gamma Spectroscopy Results for Surface Soil Samples Comprising the Statistical Sample Population MEASUREMENT ID Co-60 Cs-134 Cs-137 Ni-63 Sr-90 (pCi/g)

(pCi/g)

L3-10222A-FRGS-001SS 3.02E-02 0.00E+00 0.00E+00 5.45E+00 0.00E+00 L3-10222A-FRGS-002SS 0.00E+00 4.60E-03 2.51E-02 0.00E+00 5.02E-05 L3-10222A-FRGS-003SS 4.71E-02 0.00E+00 5.95E-04 8.50E+00 1.19E-06

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[21]

MEASUREMENT ID Co-60 Cs-134 Cs-137 Ni-63 Sr-90 (pCi/g)

(pCi/g)

L3-10222A-FRGS-004SS 2.17E-02 3.12E-02 1.76E-02 3.92E+00 3.52E-05 L3-10222A-FRGS-005SS 3.98E-02 2.04E-02 1.28E-02 7.18E+00 2.56E-05 L3-10222A-FRGS-006SS 3.24E-02 5.48E-03 1.58E-02 5.85E+00 3.16E-05 L3-10222A-FRGS-007SS 1.60E-02 8.30E-04 2.83E-02 2.89E+00 5.66E-05 L3-10222A-FRGS-008SS 9.48E-03 2.37E-02 1.17E-04 1.71E+00 2.34E-07 L3-10222A-FRGS-009SS 1.00E-02 0.00E+00 0.00E+00 1.80E+00 0.00E+00 L3-10222A-FRGS-010SS 0.00E+00 0.00E+00 2.60E-03 0.00E+00 5.20E-06 L3-10222A-FRGS-011SS 1.60E-02 0.00E+00 0.00E+00 2.89E+00 0.00E+00 L3-10222A-FRGS-012SS 5.58E-04 0.00E+00 2.27E-02 1.01E-01 4.54E-05 L3-10222A-FRGS-013SS 0.00E+00 0.00E+00 9.92E-03 0.00E+00 1.98E-05 L3-10222A-FRGS-014SS 8.66E-03 0.00E+00 0.00E+00 1.56E+00 0.00E+00 L3-10222A-FRGS-015SS 1.50E-02 4.72E-02 9.82E-03 2.71E+00 1.96E-05 Table 14 -

Basic Statistical Properties of Systematic Sample Population ROC Mean Median Max Min Std. Dev.

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

(pCi/g)

(pCi/g) per ROC Per ROC Co-60 1.65E-02 1.50E-02 4.71E-02 0.00E+00 0.01506 4.26 3.86E-03 9.66E-02 Cs-134 8.89E-03 0.00E+00 4.72E-02 0.00E+00 0.01475 6.77 1.31E-03 3.28E-02 Cs-137 9.69E-03 9.82E-03 2.83E-02 0.00E+00 0.01022 14.18 6.83E-04 1.71E-02 Ni-63 2.97E+00 2.71E+00 8.50E+00 0.00E+00 2.71634 3572.1 8.31E-04 2.08E-02 Sr-90 1.94E-05 1.96E-05 5.66E-05 0.00E+00 0.00002 12.09 1.60E-06 4.01E-05 The off-site laboratory, Eberline Analytical, processed the two (2) samples selected for HTD ROC analysis as specified in the survey design. Sample numbers L3-10222A-FRGS-001-SS-A and L3-10222A-FRGS-004-SS-A were 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. LTP Chapter 5, section 5.1 states that for soil samples or concrete cores with positive results for both a HTD ROC and the corresponding surrogate radionuclide (Cs-137 or Co-60), the HTD to surrogate ratio will be derived. This threshold was not encountered during the FSS of survey unit 10222. No ROC were positively detected at concentrations greater than MDC for both samples. The results are provided in Table 15.

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[22]

Table 15 -

Off-Site Analysis Results (Eberline Analytical) for Sample ID #s L3-10222A-FRGS-001-SS-A and L3-10222A-FRGS-004-SS-A Sample # L3-10222A-FRGS-001-SS-A ROC Result Uncertainty MDC

>MDC (pCi/g)

(pCi/g)

Co-60 1.02E-02 2.21E-02 2.64E-02 No Cs-134

-6.12E-04 1.14E-02 3.32E-02 No Cs-137 1.63E-02 2.08E-02 3.34E-02 No Ni-63

-3.70E-01 2.77E-01 4.89E-01 No Sr-90 2.82E-01 1.54E-01 2.95E-01 No Sample # L3-10222A-FRGS-004-SS-A ROC Result Uncertainty MDC

>MDC (pCi/g)

(pCi/g)

Co-60

-6.99E-04 2.58E-02 2.90E-02 No Cs-134

-4.44E-03 9.41E-03 2.36E-02 No Cs-137

-6.65E-03 2.01E-02 3.18E-02 No Ni-63

-2.03E-02 2.97E-01 5.09E-01 No Sr-90

-1.80E-02 1.55E-01 3.34E-01 No The implementation of survey specific QC measures included the collection of one (1) sample (L3-10222A-FQGS-007-SS) 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 16. Gamma spectroscopy results (summarized in Table 18) indicate that concentrations for Cs-137, Co-60 and Cs-134 were less than MDC in the sample. The concentration for Ni-63 and Sr-90 are inferred based on the maximum ratios as specified in Table 7.

Table 16 -

Summary of Gamma Spectroscopy Results for QC Surface Soil Sample MEASUREMENT ID Co-60 Cs-134 Cs-137 Ni-63 Sr-90 (pCi/g)

(pCi/g)

L3-10222A-FQGS-007-SS 1.43E-03 0.00E+00 1.90E-02 2.58E-01 3.80E-05 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:

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[23]

Equation 5 1

2 2

1 1

+

DCGL C

n n

Where:

Cn

= concentration of radionuclide n DCGLn

= DCGL of radionuclide n.

The results of the unity rule calculation for the ROC in the systematic sample population as well as the judgmental samples for survey unit 10222 are provided in Table 17.

Table 17 -

Sum-of-Fractions for Individual Surface Soil Samples (Systematic and QC)

MEASUREMENT ID FRACTION OF OPERATIONAL DCGL SOF Co-60 Cs-134 Cs-137 Ni-63 Sr-90 L3-10222A-FRGS-001-SS 0.02768 0.00000 0.00000 0.00596 0.00000 0.03364 L3-10222A-FRGS-002-SS 0.00000 0.00265 0.00691 0.00000 0.00002 0.00959 L3-10222A-FRGS-003-SS 0.04317 0.00000 0.00016 0.00929 0.00000 0.05263 L3-10222A-FRGS-004-SS 0.01989 0.01800 0.00485 0.00428 0.00001 0.04703 L3-10222A-FRGS-005-SS 0.03648 0.01177 0.00353 0.00785 0.00001 0.05964 L3-10222A-FRGS-006-SS 0.02970 0.00316 0.00435 0.00639 0.00001 0.04361 L3-10222A-FRGS-007-SS 0.01467 0.00048 0.00780 0.00316 0.00002 0.02612 L3-10222A-FRGS-008-SS 0.00869 0.01368 0.00003 0.00187 0.00000 0.02427 L3-10222A-FRGS-009-SS 0.00917 0.00000 0.00000 0.00197 0.00000 0.01114 L3-10222A-FRGS-010-SS 0.00000 0.00000 0.00072 0.00000 0.00000 0.00072 L3-10222A-FRGS-011-SS 0.01467 0.00000 0.00000 0.00316 0.00000 0.01782 L3-10222A-FRGS-012-SS 0.00051 0.00000 0.00625 0.00011 0.00001 0.00689 L3-10222A-FRGS-013-SS 0.00000 0.00000 0.00273 0.00000 0.00001 0.00274 L3-10222A-FRGS-014-SS 0.00794 0.00000 0.00000 0.00171 0.00000 0.00965 L3-10222A-FRGS-015-SS 0.01375 0.02724 0.00271 0.00296 0.00001 0.04666 L3-10222A-FQGS-010-SS 0.00131 0.00000 0.00523 0.00028 0.00001 0.00684 Systematic Measurements Number of Systematic Measurements =

15

of Systematic Measurements with SOF > 1 =

0

of Systematic Measurements with SOF > 0.1 (HTD Assessment) =

0

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[24]

MEASUREMENT ID FRACTION OF OPERATIONAL DCGL SOF Co-60 Cs-134 Cs-137 Ni-63 Sr-90 Max Individual Systematic Measurement SOF =

0.0596 Mean Systematic Measurement SOF =

0.0261 The mean of all identified isotopes are less than the Consultation Triggers for Residential Soil Concentration depicted in Table H.1 of NUREG 1757, Vol.1, Rev. 2 (MOU Table 1).

The full table is included in Attachment 4 of this Release Record.

8.

QUALITY CONTROL The on-site laboratory processed one (1) split sample, L3-10222A-FQGS-007-SS, 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 15). There was acceptable agreement between field split results. Refer to Attachment 5 for data and quality control analysis results.

9.

INVESTIGATIONS AND RESULTS No investigations were performed in survey unit 10222.

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 Nine (9) sample locations were relocated due to the elevated lake level. Approximately half of the survey unit was covered in water during FSS. Details of the surface soil sample locations and the water level is provided in Figure 4 on Attachment 1.

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 16) for completeness and consistency. Documentation was complete and legible. Surveys and sample collection were consistent with the DQOs and were sufficient to ensure that

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[25]

the survey unit was properly designated as Class 3. The sampling design had adequate power as indicated by the Retrospective Power Curve.

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 Operational DCGL 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 Operational DCGLs. 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 6.

13.

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

14.

CONCLUSION Survey unit 10222 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 Operational DCGL 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

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[26]

properly classified as Class 3.

The dose contribution from soil in survey unit 10222 is 0.1673 mrem/yr TEDE, based on the average concentration of the ROC in samples used for non-parametric statistical sampling.

Survey unit 10222 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 TSD 11-004, Ludlum Model 44-10 Detector Sensitivity

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

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

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

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

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[27]

16.

ATTACHMENTS

- Figures and Maps

- Scan Data

- Sample Analytical Reports

- Consultation Triggers for Residential Soil Concentration

- QC Sample Assessment

- Graphical Presentations

[28]

ATTACHMENT 1 FIGURES AND MAPS

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[29]

Figure 1 Survey Unit 10222 Boundary

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[30]

Figure 2 Survey Unit 10222 Characterization Survey Scan Areas

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[31]

Figure 3 Survey Unit 10222 Characterization Survey Sample Locations

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[32]

Action Level Scan Alarms (cpm)

(cpm)

(cpm) 44-10 PR311786 304713 10222 GS010 2/21/2017, 14:59 1900 1688 2127 No 44-10 PR311786 304713 10222 GS010 2/21/2017, 14:59 1930 1688 2127 No 44-10 PR311786 304713 10222 GS010 2/21/2017, 15:00 1890 1688 2127 No 44-10 PR311786 304713 10222 GS010 2/21/2017, 15:01 1660 1688 2127 No 44-10 PR311786 304713 10222 GS010 2/21/2017, 15:03 2090 1688 2127 No 44-10 PR311786 304713 10222 GS010 2/21/2017, 15:03 1860 1688 2127 No 44-10 PR311786 304713 10222 GS010 2/21/2017, 15:04 1730 1688 2127 No

[58]

ATTACHMENT 3 SAMPLE ANALYTICAL REPORTS

3/1/2017 2:45:19PM

~,-~---~~~:1\\pex-Gamma Analysis Report for 01-Mar-17-10027 L310222AFRGS001SS DRIED GAMMA SPECTRUM ANAL YSl,'3 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 011 Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number RH Height Certificate Name Certificate Date

01-Mar-17-10027

L310222AFRGS001SS DRIED

Sand

1. 727E+03 grams

Default

2/27/2017 1 :05:00PM 3/1/2017 2:35:09PM

130G_Sand

Administrator

P11314

~ 130G_Sand

600.0 seconds

600.4 seconds

. 0.07%

3.00

120- 8192

120-8192 1.000 keV

11/10/2016

3/1/2017

initial 11/16/16

2158 1726.98 gram

Eu 155-Na22

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

3/1/2017 2:45:12PM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of7

3/1/2017 2:45:19PM Page2 of7 Analysis Report for 01-Mar-17-10027 L310222AFRGS001 SS DRIED Poak Energy ROI ROI No.

(JreV) start end 1

77.23 305 -

313 2

238.63 948 -

958 3

295.27 1173 - J.186 4

311.98 1244 - 1251 5

352.00 1401 - 1414 6

510.92 2036 - 2048 7

583.08 2325 - 2336 8

609.25 2427 - 2442 9

911. 23 3636 - 3648 10 1461. 07 5831 - 5852 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centroid 309.46 954.08 1180.38 1247.11 1407.00 2042.02 2330*. 44 2435.03 3642.39 5842.21 No background subtract performed on this spectrum.

Met Pea:,

NetArea

.Continuum Area Unc9rta/nty Counts 3.76E+Ol 12.77 5.84E+Ol 1.05E+02 14.92 4.92E+Ol 6.44E+Ol 12.37 3.16E+Ol 7.87E+OO 4.74 7.13E+OO

1. 06E+02 13.71 2.95E+01 2.30E+Ol 8.40 1.80E+01 3.07E+Ol 7.89

1. 23E+Ol 1.05E+02

11. 62

1. OOE+Ol 3.38E+Ol 6.50 3.25E+OO 2.25E+02 15.35 2.75E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Ubrary\\ZION LIB-BNLNLB IDENTIFIED NUCLIDES Nuclide Id Energy Y!eld(%)

Activity Activity

,Vame Confidence (keV)

(pCUgrams)

Uncertainty K-40 0.99 1460.82 10.66 7.36E+OO 5.94E-01 Tl-208 0.99 583.19

85.00 6.78E-02

1. 79E-02 Pb-212

1. 00 115. 18 0.60 238.63 43.60 2.45E-01 4.00E-02 300.09 3.30 Pb212-XR

0. 99 74. 82 10.28 77. 11 17.1 0

3. 49E-O:t

1. 24E-01 FWHM (keV) 0.95 0.87 0.79 0.57 1.15 0.38 0.80 1.15 0.44

1. 70

.3/1/2017 2:45:19PM P::.ge3of7 Analysis Report for 01-Mar-17-10027 L310222AFRGS001SS DRIED NucJJdlJ Id Energy Y!e!d(%)

Activi'ty Activity Name Confidence (k*VJ (pCi/gram~)

Uncertainty Pb212-XR 0.99 87.35 3.97

89. 78

1. 46 Bi-214

1. 00 609.32 45.49

4. 46E-01 5.61E-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 1401.52

1. 33 1407.99 2.39 1509.21 2.13 1661.27

1. 05 1729.59 2.88 1764.49 15.30 1847. 43 2.03 2118. 51 1.16 Pb-214

0. 99 241.99 7.25 295.22 18.42

4. OSE-01 8.42E-02 351. 93 35.60 3.94E-01

5. 97E-02 785.96

1. 06 Pb214-XR 0.99

74. 82 5.80

77. 11 9.70 6.16E-Ol 2.20E-01 87.35 2.24 89.78 a.a~

Ac-228 1.00 129. 07 2.42 209.25 3.89 270.24 3.46 328. 00

2. 95 338.32

11. 27 409.46

1. 92 463. 00 4.40 794.95 4.25 911. 20 25.80 3. 31E-01 6.54E-02 964.77 4.99 968.97 15.80 1588.20 3.22

= Energy line found In the spectrum.

- = Manually added nuclide.

? = Manually edited nucllde.

@ = Energy llne not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma

3/1/201?

2:45:19PM Analysis Report for 01-Mar-17-10027 L310222AFRGS001SS DRIED INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Tl-208 X

Bi-211 Pb-212

?

Pb212-XR Bi-214 Pb-214

?

Pb214-XR Ac-228 Nuclide id Confidence 0.990 0.998

a. an

1. 000 0.999

1. 000 0.999 0.999

1. 000

?

nuclide is part of an undetem,ined solution X

nuclide rejected by the interference analysis wtmean Activity (pCUgrams) 7.36E+OO 6.78E-02 2.45E-Ol 3.49E-Ol 4.46E-Ol 3.97E-Ol 6.16E-01 3.31E-Ol

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma wt mean Activity Uncertainty 5.94E-01 1.79E-02 4.00E-02 1.24E-Ol 5.61E-02 4.87E-02 2.20E-01 6.54E-02 Page4 of7 Comments

3/1/2017 2:45:19PM Analysis Report for 01-Mar-17-10027 L310222AFRGS001SS DRIED

+

Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel PeakNo.

Energy (keV}

4 311.98 6

510.92 M = First peak in a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFJED PEAKS

3/1/2017 2:45:12PM

120

8192 Poak Size (CPS)

1. 31111E-02 3.83943E-02 Peak CPS(%}

Uncertainty G7.;;)

36.45 NUCLIDE MDA REPORT Pealr Type Nucllde Library Used

C:\\Canberra\\Apex\\Root\\Oefault\\Llbrary\\ZION LI B-BNL.NLB Nuclide Energy Yield(%)

Activity Nuclide MDA

.UneM'DA Name (keV)

(pCVgrams)

(pCUgrams)

(pCVgn:ms)

BE-7 477.60

.10. 44

-2.llE-01 4.25E-01 4.25E-01 K-40 1460. 82 10.66 7.36E+D0 4.SOE-01 4.SOE-01 Co-60 1173.23 99.85 3.02E-02 6.7:E-02 8.32E-02 1332.49 99. 98

-7.43E-03 6.77E-02 Nb-94 702.65 99.81

-8.97E-03 5.82E-02

5. 82E-02 871. 09 99.89 2.39E-02 5.97E-02 Ag-108m 79.13 6.60

-5.60E-01 4.62E-02

1. 44E+OO 433.94 90.50

-2.48E-02 4.62E-02 614.28 89.80

-4.41E-02 9.30E-02 722.94 90.80

-8.35E-03 6.41E-02 Sb-125 176. 31 6.84

-2.71E-Ol

1. 4 7E-01 5.BOE-01 380.45

1. 52

-l.53E+OO 2.88E+OO 427.87 29.60

4. 72E-02 1.47E-Ol 463.36 10.49 3.78E-02 4. 72E-Ol 600.60 17.65

1. 63E-02

2. 64E-01 606. 71

4. 98 3.98E+OO 2. 19E+OO 635. 95

11. ~2 4.26E-01 4. 68E-Ol PageS of7 Tolerance Nuclide

'tl't~

If;!/ lfo.511

' J-J-'7

3/1/2017 2:45:19PM Page6of7 Analysis Report tor 01-Mar-17-10027 l310222AFRGS001 SS DRIED Nuclide Energy Yield{%)

Activity NuclldeMDA Llneli1DA Name (keV)

(pCl/grams)

(pCVgrams)

(pCUgrams)

Sb-125 671. 44

1. 79

-6.23E-01

1. 4 '7E-01 3.15E+OO Ba-133 79.61 2.65 -l.96E+00

1. OOE-01 3. 47E+OO

81. 00 32.90

-1.lOE-01 2.31E-01 276.40 7. 16 3.94E-01 6.64E-01 3*02. 85 18.34

-1.71E-01 2.39E-Ol 356.01 62.05

-3.85E-02 1.00E- 01 383.85 8.94

-9.23E-02 4.84E-Ol Cs-134 475.36

1. 48 6.44E-01 6.59E-02 3.13E+00 563.25 8.34

- l.23E-Ol 6.12E-01 569. 33 15.37 1.77E-01 3.17E- 01 604. 72 97.62

-4.lSE-02 9. 0SE-02 795.86 85.46

-3. 09E-02 6.59E-02 801. 95 8.69

-4.59E-02 6.65E-01 1038. 61

0. 99 3.42E+OO 7.77E+00 1167.97

1. 79 2.SOE-01

4. 48E+OO 1365.19 3.02 1.55E+OO

2. 61E+OO Cs-137 661. 66 85.10

-l.75E-02 6.67E-02

6. 67E-02 Eu-152 121.78 28.67

-9.93E-02 l.56E-01

1. 56E-01 244.70 7.61

-8.96E-01 6.14E-01 295. 94 0.45 1.44E+Ol 1.SOE+Ol 344.28

26. 60

- 3.61E-02

1. 62E-01 367.79 0.86

-2.37E+OO 5.06E+OO 411.12 2.24

1. 94E+OO 2.19E+OO 443.96 2.83

-7.53E-01 l.45E+OO 488.68 0.42

-1. 04E+OO

1. 08E+Ol 563.99

0. 49

-2.llE+OO l.04E+01 586.26 0.46

-6.95E+OO 1.70E+Ul 678.62 0.47

-l.81E+OO 1.09E+Ol 688.67 0.86 3.48E+OO 6.44E+OO 719. 35 0.28 8.35E-01 1,71E+Ol 778.90 12.96

-3.51E-01 4.37E-01 810.45 0.32 6.99E+OO 1.81E+Ol 867.3?

4.26

-1. 21E+OO 1.33E+OO 919. 33 0.43

-3.02E+OO 1.42E+Ol 964.08 14.65

-1.85E-01 4.99E-Ol 1085.87 10.24

-4. 23E-02 7.04E-01 1089.74

1. 73 2.54E+OO 4. 09E+OO 1112.07 13.69 -1.16E-01 4.90E-01 1212.95

1. 43

-4.50E+OO 6.05E+OO 1249.94

0. 19 2.88E+00 3.43E+Ol 1299.14

1. 63

-5.90E-01 3. 69E+OO 1408. 01

21. 07

-2.74E-01 3.35E-01 1457.64 a.so 1.60E+02 5.25E+Ol 1528.10 0.28 5.llE+OO l.59E+Ol Eu-154

i.23.07 40.40

-1.21E-02

l. 18E-01 1.18E-01 247.93 6.89 2.20E-01

6. lOE-01 591.76 4.95 4.40E-01

1. 12E+OO 692.42

1. 78

-2. 72E+OO 2.62E+OO 723.30 20. 06 O.OOE+OO 3.00E-01 756.80 4.52 4.42E-01 1.33E+OO 873. 18 12. 08

-3.76E-O ::'..

4.lOE-01

3/1/2017 2:45:19Piv1 Page7 of7 Analysis Report for 01-Mar-17-10027 L310222AFRGS001SS DRIED Nuclide Energy Yield(%)

Activity NuclldeMDA

!.ineMDA Name (keV)

(pCVgrams)

(pCilgram5)

(pCUgram:s)

Eu-154 996.29 10.48

3. 32E-01 1.18E-01 6.77E-01 1004.76 18.01 l.61E-01 3.81E-01 1274.43 34.80 5.67E-02 2.16E-01 1596.48

1. 80

-1.00E+OO 2.32E+OO Eu-155 45.30

1. 31 1.24E+OO

2. 41E-01

1. 28E+Ol 60.01 1.22

-2.22E+OO 1.38E+Ol 86.55 30.70

1. 06E-01 2. 41E-01 105.31

21. 10 9.99E-02

2. 66E-01 Ra-226 186.21 3.64 2.96E-Ol

1. 33E+OO l.33E+OO Pa-231 27.36 10.30 O.OOE+OO

1. 0'7E-01 1.07E-01 283.69

1. 70

-3.49E-01

2. 33E+OO 300.07 2.47 5.16E-01 1. 94E+OO 302.65 2.20

-2.42E+OO 1.99E+OO 330.06

1. 40

1. 97E+OO 3.39E+OO U-:-235 143.76 10.96

1. 37E-01 8.48E-02 4.12E-01 163.33 5.08

-5.03E-01 7.99E-01 185.71 57.20 5.lSE-02

8. 48E-02 202. 11

1. 08

1. 29E+OO 3.92E+OO 205.31 5.01

-1. 33E+OO 8.0lE-01 Am-241 59.54 35.90 6.0lE-02 4. 87E-01 4.87E-01

-,. = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

= MDA value not calculated

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

?

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

45 1000 2000 3000

~

ROI Type: 1 00000021.J6.CNF

~

4000 channel 5000 Live TiM :600.000 sec Real lilll! :60D.-43D sec Start:

l: -0.0(keV)

Stop : 8192:2047.B(keY)

Acq. start :Wed Nar 0114:35:09 2017 6000 7000 8000

.'. ~~;;,J.\\pex-Gam111a 3/212017 8:02:42AM Analysis Report for 01-Mar-1M0028 L310222AFRGS002SSS DRIED 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

01-Mar-17-:10028

L310222AFRGS002SSS DRIED

Sand 1.548E+03 grams

DefauH

2/27/2017 12:55:00PM

3/2/2017 7:52:33AM

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

312/2017

lnitial 11/16/16

2166

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM P_E_A_K_A_N_~_L Y._SIS REPORT ~ 7 Peak Analysis Performed on

3/2/2017 8:02:36AM Peak Analysis From Channel

120 Peak Analysis To Channel

8192 Pagel of7

3/2/2017 8:02:42AM Page2 of7 M

Ill Analysis Report for 01-Mar-17-10028 L310222AFRGS002SSS DRIED Peak Energy ROI ROI No.

{keV}

start end 1

74.67 297 -

313 2

77.14 297 -

313 3

238.68 949 -

960 4

295.15 1173 - 1185 5

351. 91 1402 - 1413 6

583.11 2324 - 2338 7

609.25 2427 -

2443 8

911. 06 3636 -

3648 9

1460.80 5831 - 5852 M = First peak In a mutiiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centm/d 299.23 309.07 954.30 1179.90 1406.64 2330.57 2435.03 3641.70 5841.13 No background subtract performed on this spectrum.

Net Peak Net Area Continuum Area Uncortainty Counts 2.18E+Ol

11. 52 3.53E+Ol 6.06E+Ol 22.22 6.09E+Ol 3.24E+01 14.18 4.26E+01 8.03E+O l 12.38 2.77E+01 l.32E+02 12.79

1. 26E+01 5.38E+Ol 8.28 5.16E+OO 1.01E+02

10. 70 4.32E+OO 3.17E+Ol 6.56 4.29E+OO

1. 91E+0 2

14. 46 5.09E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

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

Activity ActivitJ/

Name Confidence

{keV)

(pCUgrams}

Uncertainty

-40

1. 00 1460.82

10.66 4.95E+OO 4.32E-01 l - 208 0.99 583.19

85.00 9.18E-02

1. 52E-02 Pb-212

1. 00 115.18 0.60 238.63

43.60

1. 62E-Ol 2.81E-02 300.09 3.30 Bi-214

1. 00 609. 32

45. 4 9

3. 31E-Ol 4.04E-02 768.36 4.89 806.18 1.26 FWHM (keV)

0. 65

.Q. 82 0. 80 1.27 0.36

0. 76

1. 39

1. 62

Analysis Report for 01-Mar-17-10028 L310222AFRGS002SSS DRIED Nuclide Id Energy Name Confidence (keV)

Bi-21:4 1.00 934.06 1120.29 1155.21 1238.12 128G.98 1377.67 1385.31 1401. 52 1407.99 1509. 21 1661.27 1729.59 1764.49 1847.43 2118. 51 Pb-214

1. 00 241.99 295.22 351.93 785.96 Pb214-XR 0.99 74.82

77. 11 87.35 89. 78 Ac-228 0.99 129.07 209.25 270.24 328.00 338.32 409.46 463.00 794.95 911.20 964.77 968.97 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 312/2017 8:02:42AM Page 3 of7 Yield(%)

Activity Activity (pCi/grams)

Uncertainty 3.11 14.92

1. 63 5.83 1.43 3.99 0; 79 1.33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 7.25 18.42 3. 82E-01 6.64E-02 35.60 3.73E-01 4.68E-02

1. 06 5.80 4.76E-01

2. 57E-01 9.70 7.29E-01 2. 79E-01 2.24 0.82 2.42 3.89

3. 4 6 2.95

11. 27

1. 92 4.40 4.25 25.80 2. 44E- 01 5.lSE-02 4.99 15.80 3.22 INTERFERENCE CORRECTED REPORT

Analysis Report for 01-Mar-17-10028 L310222AFRGS002SSS DRIED Nucllde Name K-40.

Tl-208 X

Bi-211 Pb-212 X

Pb212-XR Bi-214 Pb-214 Pb214-XR Ac-228 Nuclide Id Confidence 1.000 0.999 0.894

1. 000 0.999 1.000

1. 000 0.999 0.999

?

X

=

nuclide ls part of an undetermined solution nuclide rejected by the Interference analysis 3/2/2017 8:02:42AM Wt mean Wt mean Activity Activity (pCilgrams)

Uncertainty 4.95E+OO 4.32E-01 9.18E-02 1.52E-02 l.62E-01 2.BlE-02 3.31E-01 4.04E-02 3.76E'-01 3.82E-02 5.92E-01

1. 89E-01 2.44E-01 5.lSE-02

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Page4of7 Comments

3/2/2017 8:02:42AM Analysis Report for 01-Mar-17-10028

+

L310222AFRGS002SSS DRIED Peak Locate Per1onned 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

3/2/2017 8:02:36AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty Peak Type NUCLIDE IViDA REPORT Nuclide Library Used

C :\\Canberra\\Apex\\Root\\Defautt\\Library\\ZI ON LIB-BN L. NLB Nuclide Energy Yield(%)

Activity NuclldeMDA LlneMDA Name (keV)

(pCVgrams)

(pCUgrams)

(pCi/grams)

BE-7 477.60 10. 44

1. 27E-01 3.29E-Ol

3. 29E-Ol K-40 1460. 82

10. 66 4.95E+OO 4.SOE-01

4. SOE-01 Co-60 1173. 23 99.85 -l.78E-02 4.45E-02 5.88E-02 1332.49 99.98

-7.73E-03 4. 45E-02 Nb-94 702.65 99.81

-1. 91E- 03 4.28E-02

4. 28E-02 871. 09 99.89 2.64E-02

5. 06E-02 Ag-108m 79.13 6.60

-2.65E-01 3.0BE-02 1.0lE+OO 433.94 90.50 -2. 89E-02 3.08E-02 614.28 89.80

-5.57E- 02

6. 80E-02 722.94 90.80

1. 83E-03

4. 09E-02 Sh-125 176.31 6.84

-3.. 63E-02

1. llE-01 4.14E-01 380.45

1. 52 9. 0BE-01

2. 31E+OO 427.87

29. 60

-4.91E-02

l. llE-01 463. 36 10.49 -2.64E-02 3.09E-01 600.60 17. 65

- 5.60E-02 l.85E-Ol 606.71 4.98

- l.93E- 01 l.62E+OO 635.95 11.22

-3.44E-D2 3.12E-Ol 671. 44

1. 79 4.48E- 02 2.18E+OO Ba-133 79.61 2.65 -6. 29E-Ol 7.34E-D2 2. 4 0E+OO Page S of1 Tolerance Nuclide

3/2/2017 8:02:42AM Page6 of7 Analysis Report for 01-Mar-17-10028 L310222AFRGS002SSS DRIED Nuclide Energy Yield{'/,,)

Activity NuclldeMDA LlneMDA Name (keV}

(pCVgrams)

(pCUgramsJ (pCUgrams)

Ba-133 Bl. 00 32.90

-2.SSE-01 7.34E-02

1. 37E-01 276.40 7.16

-1.41E-01 4. 44E-01 302.85 18.34 8.65E-02

1. 73E- 01 356.01 62.05

-3.63E-02

7. 34E-02 383.85 8.94 -1. 22E-Ol 3. 39E-01 Cs-134 475.36 1.48

6. 95E-01 4.91E-02

2. 2BE+OO 563.25 8.34

-4.31E-Ol

4. 31E-Ol 569.33 15.37 6.57E-02 2. 71E-Ol 604.72

97. 62 4.60E-03

6. 78E-02 795.86 85.46 2.72E-02 4

91E-02 801. 95 8.69

-2.68E-02

4. 48E-01 1038.61 0.99 4.40E+OO

5. 35E+OO 1167.97

1. 79 1.64E+OO 3.47E+OO 1365.19 3.02 4. 79E-01 l. 64E+OO Cs-137 661. 66 85.10 2.SlE-02 5.67E-02

5. 67E-02 Eu-152 121. 78 28.67 4.36E-02 1.llE-01 1

llE-01 244. 70 7.61 3.59E-01

5. lSE-01 295.94 0.45 1.64E+D1 1. 18E+Ol 344.28 2 6. 60

-1.93E-02 1. 22E-01 367.79 0.86

-2.66E+OO

3. 66E+OO 411.12 2.24 2.52E-01 1. 63E+OO 443.96 2.83

-3.27E-02 1.19E+OO 488.68 0.42 5.SOE+OO

7. 86E+OO 563.99 0.49 -5.34E-01

7. 60E+OO 586.26 0.46

-1.91E+OO

1. 36E+Ol 6'/8. 62 0.47

-6.37E-01

8. 67E+OO 688.67 0.86

-7.78E-01

5. lOE+OO 719.35 0.28

1. 66E+00 1. 21E+Ol 778.90 12.96 8.72E-02

2. 57E-01 811..l.45 0.32 6.93E-Ol

1. 25E+Ol 867. 37 4.26 3.02E- 01 1.16E+OO 919.33 0.43 8.40E+OO 1. 08E+Ol 964.08 14.65

1. 69E-02 4. 84E-01 1085.87 10.24 -1. 86E-Ol

4. 69E-01 1089.74

1. 73 2.08E+OO 2. 86E+OO 1112.07 13.69

1. 71E-Ol

4. 13E-01 1212.95

1. 43 1.27E+OO 5.08E+OO 1249.94

0. 19 2.03E+Ol

3. 31E+Ol 1299.14

1. 63

2. 80E+OO

3. 62E+OO 1408.01 21.07

-4.46E-02

2. lOE-01 1457.64 0.50

1. 05E+02

3. 89E+Ol 1528.10 0.28 8.13E+OO

1. 67E+Ol Eu-154 123.07 40.40

-2.25E-02 7. 72E-02 7.72E-02 247.93 6.89

- l.14E- 01 4.. 31E-01 591. 76 4.95

- 6. 53E- 01 6.53E- 01 692.42

1. 78 l.16E+OO

2. 56E+OO 723.30 20.06 -6.42E-02

1. 90E-01 756.80

4. 52 l.78E-01 9.37E-01 873.18 12.08 1.45E-03

4. 04E-01 996. 29 10.48 2.67E-01 4.79E-Ol 1004. 76 18.01

-1. 42E- 01 2.60E-Ol 1274.43 34.80

- 4.66E- 02 l.71E-01

3/2/2017 8:02:42AM P-age 7 of7 Analysis Report for 01-Mar-17-10028 L310222AFRGS002SSS DRIED Nuclide Energy Yield(%)

Activity NuclldeMDA LineMDA Name (keV)

(pCl/grams)

(pCUgrams)

Eu-154 1596.48

1. 80

-1.39E+OO

7. 72.E-02 2. 42E+OO Eu-155 45.30

1. 31 3.06E-01 1.63E-01

8. 68E+OO 60.01 1.22

-4.57E+OO

8. 52E+OO 86.55 30.70 9.45E-02

1. 63E-01 105. 31 21.10 2.47E-D3 1. 95E-01 Ra-226 186.21

3. 64 2.89E-01 8.76E-01

8. 76E-01 Pa-231 27.36 10.30 O.OOE+OO 7.75E-02

'7.7SE-02 283.69

1. 70 1.48E+OO 1. 98E+OO 300.07 2.47

-1. l 7E+OO 1. 31E+OO 302.65 2.20 9.29E-01 1.48E+OO 330.06

1. 40

1. 53E+OO

2. 58E+OO U-235 143.76

10. 96 8.06E-02 5. 62E-02

3. OlE-01 163.33 5.08

-7.89E-02

5. 92E-01 185.71 57.20 2.78E-02

5. 62E-02 2 02.11

1. 08 2.56E-01

2. 64E+OO 205.31 5.01 1.68E-03 6.16E-01 Am-241 59.54 35.90

-1.44E-01 3.0lE-01

3. OlE-01

+ = Nuclide iqentified 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

60 55 45 40 35 1000 2000

~

ROI Type: 1 3000 00000021 4000 Channel 5000 Live Tint :600.000 sec Rea.1 'Tia :600.370 sec Sta.rt:

1: -0.O(kev) stop : B19Z:2047.8(kev)

Arq. Start :'11,u Mar 02 07: 52: 33 2017 6000

~

ROI Type: 2 7000 8000

3/1/2017 7:25:44AM Analysis Report for 01-Mar-17-10003 L310222AFRGS003SS GAMMA SPECTRUM ANAL YS/S Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procodure Operator Detector Name Geometry UveTime 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 Dane On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

01-Mar-17-10003

L310222AFRGS003SS

Sand 1.731E+03 grams

Default

2/23/2017 2:00:00PM

3/1/2017 7:15:34AM

130G_Sand

Administrator

P40818B

130G_Sand 600.0 seconds

601.0 seconds

0.17 %

3.00

120 -8192

120-8192

1.000 keV

1118/2017

3/1/2017

2133

1000.00 gram

Eu15s.Na22

1/30/2012 12:00:00PM PEAK ANAL YS/S REPORT Peak Analysis Performed on

3/1/2017 7:25:37AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of7

3/1/2017 7:25:44AM Page2of 7 Analysis Report for 01-Mar-17-10003 L310222AFRGS003SS Peak Energy ROI ROI No.

(keV) start end 238.56 949 -

960 2

295.21 1176-1186 3

351. 82 1402 - 1414 4

583.25 2327 - 2337 5

609.27 2429 -

2442 6

911. 37 3640 - 3649 7

1460.79 5833 - 5852 M = First peak in a multiplet region m,:: OUler peak in a multiplet region F,:: Fitted singlet Errors quoted at 1.000slgma Peah Centroid 954.33 1180.76 1407.03 2332.20 2436.26 3644.45 5842.99 No background subtract performed on this spectrum.

Met Peak Net Area Area Uncertaint)1 8.56E+Ol 14.73 3.24E+01 10.31 6.83E+Ol 9.93 3.90E+Ol 6.97 5.90E+Ol 8.90

l. 86E+Ol 5.79

l. 90E+02

15. 02 NUCLIDE /DE.NT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB Continuum FWHM Counts (keV) 5.24E+Ol

0. 89 3.06E+Ol 1.17 1.17E+Ol 0.80 4.0SE+OO 0.50 7.0SE+OO 0. 78 6.42E+OO o.~3 1.0lE+Ol

1. 62 IDENTIFIED NUCLIDES Nucllde Id Ene1vy Yield(%}

Activity Activity Name Confidence (keV)

(pCUgrams)

Uncertainty K-40

1. 00 1460.82 10.66 4.91E+OO 4.43E-01 Tl-208 0.99 583.19

85. 00 6.61E-02

1. 25E- 02

'l:)-212 0.99 115.18 0.60 238.63 43.60 1.52E-01 2.88E-02 300.09 3.30 Bi -214

1. 00 609.3.'.!

45.49 l.93E-01 3.13E-02 768. 36 4.89 806.18

1. 26 934.06

3. 11 1120.29 14. 92

Analysis Report for 01-Mar-17-10003 L310222AFRGS003SS Nuclide Id EnGffJY Name Confidence (keV)

Bi-214

1. 00 1155.21 1238.12 1280.98 1377.67 1385.31 1401. 52 1407. 99 1509.21 1661. 27 1729.59 1764.49 1847.43 2118. 51 Pb-214 0.99 241. 99 295.22 351.93 785.96 Ac-228 0.99 129.07 209.25 270.24 328.00 338.32 409.46 463. 00 794.95 911.20 964.77 968. 97 1588. 20

= Energy line found In the spectrum.

- = Manually added nuclide.

? = Manually edited nuclide.

@ = Energy llne not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nudide confidence Index threshold ;; 0.30 Errors quoted at 1.000sigma 3/1/2017 7:25:44AM Page3 of7 Yield(%)

Activity Activity (pCl/grams)

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 1.16 7.25 18.42 1.54E-01 5.06E-02 35.60

1. 92E-Ol 3.18E-02

1. 06 2.42 3.89 3.46 2.95 11. 27

1. 92

4. 40

4. 25 25.80

1. 42E-01

L 46E-02 4.99 15.80 3.22 INTERFERENCE CORRECTED REPORT

Analysis Report for 01-Mar-17-10003 L310222AFRGS003SS tiuclide Nuclide Name Id Confidence K-40

1. 000 Tl-208 0.999 X

Bi-211

0. 913 Pb-212

0. '.799 Bi-214

1. 000 Pb-214 0.999 Ac-228 0.999

? = nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis 3/1/2017 Wt mean Activity (pCi/grams) 4.91E+OO 6.61E-02

1. 52E-01 1.93E-01 1.81E-Ol

1. 42E-01

@ = nuclide contains energy llnes not used in Weighted Mean Activity Errors quoted at 1.000sigma 7:25:44AM Page4 of7 Wt mean Comment!

Activity Uncertainty 4.43E-Ol 1.25E-02 2.88E-02 3.13E-02 2.69E-02 4.46E-02

+

3/1/2017 7:25:44AM Analysis Report for 01-Mar-17-10003 L310222AFRGS003SS 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

3/1/2017 7:25:37AM

! 120

8192 Peak CPS {°h)

Peak Size (CPS}

Ur.certainty NUCLIDE MD/.J. REPORT Peal:.

Type Nuclide Library Used

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

ActJvtty NuclideMDA LineMDA Name (lceVJ (pCVgrams)

(pCl/grams}

(pCVgrams)

BE-7 477.60 10.44

-2.31E-01 3.76E-01 3.76E-01 K-40 1460.82 10.66 4.91E+OO 5.99E-01 5.99E-01 Co-60 1173.23 99.85 4.71E-02 4.64E-02 5.73E-02 1332.49 99.98

-2.19E-02 4.64E-02 Nb-94 702.65 99.81

-7.lBE-03 4. 21E-02 4.42E-02 871. 09 99.89

-6.56E-04 4.21E-02 Ag-108m 79.13 6.60 1.32E+OO 3.92E-02 1.55E+00 433.94 90.50

-l.39E-02 3.92E-02 614. 28 89.80 -4.00E-02 5.83E-02 722.94 90.80 5.09E-02 5.77E-02 Sb-125 176.31 6.84 4.0lE-03 J.. 30E-D1 5.22E-Ol 380.45 1.52 5.62E- 01 2.25E+OO 427.87 29.60

1. lSE-01

1. 30E- 01 4 63. 36 10.49 -1.18E-01

3. 80E-01 600.60 17.65 1.52E-01

2. 36E-01 606.71 4.98

1. 90E+OO 1.37E+OO 635.95 11.22 -1. 90E-01 2.57E-01 671. 44

1. 79

- 1.34E- 01 2.07E+OO Ba-133

79. 61

2. 65 1.96E+ OO 7.45E-02 3. 6SE+OO Page S of7 Tolerance Nuclide

3/1/2017 7:25:44AM Page 6 of7 Analysis Report for 01-Mar-17-10003 L310222AFRGS003SS Nuclide Energy Yield{%)

Activity Nuclide i".fDA L.lneMDA Name (keV)

(pCUgrams)

(pCVgrams)

Ba-133

81. 00 32.90

-2.06E-01 7.45E-02

2. 46E-01 276. 40 7.16 2.42E-01

5. 07E-01 302.85 18.34

6. llE-02 1. 94E-01 356. 01 62.05 1.30E-02

7. 45E-02 383.85 8.94 1.lOE-01

3. 83E-01 Cs-134 475.36

1. 48

-8.26E-01 5.12E-02

2. 61E+OO 563.25 8.34 2.27E-01 4.79E-01 569.33 15.37 -1. 88E-01

2. 58E-01 604.72 97.62

-2.94E-02

6. 37E-02 795.86 85.46

-1. 0SE-03 5.12E-02 801.95 8.69

-l.41E-01 4. 34E-01 1038.61 0.99

-3.95E+OO

4. 28E+OO 1167. 97

1. 79

1. 41E+OO 3. 40E+OO 1365.19 3.02

-7.26E-03

1. 27E+OO Cs-137 661. 66

85. 10 5.95E-04 4. 60E-02

4. 60E-02 Eu-152 121. 78 28.67

2. 66E-02 1.32E-Ol

1. 36E-Ol 244.70 7.61 3.60E-01

5. 27E-01 295.94 0.45 4.76E+OO

9. 97E+OO 344.28 26.60

-5.29E-02 1. 32E-01 367.79 0.86

-2.24E+OO 3.55E+OO 411.12

2. 24

1. 59E-02 1. 63E+OO 443.96 2.83 4.llE-01 1. 26E+00 488.68

0. 42

-9.0SE-01

9. 08E+OO 563.99 0.49 7.02E+OO 8.24E+OO 586.26 0.46

1. 24E+Ol

1. 20E+Ol 6'/8. 6.2 0.47 1.70E-Ol 8.27E+OO 688.67 0.86 2.39E+OO 4

38E+OO 719.35 0.28 8.35E-01

1. 42E+Ol 778.90 12.96

-8.46E-02 3.24E-01 810.45 0.32 1.31E-01 1. 18E+Ol 8 67. 3 7 4.26 6.88E-02 1. 04E+OO 919.33 0.43

-9.63E+OO

9. 36E+OO 964.08 14.65 2.94E-01 4.44E-01 1085.87 10.24 7.75E-02 5.41E-01 1089.74

1. 73

1. 49E+OO 3.34E+OO 1112. 07 13.69 4.14E-03 3.23E-01 1212.95

1. 43 2.92E-Ol

4. 61E+OO 1249.94 0.19 -l.03E+Ol

3. 09E+Ol 1299.14

1. 63 3.23E-Ol

3. 03E+OO 1408.01 21.07

-7.75E-02 2.57E-Ol 11,157.64 0.50

1. 11E+02 3.98E+Ol 1528.10 0.28

3. 04E+OO.

1.13E+Ol Eu-154 123. 07 40.40

-3.37E-03 9.43E-02 9.43E-02 247.93 6.89

-8.57E-02 4.70E-Ol 591.76 4.95 4.87E-01 7.47E-01 692. 42

1. 78 8.93E-Ol 2.23E+OO 723.30 20.06

1. 74E-01 2.61E-Ol 756.80 4.52 3.95E-01

8. 68E-01 873.18 12.08 2.llE-02 3.68E-01 996.29 10.48 1.16E-01 4.99E-01 1004.76 18.01 4.40E-02 2.52E-Ol 1274.43 34.80 4.09E-03 l.49E-Ol

3/1/2017 7;25:44AM Page? of7 Analysis Report for 01-Mar~17-10003 L310222AFRGS003SS Nuclide i:nerr,y Yield(%)

Activity Nuf:lide f'ADA LineMDA Name (keV)

(pCUgrams)

{pCUgrams)

(pCl/grams)

Eu-154 1596.48

1. 80 9.89E-01 9.43E-02 2

41E+OO Eu-155 45.30

1. 31

-7.29E+OO 2.21E-01

2. OlE+Ol 60.01 1.22

-7. 94E+OO 2.11E+01 86.55 30.70 2.lOE-02

2. 28E-01 105.31 21.10

-4.84E-02

2. 21E-01 Ra-226 186.21

3. 64 2. 19E-Ol

9. 64E-01

9. 64E-01 Pa-231 27.36 10.30 O.OOE+OO l.84E-01 1. 84E-Ol 283.69

1. 70 8.14E-01

2. 09E+OO 300.07

2. 47

-9..22E-02

1. 47E+OO 302.65 2. 20

1. 23E-01

1. 60E+OO 330.06

1. 40

-2.41E-01

2. 55E+OO U-235 143.76 10.96 7.llE-02 6.12E-02

3. 61E-01 163.33 5.08 1.92E-01 7

60E-01 185.71 57.20 9.84E-03 6.12E-02 202. 11

1. 08

-1.07E+OO

3. 35E+OO 205.31 5.01

-8.82E-Ol 7. 11E-01 Am-241 59.54 35.90

-6.83E-01 7.33E-Ol

7. 33E-01

+

= Nuclide identified during the nuclide identification

= Energy line found In the spectrum

= MDA value not calculated

= Half.-tife too short to be able to perform the decay correction 1

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

60 55 50 45 1000 2000 3000

~

ROI Type: 1 00000021 4000 channel

.CNF 5000 Lift Ti11e

&OD.ODO m R!ll Tille :601.010 Ste start:

1: -0.0(lev) stop : 8192:Z047,4(kev) c.cq. Start :Wl!d Nar 01 07:15:34 2017 6000 7000 8000

3/1/2017 3:12:46PM

.. ---'fylApex-Gamma Analysis Report for 01-Mar-17~10029 L310222AFRGS004SS DRIED GAMMA SPECTRUM ANAL YSJS Sample ldentificatio11 Sample Description Sample Type Unit Sample Point Sample Size Facillty Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time RealTime Dead Time Peak Locate Threshold Peak Locate Range {in chatmels}

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

01-Mar-17-10029

L310222AFRGS004SS DRIED

Sand

1.637E+03 grams

Default

2/27/2017 12:45:00PM

3/1/2017 3:02:36PM

130G_Sand

Administrator

P40818B

130G_Sand

600.0 seconds

601.1 seoonds

0.18 %

3.00

120-8192

120- 8192

1.000 keV

1/18/2017

3/1/2017

2158

1000.00 gram

Eu155-Na22

1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/1/2017 3:12:40PM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of7

3/1/2017 3:12:46PM Page2 of7 Analysis Report for 01-Mar-17-10029 L310222AFRGS004SS DRIED Peak Energy ROI ROI Peak Net Peak NetArea Continuum No.

{keV}

start end Centroid Area Uncertainty Counts 1

77.03 305 -

315 2

238.60 949 -

959 3

295.23 1175 - 1185 4

351.87 1401 - 1415 5

582.86 2323 - 2335 6

609.26 2429 - 2443 7

911. 03 3636 - 3652 8

968.63 38 68 - 3879 9

1460.59 5832 - 5853 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma 308.86 954.48 1180.84 1407.22 2330.66 2436.22 3643.07 3873.50 5842.19 No background subtract performed on thrs spectrum.

2.16E+Ol

13. 63 6.74E+01 8.57E+Ol 14.57 5.33E+Ol 5.40E+O l 10.36 2.20E+Ol

1. 06E+02 13.15 2.34E+Ol 3.29E+01 7.76

1. OlE+Ol 9.77E+01

10. 89 7.35E+OO 4.14E+01

7. 92 6.60E+OO 2.26E+Ol 6.42 7.44E+OO l.69E+02 14.10 8.08E+OO NlJCLIDE /DENT/FICA TION REPORT Nuclide Library Used

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

Activity Activity Name Confidence (keV)

(pCVgrams)

Uncertainty

-40 0.99 1460.82 10.66 4. 62E+OO 4.34E-01

~1-208 0.98 583.19 85.00 S. 90E-02

1. 43E-O:::!

Pb-212

1. 00 115.18

0. 60 238.63

43.60 l.61E-01 3.02E-02 300.09 3.30 Pb212-XR

1. 00 74.82 10.28 77.11

17.10 2.43E-Ol 1.55E-01 87.35 3.97 FWHM (keV)

0. 45

0. 83 0.85

0. 89 1.44 1.15 0.43

0. 81

1. 88

3/1/2017 3 :12;46PM Page 3 of7 Analysis Report for 01-Mar-17-10029 L310222AFRGS004SS DRIED Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCVgrams)

Uncertainty Pb212-XR 1.00 89.78

1. 46 Bi-214 1.00 609.32

45.49 3.37E-01 4.27E-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 1401.52

1. 33 1407.99 2.39 1509.21 2.13 1661.27

1. 05 1729.59 2.88 1764.49 15.30 1847.43 2.03 2118.51 1.16 l?b-214

1. 00 241.99 7.25 295.22 18.42 2.72E-01 5. 64E-02 351.93

35.60 3.14E-Ol 4.64E-02 785. 96 1.06 Pb214-XR

1. 00 74.82 5.80 77. 11

9.70 4.28E-01 2.74E-01 87.35 2.24 89.78 0.82 Ac-228 0.99 129. 07 2.42 209.25 3.89 270.24 3.46 328.00 2.95 338.32 11.27 40 9. 4 6

1. 92 463. 00 4.40 794.95

4. 25 911.20 25.80 3.34E-01 6.56E-02 964.77 4.99 968.97

15.80

3. llE-01 8.94E- 02 1588.20 3.22

= 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

3/1/2017 3:12:46PM Analysis Report for 01-Mar-17-10029 L310222AFRGS004SS DRIED INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Tl-208 X

Bi-211 Pb-212

?

Pb212-XR Bi-214 Pb-214

?

Pb214-XR Ac-228 Nuclide Id Confidence 0.991 0.983 0.902

1. 000

1. 000 0.995 7

= nuclide is part of an undetennined solution X

= nuclide rejected by the Interference analysis Wt mean AcUvlty (pCi/grams) 4.62E+OO 5.90E-02 1.61E-01 2.43E-01 3.37E-01 2.97E-Ol 4.28E-01 3.26E-01

@ = nuclide oontains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Activity Uncertainty 4.34E-01

1. 43E-02

3. 02E-02

1. 55E-01 4.27E-02 3.58E-02 2.74E-Ol 5.29E-02 Page4of7 Comments

+

3/1/2017 3: 12:46PM Analysis Report for 01-Mar-17-10029 L310222AFRGS004SS DRIED 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

3/1/2017 3:12:40PM

120

8192 Peak CPS {°A>)

Peak Size (CPS)

Uncertainty NUCLIDE MDA REPORT Peak Type Nuclide Library Used

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

Activity Nuclide l.fDA Line,'1DA Name (kev,J (pCVgrams)

(pCUgrams)

(pCl/grams)

BE-7 477.60 10.44

-2.83E-02 4.46E-01

4. 46E-Ol K-40 1460.82 10.66 4.62E+OO 5.86E-01 5. 86E-01 Co-60 1173.23 99.85 4.36E-02 4.46E-02

7. 03E-02 1332. 4 9 99.98 2.17E-02 4. 46E-02 Nb-94 702.65 99.81 -3.0lE-02 4.14E-02 4, 14E-02 871.09 99.89

4. 82E-03 4. 91E-02 Ag-108m 79.13 6.60

-3.SOE-01 4.58E-02 1. 54E+OO 433.94 90.50

-1.44E-02 4.SBE-02 614.28 89.80 -3.59E-02 7.52E-02 722.94 90.80 3.56E-02

5. 94E-02 Sb-125 1:6.31 6.84

-1.89E-Ol

1. 31E-01

5. 28E-01 380.45

1. 52 5.84E-01

2. 46E+OO 427. 8"7 29.60

-4.63E-02 1.31E-01 4 63. 36 10.49 2.60E-Ol 3. 81E-01 600.60 17.65 -7.00E-02 2.37E-01 606.71 4.98 3.25E+OO

1. 7 3E+OO 635.95 11.22 2.46E-01 4.21E-01 671. ~4

1. 79 7.76E-Ol

2. 98E+OO Ba-133 79.61 2.65 -2.21E-Ol 8.36E-02 3.62E+OO Pages of7 Tolerance Nuclide

3/1/2017 3:12:46PM Page 6 of7 Analysis Report for 01-Mar-17-10029 L310222AFRGS004SS DRIED Nuclide Energy Yield(%)

Activity NuclldeMDA LlneMDA Name (keV)

(pCUgrams)

(pCVgrams)

(pCVgram$)

Ba-133

81. 00 32.90

-1. lSE-01 8.36E-02

2. 38E-01 276.40 7.16

-5.89E-02

5. 63E-Ol 302.85 18.34

-1. 62E-01

2. OlE-01 356.01 62.05

1. BlE-02

8. 36E-02 383.85 8.94

-4.31E-01

3. 90E-01 Cs-134 475.36 1.48 1.09E+OO 5.96E-02

3. 07E+OO 563.25 8.34

-3.48E-Ol

5. 65E-01 569.33 15.37

1. 59E-01

3. 21E-01 604.72

97. 62

-2.18E-02

7. 84E-02 795.86 85.46 3.12E-02

5. 96E-02 801.95 8.69

-6.28E-02

5. lOE-01 1038.61

0. 99

-5.BSE+OO

5. 62E+OO 1167.97

1. 79 l.04E+OO 4.16E+OO 1365.19 3.02 2.27E-01

1. 58E+OO Cs-137 661. 66 85.10 l.76E-02 5, 96E-02

5. 96E-02 Eu-152 121. 78 28.67

-3.32E-02

1. 36E-01

1. 46E-Ol 244.70

7. 61 2.53E-01

5. 62E-01 295.94 0.45 1.0SE+Ol 1. 13E+Ol 344.28 26.60

-9.SlE-02

1. 36E-Ol 367. 79

0. 86

-1. 64E+OO

4. 45E+OO 411.12 2.24

-5.13E-01 1. 80E+OO 443.96 2.83

-9. 35E-02 1.55E+OO 488.68 0.42

l. 87E+OO

1. OlE+Ol 563.99 0.49

3. 41E+OO 9.95E+OO 586.26 0.46

-9.35E+OO l.41E+Ol 678.62 0.47

-1. 09E-Ol

9. 30E+OO 688.67 0.86 2.64E+OO 5.16E+DO 719.35 0.28 6.65E+OO l.70E+Ol 778.90 12.96 1.19E-Ol

3. OOE-01 810. 45 0.32

-1.39E+Ol 1.42E+Ol 8 67. 37 4.26

-7.20E-01

1. 20E+00 919.33 0.43 5.02E+OO

1. 24E+01 964.08 14.65

-1.22E-01 5.24E-01 1085.87 10.24 4.30E-01 S.95E-01 1089.74

1. 73 7.04E-01

3. 39E+OO 1112.07 13.69 -1. 33E-02 4.70E-01 1212.95 1.43 1.57E+OO 4.87E+OO 1249.94 0.19

-1.03E+Ol 3.19E+Ol 1299. 14

1. 63 7.12E-Ol 3.0BE+OO 1408. 01

21. 07

1. 25E-01 2.97E-01 1457.64 0.50 8.54E+Ol 3.89E+Ol

~.528.10 0.28

-7.23E+00 l.67E+Ol Eu-154 123.07 40.40 5.47E-02

1. OSE-01 l.OSE-01 247.93 6.89

-1.98E-01 5.42E-01 591.76 4.95 8.30E-02 9.97E-01 692. 42

1. 78 4.02E-01 2.60E+OO 723.30 20. 06 2.lOE-01 2.73E-01 756.80 4.52

-2.46E-01 8.43E-01 873.18 12.08 l.33E-02 3.79E-01 996.29 10.48

-4.72E-02 3.98E-01 1004.76 18.01 2. llE-01 2.81E-01 1274.43 34.80

-l.19E-01

1. 52E-01

3/1/2017 3:12:46PM Page7 of7 Analysis Report for 01-Mar-17-10029 L310222AFRGS004SS DRIED Nuclide Energy Yield(%)

Activity NuclldeMDA LineMDA Name (keV)

(pCUgrams)

(pCi/grams)

Eu-154 1596.48 1.80 7.83E-Ol l.OSE-01 3. 27E+OO Eu-155

45. 30

1. 31 4.00E+OO 2.47E-Ol

2. 35E+Ol 60.01

1. 22

-1. 05E+Ol 2.19E+Ol 86.55 30.70 8.74E-02

2. 47E-01 105.31 21.10

l. 62E-01 2. 67E-01 Ra-226 186.21

3. 64 3.20E-Ol 1.15E+OO 1.15E+OO Pa-231 27.36 10.30 O.OOE+OO

1. 95E-01 1. 95E-01 283.69

1. 70 7.53E-01 2. 30E+OO 300. 07 2.47

-1.68E+OO 1. 62E+OO 302.65 2.20

-1. llE+OO 1. 69E+OO 330.06 1.40 6.73E-02

2. 74E+OO U-235 143. 76 10.96 -1. 16E-01 7.26E-02

3. 93E-01 163.33 5.08 3.03E-01

7. 79E-01 185.71 57.20 6.72E-03

7. 26E-02 202. 11

1. 08

-9.21E-01 3. 69E+OO 205.31 5.01

-4.13E-01

7. 62E-01 Am-241 59.54 35.90

-3.06E-01 7.87E-01

7. 87E-Ol

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

> = MDA value not calculated

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

?

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

60 55 40 35

~

sn cl,

c: 3 30

~

1000

~

ROI Type: 1 2000 3000 00000021 4000 Channel 5000.

Live Time :600.000 sec Real Time :601.110 sec Start:

1: -0.Q(kev) stop : mz :2047.4(kev)

ACq, Start :wed Mar 0115:02:36 2017

= z 6000 7000 8000

£ **

~'>*

.*~-=~Apex-Gamma Analysis Report for 01-Ma;-17-10004 L310222AFRGS005SS 3/1/2017 7:25:51AM 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 lime Real Time DeadTime 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 Callbratlon Description Sample Number Fill Height Certificate Name Certificate Date

01-Mar-17-10004

L310222AFRGS005SS

Sand

1.637E+D3 ml

Oefault

2/23/2017 1:52:00PM

3/1/2017 7:15:42AM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

. 600.4 seconds

0,07%

3.00

120- 8192

1.000 keV 11/10/2016

3/1/2017

initial 11/16/16

2134

1000.00 gram

Eu155-Na22

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

3/1/2017 7:25:45AM Peak Analysis From Channel

120 Peak Analysis To Channel

8192 Page 1 of7

3/1/2017 7:25:51AM Page2 of7 Analysis Report for 01-Mar-17-10004 L310222AFRGS005SS Peak Energy ROI ROI Peak Net Peak Net Area Continuum No.

{keV) start end Centroid Area Unce,tainty Counts 1

77.12 305 -

313 2

238.58 945 -

959 3

295.17 1174 - 1186 4

351. 85 1401 - 1415 5

583.13 2324 - 2336 6

609.36 2429 - 2443 7

1460.90 5831 - 5852 M = First peak in a multiplet region m = Other peak rn a multiplet region F = Fitted singlet Errors quoted at 1.000slgma 309.00 953.91 1179.98 1406. 40 2330.65 2435.47 5841. 52 No background subtract performed on this spectrum.

1. 88E+O l 11.40 5.12E+Ol 1.16E+02 14.92 3.70E+Ol 4.55E+Ol 9.84 1.95E+01

7. llE+Ol 9.85

8. 95E+OO 4.25E+Ol 7.72

6. 50E+OO 4.90E+01 8.30 7.02E+OO 2.20E+02 15.16 2.59E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

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

Activity Activity Name Confidence (keV)

(pC//mL)

Uncertainty K-40 0.99 14 60.82 10.66 5.41E+OO 4.40E-01 Tl-208 1.00 583.19 85.00 6.85E-02 1.31E-02

'J-212

1. 00 115.18 0.60 238.63

43.60 l.93E-Ol 2.93E-02 300.09 3.30 Pb212-XR

1. 00 74.82 10.28 77.11

17.10

l. 21E-01 7.46E-02

87. 35 3.97 89.78

1. 46 Bi-214

1. 00 609. 32 45.49 1.52E-Ol 2.74E-02 FWHM (keV)

0. 51

a. 65 1.28 0.72 1.16

0. 52

1. 34

Analysis Report for 01-Mar-17-10004 L310222AFRGS005SS Nuclide Id Energy Name Confidence

{keV)

Bi-214

1. 00 768.36 806.18 934.06 1120.29 1155. 21 1238. 12 1280.98 1377.67 1385.31 1401.52 1407.99 1509.21 1661.27 1729.59 1764.49 1847.43 2118. 51 Pb-214 0. 99 2 41-.99 2 95.22 351.93 785.96 Pb214-XR 1.00 74.82 77.11 87.35 89.78

= 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 Nudide confidence index threshold= 0.30 Errors quoted at 1.000sigma 3/1/2017 7:25:51AM Page 3 of7 Yield{°;ft}

Activity Activity

_(pCUmL)

Uncertainty 4.89

1. 26

3. 11

14. 92

1. 63 5.83

1. 43

3. 99

0. 79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 7.25 18.42 2. 0SE-01 4.72E-02 35.60

1. 89E-01 3.03E-02

1. 06 5.80 9.70

2. 14E-01 l.32E-01 2.24 0.82 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean wtmean Comments Name Id Activity Activity Confidence (pCVmL)

Uncertainty K-40 0.999 5.41E+OO 4.40E-01 Tl-208

1. 000 6.85E-02

1. 31E-02

Analysis Report for 01-Mar-17-10004 X

?

? =

X =

L310222AFRGS005SS Nucl/cJe Name Nuclide Id Confidence Bi-211 Pb-212 Pb212-XR Bi-214 Pb-214 Pb214-XR 0.908

1. 000

1. 000 0.999 1.000 nuclide is part of an undetermined solution nuclide rejected by the interference analysis 3/1/2017 7:25:51AM Wt mean Wt mean Activity Activity (pCUmL)

Uncertainty

1. 93E-Ol 2.93E-02 1.21E-Ol 7.46E-02 1.52E-Ol 2.74E-02 l.94E-Ol 2.55E-02 2.14E-01 1.32E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma Page4of7 Comments

3/1/2017 7:25:51AM Analysis Report for 01*Mar*17-10004 L310222AFRGS005SS

+

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 UNIDENTrFtED PEAKS

3/1/2017 7:25:45AM

120

B192 Peak CPS(%)

Peak Size (CPS)

Uncertainty JVUCLIDE MDA REPORT Nuclide Library Used

C:\\Canbemi\\Apex\\Root\\Default\\Ubrary\\ZJON LIB*BNL.NLB Nuclide Energy Yield(%)

Activity NuclldeMDA Name (keV)

(pCUmL)

(pCVmL)

BE-7 477.60 10.44 8.97E-02 3.0SE-01 K-40 1460.82 10.66 5.41E+OO 3.25E-01 Co-60 1173.23 99.85 3.98E-02 3.80E-02 1332.49 99.98

-6.53E-03 Nb-94 702.65 99.81

-3.42E-03 3.45E-02 871. 09 99.89 1.?0E-02 Ag-108m 79.13 6.60 l.63E-02 3.57E-02 433.94 90.50

-1.18E-02 614. 2 8 89.80 -3.lSE-02 722.94 90.80 6.SOE-03 Sb-125 176.31 6.84

1. 21E-01 1.lOE-01 380.45

1. 52

-l.03E+OO 427.87 29.60 4.60E-02 4 63. 3 6 10.49 -3.48E-01 600.60 17.65 1.49E-01 606.71 4.98 -3.17E-Ol 635. 95 11.22 9.77E-02 671. 44

1. 79

1. OlE+OO Ba-133 79.61 2.65 9.07E-02 5.58E-02 Peak Type LineMDA (pCUmL) 3.0SE-01 3.25E-01

5. 91E-02

3. BOE-02 3.45E-02

3. 90E-02

8. 89E-01 3.57E-02

4. 95E-02 4.27E-02 4.28E-01 1.97E+OO

1. lOE-01 3.56E-01 2.25E-Ol

1. 25E+OO 3.86E-Ol 1.92E+OO 2.19E+OO Page 5 of7 Tolerance Nuclide

3/1/2017 7:25:51AM Page 6 of7 Analysis Report for 01-Mar-17-10004 L310222AFRGS005SS Nucllde Energy Yield(%)

Activity NuclldeMDA LlneMDA Name (keV)

(pCUmL)

(pCVmL)

(pCUmL)

Ba-133

81. 00 32.90 -5.lSE-02 S.58E-02

1. 52E-01 276. 40 7.16 1.78E-Ol

4. 81E-01 302. 85 18.34

-1. 67E-02

1. 48E-01 356.01

62. 05

1. 81E-02 5. 58E-02 383.85 8.94

-1. 44E-01 3. 31E-01 Cs-134 475.36

1. 48 2.20E-Ol

4. 98E-02 2. OOE+OO 563.25 8.34

-9.34E-02 3. 65E-01 569. 33 15.37 7.03E-02 2. 41£-01 604. 72 97.62

-9.99E-03

5. 42E-02 795.86 85.46 2.04E-02 4. 98E-02 801. 95 8.69 -1.90E-01

4. 37E-Ol 1038.61 0.99 2.61E-01 5.29E+OO 1167.*97

1. 79

1. 03E+OO 3. 04E+OO 1365.19 3.02 4.96E-01 1. 21E+00 Cs-137 661. 66

85. 10

1. 28E-02 3.99E-D2

3. 99E-02 Eu-152 121.78 28.67

-9.74E-03 1.03E-Ol 1. 03E-Ol 244. 70

7. 61

1. 27E-Ol

4. 53E-01 295.94 0.45 7.32E+OO

9. 02E+OO 344.28 26.60 3.09E-02 1.14E-01 367.79

0. 86 1. 54E+OO 3.47E+OO 411. 12 2.24 2.66E-01 1. 49E+OO 443.96 2.83

-3.42E-01

1. 09E+OO 488.68 0.42 2.88E-01 8. 13E+OO 563.99 0.49

-3.82E+OO 6.18E+OO 586.2 6 0.46

-6.29E+OO

1. 21E+Ol 678.62 0.47

-5.46E+OO

7. SlE+OO 688.67 0.86

9. 96E-Ol

4. 37E+OO 719.35 0.28

-4. 33E+OO 1. 26E+Ol 778.90 12.96 -5.23E-01 2. 44E-Ol 810.45 0.32 5.28E+OO l.12E+Ol 867.37 4.26 -1.27E+ OO 7

98E-01 919.33

0. 43

1. 43E+00

1. 29E+Ol 964. 08 14.65

1. 86E-Ol 4.06E-Ol 1085.87 10.24 8.15E-02 5.14E-01 1089.74

1. 73

-1.79E+OO

2. 71E+OO 1112. 07 13.69 -1.54E-Ol

3. 83E- 01 1212.95 1.43 -3.26E+OO

5. OlE+OO 1249.94 0.19 2.96E+OO

3. OOE+Ol 1299.14 1.63

1. lOE+OO 3.16E+OO 1408.01 21.07

-8.81E-02

1. 64E-01 1457.64 0.50 l.12E+02 3. 89E+01 1528.10 0.28 -5. 0SE+OO

1. OBE+Ol Eu-154 123.07 40. 40

-4.42E-02 7.0lE-02

7. OlE-02 247.93 6.89 -2.41E- 01

4. 25E-Ol 591. 76 4.95 4.45E-01 7. 39E-Ol 692.42

1. 78 3.99E-01

2. 07E+OO 723.30 20.06 9.35E-02 2. 02E-Ol 756.80 4.52

1. 87E- 01

9. 06E-01 873.18 12.08 -3.64E-02

3. 23E-01 996. 29 10.48 -6. 68E-02 4.54E-01 1004.76 18.01

-1. 04E-01

2. 66E-Ol 1274.43 34.80 -l.91E-02 l.37E-01

3/1/2017 7:25:51AM Page7 of7 Analysis Report for 01-Mar-17-10004 L310222AFRGS005SS Nuclide Energy Yield(%)

Activity NuclldeMDA i...lneMDA Name (keV)

(pCilmL)

(pCVmL)

Eu-154 1596.48

1. 80 6.70E-02 7.0lE-02

2. 43E+OO Eu-155 45.30

1. 31 2.07E+OO 1.55E-01

8. 34E+OO 60.01

1. 22 3.79E+OO

8. 40E+OO 86.55 30.70

-1.42E-02

1. SSE~Ol 105.31 21.10

-1. 09E-01 1. 73E-Ol Ra-226 186.21 3.64

' 4. SSE-01 8.37E-Ol

8. 37E-01 Pa-231 27.36 10.30 O. OOE+OO 7.33E-02

7. 33E-02 283.69

1. 70

-6.39E-01

1. 63E+OO 300.07 2.47

-2.87E-01 1. 23E+OO 302.65 2.20

-2.59E-02 1. 28E+OO 330.06

1. 40 3.SOE-01 2. 31E+OO U-235 143.76 10.96

-6. 48E-02 5.35E-02 2. 68E-01 163.33 5.08

-1. 83E-02

5. 53E-Ol 185.71 57.20

2. 57E-02

5. 35E-02 202.11

1. 08

-l. 84E+OO

2. 61E+00 205.31 5.01

-3.89E-01

5. 64E-01 Am-241 59.54 35.90 9.26E-02 2.87E-01

2. 87E-01

+

= Nuclide identified during the nudide 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

60 55 so 45 t "'...

15 10 5

0 1000 2000

~

ROI l)'pe: 1

~

t....

~

I

....I...

3000 00000021 4000 5000 Channel Live Tint :600.000 sec Real Ti111e :600.400 sec Start:

1: -0,0(kev) stop : 8192:2047.&(kev)

Acq, start :wed ~ar 01 07:15:42 2017 6000 7000 6000

3/1/2017 7:45:44AM

. ti\\

G

_.,#~:/Mpex-amrna Analysis Report for 01-Mar-17-10005 L310222AFRGS006SS GAMMA SPECTRUM ANAL YSJS 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 DeadTime Peak Locate Threshold Peak Locate Range On 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

01-Mar-17-10005

L310222AFRGS006SS

Sand

1. 762E+03 grams

Default

2/23/2017 1 :36:00PM

3/1/2017 7:35:35AM

130G_Sand

Administrator

P40818B

130G_Sand

600,0 seconds

600.9 seconds

0.14 %

3.00

120

8192

120- 8192

1.000 keV

1/18/2017

3/1/2017

2135

1000.00 gram

Eu 155-Na22

1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/1/2017 7:45:38AM Peak Analysis From Channel

120 Peak Analysis To Channel

8192 Page l of7

3/1/2017 7:45:44AM Page 2 of7 Analysis Report for 01-Mar-17-10005 L310222AFRGS006SS Peak Energy ROI ROI No.

(keV) start end 1

238.63 949 -

959 2

295.13 1175 - 1186 3

351. 85 1398 - 1413 4

609. 34 2430 - 2444 5

910.81 3638 -

364 7 6

1460.45 5833 -

5849 M = First peak in a multiplet region m = Other peak In a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peek Centroid 954.61 1180. 41 1407.14 2436.52 3642.19 5841. 62 No background subtract perfonned on this spectrum.

Net Peal:

Net Area Continuum Area Uncertainty Counts 8.90E+Ol 12. 94 3.30E+Ol 3.46E+Ol 9.91 2.54E+Ol 6.68E+Ol 10. 49

1. 42E+Ol 5.93E+Ol 8.37 3.75E+OO

l. 63E+01

5. 86 7.73E+OO l.02E+02

10. 73 4.25E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Ubrary\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield{°,')

Activity Activity Name Confidence (keV)

(pCUgrams)

Uncertainty K-40 0.97 1460.82 10.66 2.58E+OO 2.94E-Ol Pb-212 1.00 115.18 0.60 238.63 43.60 l.SSE-01 2.58E- 02 300.09 3.30 i-214

1. 00 609. 32 45.49 1.90E-Ol 2.92E-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. 71

0. 65 0.73

1. 19

0. 71 1.27

Analysis Report for 01-Mar-17-10005 L310222AFRGS006SS Nuclide Id Energy Name Confidence (keV)

Bi-214 1.00 1280.98 1377.67 1385.31 1401.52 1407.99 1509.21 1661. 27 1729.59 1764. 4 9 1847.43 2118.51 Pb-214 0.99 241. 99 295.22 351.93 785.96 Ac-228 0. 99 129. 07 209.25 270.24 328.00 338.32 409.46 463.00 794. 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 1.000slgma 3/1/2017 7:45:44AM Page3 of7 Yield(%)

Activity Activity (pCUgrams)

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

l. 62E-01 4. 81E-02 35.60

l. 84E-01 3. 25E-02 1.06 2.42 3.89 3.46 2.95 11.27

1. 92 4.40

4. 25 25.80 l.22E-01 4.43E-02 4.99 15.80 3.22 INTERFERENCE CORRECTED REPORT Nuclide Name Nuclide Id Co11fidence Wtmean Activity (pCUgrams)

Wt mean Comments Activity Uncerlainty

Analysis Report for 01-Mar-17-10005 L310222AFRGS006SS Nuclide Nuclide Name Id Confidence K-40 0.978 X

Bi-211 0.907 Pb-212

1. 000 Bi-214

1. 000 Pb-214 0.999 Ac-228 0.992

? = nuclide is part of an undetermina!d solution X

= nuclide rejected by the Interference analysis 3/1/2017 Wtmean Activity (pCi/grams) 2.58E+OO

1. SSE-01 l.90E-01 l.77E-Ol 1. 22E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma 7:45:44AM Page4of7 l-Wmean Comments Activity Uncertainty 2.94E-01 2.58E-02 2.92E-02 2.69E-02 4.43E-02

+

3/1/2017 7:45:44AM Analysis Report for 01-Mar-17-10005 L310222AFRGS006SS 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

3/1/2017 7:45:38AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty NUCLIDE MDA REPORT Peak Type Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL. NLB Hucllde Energy Y',e/d(%)

Aetivity Uucllde MOit LineMDA Name (keV)

(pCVgrams}

(pCUgrams)

(pCUgrams}

BE-7 477.60 10.44

1. 44E-01 4.llE-01

4. llE-01 K-40 1460.82 10.66 2.58E+OO 3.87E-Ol 3.87E- 01 Co-60 1173.23 99.85 3. 24E-02 3.93E-02

5. 63E-02 1332.49 99.98

-1.45E-02

3. 93E-02 Nb-94 702.65 99.81

-6.35E-02 3.65E-02 3.75E-02 871.09 99.89

1. 4 lE- 03 3.65E-02 Ag-108m 79.13 6. 60 1.16E+OO

3. 53E-02 1.45E+OO 433.94 90.50

-3.86E-02 3.SSE-02 614.28 89.80

-1. 72E-02 5.96E-02 722.94 90.80

- 2.llE- 02 3.53E-02 Sb-125 176.31 6.84 2.62E-01 l.12E-01 4.75E-Ol 380. 45

1. 52 5.17E-02 2.34E+OO 427.87 29.60 6.49E-02 l.12E-01 463.36 10.49

1. 32E-01

3. 35E-01 600.60 17.65

1. 49E-01 2.50E-01 606.71 4.98 1.16E+OO 1.31E+OO 635.95

11. 22 6.73E-03 3.28E-01 671.44

1. 79

- 9.64E- 01

1. 77E+OO Ba-133 79. 61 2.65

3. 78E-01

6. 30E-02 3.40E+ OO Pages of7 Tolerance Nucllde

3/1/2017 7:45:44AM Page6of 7 Analysis Report for 01-Mar-17-10005 L310222AFRGS006SS Nuclide Energy Yield(%)

Aetivlty Nuc/ideMDA LineMDA Name (keV)

(pCilgrams)

(pCVgrams)

(pCl!grams)

Ba-133 Bl. 00 32.90

-5.74E-02 6.30E-02

2. 3BE-01 276.40 7.16 2.41E-02

4. 63E-01 302. 85 18.34

-9.36E-03 1 - 86E-Ol 356.01 62.05

-3.GOE-02

6. 30E-02 383. 85 8.94

-2.91E-01

3. 57E-01 Cs-134 475.36

1. 48 3.lOE-01 4. 69E-02

2. 57E+OO 563.25 8.34 2.12E-Ol 4.22E-Ol 569.33 15.37 5.91E-02

2. 44E-01 604.72 97.62 5.48E-03 6.12E-02 795.86 85.46

-5.57E-03

4. 69E-02 801. 95 8.69 6.14E-02

3. 99E-01 1038.61 0.99

-1.20E+OO

4. 20E+OO 1167.97

1. 79

-2.14E+OO

2. 69E+OO 1365.19

3. 02

-1. 34E-01

1. 41E+OO Cs-137 661.66

85. 10

1. SBE-02

3. 67E-02

3. 67E-02 Eu-152 121. 78 28.67

-5.44E-02 1.lSE-01

1. 23E-01 244.70 7.61 6.75E-02 4. 61E-01 295.94 0.45 9.48E+OO

9. 56E+OO 344.28

26. 60

-l.57E-Ol 1.18E-D1 367.79 0.86

-2.21E+OO 3.28E+OO 411.12 2.24 6.99E-01

1. 46E+OO 443.96 2.83 -8.84E-Ol

1. llE+OO 488.68 0.42 1.88E+OO 7.84E+OO 563.99 0.49 7.04E-01

7. OOE+OO 586.26 0.46

1. 34E+Ol

l. llE+Ol 678.62 0.47 3.09E+OO

7. 94E+OO 688.67 0.86

-1.20E+OO 3.74E+OO 719.35 0.28

-3.47E+OO

8. OOE+OO 778.90 12.96 -4.26E-02 2.61E-01 810.45 0. 32

-4.16E+OO l. 12E+Ol 867.37 4.26 -3.37E- 02 8.85E-01 919.33 0.43 2.54E+00

8. 56E+OO 964.08 14.65 3.07E-Ol 3.76E-01 1085.87 10.24 -1. 61E-01 4.59E-01 1089.74

1. 73 6.66E-01 2.87E+OO 1112. 07 13. 69

-2.27E-01 2.93E-01 1212.95

1. 43 7.62E-01 3.55E+OO 1249.94 0.19

-3.51E+OO

2. 30E+Ol 1299.14

1. 63 4.BOE-01

2. 75E+OO 1408.01

21. 07 9.99E-02 2.0SE-01 1457.64 0.50 5.97E+Ol 2.87E+Ol 1528.10 0.28 4.98E+OO 1.35E+Ol Eu-154 123.07 40.40

- 4.13E-02 8.69E-02 8.69E-02 247.93 6.89 2.70E-01 4.?SE-01 591. 76 4.95 2.59E-Ol 6.38E-01 692.42

1. 78

1. 27E+00 2.14E+OO 723.30 20.06 7.lSE-02

1. 7 oE-01 756.80 4.52

-2.14E-01 6.50E-01 873.18 12.08 8.59E- 02 2.BOE-01 996.29 10.48 3. 4SE-02 3.97E-01

.004. 76 18.01

-1. 25E-02

2. 47E-01 1274.43 34.80

-6.56E-02

1. 21E-01

3/1/2017 7:45:44AM Page 7 of7 Analysis Report for 01-Mer-17-10005 L310222AFRGS006SS Nue/ido Energy Yield(%)

Activity Nucl/deMDA LJneMDA Name (keV)

(pCVgrams)

(pCUgrams)

Eu-154 1596.48

1. 80

-2.SlE+OO

8. 69E-02

1. 81E+OO Eu-155 45.30 1.31

-1. 80E+OO

2. 02E-01 1. 91E+01 60.01 1.22 6.00E-01 2.18E+Ol 86.55 30.70

-3.35E-02

2. 02E-01 105.31 21.10

-1.22E-01

2. 04E-01 Ra-226 186.21 3.64 1.75E-01 9.24E-01

9. 24E-01 Pa-231 27.36 10.30 0.00E+OO

1. SlE-01 1

81E-01 283.69

1. 70 2.64E-01 1. 73E+OO 300.07 2.47

-3.40E-02

1 - 34E+OO 302.65 2.20

-5.73E-01 1. 53E+OO 330.06

1. 40

-4.SOE-01

2. 37E+OO U-235 143.76

10. 96 3.31E-02 5.96E-02 3. 41E-01 163.33 5.08 3.57E-02 6

97E-01 185.71 57.20 2.14E-02

5. 96E-'-02 202.11

1. 08 6.70E-01 2

87E+OO 205.31 5.01 1.67E-01

6. 62E-01 Am-241 59.54 35.90

-1. 36E-01 7.53E-01

7. 53E-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

55 50 1000

~

ROI Type: 1 2000 3000 00000021 4000 channel

.CNF 5000 Live Titt :600.00D sec Rea.1 Till! :600.87D sec Start:

l: -0.0(kev}

Stop : 81!2:2047.4(kev}

Acq. start :wed 111.r 01 07:35:35 2017 6000 7000 8000

3/1/2017 7:45:49AM Analysis Report for 01-Mar-17-10006 L310222AFRGS007SS GAMMA SPECTRUM AI\\JAL YSIS 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 Callbra11on Description Sample Number Fill Height Certificate Name Certificate Date

01-Mar-17-10006

L310222AFRGS0073S

Sand

1.742E+03 grams

Default

2/23/2017 2:45:00PM

3/1/2017 7:35:41AM

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

3/1/2017

initial 11/16/16

2136

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAK ANALYSIS REPORT Page I of 7 Peak Analysis Performed on

3/1/2017 7:45:43AM Peak Analysis F om Channel

120 Peale Analysis To Channel

8192

3/1/2017 7:45:49AM Page2of7 Analysis Rei:,ort for 01-Mar-17-10006 L310222AFRGS007SS Peak Energy ROI ROI No.

(keV) start

~nd 1

77.26 306 -

313 2

238.61 947 -

960 3

295.30 1174 -

1187 4

352.01 1400 -

1413 5

609.54 2428 - 2441 6

1461. 05 5831 -

5852 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centroid 309.57 954.00 1180.49 1407.04 2436.20 5842.14 No background subtract performed on this spectrum.

NetPeak Net Area Continuum Ama Uncartainty Counts 2.40E+Ol 9.63 3.30E+Ol 6,21E+O l

13. 63 4.39E+Ol 3.99E+Ol

9. 77 2.0lE+Ol 7.72E+Ol ll.00

1. 58E+Ol 5.17E+Ol 8.94

1. 03E+Ol 1.54E+02 13.57 8.13E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

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

Actl,~lty Activity

/lame Confidence

{keV)

(pCUgrams)

Uncertainty K-40 0.99 1460.82 10.66 3.SSE+OO 3.49E-01 Pb-212

1. 00 115.18 0.60 238.63 43.60 9.?0E-02 2.27E-02 300.09 3.30

.u212-XR 0.99 74.82 10.28 77.11 17.10 1.45E-01 6.00E-02 87.35 3.97 89.78

1. 46 Bi-214 0.99 609.32 45.49

1. SlE-01 2.76E-02 768.36 4.89 806.18

1. 26 FWHM (keV) 0.76 0.73 0.79 0.40 0.66 1.36

Analysis Report for 01-Mar-17-10006 L310222AFRGS007SS Nuclide Id Energy Name Confidence (ke\\?

Bi-214

0. 99 934.06 1120.29 1155.21 1238.12 1280.98 1377.67 1385. 31 1401. 52 1407.99 1509.21 1661. 27 1729.59 1764.49 1847.43 2118.51 Pb-214 0.99 241.99 295.22 351.93 785.96 Pb214-XR 0.99 74.82 77.11 87.35 89. 78

" ; 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 3/1/2017 7:45:49AM Page: 3 of7 Yield(%)

Activity Activity (pCUgrams)

Uncertainty 3.11 14.92

1. 63 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13 1.05 2.88 15.30 2.03 1.16 7.25 18.42

1. 69E-01 4.35E-02 35.60 l.93E-01 3.16E-02

1. 06 5.80 9.70

2. 56E-01

1. 06E-01 2.24 0.82 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean wt mean Comments Name Id Activity Activity Confidence (pCUgrams)

Unce1talnty K-40 0.992 3.55E+OO 3.49E-Ol X

Bi-211 0.869 Pb-212 1.000 9.70E-02 2.27E-02

?

Pb212-XR 0.998 1.45E-01 6.00E-02

Analysis Report for 01-Mar-17-10006

?

L310222AFRGS007SS Nuclide Nuclide Name Id Confidence Bi-214

0. 997 Pb-214

0. 999 Pb214-XR 0.998

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis 3/1/2017 Vltmean Activity (pCUgrams)

1. SlE-01 1.SSE-01 2.56E-Ol

@ = nuclide contains energy lines not used In Weighted Mean Actlvlty Errors quoted at 1.000sigma 7:45:49AM Page4of7 Wt mean Comments Activity Uncertainty 2.76E-02 2.56E-02 1.06E-01

+

3/1/20"17 7:45:49AM Analysis Report for 01-Mar-17-10006 L310222AFRGS007SS PeakLocatePerfonnedon 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 lllgion F = Fitted singlet Errors quoted at 1.000slgma UNIDENTIFIED PEAKS

3/1/2017 7:45:43AM

120

8192 Peak CPS ("A)

Peak Size (CPS)

Uncertainty NUCLIDE MDA REPORT Peak Type Nuclide Library Used

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

Activity Nuclide MDA LfneMDA Name (keV}

(pCUgrams)

(pCUgrarns)

BE-7 477.60 10.44 -1. 34E-01 3.03E-01

3. 03E-01 K-40 1460. 82 10.66 3.SSE+OO 4.96E-Ol

4. 96E-Ol Co-60 1173. 23 99.85

2. 40E-03 3.57E-02

4. 38E-02 1332.49 99.98

1. 60E-02

3. 57E- 02 Nb-94 702.65

99. 81

-2.22E-0.2 3.33E-02 3. 33E-02 871. 0 9 99.89 -1. 62E-02

3. 76E- 02 Ag-108m 79.13 6.60 -2. 64E-01 2.92E-02

7. 74E-Ol 433.94 90.50 -l.28E-03

2. 92E-02 614. 28 89.80 -2.71E-02 5. 91E-02 722.94 90.80 2.26E-02

4. lOE- 02 Sb-125 176.31 6.84 4.93E- 02

9. 71E-02 3.49E-01 380. 45 1.52

- 1. 94E+OO

1. 65E+OO 427.87 29.60 3.32E-02

9. 71E-02 4 63. 36 10.49 3.7?E-02

3. 43E-Ol 600.60 17.65 6.14E-02 1.97E-01 606.71 4.98 7.13E-01

1. 24E+OO 635.95

11. 22

-3.06E-02

2. 77E-01 671.44

1. 79 -5. 25E-01

l. 55E+OO Ba-133

79. 61 2. 65

-3. 12E- 01

5. SlE-02

1. 91E+OO Page5of7 Tolerance Nucllde

3/1/2017 7:45:49AM Page6 of7 Analysis Report for 01-Mar-17-10006 L310222AFRGS007SS Nuclide Energy Yield(%)

Activity NuclideMDA LineMDA Name (keV)

(pCUgrams)

Ba-133

81. 00 32.90

-l.25E-01 5.81E-02

1. 23E-01 276.4.0 7.16 3.17E-Ol

3. 91E-01 302.85 18.34

~. 43E-02 1. 54E-01 356.01 62.05

-4.79E-03

5. 81E-02 383.85 8.94

-8.07E-02

3. llE-01 Cs-134 475.36

1. 48 9.14E-01 4. 37E-02

2. 21E+OO 563.25 8.34 1.05E-01

3. 25E-01 569.33 15.37

1. 26E-01 2.18E-01 604.72 97.62 8.30E-04

5. OSE-02 795.86 85.4 6 2.41E-02

4. 37E-02 801.95 8.69

-1.27E-01

3. 76E-01 1038.61 0.99

-2.45E-01 3.54E+OO 1167.97

1. 79

-6.26E-01

2. 29E+OO 1365.19 3.02 5.43E-01 l.21E+OO Cs-137 661. 66 85.10 2.83E-02

4. 20E-02

4. 20E-02 Eu-152 121. 78 28.67 6.37E-02 9.96E-02

9. 96E-02 244.70 7.61 2.06E-02

3. 96E-01 295.94 0.45 4.24E+OO

8. 07E+OO 344.28 26.60

-2.SOE-02 l. 07E-01 367.79

0. 86

1. 25E+OO 2.77E+OO 411.12 2.24 5.74E-Ol

1. 36E+OO 443.96 2.83

-7.31E-03 l.12E+D0 488.68 0.42

-2.99E+OO

5. 96E+OO 563.99 0.49 2.18E+OO

5. 81E+OO 586.26 0,46 4.70E+OO

1. 08E+D1 678.62 0.47 5.92E+OO 8.0lE+OO 688.67 0.86

1. 84E+OO 4.19E+OO 719.35 0.28

-7.41E-01

1. 08E+Ol 778.90 12.96

-2.D4E-01 2.lOE-01 810.45 0.32 8.59E+OO 1.15E+Ol 867.37 4.26 -2.82E-01 7.SOE-01 919.33 0.43

-4.77E+00 7.79E+OO 964.08 14.65 6.l?E-02

3. 60E-01 1085.87 10.24

-1. 46E-02 3.GSE-01 1089.74

1. 73 1.02E+OO 2.47E+OO 1112.07 13.69 1.93E-01

3. 60E-01 1212.95

1. 43 6.79E-01 3.66E+OO 1249.94 0.19

-1.71E+Ol 2.34E+Ol 12 99.14

1. 63 1.32E+OO

3. OSE+OO 1408.01 21.07 1.02E-01

1. 96E-01 1457.64 0.50 7.85E+Ol 3.14E+Ol 1528. 10 0.28

-4.74E+OO 1.13E+Ol Eu-154 123. 07 40.40

-3.39E-02 6.4"7E-02 6.47E-02 247.93 6.89

3. 31E-Ol 3.86E-01 591. 76 4.95 -2. 09E-01 4.94E-01 692.42

1. 78 4.76E-01 2.20E+OO 723.30 20.06

1. 37E-01 1.90E-01 756.80 4.52 4.37E-01 8. 86E-01 873.18 12.08 -1.06E-01 3.04E-Ol 996.29 10.48 7.24E-02 3.62E-01 1004. 76 18.01

-1.28E-01 2.31E-01 1274. 43 34.80

-8.35E-02 1.lOE-01

3/1/2017 7:45:49AM Page7 of7 Analysis Report for 01-Mar-17-10006 l310222AFRGS007SS Nuclide Energy Yield(%)

Activity Nuclide MDA LlneMDA Name (keV)

(pCVgrams)

(pCUgrams)

(pCUgn,ms)

Eu-154 1596.48

1. 80

-1. 43E+OO

6. 47E-02

1. 83E+OO Eu-155 45.30

1. 31 2.90E+OO

1. 40E-01

7. 43E+OO 60.01

1. 22

-2. 00E+OO 7

71E+OO 86. 55 30.70

1. SlE-01 1. 40E-01 105.31 21.10

-6.llE-02

1. 43E-01 Ra-226 186.21 3.64 3.96E-01 7.57E-01

7. 57E-01 Pa-231 27.36 10.30 O.OOE+OO 6.88E-02 6. 88E-02 283.69

1. 70

-1. 87E-Ol

1. 40E+OO 300.07 2.47 6.39E-02 1. 12E+OO 302. 65 2.20 6.13E-01 1. 28E+OO 330.06

1. 40 4.36E-01

2. 23E+OO U-235 143. 76 10. 96

-1. 92E-02

4. 84E-02 2. 38E-01 163. 33 5.08 3.95E-Ol

5. 04E-01 185.71 57.20 2.22E-02 4. 84E-02 202.11 1.08 5.lSE-01

2. 22E+OO 205.31 5.01

-4. 06E-01

4. 68E-01 Am-241 59.54 35.90 -1.67E-01 2.65E-01

2. 65E-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 perfonn the decay co1Tection

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

60 55 50 1000 2000 3000

~

ROI Type: 1 00000021 4000 Channel

.CNF 5000 Live Ti11e :600.0DO sec Rell Ti* :600.320 sec Start:

l: -0.D(kev}

stop : Bm: 2047. S(kev)

ACq, start :wed Nar 01 07:35:41 2017 6000 7000 8000

3/1/2017 8:02:12AM Analysis Report for 01=Mar*17*10008 L310222AFRGS008SS 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

01-Mar-17-10008

L310222AFRGS008SS

Sand

1.790E+03 grams

Default

2/23/2017 1 :30:00PM

3/1/2017 7:52:04AM

130G_Sand

Administrator

P11314

130G_Sand 600.0 seconds 600.4 seconds 0.06%

3.00 120-8192

120-8192

1.000 keV

11/10/2018

311/2017

initial 11/18/16

2138

1000.00 gram

Eu155-Na22

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

3/1/2017 8:02:o&AM Peak Analysis From Channel

120 Peak Analysis To Channel

8192 Pagel of6

3/1/2017 8:02:12AM Page 2 of6 Analysis Report for 01-Mar-17-10008 L310222AFRGS008SS Peak Energy ROI ROI No.

(keV) sttrrt end 1

238.62 948 -

960 2

295.25 1177 - 1186 3

352.01 1401 - 1414 4

609.51 2429 - 2441 5

1460.84 5830 - 5852 M = First peak In a muHJplet region m,., Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centroid 954.08 1180.28 1407.05 2436.08 5841. 30 No back.ground subtract performed on this spectrum.

N9tPealr NetArea Continuum Area Uncertainty Counts 6.90E+Ol

11. 70 2.SOE+Ol 2.lSE+Ol 8.43 2.lSE+Ol 6.17E+Ol 8.88 6.28E+OO 4.21E+Ol 7.42 4.89E+OO l.83E+02 13. 53 O.OOE+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

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

/luc/ide Id energy Yietdr,'J Activity Activity Name Confidence (keV)

(pCi/grams)

Uncertainty K-40

1. 00 1460.82 10.66 4.lOE+OO 3.52E-01 Pb-212

1. 00 115.18 0.60 238.63

43.60 1.0SE-01

1. 97E-02 300.09 3.30 Bi-214 0.99 609.32

45.49 l.20E-Ol

2. 23E-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 FWHM (keV)

0. 96

0. 63

0. 84 0.85 1.04

Analysis Report for OMAar-17-10008 L310222AFRGS008SS Nuclide Id Energy Name Confidence

{keV)

Bi-214

0. 99 1377.67 1385.31 1401.52 1407.99 1509.21 1661. 27 1729.59 1764.49 1847.43 2118.51 Pb-214 0.99 241.99 295.22 351.93 785.96

= Energy line found in the sp9Ctrurn..

= 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 1.000slgma 3/1/2017 8 :02:12AM Pagel of6 Yield(%)

Actlvt~,

Activity (pCUgrams)

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 8. 86E-02 3.54E-02 35.60 1. SOE-01 2.48E-02 1.06 INTERFERENCE CORRECTED REPORT Nuclide Name K-40 X

Bi-211 Pb-212 Bi-214 Pb-214 Nucllde Id Confidence 1.000 0.868 1.000 0.998 0.999

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis Wtmean Activity (pCUgrams) 4.lOE+OO 1.0SE-01

1. 20E-01 l.30E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma wt mean Comments Activity Uncettalnty 3.52E-01 1.97E-02 2.23E-02 2.03E-02

3/1/2017 8:02:12AM Anafysfs Report for 01-Mar-17-10008

+

L310222AFRGS008SS Peak Locate Performed en Peak Locate From Channel Peak Locate To Channel Peak No.

Energy {l::e\\f)

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

3/1/2017 8:02:06AM

120

8192 Peak CP$ rAiJ Peak Size (CPS)

Uncertainty Type NUCLIDE MDA REPORT Nuclide Library Used

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

Activity NuclldeMDA UnelifDA Name (keV)

(pCUgrams)

(pCVgrams}

(pCUgrams)

BE-7 477.60 10.44 2.23E-01 3.17E-01 3.17E-Ol K-40 14 60. 82 10.66 4.lOE+OO 6.45E-02 6.45E-02 Co-60 1173.23 99.85 -1. llE-03 3.67E-02

4. 76E-02 1332.49 99.98 9.48E-03

3. 67E-02 Nb-94 702.65 99.81

-8.87E-03 3.41E-02 3.41E-02 871. 09 99.89 2.49E-03 3.56E-02 Ag-108rn 79.13 6.60 4.SSE-01 2.90E-02 7.79E-01 433.94 90.50

-1.35E-02

2. 90E-02 614.28 89.80 -2.15E-02

4. 92E-02 722.94 90.BO 1.56E-02 4.23E-02 Sb-125 176.31 6.84 l.SlE-02 7.30E-02 3.47E-01 380.45 1.52 7.SOE-01 l.64E+OO 427.87 29.60 -1. 04E-01 7.30E-02 463. 36 10.49 2.45E-02 2.68E-01 600.60 17.65 9.25E-02

1. 69E-01 606.71

4. 98 1.36E+OO 1.03E+OO 635.95 11.22 -1.73E-01 2.56E-01 671.44

1. 79

-1.16E-01

1. 80E+OO Ba-133 79.61 2.65 9.93E-01 4.SOE-02 l.87E+OO Page4 of6 Tolerance Nuclide

3/1/2017 8:02:12AM Pages of 6 Analysis Report for 01-Mar-1 M 0008 L310222AFRGS008SS Nuclide Energy Yield(%)

Activity lluclide MDA LlneM'DA Name (keV)

(pCVgrams}

(pCVgrams)

(J:JCUgrams)

Ba-133

81. 00 32.90

-1.12E-01 4.80E-02

1. 22E-01 276.40 7.16

1. 44E-02

3. 30E-Ol 302.85 18.34 1.llE-01

i.. 52E-Ol 356.01 62.05

-1.94E-02

4. SOE-02 383.85 8.94

-8.21E-02 2. 69E-Ol Cs-134 475.36 1.48 7.17E-01 4.14E-02 2. 05E+OO 563.25 8.34 -1.l 7E-Ol 3. 74E-Ol 569.33 15.37

-1.53E-02

l.. 96E-Ol 604.72 97.62

-2.85E-02 4. 14E-02 795.86 85.46 2. 37E-02

4. 26E-02 801. 95 8.69

1. 40E-01

4. 21E-01 1038.61 0.99 1.47E-Ol 3. 85E+OO 1167.97

1. 79 4.24E-01

2. 3BE+00 1365.19 3.02 S.29E-Ol 1. 18E+OO Cs-137 661.66 85.10 l.17E-04 4.25E-02

4. 25E-02 Eu-152 121.78 28.67

- 2.14E-02 8.27E-02

8. 27E-02 244. 70 7.61 8.47E-03 3. 49E-01 295. 94 0.45

5. 43E+OO

7. 49E+OO 344.28 26.60 5.23E-03

9. 21E-02 367.79 0.86 3.91E-01 2. 90E+OO 411.12 2.24 8.97E-01

1. 33E+OO 443.96 2.83 -8.86E-01

7. 81E-Ol 488.68 0.42

.2.81E+OO

6. 94E+OO 563.99 0.49 4.0lE+OO

6. 58E+OO 586.26 0.46 l.17E+Ol

1. 03E+Ol 678.62 0.47 3.03E+OO

7. 20E+OO 688.67 0.86

-1.40E+OO 3. OSE+OO 719. 35 0.28 4.04E+OO 1. 21E+Ol 778.90 12.96 -3.81E-02 2. 39E-01 810.45 0.32 3.SSE+OO

9. 92E+OO 867.37 4.26 -4.52E- 01

6. 39E-Ol 9l9.33 0.43

-l.41E+OO

9. 60E+OO 964.08

14. 65 2.04E-01

3. 45E-01 1065.87 10.24 8. 00E-02

3. SSE-01 1089.74

1. 73 1.57E+OO 2.34E+OO 1112. 07 13.69 1.63E-Ol 3.42E-Ol 1212. 95 1.43 1.09E+OO

3. 5 6E+OO 1249.94

0. 19

-1.23E+Ol 2.49E+Ol 1299.14 1.63 -3.70E-01 2.43E+OO 1408.01 21.07 9.06E-03

1. 72E-01 1457.64 0.50 8. 83E+Ol 3.24E+Ol 1528.10 0.28

2. 64E+O.O 9.83E+OO Eu-154 123.07 40.40 -5.91E-03 5.BlE-02 5.81E-02 247.93 6. 89

-1.14E-02

3. 49E-Ol 591.76 4.95 -4.98E-Ol

4. 99E-01 692.42

1. 78.-1. 7:E+OO l. SSE+OO 723. 30 20.06 1.52E-01

i. 95E-Ol 756.80 4.52

1. 89E-01 8.29E-01 873.18 12.08 2.0lE-02

3. 12E-01 996.29 10.48

-3.41E-Ol 2.87E-01 1004. 76 18.01 -3.29E-02 l.76E-01 1274.43 34.80 7.45E-02 l.21E-Ol

3/1/2017 8 :02:12AM Page6of6 Analysls Report for 01-Mar-17-10008 L310222AFRGS008SS Nuclide Energy Y,eld(%)

ActMty llucllde MDA LJnoMDA Name (keV}

(pCVgramsJ (pCUgrams)

(pCVgrams)

Eu-154 1596.48

1. 80 7.lSE-01 5.BlE-02

1. 94E+00 Eu-155 45.30 1.31

-6.78:t+OO 1.26E-01

6. 03E+00 60.01 1.22 2.51E+OO

7. 38E+OO 86.55 30.70 6.SSE-02

.. 26E-Ol 105.31 21.10 9.27E-03 l

. 37E-Ol Ra-226 186.21 3.64

1. SBE-01 7.45E-01

7. 45E-Ol Pa-231 27.36 10.30 O.OOE+OO 6.70E-02

6. 70E-02 283.69

1. 70

-3.57E-01 l.. 27E+OO 300.07

2. 47

-2. 0BE-01 1.12E+00 302.65 2.20 7.02E-Ol 1.28E+OO 330.06

1. 40

-1. OSE-01 1

58E+OO U-235 143.76 10.96 1.24E-01 4.63E-02 2.13E-01 163.33 5.08 2.41E-01

4. 72E-01 185.71 57.20

1. 30E-04

4. 63E-02 202.11 1.08 4.7SE-Ol 2. 40E+OO 205.31 5.01

-5.12E-Ol

4. 39E-01 Am-241 59.54 35.90

1. lSE-01 2.54E-01 2, 54E-01

+

= Nuclide identified during ttie nuclide identification

= Energy line found In 1he spectrum

= MDA value not calculated

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

?

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

s, 50 45 40 35 25 0000002 T.

--- - --~

1000

~

ROI Type: 1 2000 3000 4000 channel 5000 Live Ti:R :600.000 stc Rea 1 Ti* :600.360 sec start:

1: -o.o~ev)

Stop : Sl.92: 2047. 8 (kev)

Aeq. start :wed Mar 01 07:52:04 2017 6000 7000 8000

""<~Apex-Gamma 3/1/2017 8:14:49AM Analysis Report for 01-Mar-17-10009 L310222AFRGS009SS 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 Csllbratlon Used Done On Efficiency Calibration Description Sample Number Fill Height Certificate Name Certificate Date

01-Mar-17-10009

L310222AFRGS009SS

Sand

1. 772E+o3 grams

Default

2/23/2017 10:30:00AM 3/1/2017 8:04:39AM 130G_Sand

Administrator

P40818B

130G_Sand 600.0 seconds 601.0 seconds

0.16%

3,00

120- 8192

. 1.000 keV

1/18/2017

3/1/2017

2139

1000.00 gram

Eu155-Na22

1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/1/2017 8:14:42AM Peak Analysis From Channel

120 Peak Analysis To Channel

8192 Page I of7 pw.,A-VltllOM{Ot-1 A.. l J (# f JJtr-J!::-

3/112017

S:14:49AM Page2 of7 Analysis Report for 01-Mar-17-10009 L310222AFRGS009SS Peak Energy ROI ROI No.

(keV) start end 1

238.52 949 -

959 2

338.44 1349 - 1357 3

351. 93 1401 - 1414 4

583.20 2324 - 2338 5

609.48 2428 - 2443 6

911. 08 3638 - 3650 7

968.88 3869 - 3880 8

1460.90 5833 - 5853 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centroid 954.17 1353.53 1407.44 2331. 99 2437.07 3643.27 3874.51 5843.43 No background subtract performed on this spectrum.

Net Peak NetArea Continuum Area Uncertainty Counts 9.46E+Ol

14. 88 5.34E+Ol 2.23E+Ol 7.34 1.47E+Ol 7.31E+01 1.0.21 1.09E+Ol 4.88E+01 9.01 l.13E+Ol 7.lOE+Ol 9.75 8.00E+OO 2.86E+Ol 5.66

1. 40E+OO

1. 31E+Ol 5.58 6.90E+OO

1. 10E+02 1.2.26 1.08E+Ol NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

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

Nuclide Id EneJJll'

\\'ield(%)

Activity Activity Name Confidence (keV)

(pCi/grams)

Uncerlalnty K-40 0.99 1460. 82

10.66 2.78E+OO 3.32E-Ol

~l-208

1. 00 583.19

85.00 8.0BE-02 1.57E-02 1-211 0.88 351.07 13.02

5. 49E-Ol 8.84E-02 Pb-21.2 0.99 115.18 0.60 238.63

43.60

1. 64E-Ol 2.90E-02 300.09 3.30 Bi-214 0.99 609.32 1.:

45.49 2.27E-01 3.40E-02 768.36 4.89 806.18 1.26 r-wHM (keV) 1.05

0. 68

o. 92

1. 47 0.90 0.32

1. 04 0.63

Analysis Report for 01-Mar-17-10009 L310222AFRGS009SS Nuclide Id Energy Name Confidence (keV)

Bi-214

0. 99 934.06 1120.29 1155.21 1238.12 1280.98 1377.67 1385.31 1401.52 1407.99 1509.21 1661.27 1729.59 1764.49 1847.43 2118.51 Pb-214 1.00 241. 99 295.22 351. 93 785.96 Ac-228 0.99 129.07 209.25 270.24 328. 00 338.32 409.46 463. 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 Nucllde confidence index threshold = 0.30 Errors quoted at 1.000slgma 3/1/2017 8:14:49AM Page 3 of7 Yield(%)

Activity Activity (pCUgrams)

Uncertainty 3.11 14.92

1. 63 5.83 1.43 3.99

0. 79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 7.25 18.42 35.60 2.0lE-01 3.23E-02

1. 06 2.42 3.89 3.46 2.95 11.27

1. 87E-01 6.36E-02

1. 92 4.40 4.25 25.80 2.13E-01 4.33E-02 4.99 15.80 1.67E-01 7.14E-02 3.22 INTERFERENCE CORRECTED REPORT

Analysis Report for 01-Mar-17-10009

?

L310222AFRGS009SS Nuclide Nuclide Name Id Confidence K-40 0. 999 Tl-208

1. 000 Bi-211 0. 889 Pb-212 0. 998 Bi-214 0.998 Pb-214

1. 000 Ac-228 0.999

?

= nuclide is part of an undetennined solution X

= nuclide rejected by the interference analysis 3/1/2017 Wt mean Activity (pCUgrams) 2.78E+OO 8.0SE-02 5.49E-01 l.64E-Ol 2.27E-Ol 2.0lE-01 1.98E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma 8:14;49AM Page 4 of7 Wtmean Comments Activity Uncertainty 3.32E-01 1.57E-02 8.84E-02 2.90E-02 3.40E-02 3.23E-02 3.20E-02

+

3/1/2017 8:14:49AM Analysis Report for 01-Mar-17-10009 L310222AFRGS009SS Peak Locate Performed on Peak Locate From ChaMel 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

3/1/2017 S:14:42AM

120

8192 Peak CPS(%)

Pealr Size (CPS)

Uncen'Slnty A/UCL/DE MDA REPORT Peak Type Nuclide Library Used

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

Activity Nucl/deMDA L/neMDA Name (keV)

(pCVgramsJ (pCVgrams)

(pCUgrams)

BE-7 4 77. 60 10. 44

-l.54E-01 3. 39E-01 3.39E-01 K-40 1460.82 10.66 2.78E+OO 6.16E-01 6. 16E- 01 Co-60 1173.23 99.85 6.82E-03 3.13E-02

4. 79E-02 1332.49 99.98

1. OOE-02

3. 13E-02 Nb-94 702.65 99.81

-4.03E-02 4.22E-02 4. 32E-02 871.09 99.89

l. 07E- 02

4. 22E-02 Ag-108rn 79.13 6.60 -4. llE-01 3.99E-02

1. 50E+OO 433.94 90.50

-3.68E-03

3. 99E-02 614. 28 89.80

-2.45E-02 6.90E-02 722.94 90.80

1. 71E-02 5.25E-02 Sb-125 176.31 6.84

-1.04E-01 1. 13E-01 4.92E-01 380.45

1. 52

-9.61E- 01 2.03E+OO 427.87 29.60 -3.0lE-02

l. 13E-01 463.36 10.49 2.23E-Ol

3. 66E-01 600.60 17.65

- 6.22E-02 2.20E-01 606.71 4.98 1.77E+OO

1. 39E+OO 635.95

11. 22

-4.38E- 02 3.33E-01 671. 44

1. 79 3.57E-Ol 2.26E+OO Ba-133 79. 61 2.65 -2. 06E+OO 6.46E- 02

3. 53E+OO Page 5 of7 Tolerance Nuclide

3/1/2017 8:14:49AM Page6of7 Analysis Report for 01-Mar-17-10009 L310222AFRGS009SS Nuclide Energy Yield(%}

Activity Nuclide A1DA LlneMDA Name (lceV)

(pCUgrams)

(pCl!grams)

Ba-133

81. 00 32.90

-1.89E-Ol 6.46E-02 2. SOE-01 276.40 7.16 7.llE-02 5

38E-01 302.85 18.34 6.91E-02 1. 91E-01 356.01

62. 05

-4.31E-02

6. 46E-02 383.85 8.94 5.60E-02

3. 60E-01 Cs-134 475.36

1. 48

-7.56E-Ol 4.66E-02

2. 30E+OO 563. 25 8.34

-5.59E-02

4. 68E-01 569.33 15.37 5.64E-02

2. 83E-Ol 604.72

97. 62

-3.88E-02

6. 22E-02 795.86 85.46

-1.58E-02 4. 66E-02 801. 95 8.69 7.27E-04

5. 06E-01 1038.61 0.99 5.36E-01 4

98E+OO 1167.97

1. 79

-2.08E+OO

2. 83E+OO 1365.19 3.02

-2.82E-01 1. 40E+OO Cs-137 661. 66 85.10

-1.00E-02 4.30E-02

4. 30E-02 Eu-152 121.78 28.67 6.46E-02

1. 25E-Ol 1. 35E-01 244.70 7.61 9.52E-02 5.30E-01 295.94 0.45 3.48E+OO 9.54E+OO 344.28 26.60

-2.27E-02

1. 25E-Ol 367.79 0.86 5.86E-01 3.71E+OO 411.12

2. 24 4.27E-01

1. 68E+OO 443.96 2.83

1. 44E-02 l.46E+OO 488.68 0.42 -5. 39E+OO

8. OSE+OO 563.99 0.49 -9.81E-Ol 8. 17E+OO 586.26 0.46

-6.15E+00

1. 34E+Ol 678.62 0.47

-l.61E+OO

7. 90E+OO 688.67 0.86

-l.09E+OO 3.84E+OO 719.35 0.28

-8.65E-01 1. 54E+Ol 778.90 12.96 -3.04E-01

2. 68E-01 810. 45 0.32 l.13E+Ol 1.48E+Ol 867.37 4.26

-1. 89E+OO

9. 36E-01 919.33 0.43

-1.90E+00 9.72E+OO 964.08

14. 65

-1.23E-Ol 4. 39E-01 1085.87 10.24

-1.0SE-01 4.14E-01 1089.74

1. 73 1.04E+OO

2. 63E+OO 1112.07 13.69 -8.36E-02 3. 26E-01 1212. 95 1.43

-9.09E-Ol 3.32E+OO 1249.94 0.19

-6.39E+OO 2.72E+Ol 1299.14

1. 63

-2.81E+OO 2.36E+OO 1408. 01 21.07

-4.97E-03

1. 69E-01 1457.64 0.50 5.87E+Ol 3.07E+Ol 1528.10 0.28 5.94E+OO l.45E+01 Eu-154 123.07 40.40 1.82E-02 9.63E-02

9. 63E-02 247.93 6.89 l.OSE-01

5. 36E-01 591. 76 4.95 -3.45E-01 8.00E-01 692.42

1. 78

1. 34E-01 2.27E+OO 723.30 20.06 -5.90E-02 2.31E-01 756.80 4.52 5.52E-01

1. OlE+OO 873.18 12.08 -1. 7 6E-02 3.41E-01 996.29 10.48 2.35E-Ol 3.82E-01 1004.76 18.01 -1. 87E-Ol

2. 15E-Ol 1274.43 34.80 -6.83E-02

1. 41E-01

3/1/2017 8:14:49AM Page7 of7 Analysis Report for 01-Mar-17-10009 L310222AFRGS009SS Nuclide Energy Y1o1dr-'J Activity NuclideMOA LineMDA Name (keV)

(pCVgrams)

Eu-154 1596.48

1. 80

-1. 41E-01 9.63E-02

2. 65E+OO Eu-155 45.30

1. 31

-5.88E-01 2.llE-01

2. 02E+01 60.01

1. 22

-7.53E-01

2. 28E+Ol 86.55 30.70 9.lBE-03

2. 31E-01 105.31 21.10

-1. 04E-Ol

2. llE-01 Ra-226 186.21 3.64 7.0SE-01 1.13E+OO 1.13E+OO Pa-231 27. 36 10.30 O.OOE+OO

1. BOE-01 1. SOE-01 283.69

1. 70

-1.64E+OO

1. 72E+OO 300.07 2.47

- 2. SOE+OO 1. 35E+OO 302.65 2.20 9.57E-01 1. 62E+OO 330.06

1. 40 l.17E-Ol

2. SBE+OO u-235 143.76 10.96 2.66E-02 7.23E-02

3. 67E-01 163. 33 5.08

-l.35E-01

6. 84E-01 185.71

57. 20 4.55E-02

7. 23E-02 202.11

1. 08

-l.30E+OO

2. 98E+OO 205.31 5.01

- 4.03E-Ol

6. 62E-01 Am-241 59.54 35.90

1. 4 ?E-02 7.95E-01

7. 95E-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

60 55 50 1000 2000 3000

~

ROI Type: 1 00000021 4000 channel

.. CNF 5000 Live Ti.Ill! :600.000 5ec Real Tilt :600.980 sec Start:

1:

-(J.O(kev)

StDp : ll.92:2047.4(keV)

Acq. start :wed Mar 01 Da:04:39 2017 6000 7000 8000

3/1/2017 8:14:56AM Analysls Report for 01-Mar-17-10010 L310222AFRGS01 OSS GAMMJt. SPECTRUM ANAL YS/S Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facillty 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 Callbratlon Description Sample Number Fill Height Certificate Name Certificate Date

01-Mar-17-10010

L310222Ar-RGS010SS

Sand

1.635E+03 grams

Default

2/23/2017 2:15:00PM

3/1/2017 8:04:46AM

130G_Sand

Administrator

P11314

~30G_Sand

600.0 seconds

600.3 seconds

0.06%

3.00

120 - 8192

120-8192

1.000keV

11/10/2016

3/1/2017

initial 11 /16/16

2140

1000.00 gram

Eu155-Na22

12/22/2U08 12:00:00PM PEAK ANAL YS/S REPORT Peak Analysis Performed on

3/1/2017 8:14:50AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of7

3/1/2017 8:14:56AM Page2of7 Analysis Report for 01*Marp17*10010 L310222AFRGS010SS Peak Energy ROI ROI No.

(keV) start end 1

238.71 949 -

959 2

295.13 1175 - 1184 3

351. 90 1400 - 1412 4

583.43 2327 - 2337 5

609.39 2429 - 2443 6

1120. 72 44 75 - 4486 7

1460.84 5831 - 5851 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted sing let Errors quoted at 1.000slgma Pet:.k Centroid 954. 41 1179.80 1406.62 2331. 85 2435.58 4480.28 5841.29 No background subtract performed on this spectrum.

NetPeak NetArea Continuum Area Uncertainty Counts 1.10E+02 13.10 2.59E+Ol 2.95E+Ol 7.59 1.25E+Ol 6.15E+Ol 8.86 6.50E+00 2.43E+Ol 6.34 6.70E+OO 5.19E+O l 8.83 9.13E+OO

1. 90E+Ol 5.16 3.00E+OO 1.54E+02 12.41 O.OOE+OO NUCLIDE /DENT/FICA TION REPORT Nucllde Library Used

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

Activity Activity Name Confidence (lteV)

(pCUgrams)

Uncertainty K-40

1. 00 1460.82 10.66 3.78E+OO 3.46E-Ol Tl-208

0. 99 583.19

85.00 3.92E-02

1. OSE-02

'b-212

0. 99 115.18

0. 60 238.63

43.60 l.83E-Ol 2.63E-02 300.09 3.30 Bi-214 0.99 609.32 45.49 1.61E-01 2.91E-02 768.36 4.89 806.18 1.26 934.06 3.11 1120. 29 *

14. 92 2.76E-01 7.57E-02 FWHM

{keV)

0. 94

0. 87

0. 66

0. 95 0.53 1.20

1. 65

Analysis Report for 01-Mar-17-10010 L310222AFRGS010SS Nuclide Id Energy Name Confidence (keV)

Bi-214 0.99 1155.21 1238.12 1280.98 1377.67 1385.31 1401. 52 1407.99 1509.21 1661. 27 1729.59 1764.49 1847.43 2118.51 Pb-214 0.99 241. 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 Errots quoted at 1.000slgma 3/1/2017 8:14:56AM Pege3 of7 Yield(%)

Activity Activity (pCUgrams)

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 1.16 7.25 18.42 1.33E-01 3.58E-02 35.60 1.64E-01 2.70E-02 1.06 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean wt mean Comments Name Id Acti~,;ty Activity Confidence (pCUgrams)

Uncerta.lnty K-40 1.000 3.78E+OO 3. 46E-01 Tl-208 0.990 3.92E-02

1. 05E-02 X

Bi-211 0.895 Pb-212 0.999

1. 83E-01 2. 63E-02 Bi-214 0.996 l.76E-01 2. 72E-02 Pb-214 0.999 1.53E-01 2.16E-02

Analysis Report for 01-Mar-17-10010 L310222AFRGS01 OSS

? = nuclide is part of an undetem,lned solution X

= nuclide rejected by the interference analysis

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1..000sigma 3/1/2017 8:14:56AM Page4of7

3/1/2017 8:14:56AM Analysis Report for 01-Mar-17-10010 L310222AFRGS010SS

+

Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Ener(Jy (keV)

All peaks were identified.

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

3/1/2017 8:14:50AM

120

8192 Peak CPS ("A)

Peak Size (CPS)

Uncertainty NUCLIDE MDA REPORT Peak Type Nuclide Library Used

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

Activity NuclldeMDA UnelADA Name (keV)

(pCilr,rams)

(pCl!grams)

(pCUgrams)

BE-7 477. 60

10. 44 l.26E-01 3.52E-01 3.52E-Ol K-40 1460.82

10. 66 3. 78E+OO 7. 0GE-02

7. 06E-02 Co-60 1173.23 99.85

-5.14E-02 4.76E-02 5.21E-02 1332.49 99.98 -1.49E-02

4. 76E-02 Nb-94 702.65 99.81

l. SOE-02 3. 26E-02 3.26E-02 871. 09 99.89

-1.64E-02 3.79E-02 Ag-108m 79.13 6.60 3.16E-01 3.63E-02 8.52E-01 433.94 90.50

-S.35E-03 3.63E-02 614.28

89. 80 l.02E-02 5.61E-02 722.94 90.80

-2.00E-02 4.SSE-02 Sb-125 176.31 6.84 4.09E-02 8.86E-02 3.88E-01 380. 45

1. 52

- 4.00E- 01

1. 85E+OO 427.87 29.60 -5.00E-02

8. 86E-D2 463. 36 10.49 4.35E-03 2.88E-01 600.60 17.65 2.88E-02 2.06E-01 606.71 4.98 -1. 09E-03

l. 26E+OO 635.95

11. 22

-1. BSE-01 2.SSE-01 671. 44 1.79

- 1.61E-Ol

2. 20E+OO Ba-133 79.61 2.65 1.09E+OO 5.53E- 02

2. 08E+OO PageS of7 Tolerance Nuclide

3/1/2017 8:14:56AM Page 6 of7 Analysis Report for 01-Mar-17-10010 L310222AFRGS010SS Nuclide Energy Yield(%)

Activity Nuc:lideMDA LineMDA Name (keV)

(pCUgrams)

(pCilgrams)

(pCUgrams)

Ba-133

81. 00 32.90

-1.16E-01 5.53E-02

1. 43E-01 276.40 7.16

2. 24E:...01

3. 78E-01 302.85 18.34 9.92E-02

1. 55E-Ol 356.01 62.05

-3.94E-02

5. 53E-02 383.85 8.94

-1. 29E-01 3.16E-Ol Cs-134 475.36

1. 48

-3.02E-01 4.43E-02

2. 38E+OO 563.25 8.34 3.lOE-01

4. 26E:...01 569.33 15.37 6.83E-02

2. OOE-01 604.72

97. 62

-1. 3 6E-02 5.13E-02 795.86 85.46

-9.03E-03

4. 43E-02 801. 95 8.69

..:1.77E-02 4.13E-01 1038.61 0.99 1.07E+OO

4. 61E+OO 1167. 97

1. 79 1.59E+OO 2. 97E+OO 1365.19 3.02 1.71E-01 1

36E+OO Cs-137 661. 66 85.10 2.60E-03 4.20E-02 4.20E-02 Eu-152 121. 78

28. 67

-1.66E-02 9.81E-02

9. 81E-02 244.70

7. 61 7.32E-02 3

91E-01 295.94 0.45

1. 51E+00 7.SSE+OO 344.28 26.60 4.13E-02

1. 15E-01 367.79 0.86 2.12E+00

3. 65E+OO 411.12 2.24 1.98E-01

1. 51E+OO 443.96 2.83

-1.27E+00

1. 03E+OO 488.68 0.42

-1.44E-02 6.18E+OO 563.99 0.49

-3.54E-01

6. 93E+OO 586.26 0.46 6.15E+OO 1. 06E+Dl 678.62 0.47

-4.68E+OO

7. 34E+OO 688.67 0.86 l.71E+OO

3. 86E+OO 719.35 0.28

-2.57E+OO

1. 45E+01 778.90 12.96 -1.lSE-01

2. 70E-01 810.45 0.32

-1.45E+OO l.25E+Ol 8 67. 37

4. 26 1.66E-01 9.13E-Ol 919.33 0.43

-6.74E+OO 9.20E+OO 964. 08 14.65 2.6BE-01

3. 95E-01 1085.87 10.24 2.59E-02 4. lSE-01 1089.74

1. 73 2.77E-01

2. 56E+OO 1112.07 13.69 9.89E-02 2. 96E-01 1212. 95

1. 43 8.02E-02 4. 31E+OO 1249.94 0.19 2.31E+Ol

3. 32E+01 1299.14

1. 63

-2.60E+OO

2. 30E+OO 1408.01

21. 07

-1.12E-02

1. 88E-01 1457.64 0.50 7.12E+Ol 3.26E+Ol 1528.10 0.28

-4.45E+OO 9.30E+OO Eu-154 123.07 40.40 -1. 40E-02 7. llE-02 7.llE-02 247.93 6.89 2.40E-01 3.75E-01 591. 76 4.95 4.44E-01 7.53E-Ol 692.42

1. 78

-8.14E-Ol

1. 87E+OO 723.30 20.06 4.38E-02 2.18E-Ol 756.80 4.52

-2.94E-Ol

7. 36E-01 873.18 12.08

-1.03E-01 3.24E-01 996.29 10.48 -4.20E-01 3.8SE-01 1004.76 18.01

1. 90E-01 2.53E-01 1274.43 34.80 -2. 28E-01

1. 23E-01

3/1/2017 8:14:56AM Page7of7 Analysis Report for 01-Mar-17-10010 L310222AFRGS01 OSS Nuclide Energy Yield(%)

Activity Nuc/ldeMDA LlneMDA Name (keV)

(pCVgrams)

(pCi/grams)

Eu-154 1596.48

1. 80

1. lOE+OO 7.llE-02

2. 44E+OO Eu-155 45. 30 1.31

-8.02E-01

1. 48E-01 7.12E+OO 60.01

1. 22

-8.31E-01

8. 34E+OO 86.55 30.70 3.98E-02

1. 57E-Ol 105.31 21.10

-6.57E-02 1. 48E-Ol Ra-226 186.21 3.64

1. 77E-01 8.02E-Ol

8. 02E-01 Pa-231 27. 36 10.30 O.OOE+OO 7.33E-02

7. 33E-02 283.69

1. 70

-4.lSE-01 1

41E+OO 300.07

2. 47

-l.18E+OO 1. 06E+00 302. 65 2.20 8.55E-01

1. 29E+OO 330.06 1.40

-1. 38E+OO 2.17E+OO U-235 143.76 10.96 2. 33E-02 5. 19E-02 2.49E-01 163.33 5.08

1. 32E-01

5. 34E-Ol 185. 71 57.20 2.83E-02 5.19E-02 202. 11

1. 08 6.41E-01

2. 47E+OO 205.31 5.01

-3. 66E-02

5. 56E-01 Am-241 59.54 35.90

-5.75E-02 2.90E-01

2. 90E-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 Cunie MDA at 95% confidence level

60 55 50

~

ROI Type: 1 1000 2000 3000 00000021 4000 channel

.CNF i

5000 Live Time :600.000 HC

Real Tia :&00,340 sec Start:

1: --0.0(kev)

Stop : 8192:ZD47.B(kev)

Aeq. snrt :Wtd Mar 01 08:04:46 2017 6000 7000 8000

3/1/2017 B:26:34AM Analysis Report for 01-Mar-17-10011 L310222AFRGS011SS GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size F'acillty Sample Taken On Acquisition Started Procedure Operator Detector Name Geomeby Live Time Real Time Deadllme 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 Cn Efficiency Calibration Description Sample Number Fm Height Certificate Name Certificate Date

01-Mar-17-10011

L310222AFRGS011 SS

Sand

1. 768E+03 grams

Default

2/23/2017 10:10:00AM

3/112017 8:16:24AM

130G_Sand

Administrator

P40818B

130G_Sand

600.0 seconds

600.9 seconds

0.15%

3.00

120- 8192

120-8192

1.000 keV

1/18/2017

3/1/2017

2141

1000.00 gram

Eu155-Na22

1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/1/2017 8:26:27AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of7

3/1/2017 8:26:34AM Page2of7 Analysis Report for 01-Mar-17-10011 L310222AFRGS011 SS Peak Energy ROI ROI Peak Net Peak NetArea Continuum No.

(keV) start end Centroid Area Uncertainty Counts 1

238.61 947 -

961 2

295.05 1173 - 1185 3

351. 82 1399 - 1412 4

582.89 2326 - 2335 5

609.23 2430 - 2441 6

1460.53 5833 - 5851 M = First peak in a multiplet region m== Other peak In a multiplet region F = Fitted singlet Errors quoted at 1.000sigma 954.54 1180.11 1407.01 2330.75 2436.07 5841.94 No background subtract performed on this spectrum.

6.20E+Ol 14. 51 4.90E+Ol 3.97E+Ol 9.53 1.93E+01 5.SOE+Ol 10.09

1. 70E+01

1. 75E+Ol 5.87 7.SOE+OO 3.97E+Ol 7.63 7.32E+00

1. 40E+02 12.13 2.23E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

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

Activity Activity Name Confidence (keV)

(pCUgrams)

Uncertainty K-40 0.98 1460.82

10.66 3.54E+OO 3.43E-01 Tl-208 0.98 583.19

85.00 2.90E-02 9.89E-03 Pb -212

1. 00 115. 18 0.60 238.63

43.60

1. 0SE- 01 2.66E- 02 300.09 3.30 Bi-214 0.99 609.32 45.49

1. 27E-01 2.56E-02 768.36 4.89 ao6.1a 1.26 934.06 3.11 1120.29 14.92 1155.21

1. 63 FWHM (keV)

0. 74 0.87 0.80 0.35 0.76

1. 61

Analysis Report for 01-Mar-17-10011 L310222AFRGS011 SS Nuclide Id

EnergJ, Name Confidence (keV)

Bi-214

o. 99 1238.12 1280.98 1377.67 1385.31 1401. 52 1407. 99 1509.21 1661.27 1729.59 1764.49 1847.43 21.18.51 Pb-214 0.99 241. 99 295.22 351.93 785.96

= Energy line found In the spectrum.

- = Manually added nuclide.

? = Manually edited nucllde.

@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000 keV Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma 3/1/2017 8:26:34AM Page 3 of7 Yield{%)

Activif]I Actiitity (pCilgrams)

Uncertainty 5.83

1. 43 3.99 0.79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03

1. 16 7.25 18.42 1.SSE-01 4.68E-02 35.60 1.SlE-01 3.03E-02

1. 06 INTERFERENCE CORRECTED REPORT Nuclide Nuclide Wt mean Wt mean Comments Name Id Activity Activity Confidence (pCUgrams)

Uncertainty K-40 0.986 3.~4E+OO 3.43E-01 Tl-2 08 0.986 2.90E-02 9.89E-03 X

Bi-211 0. 914 Pb-212

1. 000 1.08E-01 2.66E-02 Bi-214 0.999

1. 27E-Ol 2. 56E-02 Pb-214 0.997 1.61E-01 2.54E-02

Analysis Report for 01-Mar-17-10011 L310222AFRGS011SS 7 = i1Uclid~ i:; part of an undetermined solution X = nuclide rejected by the interference analysis

nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma 3/1/2017 8:26:34AM Page4 of7

+

3/1/2017 8:26:a4AM Analysis Report for 01-Mar-17-10011 L310222AFRGS011SS Peak Locate Perfonned on Peak Locate From Channel Peak Locate To Channel Peak No.

Ene,gy (ke\\J}

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

3/1/2017 8:26:27AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty NLICLIDE MDA REPORT Peak Type Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNU,ILB Nuclide Energy Yield{%)

Activity NuclideMDA Llnel.1DA Name

{ke\\?

(pCUgrams)

(pCUgrams}

(pCUgrams)

BE-7 477.60 10.44

-1. SSE-01 3.28E-01

3. 28E-01 K-40 1460.82 10.66 3.54E+OO

3. 04E-01

3. 04E-01 Co-60 1173.23 99.llS

-1.lOE-02 4. 91E-02

5. 49E-02 1332.49 99.98 1.60E-02

4. 91E-02 Nb-94 702.65 99.81 9.71E-03 3.SlE-02

3. 92E-02 871. 09 99.89

-4.67E-04

3. SlE-02 Ag-108m 79. 13 6.60 6.78E-01

4. 09E-02

1. 35E+OO 433.94 90.50

1. 97E-02

4. 09E-02 614.28 89.80

-5.49E-02 5. 89E-02 722.94 90.80

1. 83E-02

4. 94E-02 Sb-125 176.31 6.84 6.65E-02 1.13E-01

4. 69E-Ol 380.45 1.52 4.98E-01

2. 06E+OO 427.87

~9.60

-6.74E-02 l.13E-01 463.36 10.49

-2.36E-03

3. 53E-01 600.60 17.65

-5.17E-03 2. 04E-01 606.71 4.98 9.56E-01

l. 16E+OO 635.95

11. 22 8.77E-02 3.34E-01 671. 44

1. 79

7. SlE-01 2.26E+OO Ba-133 79.61 2.65 -9.67E-01 6.28E-02 3.17E+OO Pagc:5 of7 Tolerance Nuclide

3/1/2017 8:26:34AM Page 6 of7 Analysis Report for 01-Mar-17-10011 L31D222AFRGS011SS Nuclide Energy Yleld(Y.)

Activity Muf;lide MDA LineMDA Name (keV)

(pCVgrams)

(pCHgrams)

Ba-133

81. 00 32.90

-1. 66E-01 6.28E-02 2. 33E-Ol 276.40 7.16

-9.52E-02

4. SlE-01 302.85 18.34 1.lOE-01 1. 88E-Ol 356.01 62.05

-l.lOE-02 6. 28E-02 383.85 8.94 7.88E-02

3. 70E-01 Cs-134 475.36

1. 48

-1.22E-Ol 4. 02E-02

2. lSE+OO 563.25 8.34 2.52E-01

4. 46E-01 569.33 15.37 5.90E-02

2. 44E-01 604.72

97. 62

-1.53E-02

5. 43E-02 795.86 85.46

-3.48E-03 4. 02E-02 801.95 8.69 4.39E-02

4. 74E-01 1038.61 0.99 5.37E-02 4. 19E+OO 1167.97

1. 79

-4.54E+00 2. 68E+OO 1365.19 3.02 6.82E-01

1. 40E+OO Cs-137 661. 66 85.10

-1. 97E-02 3.78E-02

3. 78E-02 Eu-152 121. 78 28.67 4.23E-02

1. 22E-01 1. 22E-01 244.70

7. 61

-2.90E-01 4. 62E-01 295. 94 0.45 4.54E+OO

8. 94E+OO 344.28 26.60 7.25E-04 1. 33E-01 367. 7 9 0. 86

-3.83E+OO 3. 21E+OO 411.12 2.24

1. 95E-01

1. 48E+OO 443.96

2. 83

-4.82E-01 1.23E+OO 488.68 0.42 4.4BE-01

7. 67E+OO 563.99 0.49

-1.33E+OO

7. 27E+OO 586.26 0.46

1. OSE-01

1. 08E+Ol 678.62 0.47

-2.lOE+OO

6. 93E+OO 688.67 0.86 5.97E-Ol

4. 78E+OO 719.35 0.28 l.29E+Ol

1. 49E+Ol 778.90 12.96 -8.67E-02

2. 78E-01 810.45 0.32

-8.34E+OO l.22E+Ol 867. 37 4.26 2.0lE-01 9.38E-Ol 919.33 0.43

-5.16E+OO 8.53E+OO 964.08 14.65 2.02E-01 3.75E-01 1085.87 10.24

- 2.45E-01 3.32E-Ol 1089.74

1. 73 8.SSE-01 1.97E+OO 1112.07 13.69 -1.21E-01

2. 66E-01 1212. 95 1.43

-1.73E+OO 3.44E+OO 1249.94 0.19

-4.45E+OO 3.23E+01 1299.14

1. 63 6.65E-Ol

2. 96E+OO 1408.01

21. 07

-1. 34E-01

2. 0SE-01 1457.64 0.50 7. 83E+Ol

3. 26E+Ol 1528.10 0. 28 1.98E+OO 9.59E+OO Eu-154 123.07 40.40

- 7.06E-02 8.38E-02

8. 38E-02 247.93 6.89 3.16E-02 4.57E-01 591. 76 4.95

-6.87E-Ol 6.70E- 01 692. 42

1. 78

-8.97E-01 2.37E+OO 723.30 20.06

-8.0BE-02

2. 12E-01 756.80 4.52 4.07E-01 9.89E-Ol 873.18

12. 08

1. 39E-D1

2. 68E-01 996.29 10.48 2. 54E-Ol 5.18E-01 1004.76 18.01 -2.86E-01 2.54E-01 1274.43 34.80

- 7.82E- 02

1. 21E-Dl

3/1/2017 8:26:34AM Page 7 of7 Analysis Report for 01-Mar-17-10011 L310222AFRGS011 SS Nuclide Energy Yield{%)

Activity NuclldeMDA LineMDA Name (keV)

(pCUgrams)

(pCVgrams)

(pC/lgrams)

Eu-154 1596.48

1. 80

-7.39E-Ql 8.38E-02 1

80E+OO Eu-155 45.30

1. 31

-1. 03E+OO 2.00E-01

1. 90E+Ol 60.01

1. 22

-3.82E+OO

2. OOE+Ol 86.55 30.70

-1.32E-01

2. OOE-01 105.31 21.10 2.24E-02

2. 06E-01 Ra-226 186.21

3. 64

-1.14E-01 8.22E-01

8. 22E-01 Pa-231 27.36 10.30 O.OOE+OO 1.BlE- 01 1 *. SlE-01 283.69

1. 70

-1.39E+OO

1. 69E+OO 300. 0?

2.47 1.33E-02

1. 39E+OO 302.65 2.20 7.52E-01

1. 57E+OO 330.06

1. 40 1.06E+OO

2. 54E+OO U-235 143.76 10.96 5.75E-02 5.3SE-02

3. 17E-01 163.33 5.08

-1.12E-Ol

6. 31E-01 185.71 57.20 1.77E-03

5. 35E-02 202.11

1. 08

-l.78E+OO

2. 78E+OO 205.31 5.01

-4.25E-02

6. 34E-Ol Am-241 59.54 35.90

-1.SSE-02 7.12E-01

7. 12E-01

+

= Nuciide 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

+-'

C 8301 25 le 20 r

m...

15

~

10 5

1000

~

ROI Type: 1

~

,4...

~

2000 3000 00000021 4000 channel

.CNF 5000 Live Ti* :&00.000 sec Real Till!! :600,890 S!C:

Start:

1: -0.0(kev)

Stop : 8192:2047,4(kev)

Atq. start :wl!d '.~r 01 OB: lli:24 2017

~

6000 7000 8000

.,~~Apex-Gamma 3/1/2017 8:26:39AM Page I of7 Ana/~,s!s Report for 01-Mar-1 ?-10012 L310222AFRGS012SS GAMlvfA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Faclllty Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peal! Locate Range (in channels)

Peak Area Range (in channels)

Identification Energy Tolerance Energy Calibration Used Done On Efficiency calibration Used Done On Efficiency C811bration Description Sample Number Fill Height Certificate Name Certificate Date

01-Mar-17-10012

L310222AFRGS0125S

Sand

1. 790E+03 grams

DefauH

2/23/2017 9:50:00AM

3/1/2017 8:16:30AM

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

3/1/2017

initial 11/16/16

2142

1000.00 gram

Eu155-Na22

12/22/2008 12:00:00PM PEAi< ANAL YS/S REPORT Peak Analysis Perfonned on

3/1/2017 8:26:33AM Peak Analysis From Channel

120 Peak Analysis To Channel

8192 f t///

,...... t 7

)/

D p,rA v~u r>wn oiJ

,1., <I. *.11,1:- ~ -.........

3/1/2017 8:26:39AM Page2of7 Analysis Report for 01-Mar-17-10012 L310222AFRGS012SS Peak Energy ROI ROI

No.

(keV) start end 1

77.05 305 -

314 2

238.64 948 -

960 3

295.15 1175 - 1187 4

351.88 1399 - 1412 5

583.32 2324 - 2338 6

609.37 24:-:SO - 2443 7

911.12 3636 - 3649 8

1460.85 5833 - 5851 M = First peak In a multiplet region m = other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000slgma Peak Centroid 308.73 954.14 1179.88 1406.55 2331. 42 2435.53 3641. 93 5841.34 No background subtract performed on this spectrum.

NetPeak NetArea Continuum Area Uncertainty Counts 3.04E+Ol

13. 94 7.16E+Ol 1.83E+02 l 7. 43

4. 57E+Ol 7.46E+Ol 10.54

1. 34E+Ol

1. OOE+02 1.2.76 2.27E+Ol 6.45E+Ol 9.28 7.50E+OO 7.63E+Ol

10. 88 1.37E+Ol 3.81E+01

6. 62 l.94E+OO

1. 20E+02 11.56 4.34E+OO NUCLIDE IDENTIFICATION REPORT Nucllde Library Used

C:\\Cenberra\\Apex\\Root\\Default\\Llbrary\\ZION LIB-BNLNLB IDENTIFIED NUCLIDE$

Nuclide Id Energy Yield(%)

Activity Activity Name Confidence (keV)

(pCUgrams)

Uncertainty K-40

1. 00 1460.82

10.66 2.68E+OO 2.84E-Ol 1-208 0.99 583.19 85.00 9.SlE-02

1. 48E-02

_b-212

1. 00 115.18

0. 60 238.63 43.60

2. 79E-01

3. 47E-02 300.09 3.30 Pb212-XR

1. 00 74.82 10.28 77.11

17.10 1. 80E- 01 8.45E-02 87.35 3.97 89.78 1.46 FWHM (keV}

0.76

0. 94

0. 64 1.16

0. 90 1.16

0. 71

1. 04

3/1/2017 8:26:39AM Page 3 of7 Analysis Report for 01-Mar-17-10012 L310222AFRGS012SS Nuc//de Id Energy Yield(%)

ActlvitJ" Activity Name Confidence (keV)

(pCUgrams)

Uncert.alnty Bi-214 1.00 609.32

45.49 2.17E-Ol 3.36E-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 1401. 52 1.33 1407.99 2.39 1509.21 2.13 1661.27

1. 05 1729.59 2.88 1764.49 15.30 1847.43 2.03 2118.51 1.16 Pb-214

1. 00 241.99 7.25 295.22 18.42 3.07E-Ol 4.98E-02 351. 93 35.60 2.44E-01 3,67E-02 785.96

1. 06 Pb214-XR 1.00 74.82 5.80 77.11

9.70 3.17E-01 1.SOE-01 87.35 2.24

89. 78 0.82 Ac-228

1. 00 129.07 2.42 209.25 3.89 270.24 3.46 328.00 2.95 338.32

11. 27 409.46

1. 92 463. 00 4.40 794.95 4.25 911.20 25.80 2.53E-01

4. 54E-02 964.77 4.99 968.97 15.80 1588.20 3.22

" = 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

3/1/2017 8:26:39AM Analysis Report for 01-Mar-17-10012 L310222AFRGS012SS INTERFERENCE CORRECTED REPORT Nuclide Nuclide Name Id Confidence K-40

1. 000 Tl-208 0.997 X

Bi-211 0.899 Pb-212

1. 000

?

Pb212-XR

1. 000 Bi-214

1. 000 Pb-214

1. 000

?

Pb214-XR

1. 000 Ac-228

1. 000

? = nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis Wt mean Activity (pCl/grams) 2.68E+OO 9.SlE-02 2.79E-01

1. BOE-01 2.17E-Ol 2.66E-Ol 3.17E-Ol 2.53E-Ol

@ = nuclide contains energy lines not used ln Weighted Mean Activity Errors quoted at 1.000sigma Wt mean Activitjr Uncertainty 2.84E-01

1. 48E-02 3.47E-02 8.45E-D2 3.36E-02 2.96E-02

1. SOE-01 4.54E-02 Page4of7 Comments

+

3/1/2017 8:26:39AM Analysts Report for 01-Mar-17-10012 L310222AFRGS012SS 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

3/1/2017 8:26:33AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty NUCLIDE MDA REPORT Peak Type Nuclide Library Used

C:\\Can berra\\Apex,Root\\Default\\Llbrary\\ZI ON LIB-BNL. NLB Nuclide Energy Yield(%)

Activity Nuclide MOA LlneMDA Name

{keV)

(pCVgrams)

(pCVgmms)

(pCilgrams)

BE-7 477.60 10.44 -4.21E-03 3.56E-01

3. 56E-Ol K-40 1460.82 10.66 2.68E+OO 3.49E-Ol

3. 49E-01 Co-60 1173. 23 99. 85

-1.33E-02 4.SOE-02 4. 64E-02 1332.49 99.98 5.58E-04

4. 50E-02 Nb-94 702.65 99. 81

1. 70E-02 3.56E-02 4. 17E-02 871. 09 99. 89

-1. 68E- 02

3. 56E-02 Ag-108m 79.13 6.60

1. 63E-01 3.59E-02 9.52E-01 433.94 90.50 2.83E-02 3. 59E-02 614.28 89.80

- 2.48E-02 6.23E-02 722.94 90.80 1.llE-02 5. lSE-02 Sb-125 176.31 6.84

1. 98E-01 9.30E-02 4.35E-01 380.45

1. 52 5. 26E-02 1.85E+OO 427.87 29. 60

-8. 57E-02 9.30E-02 4 63. 36 10.49 2.52E-01 3. 45E-01 600.60 17.65 -7.04E-03 1.88E-01 606.71 4.98

-1.26E+OO

1. 35E+OO 635.95

11. 22 l.42E-01 3.37E-Ol 671. 44

1. 79

-5.SlE-01 1.93E+OO Ba-133

79. 61 2. 65

6. 54E-Ol

6. 39E-02 2. 33E+OO PageS of7 Tolerance Nuclide

311/2017 8:26:39AM Page 6of7 Analysis Report for 01-Mar-17-10012 L310222AFRGS012SS Nuclide Energy Yield(%)

Activity NuclldeMDA LineMDA Name (keV)

(pCUgra.ms)

(pCilgrams)

(pCl/grams)

Ba-133 81.00 32.90

-1. 36E-Ol 6.39E-02 1. 54E-01 276.40 7.16

1. 71E-01 4. 19E-01 302.85 18.34 5.66E-02 1. 78E-01 356. 01

62. 05

-2.29E-02

6. 39E-02 383.85 8.94

-1. 07E-01

3. llE-01 Cs-134 475.36

1. 48 9.32E-01 4. 75E-02

2. 42E+OO 563.25 8.34 8.57E-02

3. 59E-01 569.33 15.37 7.20E-02

2. 42E-01 604.72

97. 62

-6. 77E-02

5. 38E-02 795. 86 85.46

-2.75E-03

4. 75E-02 801. 95 8.69

1. 49E-01

4. 60E-01 1038.61

0. 99

-8. llE-01 2. 97E+OO 1167.97

1. 79 8.70E-01

2. 30E+OO 1365.19 3.02

-5.67E-02 1. 47E+00 Cs-137 661. 66 85.10 2.27E-02 4.25E-02 4. 25E-02 Eu-152 121.78 28.67

-1. 83E-02

1. OOE-01

1. OSE-01 244.70 7.61

1. 16E-01

4. 60E-Ol 295.94 0.45 2.32E+OO

9. 06E+OO 344.28

26. 60

-6.18E-02

1. OOE-01 367.79 0.86 8.12E-01

2. 94E+OO 411.12 2.24 7.96E-01

1. SOE+OO 443.96 2.83 4.19E-01

1. 05E+OO 488.68 0.42

-5.92E-Ol

6. 94E+OO 563.99 0.49

-1. 92E+OO

6. 07E+OO 586.26

0. 46

-5.53E+OO

1. 30E+01 678.62

0. 47 7.69E+OO

8. 09E+OO 688.67

0. 86 5.75E-Ol

4. 25E+00 719.35 0. 28 9.25E+00

1. 47E+Ol 779.90 12.96

-1. 92E-Ol 2. 23E-01 810.45 0.32 2.0SE-01 1.14E+Ol 867.37 4.26

-6. 67E-O*l 8.34E-01 919.33 0.43

-9.57E+OO

8. 91E+OO 964.08 14.65 6.06E-02

4. 14E-01 1085.87

10. 24

-1. 04E-Ol 3.82E-01 1089.74

1. 73

-3.37E-01 2.34E+OO 1112.07 13.69

-3.44E-02 3.17E-01 1212.95

1. 43

-5.75E-Ol 3.56E+OO 1249.!)4 0.19 l.53E+Ol 2.68E+Ol 1299. 14 1.63 1.02E+OO 2.72E+OO 1408. 01 21.07 8.83E-02

l. BlE-01 1457.64 0.50 5.73E+Ol

2. 73E+01 1528.10 0.28 4.40E+OO

1. 20E+Ol Eu-154 123.07 40.40 2.0SE-02 7. 67E-02

7. 67E-02 247.93 6.89

-8.65E-02

4. 04E-01 591. 76 4.95 3.81E-Ol 6.63E- 01 692.42

1. 78

-2.32E-01

1. 98E+00 723.30 20.06

-7.95E-02 2.30E-Ol 756.80 4.52

-7.57E-Ol

6. 94E-01 873. 18 12.08

-l.OSE-01

2. 96E-01 996.29 10.48

-2.BlE-02 3.SSE-01 1004.76 18.01 9.SOE-02 2.19E-01 1274.43 34.80

- 5. 93E-02 l.41E-01

3/1/2017 8 :26:39AM Page 7 of7 Analysis Report for 01-Mar-17-10012 L310222AFRGS012SS Nut/Ide Energy Yield(%)

Activity Nuc/ideMDA LineMDA Name (keV)

(pCUgrams)

(pCVgrams)

(pCl/grams)

Eu-154 1596.48

1. 80

-5.36E-01 7.67E-02 2. 09E+OO Eu-155 45.30

1. 31

1. 48E+OO

1. SSE-01 7. 95E+OO 60.01

1. 22 1.75E+OO

8. 72E+00 86.55 30.70 l.63E-02

l. 56E-01 105.31 21.10

-1.91E-02

1. 55E-01 Ra-226 186.21 3.64 7.24E-01 9.24E-Ol

9. 24E-01 Pa-231 27.36 10.30 O.OOE+OO

6. 70E-02

6. 70E-02 283.69

1. 70

-1.27E+OO

1. 46E+OO 300. 07 2.47 2.20E-01

1. 33E+00 302.65 2.20 9.39E-01

1.. 50E+OO 330.06

1. 40

-1. 79E-01

2. 38E+OO U-235 143.76 10.96

-7. 39E-02 5.94E-02

2. 69E-Ol 163.33 5.08

-l.SSE-01

5. 24E-01 185.71 57.20

4. 03E-02

5. 94E-02 202.11

1. 08

-2.37E+OO

2. 60E+OO 205.31

5. 0-1

1. llE-01

5. 63E-01 Am-241 59.54 35.90 1.09E-01 3.00E-01

3. OOE-01

= Nuclide Identified during the nuclfde 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 MCA at 95% confidence level

60 55 50 45 1000 2000 3000

~

ROI Type: 1 00000021 4000 channel 5000 Liw Ti11e :600.000 sec Real Tift :600.180 sec start:

1: -D.D(ktV)

Stop : 8192:2047.l(k~

Acq. Start :llfl!d Mar 01 08 : 16: 30 2017 0 !

6000 7000 8000

(:*.

G

-~:~~~f/\\pex-amma 3/1/2017 8:40:09AM Analysis Report for 01-Mar-17-10013 L310222AFRGS013SS 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 Rea/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 Callbratlon Description Semple Number Fill Height Certificate Name Certificate Date

01-Mar-17-10013

L310222AFRGS013SS

Sand 1.790E+03 grams

Default

2/23/2017 9:35:00AM

3/1/2017 8:30:00AM

130G_Sand

Administrator

P40818B

130G_S8nd

600.0 seconds

601.0 seconds

0.16 %

3.00

120-8192

120 - 8192

1.000 keV

1/18/2017

3/1/2017

2143

1000.00 gram

Eu155-Na22

1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/1/2017 B:40:03AM Peak Analysis From Channel

120 Peak Analysis To Channel

8192 Page I of7

.Ntt(J,J

_....Ai.,J,Dti.,~On**

,JI-'!' r, 1/_J,_j

. f, --

3/1/2017 8:40:09AM Page2of7 Analysis Reportfor 01-Mar-17-10013 L310222AFRGS013SS Peak Energy ROI ROI Peak Net Peak Net Area Continuum No.

(keV) start end Centroid Area Uncertainty Counts 1

77.13 305 -

312 2

238.61 948 -

959 3

295.15 1175 - 1186 4

352.02 1402 - 1413 5

609. 20 2428 - 2443 6

911.08 3637 - 3649 7

1460.65 5833 - 5851 M "' First peak in a multiplet region m "' Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000slgma 309.26 954.53 1180.49 1407.83 2435.97 3643.28 5842.43 No background subtract performed on this spectrum.

2.44E+Ol 9.22 2.96E+Ol 9.60E+Ol 13.91 3.90E+01 4.llE+Ol 9.99 2.29E+Ol 5.89E+01 10.58 2.llE+Ol 7.20E+01 9.49 5.98E+OO 3.40E+01 7.09 5.95E+OO 9.56E+O l 10.20 2.43E+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)

(pCUgrams)

Uncertainty K-40 0.99 1460. 82 10.66 2.39E+OO 2.75E-01 Pb-212 1.00 115. 18

0. 60 238.63

43.60 1. 64E-01 2.73E-02 300.09 3. 30

.l?b212-XR

1. 00 74.82 10.28

77. 11 17.10

2. SOE-01 9.78E-02 87.35 3.97 89.78

1. 46 Bi-214

0. 99 609.32 45.49 2.27E-01 3.29E-02 768.36 4.89 FM/HM (keV) 0.35 1.05 1.03 0.76

1. 32

0. 61 1.25

Analysis Report for 01-Mar-17-10013 L310222AFRGS013SS Nuclide Id Energy Name Confidence (keV)

Bi-214 0.99 806.18 934.06 1120.29 11'.55.21 1238.12 1280.98 13'?7.67 1385.31 1401. 52 1407. 99 1509.21 1661.27 1729.59 1764.49 1847.43 2118.51 Pb-214 0.99 241.99 295.22 351.93 785.96

")b214-XR

1. 00 74.82 77.11 87.35 89.78 Ac-228 0.99 129.07 209.25 270.24 328.00 338.32 409.46 463.00 794.95 911. 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 3/1/2017 8:40:09AM Page3 of7 Yield(%)

Activity Activity (pCl/grams)

Uncertainty 1.26 3.11 14.92

1. 63 5.83

1. 43 3.99

o. 7 9 1.33 2.39 2. 13

1. 05 2.88 15.30 2.03 1.16 7.25 18.42 1.8 9E-01

4. 83E-02 35.60

1. 6DE-01 3.lSE-02

1. 06 5.80 9.70 4.41E-01

1. 74E-01 2.24 0.82 2.42 3.89 3.46 2.95 11.27

1. 92

,4. 40 4.25 25.80

2. 52E-01 5.35E-02 4.99 15.80 3.22

3/1/2017 8:40:09AM Analysis Report for 01-Mar-17-10013 L310222AFRGS013SS INTERFERENCE CORRECTED REPORT X

?

Nuclide Name K-40 Bi-211 Pb-212 Pb212-XR Bi-214 Pb-214 Pb214-XR Ac-228 Nuclide Id Confidence 0.995 0.864

1. 000

1. 000 0.999 0.999 1.000 0.999

?

= nuclide is part of an undetermined solution X = nuclide rejected by the interference analysis Wt mean Activity (pCi/grams) 2. 39E+OO l.64E-01 2.SOE-01 2.27E-01 1.69E-Ol 4.41E-01 2.52E-01

@ = nuclide contains energy lines not used In Weighted Mean Activity Errors quoted at 1.000sigma Wtmean At:tivity Uncerlalnty 2.75E-01 2.73E-02 9.78E-02 3.29E-02 2.64E-02

1. 74E-01 5.35E-02 Page4of7 Comments

+

3/1/2017 8:40:09AM Analysis Report for 01-Mar-17-10013 L310222AFRGS013SS Peak Locate Performed on Peak Locate F.rom Channel Peak Locate To Channel Peak No.

Energy (l;e VJ All peaks were identified.

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000$1gma UNIDENTIFIED PEAKS

3/1/2017 8:40:03AM

120

8192 Pcalr CPS (%)

Peak Size (CPS) l lncerlainty NUCLIDE MDA REPORT Peale Type Nuclide Library Used

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

Activity NuclideMDA LlneMDA Name (keV}

(pCVgrams)

(pCUgrams)

(pCVgrams)

BE-7

4. 77. 60 10.44 -9.38E-02 3.96E-Ol

3. 96E-01 K-40 1460.82 10.66

2. 39E+OO 3.lSE-01 3.lSE-01 Co-60 1173.23 99.85

-6.19E-03 4.49E-02

4. 89E-02 1332.49 99.98

-1.95E-02 4.4.9E-02 Nb-94 702.65 99.81 -l. 86E-03 3.78E-02 3. 78E-02 871. 09 99.89

1. 35E-02

4. 87E-02 Ag-108m 79.13 6.60

-3.12E-Ol 4.14E-02

1. 30E+OO 433.94 90.50

-3.04.E-03

4. 14E-02 614.28 89.80 -2.48E-02

5. 92E-02 722.94 90.80 8.03E-03

4. 79E-02 Sb-125 176.31 6.84 7.llE-02 1.18E-01 5.0lE-01 380.45

1. 52

-1.16E-01 2.18E+OO 427.87 29.60 1.77E-02 l.18E-01 4 63. 36 10.49

1. 84E-01 4.05E-01 600.60 17.65 3.07E-02

1. 88E-01 606.71 4.98 2.37E+OO 1.38E+00 635.95 11.22

-7.68E-02 3.00E-01 671. 44

1. 79

-2.30E+OO 2.14E+OO Ba-133 79. 61 2.65

-1.25E+OO 7. 25E-02 3.12E+OO Page 5 of1 Tolerance Nuclide

3/1/2017 8:40:0BAM Page6of7 Analysis Report for 01-Mar-17-10013 L310222AFRGS013SS Nuclide Energy Yield(%)

Activity NuclideMDA Llne fJDA Name (keV)

(pCVgrams)

(pCl/grams)

(PCl/grams)

Ba-133

81. 00 32.90 S.56E-03 7.2SE-02

2. 21E-Ol 276.40 7.16 -9.83E-02

4. 27E-01 302.85 18.34 6.39E-02

1. SOE-01 356. 01 62.05

-3.26E-02 7. 25E-02 383.85 8.94

-2.62E-Ol

3. 21E-01 Cs-134 475.36

1. 48

1. 36E+OO 4.llE-02

2. 75E+OO 563.25 8.34

-8.82E-02

4. 85E-01 569.33 15.37

-7.19E-02

2. 41E-Ol 604. 72 97.62

-2.26E-02

6. 20E-02 795.86 85.46

-6.78E-03

4. llE-02 801. 95 8.69 1.36E-01 4. 56E-01 1038.61 0.99 2.21E+OO

4. 68E+OO 1167.97

1. 79

-1.96E+OO 2. 48E+OO 1365.19 3.02 -5.00E-01

1. 39E+OO Cs-137 661. 66 85.10 9.92E-03 4.90E-02 4. 90E-02 Eu-152 121. 78 2~. 67 3.SlE-02 l.12E-01

1. 30E-01 244. 70

7. 61 2.65E-01

5. OOE-01 295.94 0.45

-3.60E+OO

9. 27E+OO 344.28 26.60

-6.89E-02 1. 12E-Ol 367.79

0. 86

-8.99E-01

3. 43E+OO 411.12 2.24 3.66E-Ol 1. 63E+OO 443. 96 2.83 3.68E-01 1. 27E+OO 488.68 0.42

-7.36E+OO

7. 86E+OO 563. 99 0.49 7.19E+OO

8. 67E+OO 586.26 0.46 1.56E+Ol 1. 28E+Ol 678.62 0.47 5.13E+OO

8. 83E+OO 688.67 0.86 9.58E-01

3. 92E+OO 719.35 0.28

-S.65E+OO

1. 24E+Ol 778.90 12.96 -4.16E-02 2

91E-Ol 810.45

0. 32 1.62E+OO

1. 33E+Ol 867.37 4.26 -1. 41E+OO

1. OSE+OO 919.33 0.43

-1.23E+OO

8. 74E+OO 964.08 14.65 9.99E-02 3.30E-01 1085.87

10. 24 -l.02E-01 3.28E-01 1089.74

1. 73

-9.37E-02 2.25E+OO 1112.07 13.69 -7.49E-02

3. 33E-01 1212.95 1.43

-2.04E+OO 3.18E+OO 1249.94 0.19 1.78E+Ol

3. 06E+Ol 1299.14

1. 63

-1. 04E+OO 3.03E+OO 1408.01

21. 07 6.15E-02

1. 67E-Ol 1457.64 0.50 5.lSE+Ol

2. 70E+Ol 1528.10 0.28 5.88E+OO

1. 43E+Ol Eu-154 123.07 40.40 1.04E-02 9.21E-02 9.21E-02 247.93 6.89 -3.SlE-01 4.27E-01 591. 76 4.95

- 3.0BE- 01 7.37E- 01 692. 42

1. 78

-2.21E-01 2.06E+OO 723. 30 20.06 9.45E-02 2.21E-Ol 756.80 4.52 9.26E-02 9.59E-01 873.18 12.08

1. 04E-01 3.96E-01 996.29 10.4.8 2.63E-02 4.04E- 01 1004.76

18. 01

-5.5 6E- 02

2. 21E-Ol 1274.43 34.80

- 3.68E- 02 l.44E- 01

3/1/2017 8:40:09AM Page 7 of7 Analysis Report for 01-Mar-17-10013 L310222AFRGS013SS Nuclide Energy Yield(%)

.'~ctlvlty UuclideMDA LineMDA Name (keV)

(pCUgrams)

Eu-154 1596.48 1.80

-1.23E+OO 9.21E-02 2. 33E+OO Eu-155 45.30

1. 31 1.09E+Ol 2.18E-Ol 2. 06E+01 60.01

1. 22

1. 07E+Ol 2. 23E+Ol 86.55 30.70

1. OBE-01 2.18E-01 105.31 21.10

-2.87E-02 2. 25E-01 Ra-226 186.21 3.64 8.94E-01 9.98E-01 9. 98E-01 Pa-231 27.36 10.30 O.OOE+OO

1. 78E-01

1. 78E-01 283.69

1. 70

-5.30E-01

1. 82E+OO 300.07 2.47 2.25E-01

1. 32E+OO 302.65 2.20 7.32E-01 1. 50E+OO 330.06

1. 40

-1.90E+OO

2. 28E+OO U-235 143.76 10.96

-4.76E-02 6.32E-02

3. 45E-Ol 163. 33 5.08

-5.17E-02

7. 07E-Ol 185.71 57.20 4.84E-02

6. 32E-02 202.11

1. 08

-6.87E-Ol

2. 98E+OO 205.31 5.01

-3.30E-D1

6. 34E-01 Am-241 59.54 35.90 l.38E-01 7. 72E-Ol

7. 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

E 60-f 55 50

~

ROI Type: 1 1000 2000 3000 0000002:

4000 channel

'" CNF 5000 Live rime :600.000 sec Real Time :600.960 sec Start:

1: -<I.O{kev}

5tap : 8192: ZD41. 4(kev)

Aeq. Start :ll'ed Jllir 01 08:30:00 2017 6000 7000 8000

3/1/2017 8:40:14AM

,t. * *.A-~ pex Gamm"'

,C~ ~i;; *..

.* 'Cl Analysis Report for 01-Mar-17-10014 L310222AFRGS014SS GAMMA SPECTRUM ANAL YSJS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Llvenme Real Time Dead Tlme 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

01-Mar-17-10014

L310222AFRGS014SS

Sand 1.803E+03 grams

Default

2/23/2017 9:20:00AM

3/1/2017 8:30:0SAM

130G_Sand

Administrator

P11314

130G_Sand

600.0 seconds

600.4 seconds

0.06%

3.00

120 - 8192

120- 8192

1.000keV

11/10/2016

3/1/2017

initial 11/16/16

2144

1000.00 gram

Eu155-Na22

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

3/1/2017 8:40:0BAM Peak Analysts From Channel

120 Peak Analysis To Channel

8192 Page I of6

3/1/2017 8:40:14AM Pagc2of6 Analysis Report for 01-Mar-17-10014 L310222AFRGS014SS Peak Energy ROI ROI No.

(keV) start end 1

238.62 948 -

959 2

295.29 1175 - 1185 3

352.13 1401 - 1412 4

609.31 2429 - 2441 5

1460.87 5831-5852 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centroid 954.08 1180.43 1407.53 2435. 29 5841.44 No background subtract performed on this spectrum.

Net Peak NetAnta Continuum Area Uncertainty Counts 9.40E+Ol 13.29 3.30E+Ol 3.07E+Ol 9.21 2.23E+Ol 4.95E+Ol 8.70 1.05E+01 4.73E+Ol 8.10

6. 71E+OO l.85E+02 14.28 5.24E+OO NUCLIDE IDEbJTIF/CA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Library\\ZION LIB-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id

EnergJ, Yield{%)

Activity Activity Name Confidence (keV)

(pCVgrams)

Uncertainty K-40

1. 00 1460.82 10.66

4. llE+OO 3.65E-Ol Pb-212

1. 00 115.18

0. 60 238.63

43.60

1. 42E-01 2.31E-02 300.09 3.30 t.-214 1.00 609.32 45.49

1. 33E-01 2.42E-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 FWHM (keV)

1. 04 0.46

0. 98 0.54 1.38

Analysis Report for 01-Mar-17-10014 L310222AFRGS014SS Nuclide Id Energy Name Confidence (keV)

Bi-214

1. 00 1377. 67 1385.31 1401. 52 1407.99 1509.21 1661.27 1729.59 1764.49 1847.43 2118.51 Pb-214 0 99 241. 99 295.22 351.93 785.96

= Energy llne 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 fndex threshold = 0.30 Errors quoted at 1.000sigma 3/1/2017 8:40:14AM Page3 of6 Yield(%)

Activity Activity (pCUgrams)

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 1.25E-Ol 3.90E-02 35.60 1.20E-01 2.31E-02

1. 06 INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Pb-212 Bi-214 Pb-214 Nuclide Id Confldonce

1. 000 1.000

1. 000 0.996

? = nuclide is part of an undetennined solution X

"' nuclide rejected by the Interference analysis Wt mean Activity (pCUgrams) 4.llE+OO

1. 42E-01

1. 33E-Ol

1. 21E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000slgma Wt moan Comments Activity Uncertainty 3.65E-Ol 2.31E-02 2.42E-02 l.99E-02

3/1/2017 8 :40:14AM Analysis Report tor 01-Mar-17-10014

+

L310222AFRGS014SS Peak Locate Performed on Reak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

All peaks :-vere Identified.

M = First peak in a multrplet region m = OU'ler peak in a multiplet region F = Fitted singlet Errors quoted at 1.000Slgma UNIDENTIFIED PEAKS

3/1/2017 8:40:0BAM

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}

(pCUgrems)

(pCUgrams)

BE-7 477.60

10. 44 1.68E-Ol 2.89E-01

2. 89E-01 K-40 1460.82 10.66

4. llE+OO 3.95E-01

3. 95E-Ol Co-60 1173. 23 99. 85 9.29E-03 4.16E-02

5. OSE-02 1332.49 99.98 8.66E-03 4. 16E-02 Nb-94 702. 65 99.81 1.SOE-02 3.33E-02

3. 38E- 02 871. 09 99.89 -1.24E- 02 3.33E-02 Ag-108m 79.13 6.60 2.13E-01 3.04E-02

8. 14E-01 433.94 90.50

-l.12E-02

3. 04E-02 614.28 89. 80

-2.06E-02

4. 94E-02 722.94 90.80 l.6SE-02

4. 20E-02 Sb-125 176.31 6.84 2. 37E-01

1. OlE-01 3. 64E-Ol 380.45

1. 52

- 7.71E-01

1. 60E+OO 427.87 29.60 -l.20E-02

1. OlE-01 463.36 10.49 l.46E-01 2. 99E-01 600.60 17.65 3.61E-02 2.04E-Ol 606.71 4.98 1.66E+OO l. 14E+OO 635.95 11.22 -1. 41E-01 2.75E-Ol 671. 44

1. 79

-5.59E- 01

1. 96E+OO Ba-133 79.61 2.65 -1. 60E-01 5.25E-02

1. 94E+OD Page 4 of6 Tolerance Nuclide

3/1/2017 8 :40:14AM Page S of6 Analysis Report for 01-Mar-17-10014 L310222AFRGS014SS Nuclide Energy Yield{%}

Activity Nuclide IJiDA LineMDA Name (keV)

(pCilgrams)

(pCUgrams)

Ba-133

81. 00 32.90

-1.42E-01 5.25E-02

1. 26E-01 27 6. 4 0 7.16 6.79E-02 3. 85E-01 302.85 18.34 5.55E-02

1. 41E-Ol 356.01 62.05

-3.SSE-02

5. 25E-02 383.85

8. 94

-1.77E-01

2. 67E-Ol Cs-134 475.36

1. 48

-1.02E+OO

4. 12E-02

1. 82E+OO 563.25 8.34

-2.SlE-01 3. 48E-Ol 569.33 15.37 8.22E-02 2. llE-01 604. 72 97.62

-2.65E-02

4. 97E-02 795.86 85.46

-9.32E-03 4.12E-02 801. 95 8.69

-6.75E-02 3

97E-01 1038. 61 0.99 1.42E-01 3. 69E+OO 1167.97

1. 79 5.67E-02 2. 99E+OO 1365.19 3. 02 8.SSE-02

J_ - 30E+OO Cs-137 661. 66 85.10

-2.69E-02 3. 23E-02

3. 23E-02 Eu-152 121. 78 28.67 3.42E-02 9.16E-02 9.16E-02 244.70 7.61 2.08E-01 3. 93E-01 295.94 0.45 3.90E+OO

7. 98E+OO 344.28

26. 60 6.09E-03 9. 83E-02 367.79 0.86 4.65E-01

2. 87E+OO 411. 12 2.24 3.37E-Ol 1. 20E+OO 443.96 2.83

- 1.45E-Ol

1. 07E+OO 488.68

0. 42

- 5.49E+OO

6. 21E+OO 563.99 0.49

-3.26E+OO 5. 89E+00 586.26 0.46 3.95E+OO 9. 91E+OO 678. 62 0.47

-8.68E-01

7. 45E+OO 688.67 0.86

-3.47E+OO

3. 29E+OO 719.35 0.28 l.94E+OO 1. OBE+Ol 778.90 12.96 9.91E-02

2. 37E-Ol 810.45 0.32

1. 09E+OO

1. llE+Ol 867.37 4.26

- 5.37E- 01

7. 25E-01 919. 33 0.43

-1.00E+OO

8. 35E+OO 964.08 14.65 -2.79E-01

3. 25E-Ol 1085.8'?

10.24 -3.84E-01 3.24E-Ol 1089.74

1. 73

1. 53E+OO

2. 77E+OO 1112.07 13.69 -4.71E-02

3. SSE-01 1212.95

1. 43

1. 78E+OO

3. 46E+OO 1249.94 0.19

1. 28E+Ol

2. 66E+Ol 1299.14 1.63 -5.02E-01

2. 31E+OO 1408.01

21. 07 7.67E-02

1. 71E-01 1457.64 0.50 9.29E+Ol

3. 31E+Ol 1528.10 0.28 3.49E+OO

1. 09E+Ol Eu-154 123.07 40.40

-3.37E-02 6.21E-02 6.21E-02 247.93 6.89 2.77E- 01 3. 64E-01 591. 76 4.95

-8.19E- 02

6. 83E-01 692.42

1. 78

-5.33E-02

1. 60E+OO 723.30 20.06 2.53E-02

1. 91E-Ol 756.80 4.52

-1.85E-Ol E.23E-01 873.18

12. 08 3. 52E-02

2. 85E-01 996.29 10.48 -9.73E-02 3.72E- 01 1004. 76 18.01 -2.03E-03

1. 83E-01 1274.43 34.80

2. 74E-02

1. 40E-01

3/1/2017 8:40:14AM Page 6of6 Analysis Report for 01-Mar-17-10014 L310222AFRGS014SS Nuclide Energy Yield(%)

Activity NuclldeMDA Linel;IDA Name (keV)

(pCUgrams}

(pCVgrams)

(pCl/grams)

Eu-154 1596.48

1. 80 9.46E-02 6.21E-02 2. 08E+OO Eu-155 45.30 1.31

-5.68E+OO

1. 2':'E-01 5. SSE+OO

60. 01 1.22 -9. 45E-02

7. 21E+OO 86.55 30.70

-1. 03E-02

1. 27E-Ol 105.31 21.10 2.67E-02

1. 35E-01 Ra-226 186.21

3. 64 3.92E-01 7.48E-01 7. 48E-Ol Pa-231 27.36 10.30 O. OOE+OO 6.6SE-02

6. 65E-02 283.69

1. 70

-6.48E-02 1. 33E+00 300.07 2.47

-1.llE-01 1.14E+OO 302.65 2.20 2.18E-01 1.17E+OO 330.06 1.40

-1.80E-01

2. llE+OO U-235 143. 76

10. 96

-2.53E-03 4.73E-02 2. 47E-01 163. 33 5.08 5.06E-02 4. 62E-Ol 185.71 57.20 l.42E-02

4. 73E.-02 202.11 1.08

-5.27E-01

2. 08E+OO 205.31 5.01

-2.21E-01 4. 64E-01 Am-241 59.54 35.90 3.74E-02 2. 61E-Ol

2. 61E-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

60 55 1000

~

ROI Type: 1 2000 3000 00000021 4000 channel

.CNF 5000 Live Time :&00.000 sec Real Tine :600.380 sec start:

1: -0.0(lc.ev)

Stop : 1192:2047,8{kev)

ACQ. Start :Wed Mar 01 OB:30:0& 2017 6000 7000 8000

~~,Apex-Garnrna 311/2017 8:53:17AM Analysis Report for 01-Mar-H-10015 L310222AFRGS015SS GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator DetectorName 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

01-Mar-17-10015

L310222AFRGS015SS

Sand 1.698E+03 grams

Default

2/23/2017 1:43:00PM

3/1/2017 8: 43:08AM

130G_Sand

Administrator

P40818B

130G_Sand 600.0 seconds

600.9 seconds

0.15%

3.00

120-8192

120 - 8192

1.000 keV

1/18/2017

3/1/2017

2145

1000.00 gram

Eu155-Na22

1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Performed on

3/1/2017 8:53:11AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of7

3/1/2017 8:53:17AM Page2of7 Analysis Report for 01-Mar-17-10015 L310222AFRGS015SS Peak Energy ROI ROI No.

(keV) start end 1

238.74 946 -

960 2

295.53 1176 - 1186 3

351.95 1401 - 1414 4

510.57 2036 - 204 6 5

583.20 2328 -

2337 6

609.36 2431 - 2442 7

911. 34 3639 - 3649 8

1460.72 5831 - 5852 M = First peak in e multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Pea!r Centroid 955.04 1182. 03 1407.53 2041. 63 2332.02 2436.62 3644.33 5842. 72 No background subtract perfonned on this spectrum.

NetPeak NetArea Continuum Area Uncertainty Counts 9.76E+Ol lS.37 4.74E+Ol 3.88E+Ol 8.39 1.32E+Ol 5.SOE+Ol 11.20 2.SOE+Ol

1. 67E+Ol 6.78

1. 23E+Ol L 70E+Ol 5.34 S.OOE+OO 4.84E+Ol 8.23 7.62E+OO

1. 37E+Ol 5.16 S.30E+OO

1. 43E+02

12. 37 2.65E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

C:\\Canberra\\Apex\\Root\\Default\\Llbrary\\ZION LIB-BNLNLB IDENTIFIED NUCLIDES Nuclide Id En9YrJy Yield(%)

Activity Activity Name Confidence (keV)

(pCUgrams)

Uncertainty K-40 0.99 1460.82

10.66 3.7 8E+OO 3.65E-Ol

"'l-208

1. 00 583.19

85.00 2.94E-02 9.40E-03 D-212 0.99 115.18 0.60 238.63 43.60 1.76E-Ol 3.12E-02 300.09 3.30 Bi-214

1. 00 609. 32 45.49

1. 61E-Ol

2. 91E-02 768.36 4. 89 806.18

1. 26 934.06 3.11 FWHM (ke\\?

0. 96 0.83

0. 63

a. so 0.35 0.59 0.58

1. 41

Analysis Report for 01-Mar-17-10015 l310222AFRGS015SS Nuclide Id Energy Name Confidence (keV)

Bi-214

1. 00 1120.29 1155.. 21 1238.12 1280.98 1377.67 1385.31 1401.52 1407.99 1509. 21 1661.27 1 729.59 1764.49 1847.43 2118. 51 Pb-214 0.99 241. 99 295. 22 351".93 785.96 Ac-228 0.99 129.07 209.25 270.24 328.00 338.32 409.46 463.00 794.95 911.20 964.77 968.97 1588.20

= Energy line found In 1he 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 3/1/2017 8:53:17AM Page3 of7

'i'ield(%)

Activity Activity (pCVgrams)

Uncertainty

14. 92

1. 63 5.83

1. 43 3.99

0. 79

1. 33 2.39 2.13

1. 05 2.88 15.30 2.03 1.16 7.25 18.42

1. 88E-01 4.34E-02

35. 60

1. 58E-01

3. 45E-02

1. 06 2.42 3. 89 3.46 2. 95 11.27

1. 92 4.40 4.25 25.80 1.07E-01 4, 04E-02 4. 99 15.80 3.22 INTERFERENCE CORRECTED REPORT

Analysis Report fOI' 01-Mar-17-10015 L310222AFRGS015SS Nuclide Nuclide Name Id Confidence K-40 0.998 Tl-208

1. 000 X

Bi-211 0.884 Pb-212 0.998 Bi-214 1.000 Pb-214 0.995 Ac-228 0.999

?

= nuclide is part of an undetermined solution X

= nuclide rejected by the interference analysis 3/1/2017 wt mean Activity (pCi/grams) 3.78E+OO 2.94E-02 1.76E-01 1.61E-01 1.70E-01 1.0'?E-01

@ = nuclide contain~ energy llnes not used in Weighted Mean Activity Errors quoted at 1.000sigma 8:53:17AM Page 4 of7 wt mean Comments Activity Uncertainty 3.65E-01 9.40E-03 3.12E-02 2.91E-02 2.70E-02 4.04E-02

3/1/2017 8:53:17AM Analysis Report for 01-Mar-17-10015 L310222AFRGS015SS Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.

Energy (keV)

UNIDENTIFIED PEAKS

3/1/2017 8:53;11AM

120

8192 Peah CPS ('A,)

Peal-: S/7.e(CPS)

UncertaintJ/

Peak Type 4 ______ 5_1_0 ___ 5_7 ______ 2-.78736E-02

~

+

M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE MDA REPORT Nuclide Library Used

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

Activity Nuclide MDA Li11eMDA Name (keV)

(pCilgrams)

(pCVgrams)

(pCUgrams)

BE-7 477.60 10.44 4.0lE-01 4.28E-01

4. 28E-01 K-40 1460.82 10.66 3.78E+OO

3. 54E-Ol

3. 54E-01 Co-60 1173.23 99.85

1. SOE-02 4.31E-02

5. 16E-02 1332.49 99.98

-1.25E-02

4. 31E-02 Nb-94 702.65 99.81 2.0lE-02 3.79E-02

3. 90E-02 871. 09 99.89 2.33E-02

3. 79E-02 Ag-108m 79.13 6.60 1. 03E+OO 4.16E-02 1. 61E+OO 433.94 90.50 -1. 02E-02

4. 16E- 02 614.28 89.80

-2.35E- 02 6.25E-02 722.94 90.80 -9. 60E-03

4. 26E-02 Sb-125 176.31 6.84 2.64E-Ol

l. 33E-01

5. SlE-01 380.45

1. 52 2.lOE-02 2.53E+OO 427.87 29.60

-6.92E-02

1. 33E-Ol 463. 36 10.49 6.30E-02

3. 78E-01 600.60 17.65 5.99E-02

2. 25E-Ol 606.71 4.98

1. BOE+OO

1. 41E+OO 635.95

11. 22 4, 19E-02 3.17E-Ol 671.44

1. 79

-4.09E-01

1. 95E+OO Page 5 of7 TolGrance Nuclide

3/1/2017 8:53:17AM Page6 of7 Analysis Report for 01-Mar.17-10015 L310222AFRGS015SS Nuclide Energy Y,e/d("/o)

Activity NuclldeMDA l-in~MDA Name (keV)

(pCVgrams)

(pCUgrams)

Ba-133 79.61 2.65 3.90E-02 7.28E-02 3. 78E+OO

81. 00 32.90

-1.96E-02 2. 63E-01 276.40 7.16

-7.21E-02

4. SOE-01 302.85 18.34

1. 14E-01

1. 91E-01 356.01

62. 05

-1. 58E-02

7. 28E-02 383.85 8.94 2.07E-01

4. 48E-01 Cs-134 475.36

1. 48 3.95E-01 6.07E-02

2. 71E+OO 563.25 8.34

-5.28E-02 4

21E-Ol 569.33 15.37

-1. 38E-01 2. 49E-01 604.7':.

97.62

-2.SSE-02

6. SOE-02 795.86 85.46

4. 72E-02

6. 07E-02 801.95 8.69

1. 83E-02

4. 69E-01 1038.61 0.99

-4.0SE+OO 3. 68E+OO 1167.97

1. 79

-9.94.E-01 3.llE+OO 1365.19 3.02 8.88E-01

1. 60E+OO Cs-137 661. 66 85.10 9.82E-03

4. 0SE-02

4. OSE-02 Eu-152 121. 78 28.67 7.52E-D4 1.19E-01 1

30E-01 244.70 7.61

1. 88E-01

4. 87E-01 295.94 0.45 3.36E+OO

9. 15E+OO 344.28 26.60

-5.38E-02 1.19E-01 367.79 0.86 2.21E+OO

3. 92E+OO 411.12

2. 24 8.99E-D1

1. 54E+OO 443.96

2. 83 3.89E-01

1. 36E+OO 488.68 0.42 3.78E+OO

8. 31E+D0 563.99 0.49

-l.41E+OO

6. 80E+OO 586.26 0.46 3.21E-Ol

1. 04E+Ol 678.62 0.47 2.24E+OO

8. 62E+00 688.67 0.86

-1.0lE+OO

4. 58E+D0 719.35 0.28

-6.llE+OO

1. 23E+Ol 778.90

12. 96 7.99E-02 3. 06E-01 810.45 0.32

-8.42E+OO

1. 12E+Ol 867.37 4.26 8.45E-02

9. 48E-01 919.33 0.43

-3.25E+OO

8. 89E+OO 964. 08

14. 65

1. 09E-01

4. 29E-01 1085.87 10.24 1.60E-01

4. 33E-01 1089.74

1. 73

-1.38E+OO

2. 66E+OO 1112.07 13.69

1. 64E-01 3.82E-01 1212.95 1.43 1.36E- 01

4. 09E+OO 1249.94 0.19 2.03E+Ol

3. 29E+01 1299.14

1. 63 1. 74E+OO

2. 97E+OO 1408.01

21. 07 1.19E-02 1.90E-01 1457.64 0.50 7.58E+01 3.43E+Ol 1528.10 0.28 6.20E+OO 1.SlE+Ol Eu-154 123.07 40.40

-3.82E-02 9. 07E-02 9.0?E-02 247.93 6.89 2.41E-01 4.87E-01 591. 76 4.95 6.91E-01 7.77E-01 692.42

1. 78 4.90E-01 2.32E+OO 723.30 20.06 -1.48E-01

1. 88E-01 756.80 4.52 9.SlE-02 l.OlE+OO 873.18 12.08 - 4. 03E-03 3.03E-Ol 996.29 10.48 -1.BOE-01 4.SlE-01

3/1/2017 8:53:17AM Page 7of7 Analysis Report for 01-Mar-17-10015 L310222AFRGS015SS Nuclide Energy Yield{%)

Activity NuclldeMDA Line&DA fJame (keV)

(pCVgrams)

(pCUgrams)

Eu-154 1004.76 18.01

-1. 54E-01 9.0';'E-02 2. 41E-01 1274. 43 34.80

-5.47E-03 1

42E-01 1596.48

1. 80 6.72E-Ol 2. 09E+OO Eu-155 45.30 1.31 9.44E+OO 2. 13E-01 2.17E+Ol 60.01 1.22 -1.l 7E+Ol

1. 92E+Ol 86.55 30.70 6.42E-02 2.13E-01 105.31 21.10 1.llE-01 2. 39E-01 Ra-226 186.21 3.64 1.68E-Ol 9.64E-01

9. 64E-Ol Pa-231 27.36 10.30 O.OOE+OO 1.88E-Ol

1. 88E-01 283.69

1. 70 1.0l E+OO

1. 92E+OO 300.07 2.47

-1.0SE+OO 1

35E+OO 302.65 2.20 1.17E+OO 1

60E+DO 330.06

1. 40 7. 19E-01 2. 62E+OO U-235 143. 7 6

10. 96

-2.SSE-01 6.lOE-02 3.26E-01 163.33 5.08

-7.SlE-02 7.17E-Ol 185.71 57.20 2.79E-03

6. lOE- 02 202.11

1. 08 8. 40E-01 2. 98E+OO 205.31 5.01

-6.41E-01

6. 40E-01 Am-241 59.54 35.90

-6.19E-01 6.68E-Ol

6. 68E-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 7

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

60 55 1000

~

ROI rype: 1 2000 3000 00000021 4000 channel

.CNF 5000 Liw Till! :600.000 m Real Ti1e :600.930 sec Start:

1: -0.0(hY)

Stop : Bl92:2047.4(keY)

Aclf, start :ved Mar 01 08:43:08 2017 6000 7000 8000

3/1/2017 8:02:07AM Analysis Report tor 01-M~r-17-10007 L310222AFQGS007SS GAMMA SPECTRUM ANAL YSJS 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 Cellbration Description Sample Number Fill Height Ceriiflcate Name Certificate Date

01-Mar-17-10007

L310222AFQGS007SS

Sand 1.816E+03 grams

Default

2/23/2017 2:45:00PM

3/1/2017 7;51 :58AM

130G_Sand

Administrator

P40818B

130G_Sand

600.0 seconds

601.0 seconds

0.16 %

3.00

120 -8192

120- 8192

1.000 keV

1/18/2017

3/1/2017

2137

1000.00 gram

Eu155-Na22

1/30/2012 12:00:00PM PEAK ANALYSIS REPORT Peak Analysis Perfom,ed on

3/1/2017 8:02:01AM Peak Analysis From Channel Peak Analysis To Channel

120

8192 Page I of7

3/1/2017 B:02:07AM Page 2 of7 Analysis Report for 01-Mar-17-10007 L310222AFQGS007SS Peak Energy ROI ROI No.

(keV) start end 1

77.24 306 -

314 2

238.68 947 -

959 3

295.31 1177 - 1187 4

351. 86 1402 - 1415 5

583.20 2327 - 2337 6

609.26 2429 - 2444 7

910.95 3636 - 3649 8

1460.66 5832 - 5853 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma Peak Centroid 309.68 954.83 1181.16 1407.16 2331.99 2436.20 3642.76 5842.49 No background subtract performed on this spectrum.

Net Peak Net Area Continuum Area Uncertainty Counts 2.57E+Ol 10.47 3.83E+Ol 1.11E+02

13. 98 3.22E+Ol 3.46E+01 9.77 2.54E+Ol 6.57E+Ol 10.11 1.33E+01 3.75E+Ol 7.11 5.SOE+OO 6.37E+Ol 8.89 5.26E+OO 2.72E+Ol

7. 62

1. 08E+Ol 1.78E+02

13. 72 2.67E+OO NUCLIDE /DENT/FICA TION REPORT Nuclide Library Used

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

Activity Activity Name Confidence (keV)

(pCUgrams)

Uncertainty K-40

0. 99 1460. 82 10.66 4.3SE+OO 3.88E-01

...,1-208

1. 00 583.19

85.00 6.06E-02 1.21E-02 b-212 1.00 115.18 0.60 238.63 43.60

1. 87E-01 2.BOE-02 300.09 3.30 Pb212-XR

0. 99 74.82 10.28 77.11 17.10

2. 58E-Ol 1.0BE-01 87.35 3.97

89. 78 1.46 FWHM (k*VJ 0.47

0. 94 0.58

0. 61 0.78

1. 41 0.85

1. 60

3/1/2017 8:02:07AM Page 3 of7 Analysis Report for 01-Mar-17-10007 L310222AFQGS007SS Nuclide Id Energy Yield{°/o)

Activity Activity Name Confidence (keV)

(pCVgrams)

Uncertainty Bi-214 1.00 609.32

45.49 1.98E-0l 3.0lE-02 768.36 4.89 80G.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 1401.52

1. 33 1407.99 2.39 1509.21 2.13 1661.27

1. 05 1729.59 2.88 1764.49 15.30 1847. 43 2.03 2118.51

1. 16 Pb-214 0. 99 241.99 7.25 295.22 18.42 1.57E-01 4.60E-02 351.93

35.60 l.76E-Ol 3.0SE-02 785.96 1.06 Pb214-XR 0.99 74.82 5.80

?7. 11 9.70 4.SSE-01 1. 92E-01 87.35 2.24 89.78 0.82 Ac-228 0.99 129.07 2.42 209.25 3.89 270.24 3.46 328.00 2.95 338. 32 11.27 409. 46

1. 92 463. 00 4.40 794.95 4.25 911.20 25.80

1. 98E-01 5.61E-02 964.77 4.99 968.97 15.80 1588.20 3.22

= 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 1.000slgma

3/1/2017 8:02:07AM Analysis Report for 01-Mar-17-10007 L310222AFQGS007SS INTERFERENCE CORRECTED REPORT Nuclide Name K-40 Tl-208 X

Bi-211 Pb-212

?

Pb212-XR Bi-214 Pb-214

?

Pb214-XR Ac-228 Nuclido Id Confidence 0.996

1. 000 0.905 1.000 0.999

1. 000

0. 9-99 0.999 0.997

? = nuclide is part of an undetermined solution X = nuclide rejected by the Interference analysis Wt mean Activity (pCUgrams) 4.39E+OO 6.06E-02

1. 87E-01

2. 58E-01 1.98E-01 1.70E-01 4.55E-01

1. 98E-01

@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma wtmean Activity Uncertainty 3.BSE-01 1.21E-02 2.80E-02 1.08E-01 3. OlE-02 2.54E-02 1.92E-Ol 5.61E-02 Pa,se4of7 Comments

+

3/1/2017 8:02:07AM Analysis Report for 01-Mar-17-10007 L310222AFQGS007SS Peak Locate Perfonned on Peak Locate From Channel Peak locate To Channel Peak No.

Energy (keV)

All peaks were ld9ntified.

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

3/1/2017 8: 02:01AM

120

8192 Peak CPS(%)

Peak Size (CPS)

Uncertainty NUCLIDE MDA REPORT Peak Type Nuclide Library Used

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

Activity Nuc/ldeMDA LineMDA Name (keV)

(pCl/grams)

(pCVgrams)

(pCl/grams)

BE-7 477. 60 10.44

- 4.48E-02 3.47E-01 3. 47E-Ol K-40 1460.82 10. 66 4.39E+OO 3.33E-01 3. 33E-01 Co-60 1173.23 99.85

-2.15E- 03 3.58E-02

5. 09E-02 1332.49 99.98 1.43E-03

3. 58E-02 Nb-94 702. 65 99.81

-l.30E-02

4. 0lE-02 4. 29E-02 871.09 99.89

-5.29E-03

4. OlE- 02 Ag-108m 79.13 6.60

-3.55E-01 3.84E-02

1. 26E+OO 433.94 90.50

-1.87E-02 3. 84E-02 614.28 89.80 -2. 79E-02

5. 73E-02 722. 94 90.80 4. BOE-03 4. 81E-02 Sb-125 176. 31

6. 84 -l. 49E-Ol 1.17E-01

4. 68E-01 380. 45

1. 52

-1. 66E+OO

1. 83E+OO 427.87 29.60 -3. 28E-02

1. 17E-01 463.36 10.49 1.65E-01

3. 30E-Ol 600.60 17.65

1. 32E-01 2. 36E-01 606.71 4.98 2.20E+OO

1. 36E+OO 635. 95 11.22 -2.52E-01

2. 36E-01 671. 44

1. 79

-1.18E+OO

2. 33E+OO Ba-133 79.61 2. 65

-6. 89E- 01 6.31E-02 3. OSE+OO PageSof7 Tolerance Nuclide

3/1/2017 8:02:07AM Page 6 of7 Analysis Report for 01-Mar-17-10007 L310222AFQGS007SS Nuclide Energy Yield(%)

Activity NuclldeMDA LlneMDA Name

{keV)

(pCl/grams)

(pCVgrams)

Ba-133

81. 00 32.90

-7,89E-02 6.31E-02 2. OSE-01 276. 40 7.16

-3.84E-01 4. 09E-01 302.85 18. 34 3.60E-03

1. 90E-01 356.01 62.05

-1.78E-02

6. 31E-02 383.85

8. 94

-7.66E-02 3. 83E-01 Cs-134 475.36

1. 48

-1.03E+OO 4.78E-02 2. 39E+OO 563.25 8.34

-7.64E-02

4. lOE-01 569.33 15.37

1. 77E-Ol 2. 72E-01 604.72

97. 62

-3.33E-02 6. 20E-02 795.86 85.46

-1.93E-02

4. 78E-02 801.95 8.69

-2.20E-01

4. 38E-01 1038.61 0.99

-l.36E+OO 4. 74E+OO 1167.97

1. 79 2.76E+OO 3.18E+OO 1365.19 3.02

-1.86E+OO 1. 29E+OO Cs-137 661. 66 85.10

1. 90E-02 4.57E-02

4. 57E-02 Eu-152 121. 78 28.67

-7.62E-02 1.21E-Ol 1. 21E-01 244.70

7. 61 3.?0E-02

4. 71E-01 295.94

0. 45 5.08E+OO 9.46E+OO 344.28 26.60

-7.65E-02

1. 27E-Ol 367.79

0. 86

-1.lSE+OO

3. 80E+OO 411.12 2.24 3.39E-01

1. 64E+OO 443.96 2.83

- 5.91E-Ol

1. 28E+OO 488.68 0.42

- 3.45E+OO 6.86E+OO 563.99 0.49

-2.74E+OO 6.80E+OO 586.26 0.46 l.22E+Ol 1.19E+Ol 678.62 0.47

-4.16E-Ol 8.23E+OO 688.67 0.86

-2.90E-01 4.57E+OO 719. 35 0.28 7.9SE+OO

1. 36E+Ol 778.90 12.96

~.78E-02

3. 61E-01 810.45

0. 32 2.39E+OO 1. 34E+Ol 867.37 4.26

-8.2BE-01 9. 89E- 01 919. 33

0. 43

-8.87E+OO

9. 49E+OO 964.08

14. 65 3.74E-01 3.78E-01 1085.87 10.24

-5.24E-01 3.74E-01 1089. 74

1. 73 2.77E-01 2.56E+OO 1112. 07 13.69

- 7.16E-02 3.29E-Ol 1212.95 1.43 3.54E+OO 4.54E+OO 1249.94 0.19 -1. l 7E+Ol 2.33E+01 1299.14

1. 63

1. OlE+OO 3.08E+OO 1408.01 21.07

-3.91E-01 1.77E-01 1457. 64 0.50 9.65E+Ol 3.56E+01 1528.10 0.28 4.83E+OO

1. 31E+Ol Eu-154 123.07 40.40 -6.96E- 02 8.34E-02 8.34E-02 247.93 6.89 l. 92E-01 4. 65E-01 591. 76 4.95 9.83E-02 7.27E-Ol 692.42

1. '18

-7.86E-01 1.98E+OO 723.30 20.06

4. 39E-02 2. 18E-01 756.80 4.52

-6.78E-01 8.27E-01 873.18 12.08 -1.32E-02 2.94E-01 996.29

10. 48

-1.24E-01 4.22E-Ol 1004.76 18. 01 3.0BE- 02 2.33E-01 1274.43 34.80 -4. 65E- 02

1. 28E- 01

3/1/2017 8:02:07AM Page 7 of7 Analysis Report for 01-Mar-17-10007 L310222AFQGS007SS Nuclide Energy

\\1eld{%)

Activity NuclideMDA UneMDA Name (keV)

(..fJCVgnms)

(pCUgrams)

(pCi/grams)

Eu-154 1596.48 1.80

-4.94E-01 8.34E-02 2

45E+OO Eu-155 45.30 1.31 1.65E+OO 1.9SE-01 2

OOE+Ol 60.01

1. 22

-1. 21E+Ol 1. 87E+Ol 86.55 30.70 3.20E-02

1. 95E-Ol 105.31 21.10 6.49E-02 2. 41E-01 Ra-226 186.21 3.64 4.?0E-02

1. OlE+OO

1. OlE+OO Pa-231 27.36 10.30 O.OOE+OO 1.76E-Ol l.76E-01 283.69

1. 70

-8.37E-01 2. 02E+OO 300.07 2.47

-4.90E-01

1. 46E+OO 302.65 2.20

-3.67E-01

1. 58E+OO 330.06

1. 40

1. 84E+OO

2. 52E+OO U-235 143.76

10. 96

-1. 28E-01 6.60E-02

3. 47E-01 163. 33 5.08

-1.0BE-01

6. SOE-01 185.71 57.20 4.26E-02

6. 60E-02 202.11

1. 08 5.70E-01 2. 79E+OO 205.31 5.01

-2.20E-01

5. 95E-Ol Arn-241 59.54 35.90 1.19E-02 6.88E-Ol

6. 88E-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

60 55 1000

~

ROI Type: 1 2000 g7

~w I-3000 00000021 4000 channel

'.CNF 5000 Live Tia :IG0.000 sec Real li* :600.990 sec Start:

1: -0.0(kev)

Stop : 5192:2047.4(iev)

Acq. Snrt :~ Mar 01 07:51:51 2017 6000 7000 8000

[185]

ATTACHMENT 4 CONSULTATION TRIGGERS FOR RESIDENTIAL SOIL CONCENTRATION

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[186]

[187]

ATTACHMENT 5 QC SAMPLE ASSESSMENT

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222 Survey Una#:

10200 Survey Unit #

Sample Pmi#:

l..310222AF

.~

ZIONSOLUTIONSuc

MEll4rw,~IMlorrmL~ '>.':.I-,.,

Duplicate Sample Assessment 10222 Survey Unit Name:

North Beach Area Sample Deserq>1im: Cmq,arison of split smq,les collected from surface soi S81J1)les from location #7 am ana1y7ro ffliog gamma spectroscopy by on-site HpGe System The staooard sample was L3-10222A-FRGS-007SS, the oo~arison sample was L3-10222A-FQGS-007SS.

STANDARD COMPARISON Radionuclne Activity Standard Resolution Agreeirent Activity Standard CoJIJJarison Acceptable Vahle Error Range Vahle Error Rati:l (YIN)

Cs-137 2.83&02 4.20&02 0.67 0.4-2.5 1.90&02 4.57&02 1.49 y

Comrrents/Corrective Acmns: None Table is provided to show acceptance criteria used to assess sp1it.sat)1)les.

Re~clmio11 Acceptable Ratio

<4 0.4-2.5 4-7 0.5-2.0 8-15 0.15-1.66 llS-50 0.'.'5- :.33 51-200 O.SO-l..:?~

>200 0.85-US Perfonnedby: RF Y~ i,J..-IJ&-. Date:

,-lReveiwed by:

/

- A; 912112011 ~r~l.--

Date* 6 /,~/, I;;)

V I

u 7

[188]

[189]

ATTACHMENT 6 GRAPHICAL PRESENTATIONS

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[190]

Quantile Plot for Co-60 Survey Unit: L310222 Survey Unit Name: Open Land - North Beach Area Mean: 1.65E-02 pCi/g

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[191]

Quantile Plot for Cs-137 Survey Unit: L310222 Survey Unit Name: Open Land - North Beach Area Mean: 9.69E-03 pCi/g

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[192]

Histogram for Co-60 Survey Unit: L310222 Survey Unit Name: Open Land - North Beach Area Mean:

1.65E-02 pCi/g Median:

1.50E-02 pCi/g ST DEV: 0.01505563 Skew: 0.71923483 Upper Value Observation Frequency Observation 7.85E-03 4

27%

1.57E-02 4

27%

2.36E-02 3

20%

3.14E-02 1

7%

3.93E-02 1

7%

4.71E-02 2

13%

TOTAL 15

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[193]

Histogram for Cs-137 Survey Unit: L310222 Survey Unit Name: Open Land - North Beach Area Mean:

9.69E-03 pCi/g Median:

9.82E-03 pCi/g ST DEV: 0.01022223 Skew: 0.57357829 Upper Value Observation Frequency Observation 4.72E-03 7

47%

9.43E-03 0

0%

1.42E-02 3

20%

1.89E-02 2

13%

2.36E-02 1

7%

2.83E-02 2

13%

TOTAL 15

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[194]

Retrospective Power Curve for Survey Unit 10222

FSS RELEASE RECORD NORTH BEACH AREA SURVEY UNIT 10222

[195]

ATTACHMENT 7 EBERLINE ANALYTICAL REPORTS

Printed: 6/18/2018 1:45 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

Printed: 6/18/2018 1:45 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

Printed: 6/18/2018 1:45 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

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