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Revised Final Status Survey (FSS) Report - Phase 2, Release Record - Unit 1 Diesel Fuel Oil Storage Tank Room Survey Unit 06201
	ML19295G846
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	09/01/2019
From:	; ZionSolutions
To:	; Office of Nuclear Material Safety and Safeguards
Shared Package
ML19295G627	List: ML19295G587; ML19295G611; ML19295G612; ML19295G617; ML19295G621; ML19295G625; ML19295G670; ML19295G674; ML19295G699; ML19295G702; ML19295G705; ML19295G726; ML19295G728; ML19295G734; ML19295G738; ML19295G742; ML19295G747; ML19295G751; ML19295G758; ML19295G764; ML19295G768; ML19295G788; ML19295G791; ML19295G795; ML19295G816; ML19295G818; ML19295G820; ML19295G822; ML19295G826; ML19295G828; ML19295G831; ML19295G837; ML19295G841; ML19295G843; ML19295G846; ML19295G850; ML19295G853; ML19295G855; ML19295G857; ML19295G859; ML19295G863; ML19295G866; ML19295G870; ZS-2019-0090, Revised Final Status Survey (FSS) Report - Phase 2, Release Record - Waste Water Treatment Facility Survey Unit 09100;
References
	ZS-2019-0090
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ZION STATION RESTORATION PROJECT FINAL STATUS SURVEY RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 PREPARED BY / DATE: ______________________________________2019-09-01 Patsy Giza Radiological Engineer REVIEWED BY / DATE: ______________________________________2019-09-01 David Montt Radiological Engineer APPROVED BY / DATE: ______________________________________2019-09-01 D. Wojtkowiak, C/LT Manager

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

................................................................................................ 5

2. SURVEY UNIT DESCRIPTION ...................................................................................... 6

3. CLASSIFICATION BASIS ............................................................................................... 6

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

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

6. SURVEY IMPLEMENTATION .................................................................................... 16

7. SURVEY RESULTS ........................................................................................................ 17

8. QUALITY CONTROL .................................................................................................... 22

9. INVESTIGATION AND RESULTS .............................................................................. 22

10. REMEDIATION AND RESULTS.................................................................................. 22

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN ...................................... 23

12. DATA QUALITY ASSESSMENT (DQA) ..................................................................... 23

13. ANOMALIES ................................................................................................................... 23

14. CONCLUSION ................................................................................................................. 23

15. REFERENCES ................................................................................................................. 24

16. ATTACHMENTS ............................................................................................................. 25 ATTACHMENT 1 FIGURES AND MAPS .......................................................................26 ATTACHMENT 2 ISOCS GEOMETRY ...........................................................................29 ATTACHMENT 3 QC MEASUREMENT ASSESSMENTS ...........................................40 ATTACHMENT 4 ISOCS ANALYTICAL REPORTS ....................................................42 ATTACHMENT 5 EBERLINE REPORTS .......................................................................56 323

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 LIST OF FIGURES Figure 1 - Unit 1 Diesel Fuel Oil Storage Tank Room ................................................................... 6 Figure 2 - Unit 1 Diesel Fuel Oil Storage Tank Room ISOCS Survey and Sample Map ............ 20 Figure 3 - Overview of Structural Survey Unit ............................................................................ 27 LIST OF TABLES Table 1 - Dose Significant Radionuclides and Mixture .................................................................. 8 Table 2 - Base Case DCGLs (DCGLB) from LTP Chapter 5, Table 5-3 ..................................... 10 Table 3 - Operational DCGLs (DCGLB) from LTP Chapter 5, Table 5-4 .................................. 11 Table 4 - Surrogate Ratios ............................................................................................................ 13 Table 5 - Investigation Levels....................................................................................................... 14 Table 6 - Synopsis of the Survey Design ...................................................................................... 15 Table 7 - Unit 1 Diesel Fuel Oil Storage Tank Room- Measured Concentrations of ROC for FSS ............................................................................................................ 18 Table 8 - Diesel Fuel Oil Storage Tank Room Statistical Quantities ........................................... 21 Table 9 - Summary of ISOCS Replicate Measurements for QC .................................................. 21 Table 10 - Summary of FSS Concrete Core Analysis by Eberline ............................................... 22

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

1. EXECUTIVE

SUMMARY

This Final Status Survey (FSS) Release Record for survey unit 06201, Unit 1 Diesel Fuel Oil Storage Tank Room, 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).

The FSS Sample Plan #B1-06201AF was developed in accordance with ZionSolutions procedure ZS-LT-300-001-001, Final Status Survey Package Development (Reference

3) the ZSRP LTP, and guidance from NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) (Reference 4).

In April of 2016, an FSS was conducted on the Turbine Building basement structure.

The sample plan design for the FSS of the Turbine Building did not include the surface area of the Unit 1 or Unit 2 Diesel Fuel Oil Storage Tank Rooms. A separate sample plan was written to include fifty-one (51) judgmental measurements to represent the surface area of the Diesel Fuel Oil Storage Tank Room. The weighted average of the judgmental ISOCS measurements was added to the systematic mean of the Turbine Building basement.

In accordance with ZSRP LTP Chapter 5, section 5.5.2.1.2 and Table 5-19, the Turbine Building survey unit has a MARSSIM classification of 3. The Diesel Fuel Oil Storage Tank Room was re-classified as a Class 1 due to it becoming a pathway for radioactive waste removed from the Auxiliary Building during decommissioning.

Final Status Survey was performed on the Diesel Oil rooms to demonstrate that the concentrations of residual radioactivity were equal to or below site-specific Derived Concentration Guideline Levels (DCGL) corresponding to the dose criterion in 10 CFR 20.1402. The Diesel Fuel Oil Storage Tank Room has a MARSSIM Classification of 1. A Sample Plan was designed based upon use of the Sign Test as the nonparametric statistical test for compliance. Both the Type I () and Type II ()

decision error rates were set at 0.05. The Canberra In Situ Object Counting System (ISOCS) was selected as the primary instrument used to perform FSS. To ensure 100%

of the surface area was surveyed in accordance with the classification, fifty-one (51)

ISOCS measurement locations were selected using several adjusted Field-of-View (FOV) geometrys as specified in ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures (Reference 5).

The results of the 51 ISOCS judgmental measurement results showed that the Sum-of-Fractions (SOF) for each measurement was less than one (1) when applying the respective Operational Derived Concentration Guideline Levels (OpDCGL) for the

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Turbine Building Basement from ZionSolutions TSD 17-004, Operational Derived Concentration Guideline Levels for Final Status Survey (Reference 6). Therefore, the null hypothesis is rejected and the Unit 1 Diesel Fuel Oil Storage Tank Room is acceptable for unrestricted release.

2. SURVEY UNIT DESCRIPTION Unit 1 Diesel Fuel Oil Storage Tank Room was located on the 570 foot elevation and housed the oil for the Unit 1 Diesel Generator. The rooms were adjacent to the Turbine Building on the West side of the G (Column) Wall which divided the Turbine Building and Auxiliary Building. The entrance into the Unit 1 Diesel Fuel Oil room was from the Steam Tunnel stair wells from elevation 592 of the TB to the 570 foot elevation. (See Figure 1) The area of this structural survey unit is estimated at approximately 813 m2.

Figure 1 - Unit 1 Diesel Fuel Oil Storage Tank Room

3. CLASSIFICATION BASIS The Turbine Building basement (survey unit 06100) was classified in accordance with ZionSolutions procedure ZS-LT-300-001-002, Survey Unit Classification (Reference 7). The Diesel Fuel Oil Storage Tank Room is part of the Turbine Building basement survey unit. The Turbine Building was classified as a mixture of Class 2 and Class 3 structural survey units in accordance with the Zion Station Historical Site Assessment (HSA) (Reference 8). In LTP Chapter 5, section 5.5.2, it states that the survey units designated for structures below 588 foot elevation from the HSA that were presented in LTP Chapter 2, Table 2-2 were based on screening values and source term assumptions

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 that are significantly different from the Basement Fill Model (BFM) and are therefore not applicable. LTP Chapter 5, section 5.5.2.1.1 states that the FSS units for the basements of the Turbine Building, the Crib House/Forebay and the Circulating Water Discharge Tunnels are designated as Class 3 as defined in MARSSIM section 2.2 in that the FSS units are not expected to contain any residual radioactivity, or are expected to contain levels of residual radioactivity at a small fraction of the DCGLs, based on site operating history and previous radiation surveys.

During decommissioning, the primary pathway into and out of the basement of the Auxiliary Building became the Unit 1 and Unit 2 570 foot elevation Diesel Fuel Oil floors. Ramps were constructed through each into the 542 foot elevation to allow for the transit of heavy equipment and removal of radioactive commodities. Due to the introduction of radioactive material into both of these areas, they were reclassified as Class 1 survey units in accordance with ZS-LT-300-001-002.

The FSS Radiological Engineer (RE) performed a visual inspection and walk-down of the survey unit on 05/30/2018 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 in accordance with procedure ZS-LT-300-001-002 as part of the survey design for FSS.

4. DATA QUALITY OBJECTIVES (DQO)

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

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

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

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 The primary objective of the FSS sample plan is to demonstrate that the level of residual radioactivity in survey unit 06201 did not exceed the release criteria specified in the LTP and that the potential dose from residual radioactivity is As Low As Reasonably Achievable (ALARA).

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

LTP Chapter 6, section 6.5.2 discusses the process used to derive the ROC for the decommissioning of ZNPS, including the elimination of insignificant dose contributors (IC) from the initial suite. LTP section 6.5.2 also states that the Auxiliary Basement ROC and the IC percentage of 5% for adjusting ROC DCGLs will also be applied to all other basements including the Diesel Fuel Oil Storage Tank Room unless different values are justified by the results of continuing characterization or FSS HTD analysis. Table 1 presents the ROC for the Auxiliary Basement and, therefore, the Diesel Fuel Oil Storage Tank Room structural surfaces and the normalized fractions based on the radionuclide mixture.

Table 1 - Dose Significant Radionuclides and Mixture

% of Total Activity Radionuclide (normalized)(1)

Co-60 0.92%

Cs-134 0.01%

Cs-137 75.32%

Ni-63 23.71%

Sr-90 0.05%

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

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

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 The End State basements will be comprised of steel and/or concrete structures which will be covered by at least three feet of clean soil and physically altered to a condition which would not realistically allow the remaining structures, if excavated, to be occupied. The exposure pathways in the BFM are associated with residual radioactivity in floors and walls released through leaching into water contained in the interstitial spaces of the fill material. The BFM assumes that the inventory of residual radioactivity in a given building is released either instantly or over time by diffusion, depending on whether the activity is surficial or volumetric, respectively. The activity released into the fill water will adsorb onto the clean fill, as a function of the radionuclide-specific distribution coefficients, resulting in equilibrium concentrations between the fill and the water.

Consequently, the only potential exposure pathways after backfill, assuming the as-left geometry, are associated with the residual radioactivity in the water contained in the fill.

The final outputs of the BFM are the Basement Derived Concentration Guideline Levels (DCGL), in units of pCi/m2, which are calculated using the BFM Groundwater (GW) and BFM Drilling Spoils Dose Factors (LTP Chapter 6, Tables 6-24 and 6-25). The DCGLs for basement structure surfaces are calculated separately for the GW and Drilling Spoils scenarios and for the summation of both scenarios. The summation DCGL is designated as the Base Case DCGL (BcDCGL) and is used during FSS to demonstrate compliance (analogous to the DCGLW as defined in MARSSIM). The BcDCGLs are radionuclide-specific concentrations that represent the 10 CFR 20.1402 dose criterion of 25 mrem/year and are calculated for each ROC and each backfilled basement.

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

The BcDCGLs for the unrestricted release of the Turbine Building (including the Diesel Fuel Oil Storage Tank Rooms) are provided in Table 2. The IC dose percentage of 5%

was used to adjust the Turbine Building BcDCGLs to account for the dose from the eliminated IC radionuclides.

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Table 2 - Base Case DCGLs (BcDCGLB) from LTP Chapter 5, Table 5-3 Turbine Building Radionuclide BcDCGLB (pCi/m2)

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

Instrument DQOs included a verification of the ability of the survey instrument to detect the radiation(s) of interest relative to the OpDCGL. The Canberra ISOCS was selected as the primary instrument used to perform FSS of basement surfaces. Response checks were required prior to issuance and after each use. Control and accountability of ISOCS units was required to assure data quality.

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Table 3 - Operational DCGLs (OpDCGLB) from LTP Chapter 5, Table 5-4 Turbine Building Radionuclide OpDCGLB (pCi/m2)

Co-60 5.98E+06 Ni-63 1.85E+08 Sr-90 6.58E+04 Cs-134 1.35E+06 Cs-137 1.79E+06 As part of the DQOs applied to laboratory processes, analysis results were reported as actual calculated results. The actual recorded value was used as the recorded FSS result for measurement and/or sample values that are less than MDC. Negative values were recorded as zero. For radionuclides less than MDC, the value representing the highest abundance was selected. Results were not reported as less than MDC. Sample report summaries included unique sample identification, analytical method, radionuclide, result, uncertainty, laboratory data qualifiers, units, and the observed MDC.

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

5. SURVEY DESIGN Guidance for preparing FSS plans was provided in procedure ZS-LT-300-001-001 Final Status Survey Package Development. The Canberra ISOCS was selected as the primary instrument for performing FSS of basement surfaces. The ISOCS was selected as the instrument of choice to perform FSS of basement surfaces due to the fact that an ISOCS measurement will provide results that can be used directly to determine total activity with depth in concrete and, the surface area covered by a single ISOCS measurement is large (a nominal FOV of 10-30 m2) which essentially eliminates the need for a scan surveys.

In addition, after an ISOCS measurement is collected, it can be tested against a variety of geometry assumptions to address uncertainty in the source term geometry if necessary.

The source term geometry for ISOCS efficiency calibration, i.e., concentration depth profile and areal distribution of the residual radioactivity in structures, is required to generate efficiency curves (i.e., efficiency as a function of energy) for the ISOCS gamma spectroscopy measurements. The basis for the chosen ISOCS efficiency calibrations for the FSS of the Diesel Fuel Oil Storage Tank Rooms concrete are documented in

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 ZionSolutions TSD 14-022. Several different ISOCS geometries were developed for the Diesel Fuel Oil Storage Tank Rooms that ranged from a Field of View (FOV) of 50.3 m2 to a FOV of 7.06 m2. The basis for the selection of this latter geometry was the result of accessibility into open door frames with limited space.

LTP Chapter 5, section 5.5.2.1.1 states that the FSS units for the basements of the Turbine Building, the Crib House/Forebay and the Circulating Water Discharge Tunnels are designated as Class 3. During decommissioning, the primary pathway into and out of the basement of the Auxiliary Building became the Unit 1 and Unit 2 570 foot elevation Diesel Fuel Oil floors. Due to the introduction of radioactive material into both of these areas, they were reclassified as Class 1 survey units in accordance with ZS-LT-300-001-002. Consequently, the weighted average of the judgmental ISOCS measurements will be added to the systematic mean of the Turbine Building basement FSS. This is addressed in LTP Chapter 5, section 5.5.6.1. In accordance with TSD 14-014, End State Surface Areas, Volumes, and Source Terms of Ancillary Buildings (Reference 10), the total surface area of the Diesel Fuel Oil Storage Tank Room is 813 m2 .

The area-weighted SOF is calculated in accordance with LTP Chapter 5, Equation 5-8, which is reproduced as follows. The SOFBi,B variable in the equation is based on the mean of the judgmental samples.

Equation 1

, = ,

=1 where:

SOFB,B = total surface SOF including all surface survey units in basement (B)

SASUi,B = surface area of survey unit (i) in basement (B)

SAAdjust,B = adjusted surface area for DCGL calculation (Table 5-23) for basement (B)

SOFBi,B = SOFB for survey unit (i) in basement (B)

The sample plan for the Unit 1 Diesel Fuel Oil Storage Tank Room consisted of fifty-one (51) judgmental locations, to capture 100% of the surface area. Attachment 1, Figures and Maps, illustrates the locations of the ISOCS measurements taken.

The DQO process determined that Co-60, Ni-63, Sr-90, Cs-134, Cs-137 would be the ROC in survey unit 06202. During FSS, concentrations for Hard-to-Detect (HTD) ROC Ni-63 and Sr-90 are inferred using a surrogate approach specified in LTP section 5.2.11.

Cs-137 is the principle surrogate radionuclide for Sr-90 and Co-60 is the principle

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 surrogate radionuclide for Ni-63. The mean, maximum and 95% Upper Confidence Level (UCL) of the surrogate ratios were calculated in TSD 14-019 , Radionuclides of Concern for Soil and Basement Fill Model Source Terms (Reference 11) and are presented in LTP Chapter 5, Table 5-15, which is reproduced in Table 4 below.

Table 4 - Surrogate Ratios Auxiliary Building Ratios Mean Max 95%UCL Ni-63/Co-60 44.143 180.450 154.632 Sr-90/Cs-137 0.001 0.002 0.002 For the FSS of survey unit 06201, the surrogate OpDCGLs for Co-60 and Cs-137 are based on the maximum ratios from Table 4.

Equation 2 1

=

1 2 3

+ + +

2 3 Where: DCGLSur = Surrogate radionuclide DCGL DCGL2,3n = DCGL for radionuclides to be represented by the surrogate Rn = Ratio of concentration (or nuclide mixture fraction) of radionuclide n to surrogate radionuclide Using the OpDCGLs for the Turbine Building presented in Table 3 and the maximum ratios from Table 4, the following surrogate calculations were performed for FSS unit 06201; Equation 3 1

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

+

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

The surrogate OpDCGL that was used for Cs-137 in FSS unit 06201 for direct comparison of sample results to demonstrate compliance is 1.70E+06 Ci/m2.

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Equation 4 1

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

+

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

The surrogate OpDCGL that was used for Co-60 in FSS unit 06201 for direct comparison of sample results to demonstrate compliance is 8.75E+05 Ci/m2.

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

Table 5 - Investigation Levels Classification Direct Investigation Levels Class 1 >Operational DCGLW In compliance with ZS-LT-01, Quality Assurance Project Plan (for Characterization and FSS) (QAPP) (Reference 12), replicate measurements were to be performed on 5%

of the static measurement locations.

Table 6 provides a synopsis of the survey design for survey unit 06201.

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Table 6 - Synopsis of the Survey Design FEATURE DESIGN CRITERIA BASIS Survey Unit Area 813 m2 TSD-14-014

= 0.3

UBGR = SOF of 1

LBGR = SOF of 0.5 Number of Static 51 (judgmental)

Type I error = 0.05 Measurements

Type II error = 0.05

/ = 3 (adjusted)

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

Co 5.98E+06 pCi/m2

Cs-134 - 1.35E+06 pCi/m2 Operational DCGLs for Turbine Building Basement OpDCGLB

Cs-137 - 1.79E+06 pCi/m2 Unit 1 Diesel Fuel Oil Storage Tank

Ni 1.85E+08 pCi/m2 Rooms , (LTP Chapter 5, Table 5-4)

Sr 6.58E+04 pCi/m2 2 Concrete Core samples selected for HTD HTD ROC Analysis (LTP Chapter 5, section 5.1)

ROC analysis Measurement

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

Investigation Level Scan Survey Area ZS-LT-300-001-001, 813 m2 100% areal scan coverage Coverage Attachment 4 QC 5% Duplicate ISOCS Measurements (LTP Chapter 5, section 5.9)

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

6. SURVEY IMPLEMENTATION For the judgmental measurements performed in this survey unit 06201, compliance with the unrestricted release criteria was demonstrated through a combination of direct measurements using the ISOCS and analysis of concrete core samples obtained from the Diesel Fuel Oil Storage Tank Room. The concrete core data was used to validate the ratios of gamma emitters to HTD ROC.

A walk down was performed by FSS personnel on 05/30/18. A turnover survey was not required to accept the Diesel Fuel Oil Storage Tank Room survey unit for FSS as the implementation of the continuous characterization survey provided sufficient information pertaining to the radiological condition. The continuing characterization surveys included smears for loose surface contamination, eight (8) concrete core samples and several biased ISOCS measurements in suspect areas. All smear results were less than 1,000 dpm/100 cm2 and all ISOCS measurements indicated sum of fractions (OpSOF) of less than one when compared against the OpDCGLs. The Diesel Fuel Oil Storage Tank Room was deemed acceptable for turnover and FSS commenced on 06/01/18.

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

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

All ISOCS measurements were acquired using approved geometries. Various sources to detector distances were utilized due to space constraints and to ensure 100%

measurement coverage.

The ISOCS detector was positioned horizontally or vertically to the surface at the center-point of each selected measurement location. In most cases, the exposed face of the detector was positioned at a distance of 4 meters from the surface with the 90-degree collimation shield installed; this orientation corresponded to a nominal FOV of 50.3 m2, respectively. As necessary, the detector to source distance and subsequent FOV was reduced to accommodate physical constraints or obstructions while the number of measurements increased to ensure 100% areal coverage was achieved.

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

Background was not subtracted from any measurement. An OpSOF calculation was performed for each measurement by dividing the reported concentration of each ROC by

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 the OpDCGL for each ROC to derive an individual ROC fraction. The individual ROC fractions were then summed to provide a total OpSOF value for the measurement.

Three (3) duplicate measurements were taken with the ISOCS on the Diesel Fuel Oil Storage Tank Room concrete during FSS. The locations selected for taking duplicate measurements were at locations 002, 025 and 046. These locations were randomly selected using the Microsoft Excel RANDBETWEEN function. The number of replicate measurements satisfies the requirement that a minimum of 5% percent of the number of measurements that will be used for duplicate samples in accordance with the QAPP.

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

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

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

As previously stated, as the extent of this survey was the acquisition of judgmental measurements at biased locations, compliance was demonstrated by direct comparison of each measurement result to the release criterion. For building surfaces, areas of elevated activity were defined as any area identified by measurement/sample (systematic or judgmental) that exceeded the OpDCGL but was less than the BcDCGL. Any area that exceeded the BcDCGL would have required remediation. This was not the case for the FSS of the Unit 1 Diesel Fuel Oil Storage Room. All measurements taken, when compared against the OpDCGL was less than an OpSOF of one. The ISOCS measured concentration results from the Unit 1 Diesel Fuel Oil Storage are listed in Table 7. Table 8 presents the mean concentration of the judgmental measurements and the Base Case SOF (BcSOF) when compared against BcDCGL.

The sample population consisted of fifty-one (51) direct measurements that were acquired using the ISOCS. The concentrations for Ni-63 and Sr-90 are inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15. The complete ISOCS gamma spectroscopy reports are presented in Attachment 4.

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Table 7 - Unit 1 Diesel Fuel Oil Storage Tank Room- Measured Concentrations of ROC for FSS Co-60 Ni-63(1) Sr-90(1) Cs-134 Cs-137 MEASUREMENT ID OpSOF(2)

(pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-06201A-FSFC-001-GD 8.67E+03 1.56E+06 0.00E+00 6.06E+04 0.00E+00 0.055 B1-06201A-FSFC-002-GD 3.20E+04 5.77E+06 0.00E+00 3.36E+04 0.00E+00 0.061 B1-06201A-FSFC-003-GD 2.37E+04 4.28E+06 2.70E+01 2.63E+04 1.35E+04 0.055 B1-06201A-FSFC-004-GD 0.00E+00 0.00E+00 1.93E+01 5.23E+04 9.65E+03 0.044 B1-06201A-FSFC-005-GD 0.00E+00 0.00E+00 0.00E+00 5.04E+04 0.00E+00 0.037 B1-06201A-FSFC-006-GD 2.25E+04 4.06E+06 0.00E+00 6.19E+04 0.00E+00 0.072 B1-06201A-FSFC-007-GD 1.51E+03 2.72E+05 1.35E+01 2.69E+03 6.74E+03 0.008 B1-06201A-FSFC-008-GD 1.31E+04 2.36E+06 6.00E+01 4.47E+03 3.00E+04 0.036 B1-06201A-FSFC-009-GD 1.52E+04 2.74E+06 5.90E+01 3.51E+04 2.95E+04 0.061 B1-06201A-FSFC-010-GD 1.20E+04 2.17E+06 2.08E+01 6.83E+03 1.04E+04 0.025 B1-06201A-FSFC-011-GD 0.00E+00 0.00E+00 7.44E+01 6.91E+04 3.72E+04 0.073 B1-06201A-FSFC-012-GD 1.14E+04 2.06E+06 0.00E+00 5.18E+04 0.00E+00 0.051 B1-06201A-FSFC-013-GD 1.54E+04 2.78E+06 5.42E+01 5.75E+04 2.71E+04 0.076 B1-06201A-FSFC-014-GD 2.25E+04 4.06E+06 1.71E+00 3.02E+04 8.54E+02 0.049 B1-06201A-FSFC-015-GD 6.42E+03 1.16E+06 0.00E+00 4.38E+04 0.00E+00 0.040 B1-06201A-FSFC-016-GD 6.69E+03 1.21E+06 2.52E+01 4.72E+04 1.26E+04 0.050 B1-06201A-FSFC-017-GD 3.64E+04 6.57E+06 0.00E+00 5.12E+04 0.00E+00 0.080 B1-06201A-FSFC-018-GD 0.00E+00 0.00E+00 0.00E+00 2.47E+04 0.00E+00 0.018 B1-06201A-FSFC-019-GD 0.00E+00 0.00E+00 1.67E+01 6.88E+04 8.37E+03 0.056 B1-06201A-FSFC-020-GD 6.74E+03 1.22E+06 2.16E+01 0.00E+00 1.08E+04 0.014 B1-06201A-FSFC-021-GD 0.00E+00 2.16E+01 0.00E+00 1.08E+04 2.13E+04 0.024 B1-06201A-FSFC-022-GD 0.00E+00 0.00E+00 0.00E+00 2.13E+04 0.00E+00 0.063 B1-06201A-FSFC-023-GD 0.00E+00 0.00E+00 0.00E+00 9.07E+03 0.00E+00 0.039 B1-06201A-FSFC-024-GD 0.00E+00 7.52E+01 0.00E+00 3.76E+04 1.07E+04 0.064 B1-06201A-FSFC-025-GD 2.37E+04 4.28E+06 3.30E+02 0.00E+00 1.65E+05 0.124 B1-06201A-FSFC-026-GD 2.68E+03 4.84E+05 4.62E+01 3.57E+03 2.31E+04 0.019 B1-06201A-FSFC-027-GD 1.26E+04 2.27E+06 1.61E+02 1.61E+04 8.05E+04 0.074 B1-06201A-FSFC-028-GD 2.07E+03 3.74E+05 5.62E+02 1.27E+04 2.81E+05 0.177 B1-06201A-FSWC-029-GD 0.00E+00 0.00E+00 9.34E+01 3.38E+04 4.67E+04 0.053 B1-06201A-FSWC-030-GD 0.00E+00 0.00E+00 0.00E+00 6.17E+04 0.00E+00 0.046 B1-06201A-FSWC-031-GD 0.00E+00 0.00E+00 4.96E+01 1.81E+04 2.48E+04 0.028 B1-06201A-FSWC-032-GD 0.00E+00 0.00E+00 0.00E+00 1.04E+04 0.00E+00 0.008 B1-06201A-FSWC-033-GD 1.07E+04 1.93E+06 0.00E+00 1.81E+04 0.00E+00 0.026 B1-06201A-FSWC-034-GD 1.55E+04 2.80E+06 0.00E+00 5.83E+04 0.00E+00 0.061 B1-06201A-FSWC-035-GD 2.05E+04 3.70E+06 7.34E+01 4.71E+04 3.67E+04 0.080 B1-06201A-FSWC-036-GD 1.69E+04 3.05E+06 1.88E+01 5.95E+03 9.42E+03 0.029

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Table 7 (continued) - Unit 1 Diesel Fuel Oil Storage Tank Room - Measured Concentrations of ROC for FSS Co-60 Ni-63(1) Sr-90(1) Cs-134 Cs-137 MEASUREMENT ID OpSOF(2)

(pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-06201A-FSWC-037-GD 2.56E+04 4.62E+06 0.00E+00 4.86E+04 0.00E+00 0.065 B1-06201A-FSWC-038-GD 1.67E+04 3.01E+06 5.98E+01 4.06E+04 2.99E+04 0.067 B1-06201A-FSWC-039-GD 2.32E+04 4.19E+06 7.00E+01 5.19E+04 3.50E+04 0.086 B1-06201A-FSWC-040-GD 1.71E+03 3.09E+05 2.54E+01 6.65E+04 1.27E+04 0.059 B1-06201A-FSWC-041-GD 9.72E+03 1.75E+06 3.90E+01 3.95E+04 1.95E+04 0.052 B1-06201A-FSWC-042-GD 1.67E+04 3.01E+06 4.42E+01 4.34E+04 2.21E+04 0.064 B1-06201A-FSWC-043-GD 3.79E+04 6.84E+06 5.82E+01 1.68E+04 2.91E+04 0.073 B1-06201A-FSWC-044-GD 1.12E+04 2.02E+06 6.48E+01 0.00E+00 3.24E+04 0.032 B1-06201A-FSWC-045-GD 1.46E+04 2.63E+06 1.63E+02 0.00E+00 8.13E+04 0.065 B1-06201A-FSWC-046-GD 6.99E+03 1.26E+06 6.26E+01 2.23E+04 3.13E+04 0.043 B1-06201A-FSWC-047-GD 1.11E+04 2.00E+06 4.44E+02 2.57E+04 2.22E+05 0.162 B1-06201A-FSWC-048-GD 2.10E+04 3.79E+06 2.24E+01 2.43E+04 1.12E+04 0.049 B1-06201A-FSWC-049-GD 1.78E+04 3.21E+06 0.00E+00 8.29E+03 0.00E+00 0.026 B1-06201A-FSWC-050-GD 3.20E+03 5.77E+05 8.24E+00 4.12E+03 4.12E+03 0.009 B1-06201A-FSWC-051-GD 4.88E+03 8.81E+05 3.30E+01 0.00E+00 1.65E+04 0.015 (1) Inferred concentration (2) Compared against OpDCGL Direct measurement locations were denoted on the concrete surfaces of the Diesel Fuel Oil Storage Tank Room by marking an approximate 4 meter by 4 meter grid pattern using a random start point that was overlaid over the exposed surface, providing sufficient overlap between locations to ensure 100% areal coverage. ISOCS measurement locations are shown below in Figure 2 as well as in Attachment 1.

[19]

FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Figure 2 - Unit 1 Diesel Fuel Oil Storage Tank Room ISOCS Survey and Sample Map

[20]

FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Table 8 - Diesel Fuel Oil Storage Tank Room Statistical Quantities INDIVIDUAL MEASUREMENT METRICS Total Number of Judgmental Measurements = 51 Number of Quality Control Measurements = 3 Total Number of Measurements = 54 Mean Measurement OpSOF = 0.054 Max Judgmental Measurement OpSOF = 0.177 Number of Judgmental Measurements with SOF > = 1 = 0 STATISTICAL QUANTITIES AVG MEAN MEDIAN MAX MIN BcDCGL AVG STD DOSE ROC SOF PER DEV. PER (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2) ROC ROC Co-60 1.17E+04 1.20E+04 3.20E+04 0.00E+00 1.10E+04 7.03E+07 0.000 0.004 Ni-63 2.11E+06 2.17E+06 5.77E+06 0.00E+00 1.99E+06 2.18E+09 0.001 0.024 Sr-90 2.49E+01 1.93E+01 7.44E+01 0.00E+00 2.74E+01 7.74E+05 0.000 0.001 Cs-134 3.67E+04 3.51E+04 6.91E+04 2.69E+03 2.43E+04 1.59E+07 0.002 0.058 Cs-137 1.25E+04 9.65E+03 3.72E+04 0.00E+00 1.37E+04 2.11E+07 0.001 0.015 Mean BcSOF for Survey Unit = 0.004 Dose (based on Mean BcSOF) = 0.102 mrem/yr The implementation of required QC measures included the collection of 3 additional ISOCS measurements in the Diesel Fuel Oil Storage Tank Room for replicate measurement analysis. The concentrations for Ni-63 and Sr-90 are inferred based on the maximum ratios as specified in LTP Chapter 5, Table 5-15. The replicate ISOCS measurement results are provided in Table 9 below.

Table 9 - Summary of ISOCS Replicate Measurements for QC Co-60 Ni-63(1) Sr-90(1) Cs-134 Cs-137 MEASUREMENT ID SOF(2)

(pCi/m ) (pCi/m ) (pCi/m2) (pCi/m2) (pCi/m2) 2 2 B106201A-FQFC-002-GD 1.44E+04 2.60E+06 1.16E+02 4.96E+04 5.78E+04 0.087 B106201A-FQFC-025-GD 1.86E+04 3.36E+06 3.26E+02 0.00E+00 1.63E+05 0.117 B106201A-FQWC-046-GD 2.75E+04 4.96E+06 7.12E+01 1.90E+04 3.56E+04 0.066 (1) Inferred concentration (2) Compared against OpDCGL Five (5) concrete core samples were acquired at 10% of the locations where ISOCS measurements were collected with the locations selected at random. Only HTD radionuclides included as ROC (Ni-63 and Sr-90) were analyzed in the FSS confirmatory samples. The top 1/2 inch puck from each of the five concrete core samples, representing

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 the concrete from the exposed surface to a depth of 1/2 inch was analyzed by the on-site gamma spectroscopy system. Of the five (5) samples, there was no indication of plant derived radionuclides at concentrations greater than MDC. Two (2) samples were selected at random and sent to Eberline Laboratory for analysis of HTD ROC (Ni-63 and Sr-90). The analysis results indicated positive concentration of Ni-63 in sample B1-06201A-FSWC-024-CV. No other activity for any of the ROC at concentrations greater than MDC was detected in the samples. No further action or analysis was performed.

The results of the Eberline analysis are presented in Table 10 below.

Table 10 - Summary of FSS Concrete Core Analysis by Eberline B1-06201A-FSWC-027-CV ROC Result Uncertainty MDC Co-60 4.12E-02 8.87E-02 1.61E-01 Ni-63 0.00E+00 1.26E+00 2.19E+00 Sr-90 1.05E-01 4.75E-01 8.37E-01 Cs-134 0.00E+00 6.38E-02 1.46E-01 Cs-137 1.98E-01 1.41E-01 2.18E-01 B1-06201A-FSWC-024-CV ROC Result Uncertainty MDC Co-60 5.00E-02 1.58E-01 2.87E-01 Ni-63 2.14E+02 3.30E+00 1.80E+00 Sr-90 0.00E+00 4.19E-01 7.55E-01 Cs-134 7.29E-02 1.19E-01 3.17E-01 Cs-137 5.59E-02 2.21E-01 3.21E-01

8. QUALITY CONTROL The implementation of required QC measures included the collection of three additional ISOCS measurements in (survey unit 06201) for replicate measurement analysis. The complete ISOCS gamma spectroscopy reports for the replicate measurements are presented in Attachment 4. All replicate ISOCS measurements met the required acceptance criteria. The completed Replicate Sample Assessment Forms are included in Attachment 3 of this Release Record.

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

10. REMEDIATION AND RESULTS No remediation was required prior to performance of FSS.

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

11. CHANGES FROM THE FINAL STATUS SURVEY PLAN There were no addendums to the FSS plan, however, there were changes to the ISOCS survey plans as noted earlier in this Release Record. Those changes were required due to structural interferences restricting placement of ISOCS detectors that were not obvious when the FSS plan was first written. The changes in ISOCS measurement locations were made to ensure 100% areal coverage of the survey unit.

12. DATA QUALITY ASSESSMENT (DQA)

In accordance with procedure ZS-LT-300-001-004, Final Status Survey Data Assessment (Reference 13), the DQOs, sample design, and data were reviewed for completeness, accuracy, and consistency. Documentation was complete and legible. The FSS unit was properly classified as Class 1. All measurement results were individually reviewed and validated. The FOV for the number of measurements ensured 100% areal coverage of the exposed structural surfaces. The instrumentation used to perform the FSS were in calibration, capable of detecting the activity with an adequate MDC and successfully response checked prior to and following use. An adequate number of replicate measurements were taken and the results meet the acceptance criteria as specified in the QAPP.

The analytical results of the fifty-one (51) judgmental measurements were less than an OpSOF of one.

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

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

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

14. CONCLUSION Fifty-one (51) judgmental measurements were taken in Unit 1 Diesel Fuel Oil Storage Tank Room. The FOV of each measurement included the floor and three walls. The total surface area is 813 m2. The FOV for the Circular Plan geometry used for the majority of the ISOCS measurements was 28 m2, which equated to an areal coverage 100% of the surface area of the remaining Diesel Fuel Oil Storage Tank Room.

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 All of the measurements were below an OpSOF of one. The mean BcSOF for the survey unit was 0.004, which equates to a dose of 0.102 mrem/yr. The requirements for a Class 1 survey unit have been met.

Survey unit 06201 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, Multi-Agency Radiation Survey and Site Investigation Manual

5. ZionSolutions TSD 14-022, Use of In-Situ Gamma Spectroscopy for Final Status Survey of End State Structures

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

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

8. Zion Station Historical Site Assessment

9. ZionSolutions TSD 11-001, Technical Support Document for Potential Radionuclides of Concern During the Decommissioning of Zion Station

10. ZionSolutions TSD 14-014, End State Surface Areas, Volumes, and Source Terms of Ancillary Buildings

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

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

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

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

16. ATTACHMENTS Attachment 1 - Figure and Maps Attachment 2 - ISOCS Geometry Attachment 3 - QC Measurement Assessment Attachment 4 - ISOCS Analytical Report Attachment 5 - Eberline Reports

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ATTACHMENT 1 FIGURES AND MAPS

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Figure 3 - Overview of Structural Survey Unit Auxiliary Building Unit 1 -570ft. elevation Diesel Fuel Oil Storage Unit 2- 570 ft. elevation Tank Room Diesel Fuel Oil Storage Tank Room North

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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ATTACHMENT 2 ISOCS GEOMETRY

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201

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ATTACHMENT 3 QC MEASUREMENT ASSESSMENTS

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FSS RELEASE RECORD UNIT 1 DIESEL FUEL OIL STORAGE TANK ROOM SURVEY UNIT 06201 Replicate Measurement Assessment Survey Unit # 06200 Survey Unit Name Diesel Fuel Oil Storage Room Unit 1 Sample Plan # B1-06201A-F Sample

Description:

Comparison of replicate ISOCS measurements collected from measurement locations 02, 25 and

46. The standard measurements are IDs B1-06201AF-SFC-002-GD, B1-06201AF-SFC-025-GD and B1-06201AF-SWC-046-GD. The comparison measurements are IDs B1-06201AF-QFC-002-GD, B1-06201AF-QFC-025-GD and B1-06201AF-QWC-046-GD.

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

(pCi/m2) (pCi/m2) (pCi/m2) (pCi/m2)

B1-06201AF-SFC-002-GD B1-06201AF-QFC-002-GD 2.37E+0 Cs-137 7.73E+05 3 0.4-2.5 9.68E+05 2.52E+05 0.8 Y 5

B1-06201AF-SFC-025-GD B1-06201AF-QFC-025-GD 3.48E+0 Cs-137 1.65E+05 5 0.5-2.0 1.63E+05 3.36E+04 1.0 Y 4

B1-06201AF-SWC-046-GD B1-06201AF-QWC-046-GD 1.52E+0 Cs-137 3.13E+04 2 0.4-2.5 3.56E+04 1.55E+04 0.9 Y 4

Comments/Corrective Actions: There was acceptable The acceptance criterion for replicate static agreement between the standard measurement and the measurements is as per the following Table.

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

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ATTACHMENT 4 ISOCS ANALYTICAL REPORT

[42]

- - *

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

Filename: 6279 Report Generated On 6/4/2018 3:23:09 PM Sample Title B106201AFSFC001GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/4/2018 3:13:00 PM Acquisition Started 6/4/2018 3:13:07 PM Live Time 600.0 seconds Real Time 600.5 seconds Dead Time 0. 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATAVAUDATED DATE tJ*' ..,,

TIME /235'.

Q, ll,;..

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Peak Analysis Report 6/4/2018 3:23:09 PM Page 2

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Detector Name: 6279 Sample

Title:

Bl06201AFSFC001GD Peak Analysis Performed on: 6/4/2018 3:23:08 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 292- 309 300. 10 74.99 0 .82 l.43E+002 6 1. 68 2.47E+002 2 945- 962 953.60 23 8. 52 0 .81 3.92E+001 3 1 .05 5.98E+001 3 1171- 1188 1179.85 295.13 1. 02 2.75E+001 22.51 2.95E+001 4 1398- 1415 1406.65 35 1 .86 0 .98 3.64E+001 23.18 2.96E+001 5 2324- 2341 2332.68 583.45 0.30 1.12E+001 13.88 1.08E+001 6 2427- 2444 2435.48 609.16 0.90 5.62E+001 17 .70 6.76E+OOO 7 3634- 3651 3642.72 910.92 0. 47 1.65E+001 12.27 6.52E+OOO 8 5833- 5852 5842.57 1460. 36 1. 49 7. 20E+001 18.92 5.00E+OOO M = First peak in a multiplet region m == Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Interference Corrected Activity Report 6/4/2018 3 : 23:09 PM Page 3

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Sample

Title:

B106201AFSFC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M" 2 ) Uncertainty K-40 1 .000 1460.82* 10. 66 8.52797E+005 2.36034E+005 Tl-208 1 .000 583.19* 85.00 9.65150E+003 1.20576E+004 Pb-212 1. 000 238.63* 43.60 3.75533E+004 3.03238E+004 Bi-214 0 .454 609.32* 45.49 9.33312E+004 3.14453E+004 1120 .29 14.92 1764.49 15.30 Pb-214 1 . 000 295.22* 18. 42 7.07792E+004 5.91171E+004 351.93* 35.60 5.43953E+004 3.55788E+004

~ Energy line found i n t he spectrum.

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

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Interference Corrected Activity Report 6/4/2018 3:23:09 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 8.527970E+005 2.360338E+OOS Tl-208 1. 000 9.651499E+003 1. 2 05760E+O 04 Pb-212 1. 000 3.755335E+004 3.032382E+004 Bi-214 0.454 9.333123E+004 3.144526E+004 Pb-214 1. 000 5.875170E+004 3.048384E+004

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

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

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

Peak Locate Performed on: 6/4/2018 3:23:08 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 74.99 2.3832E-001 43.14 7 910.92 2.7464E-002 74.43 Sum M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Nuclide MDA Report 6/4/2018 3:23:09 PM Page s

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

Bl06201AFSFC001GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yie ld Line MDA Nuclide MDA Activity Dec. Level Name (keV) (% ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 1.951E+005 1.95E+005 8.528E+005 8.153E+004 Co-:60 1173.23 99.85 3.021E+004 2.73E+004 -6.663E+003 1.361E+004 1332.49 99.98 2.725E+004 8.673E+003 1.202E+004 Nb- 94 702.65 99.81 2.676E+004 2.68E+004 -1. 750E+004 1.227E+004 8 7 1. 09 99.89 3.316E+004 2.514E+002 1.532E+004 Ag-l08m 433.90 90.50 3.089E+004 2.99E+004 2.079E+004 1 .453E+004 614.30 89.80 4.061E+004 3.985E+004 1.916E+004 722.90 90.80 2.991E+004 -4.601E+002 1.371E+004 Cs-134 604.72 97.62 3.772E+004 3.61E+004 6.063E+004 1.782E+004 795.86 85.46 3.611E+004 1.838E+004 1. 666E+004 Cs-137 661.66 85.10 3.560E+004 3.56E+004 -4.319E+004 1 .654E+004 Eu-152 121. 78 28.67 1.283E+005 1.22E+005 6.585E+003 6.262E+004 344 .28 26.60 1. 217E+005 4.545E+004 5.819E+004 1408.01 21.07 1. 403E+005 5.931E+004 6.227E+004 Eu-154 123.07 40.40 9.094E+004 6.25E+004 4.007E+004 4 .439E+004 723.30 20.06 1. 3 69E+O 05 4.115E+004 6.282E+004 1274.43 34.80 6.254E+004 -1.229E+005 2.677E+004 Eu-155 86.55 30.70 1.516E+005 1 .52E+OOS -l.046E+004 7.433E+004 105.31 21.10 1 .840E+OOS 4.236E+004 8.992E+004

+ Tl-208 583.19* 85.00 1 .964E+004 1.96E+004 9.651E+003 8.652E+003 Bi-212 727.33 6.67 4.220E+005 4 .22E+OOS 1.692E+005 1. 940E+005

+ Pb-212 238.63* 43.60 4 .731E+004 4. 73E+004 3.755E+004 2.236E+004

+ Bi-214 609.32* 45.49 3.015E+004 3.02E+004 9.333E+004 1.283E+004 1120.29 14.92 2.681E+005 8.286E+004 1.243E+OOS 1764.49 15. 30 2.166E+005 l.791E+005 9.556E+004

+ Pb-214 295.22* 18. 42 9.145E+004 5.27E+004 7.078E+004 4.224E+004 351.93* 35.60 5.269E+004 5.440E+004 2.432E+004 Ra-226 186.21 3.64 8.818E+OOS 8.82E+005 -1 .780E+005 4.274E+OOS Ac-228 338.32 11.27 2.574E+005 1 .31E+005 2.607E+004 1.225E+OOS 911. 2 0 25.80 1. 305E+005 3.037E+004 6.025E+004 968.97 15. 80 2.123E+005 -4.329E+004 9.768E+004 Am-241 59.54 35.90 1.470E+005 1.47E+005 1.955E+004 7.184E+004

+ =Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[47]

- - - - GAMMA S P E C T R U M A N A L Y S I S *****

Filename: 6279 Report Generated On 6/5/2018 9:17:02 AM Samp le Title B106201AFSFC002GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/5/2018 9:06:00 AM Acquisition Started 6/5/2018 9:07:00 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibratioh Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATAVAUDA1ED DATE /ii"' 4-lf TIME 1a 3.f 44*1f<'di4

[48]

Peak Analysis Report 6/5/2018 9:17:02 AM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSFC002GD Peak Analysis Performed on: 6/5/2018 9:17 :01 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area . Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 293- 313 301. 01 75.22 0.81 1.06E+002 67.46 2.81E+002 2 1003- 1020 1011 .95 253.12 0.32 1.99E+001 23.47 3.61E+001 3 1171- 1188 1179.43 295.02 0.88 2.68E+001 24 .13 3.62E+001 4 1398- 1415 1406.07 351.72 1.20 5.82E+001 20.97 1.58E+001 5 2321- 2338 2329.25 582.60 0.73 2.09E+001 15.09 1. llE+OOl 6 2426- 2443 2434.19 608.84 0.34 4.30E+001 17.75 1. lOE+OOl 7 5831- 5850 5840.68 1459.89 0.41 6.54E+001 19.25 7.64E+OOO M = Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2.000 sigma

[49]

Interference Corrected Activity Report 6/5/2018 9: 17 :02 AM Page 3

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Sample

Title:

B106201AFSFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertainty K-40 0 .999 1460.82* 10.66 7.73970E+005 2.37625E+005 Tl-208 0.999 583.19* 85. 00 l .80722E+004 1 .32173E+004 Bi-214 0.454 609.32* 45.49 7.12615E+004 3.06613E+004 1120.29 14 .92 1764.49 15. 30 Pb-214 1 . 000 295.22* 18.42 6.90139E+004 6.31396E+004 351. 93* 35.60 8.68714E+004 3.39181E+004

~ Energy line found in the spectrum.

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

[50]

Interference Corrected Activity Report 6/5/2018 9 : 17:02 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2) Uncertainty K-40 0.999 7.739696E+005 2.376249E+005 Tl-208 0.999 1. 807221E+004 1. 321731E+004 Bi-214 0.454 7.126147E+004 3.066128E+004 Pb-214 1.000 8.287220E+004 2.987972E+004

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

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

- - - - UN I D E N T I F I E D P E AK S **********

Peak Locate Performed on: 6/5/2018 9:17: 01 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.22 l.7722E-001 63. 44 2 253.12 3.3229E-002 117 .71 M ; First peak in a mult iplet region m = Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[51]

Nuclide MDA Report 6/5/2018 9: 17 :02 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 2.354E+005 2.35E+005 7.740E+005 1.017E+005 Co-60 1173.23 99.85 3.069E+004 2.59E+D04 3.206E+004 l.385E+004 1332.49 99.98 2.595E+004 -3.368E+004 1. 13 7E+O 04 Nb-94 702.65 99. 81 3.191E+004 2.59E+004 7.566E+003 1 .484E+004 871.09 99.89 2.585E+004 7.682E+003 l .167E+004 Ag-108m 433.90 90.50 3.172E+004 2.99E+004 -3.979E+002 1.495E+004 614.30 89.80 4 .141E+004 6.154E+004 1.956E+004 722.90 90.80 2.991E+D04 9.432E+003 1.371E+004 Cs-134 604.72 97.62 3.772E+004 3.20E+004 3.364E+004 1. 782E+004 795.86 85.46 3.204E+004 -5.635E+003 1. 462E+004 Cs-137 6 61. 66 85.10 3.133E+004 3.13E+004 -2.763E+004 1.440E+004 Eu-152 121. 78 28.67 1.238E+005 1 .17E+D05 -6.887E+004 6.039E+004 344.28 26.60 1. 217E+005 4 .575E+004 5.819E+004 1408.01 21. 07 1. 175E+OD5 5.424E+OD3 5.084E+004 Eu-154 123.07 40.40 8.819E+004 7.81E+004 7.411E+004 4.301E+004 723.30 20.06 1.308E+005 -6.138E+OD4 5.975E+D04 1274.43 34.80 7.812E+D04 -1.166E+005 3.456E+004 Eu-155 86.55 30.70 1. 476E+005 l .48E+OD5 2.412E+005 7.233E+004 105.31 21.10 1 .850E+005 -1.249E+004 9.042E+004

+ Tl-208 583.19* 85.00 1. 939E+004 l.94E+004 1 .807E+004 8.528E+003 Bi-212 727.33 6.67 3.993E+OOS 3.99E+D05 -3.143E+004 1.826E+005 Pb-212 238.63 43.60 7.49SE+004 7.49E+004 8.776E+004 3.618E+004

+ Bi-214 609.32* 45.49 3.713E+OD4 3.71E+004 7.126E+004 1 .632E+004 1120.29 14.92 2.234E+005 - 1. 295E+005 1 .020E+005 1764.49 15.30 2.264E+OOS l.979E+005 1.005E+005

+ Pb-214 295.22* 18.42 9.935E+D04 3.94E+004 6.901E+004 4.619E+004 351.93* 35.60 3.941E+004 8.687E+004 1.768E+004 Ra-226 186.21 3.64 8.483E+OD5 8.48E+005 1.164E+005 4.106E+005 Ac-228 338.32 11. 27 2.498E+005 l.23E+OOS 3.450E+004 l.187E+005 911. 20 25.80 1.229E+005 1.197E+005 5.644E+004 968.97 15.80 1. 917E+005 9.232E+004 8.737E+004 Am-241 59.54 35.90 l. 414E+OD5 1 .41E+OOS -5.097E+OD3 6.904E+004

+ = Nuclide identified during the nuclide identification

Energy line found in the spectrum

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

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

[52]

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

Filename: 6279 Report Generated On 6/5/2018 10 :30:08 AM Sample Title B106201AFSFC003GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Samp le Type Gamma Direct Samp le Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/5/2018 10:20:00 AM Acquisition Started 6/5/2018 10:20:07 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATAVAUDATED DATEJ.a- ' - Lt TIME 12:,5 Wtut4

[53]

Peak Analysis Report 6/5/2018 10:30:08 AM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSFC003GD Peak Analysis Performed on: 6/5/2018 10:30:08 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 284- 347 300.08 74.99 1.12 1 .38E+002 17 4 .75 8.29E+002 2 944- 961 952.67 238.29 0 . 33 9.87E+OOO 30.24 6.71E+001 3 1172- 1190 1180 .72 295.34 0.88 3.51E+001 22.76 2.79E+001 4 1398- 1415 1406 .66 351.87 0.45 2.27E+001 24.29 3.83E+001 5 2033- 2050 2041 .64 510 .68 0.32 2.35E+001 12.35 4.50E+OOO 6 2321- 2338 2329.76 582.73 0.30 2.93E+001 14. 31 6.72E+OOO 7 2427- 2444 2435.61 609.19 0.90 5.08E+001 16.83 6.18E+OOO B 5833- 5852 5842.42 146 0 .32 1.18 9.13E+001 20.12 2.67E+OOO 9 7048- 7067 7057.40 1763.54 0.37 1.00E+OOl 6.32 O.OOE+OOO M Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[54]

Interference Corrected Activity Report 6/5/2018 10:3 0 :08 AM Page 3

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

Sample

Title:

Bl06201AFSFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1 .000 1460.82* 10.66 1.08170E+006 2.56175E+005 Tl-208 1.000 583.19* 85.00 2.53089E+004 1 .27350E+004 Pb-212 1.000 238.63* 43.60 9.43852E+003 2.89555E+004 Bi-214 0.710 609.32* 45.49 8.43353E+004 2.97090E+004 1120.29 14 .92 1764.49* 15 .30 9.42016E+004 6.00542E+004 Pb-214 1. 000 295.22* 18.42 9.04119E+004 6.04264E+004 351.93* 35.60 3.38908E+004 3.66457E+004

. Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0 .30 Errors quoted at 2. 000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2) Uncertainty K-40 1. 000 1. 0 81697E+O 06 2.561750E+005 Tl-208 1. 000 2.530887E+004 1.273503E+004 Pb-212 1. 000 9.438523E+003 2.895546E+004 Bi-214 0.710 8.627516E+004 2.662871E+004 Pb-214 1. 000 4.908877E+004 3.133386E+004

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

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

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

Peak Locate Performed on: 6/5/2018 1 0 :30:08 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second ~

0 Uncertainty Type Nuclide 1 74 .99 2.3000E-001 126.63 5 510 .68 3.9167E-002 52.55 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[56]

Nucl ide MDA Report 6/5/2018 10 :30:08 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC003GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 1.547E+005 1 .55E+005 1.082E+006 6.130E+004 Co-60 1173.23 99.85 3.021E+004 2.79E+004 1.740E+004 1.361E+004 1332.49 99.98 2.787E+004 2.371E+004 1.233E+004 Nb-94 702.65 99.81 2.522E+004 2.52E+004 3.552E+003 1 .150E+004 871.09 99.89 2.923E+004 6.623E+003 1.335E+004 Ag-108m 433.90 90.50 3.020E+004 3.02E+004 9.009E+003 1.419E+004 614. 3 0 89.80 3.959E+004 2.273E+004 1.865E+004 722.90 90.80 3.153E+004 1.23BE+004 1.452E+004 Cs-134 604 . 72 97.62 3.754E+004 3.36E+004 2.636E+004 1. 773E+004 795.86 85.46 3.358E+004 1 .913E+004 1. 539E+004 Cs-137 661.66 85.10 3.503E+004 3.50E+004 1 .353E+004 1.625E+004 Eu-152 121.78 28.67 1.243E+005 1. 21E+005 -7.053E+004 6.062E+004 344.28 26.60 1 .214E+005 6.167E+004 5.801E+004 1408.01 21. 07 1 .311E+005 -2.482E+004 5.765E+004 Eu-154 123.07 40.40 8.866E+004 8.87E+004 4. 784E+004 4.325E+004 723.30 20.06 l.413E+005 5.692E+004 6.502E+004 1274.43 34.80 8.931E+004 -5.577E+004 4.016E+004 Eu-155 86.55 30.70 1. SOOE+OOS 1 .SOE+005 2.038E+004 7.353E+004 105 . 31 21.10 1. 859E+005 2.646E+004 9.090E+004

+ Tl-208 583.19* 85.00 1. 565E+004 1.56E+004 2.531E+004 6.653E+003 Bi-212 727.33 6.67 4.085E+005 4.09E+005 -3.02BE+005 1 .873E+005

+ Pb-212 238.63* 43.60 4 .911E+004 4.91E+004 9.439E+003 2.326E+004

+ Bi-214 609.32* 45.49 2.889E+004 2.55E+004 8.434E+004 1. 220E+004 1120. 29 14 .92 1 .803E+005 9.007E+003 8.039E+004 1764.49* 15. 30 2.549E+004 9.420E+004 O.OOOE+OOO

+ Pb-214 295.22* 18.42 8.938E+004 5 .* 90E+O 04 9.041E+004 4.120E+004 351.93* 35.60 5.896E+004 3.389E+004 2.746E+004 Ra-226 186.21 3.64 8.310E+005 8.31E+005 8.849E+005 4.020E+005 Ac-228 338.32 11. 27 2.498E+005 1 .28E+005 3.450E+004 1.187E+OOS 911 .20 25.80 1. 2BOE+005 2.035E+004 5.901E+004 968.97 15.80 1.892E+005 1.599E+005 8.615E+004 Am-241 59.54 35.90 1.474E+005 1.47E+005 1.540E+004 7.201E+004

+ ~ Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[57]

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

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

Filename: 6279 Report Generated On 6/5/2018 12: 48: 35 PM Sample Title B106201AFSFC004GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/5/2018 12:38:00 PM Acquisition Started 6/5/2018 12: 38: 34 PM Live Time 600 , 0 seconds Real Time 600.4 seconds Dead Time 0 .07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATAVAUDATED DATE tJ-,-ll TIME 1J3~

u2.a,~;'

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Peak Analysis Report 6/5/2018 12:48:35 PM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSFC004GD Peak Analysis Performed on: 6/5/2018 12 :48:34 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 143- 158 150 .33 37.51 0.50 2.39E+001 20.28 2.61E+001 2 292- 309 300.05 74.98 1. 14 9.52E+001 63. 13 2.76E+002 3 944- 961 952.78 238.32 0.80 3.25E+001 29.87 5.85E+001 4 1171- 1188 1179.36 295.00 0.95 2.61E+001 23.39 3.39E+001 5 1398- 1415 1406.44 351.81 0.98 3.23E+001 2 1. 83 2.67E+001 6 2032- 2049 2040.25 510.33 0.50 2.39E+001 18.28 1 .81E+001 7 2322- 2339 2330.20 582.83 1. 01 2.00E+OOl 14.04 9.00E+OOO 8 2426- 2443 2434.45 608.90 0.57 6.35E+001 17.69 4.50E+OOO 9 3633- 3650 3641.48 910.61 0.29 1.85E+001 11. 51 4.SOE+OOO 10 5829- 5849 5839.78 1459.67 1.01 7.94E+001 18.84 2.57E+OOO M = First peak in a multiplet region m Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma

[59]

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Sample

Title:

B106201AFSFC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB ill * * * * * * - * .. ~ * * .. .. ... - ... ,

IDENTIFIED NUCLIDES * * '" . .......... . ' .... ' 1 Nuc lide Id Energy Yield Activity Activity Name Confidence {keV) (%) (pCi/MA2 ) Uncertainty K-40 0.998 1460.82* 10 .66 9.40485E+005 2.37503E+005 Tl- 208 1. 000 583.19* 85.00 1.72867E+004 1 .23082E+004 Pb- 212 1. 000 238.63* 43.60 3.10809E+004 2.90056E+004 Bi- 214 0. 454 609.32* 45.49 1.05355E+OOS 3.19597E+004 1120.29 14.92 1764.49 15.30 Pb- 214 1. 000 295.22* 18.42 6.73416E+004 6.12112E+004 351.93* 35.60 4.82213E+004 3.34025E+004

= Energy line found in t he spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0. 30 Errors quoted at 2. 000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.998 9.404851E+OOS 2.375033E+005 Tl-208 1 .000 l.728668E+004 1 .230823E+004 Pb-212 1.000 3.108088E+004 2.900555E+004 Bi-214 0.454 1.053553E+005 3.195970E+004 Pb-214 1. 000 5.260850E+004 2.932097E+004

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

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

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Peak Locate Performed on: 6/5/2018 12: 48: 34 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second g,. Uncertainty 0 Type Nuclide 1 37.51 3.9792E-002 84.94 2 74.98 1. 5859E-001 66.35 6 510 .33 3.9841E-002 76.45 9 910.61 3.0833E-002 62.23 Sum M = First peak in a mult iplet region m = Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2.000 sigma

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Nuclide MDA Report 6/5/2018 12: 48: 35 PM Page 6

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC004GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pci/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 1 .506E+005 1 .51E+005 9.405E+005 5.928E+004 Co-60 1173.23 99.85 2.712E+004 2.71E+004 -9.121E+003 1.206E+004 1332.49 99.98 2.908E+004 -1 .130E+004 1.294E+004 Nb-94 702.65 99.81 3.039E+004 2.82E+004 2.604E+004 l.408E+004 871.09 99.89 2.815E+004 4.776E+003 1 .282E+004 Ag-108m 433.90 90.50 3.221E+004 2.96E+004 l.595E+004 l .519E+004 614.30 89.80 4.219E+004 5.827E+004 1.995E+004 722.90 90.80 2.957E+004 -6.067E+004 1. 354E+004 Cs-134 604.72 97.62 3.999E+004 3.00E+004 5.236E+004 1.895E+004 795.86 85.46 2.999E+004 -2.028E+004 1 .360E+004 Cs-137 661.66 85. 10 3.354E+004 3.35E+004 9.650E+003 1 .551E+004 Eu-152 121 .78 28.67 1. 296E+005 1 .22E+005 -9.987E+003 6.327E+004 344.28 26.60 1.217E+005 1 .512E+005 5.819E+004 1408. 01 21.07 1.403E+005 1. 227E+005 6.227E+004 Eu-154 123.07 40.40 9.078E+004 6.03E+004 -1 .066E+005 4.431E+004 723.30 20.06 1.384E+005 9.271E+004 6.356E+004 1274.43 34.80 6.026E+004 -8.147E+004 2.563E+004 Eu-155 86.55 30.70 1 .517E+005 1 .52E+005 -8.601E+004 7.437E+004 105. 31 21 .10 1 . 865E+005 5.879E+003 9.118E+004

+ Tl-208 583.19* 85.00 1.772E+004 l.77E+004 1 .729E+004 7.690E+003 Bi-212 727.33 6.67 4 .220E+005 4.22E+005 1.479E+005 1.940E+005

+ Pb-212 238.63* 43.60 4 .602E+004 4.60E+004 3.108E+004 2.172E+004

+ Bi-214 609.32* 45.49 2.542E+004 2.54E+004 1.054E+005 1. 046E+004 1120.29 14.92 2.178E+005 8.585E+004 9.917E+004 1764.49 15 .30 1.953E+005 l .414E+005 8.491E+004

+ Pb-214 295.22* 18.42 9.612E+004 4.99E+004 6.734E+004 4.457E+004 351.93* 35.60 4 .985E+004 4.822E+004 2.290E+004 Ra-226 186.21 3.64 8.404E+005 8.40E+005 -l.423E+006 4 .067E+005 Ac-228 338.32 11. 27 2.518E+005 1 .33E+005 -2.787E+OOS 1 .197E+005 911. 20 25.80 1.330E+005 1. 887E+005 6.147E+004 968.97 15.80 2.145E+005 -4.691E+004 9.876E+004 Am-241 59.54 35.90 1.452E+005 -1.45E+005 1. 796E+005 7.090E+004

+ =Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[63]

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

Filename: 6279 Report Generated On 6/5/2018 1: 52:27 PM Sample Title B106201AFSFC005GD Sample Description Ul Diesel Fuel* Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/5/2018 1:42:00 PM Acquisition Started 6/5/2018 1:42:26 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATA VALIDATED DATE1,-,-L?

Tlfv1E ;335 anr-+,

[64]

Peak Analysis Report 6/5/2018 1:52:27 PM Page 2

- - - - P E A K ANALYSIS R E P O R T *****

Detector Name: 6279 Sample

Title:

B106201AFSFC005GD Peak Analysis Performed on: 6/5/2018 1 :52:27 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts M 1 246- 346 254.80 63.66 3.64 4.94E+001 32.04 2.68E+002 m 2 246 - 346 298.17 74.51 3.65 2.36E+002 49.02 4.98E+002 3 946- 963 954.13 238.65 1. 10 3.46E+001 30.81 6.14E+001 4 1171- 1188 1179.30 294.99 0.32 6.97E+OOO 24.53 4 .30E+001 5 1267- 1284 1275.52 319.06 0.38 5.92E-001 19.70 2.94E+001 6 1398- 1415 1406.34 351.79 0.92 6.06E+001 25.55 3. 14E+001 7 2034- 2051 2042.81 510.97 0.88 6.96E+OOO 20.24 2.90E+001 8 2426- 2444 2435. 04 609.05 0.58 4.12E+001 19. 44 l.48E+001 9 4942- 4961 4951.30 1237.82 0.29 1. 70E+001 8.25 O.OOE+OOO 10 5832- 5851 5841.22 1460.02 1. 56 9.40E+001 19.39 O.OOE+OOO M First peak in a multiplet region m == Other peak in a multiplet region F == Fitted singlet Errors quoted at 2. 000 sigma

[65]

Interference Corrected Activity Report 6/5/2018 1:52:27 PM Page 3

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Sample

Title:

B106201AFSFC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

... * **** t * ***** ** * *** IDENTIFIED NUCLIDES

t t * * * * * * * *

I

f f

I I

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.999 1460.82* 10.66 1 .11319E+006 2.49151E+OOS Pb-212 1.000 238.63* 43.60 3.31416E+004 2.99715E+004 Bi-214 0.454 609.32* 45.49 6.8390SE+004 3.32888E+004 1120.29 14.92 1764.49 15.30 Pb-214 1. 000 295.22* 18.42 1 .79700E+004 6.32626E+004 351.93* 35.60 9.058SSE+004 4.05107E+004 Am-241 0.973 59.54* 35.90 S.77523E+004 3.91947E+004

=Energy line found in t he spectrum.

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

[66]

Interference Corrected Activity Report 6/5/2018 1:52:27 PM Page 4

***

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 1.113194E+006 2.491508E+005 Pb-212 1.000 3.314156E+004 2.997150E+004 Bi-214 0.454 6.839054E+004 3.328881E+004 Pb-214 1. 000 6.946820E+004 3.411547E+004 Am-241 0.973 5.775232E+004 3.919474E+004

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

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

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

Peak Locate Performed on: 6/5/2018 1 :52:26 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide m 2 74.51 3.9336E-001 20.77 5 319.06 9.8611E-004 3330.29 7 510.97 1.1597E-002 290.89 9 1237.82 2.8333E-002 48.51 M : First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[67]

Nucl ide MDA Report 6/5/2018 1:52:27 PM Page 5

- - - - NUCLIDE MD A R E P O R T *****

Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

Bl06201AFSFC005GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/M ... 2 )

+ K-40 1460.82* 10.66 3 . 205E+004 3.20E+004 1. 113E+006 O.OOOE+OOO Co-60 1173.23 99.85 3.117E+004 2.79E+004 -4.220E+003 1. 409E+004 1332.49 99.98 2.787E+004 -2.667E+003 1. 233E+004 Nb-94 702.65 99.81 2.959E+004 2.96E+004 1.863E+004 1.368E+004 8 71. 09 99.89 3.093E+004 -3.475E+004 l.421E+004 Ag-108m 433.90 90.50 2.950E+004 2.85E+004 5.920E+003 1.384E+004 614.30 89.80 3.745E+004 2.741E+004 1.758E+004 722.90 90.80 2.853E+004 1.495E+004 l.302E+004 Cs-134 604.72 97.62 3.896E+004 3.81E+004 5.043E+004 1.844E+004 795.86 85.46 3.813E+004 6.114E+003 1.767E+004 Cs-137 661.66 85 . 10 3.166E+004 3.17E+004 -1 .809E+004 1.457E+004 Eu-152 121.78 28.67 1 .270E+005 1.06E+005 7.780E+004 6.196E+004 344.28 26.60 1 .280E+005 4.784E+004 6.136E+004 1408. 01 21. 07 1.059E+005 5.443E+003 4.507E+004 Eu- 154 123.07 40.40 8.946E+004 7.64E+004 -6.170E+004 4.365E+004 723.30 20.06 1.260E+005 -1. 135E+O 05 5.73SE+004 1274.43 34.80 7.637E+004 -6.697E+004 3.369E+004 Eu-155 86.55 30.70 1. 547E+005 1 .SSE+OOS 1 .262E+004 7.584E+004 105.31 21. 10 1. 816E+005 -1 .145E+005 8.872E+004 Tl-208 583.19 85. 00 3.551E+004 3.55E+004 -1 .494E+003 1 .659E+004 Bi-212 727.33 6.67 4.040E+OOS 4.04E+005 -3.306E+005 1 .BSOE+OOS

+ Pb-212 238.63* 43.60 4.742E+004 4.74E+004 3.314E+004 2.242E+004

+ Bi-214 609.32* 45.49 4.433E+004 4 .43E+004 6.839E+004 1 .992E+004 1120.29 14.92 2.262E+005 1. 897E+005 1.033E+005 1764.49 15.30 1. 953E+005 l.414E+005 8.491E+004

+ Pb-214 295.22* 18.42 1.085E+005 5.38E+004 1.797E+004 5.076E+004 351.93* 35.60 5.383E+004 9.059E+004 2.489E+004 Ra-226 186.21 3.64 8 . 470E+005 8.47E+005 -2.725E+005 4.100E+005 Ac-228 338.32 11. 27 2.440E+005 1 .22E+005 9.246E+004 1.158E+005 911.20 25.80 1. 216E+005 1.159E+005 5.578E+004 968.97 15.80 1. 988E+O 05 -8.923E+004 9.094E+004 Am-241 59.54* 35.90 9.222E+004 9.22E+004 5.775E+004 4.453E+004

+ = Nuclide identified during the nuclide identification

~ Energy line found in the spectrum

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

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

[68]

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

Filename: 6279 Report Generated On 6/5/2018 2:06:21 PM Sample Title B106201AFSFC006GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10 . 000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/5/2018 1 :56: 00 PM Acquisition Started 6/5/2018 1 :56:20 PM Live T ime 600 . 0 seconds Real T ime 600.4 seconds Dead Time 0 .07 %

Energy Calibration used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN

[69]

Peak Analysis Report 6/5/2018 2:06:21 PM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSFC006GD Peak Analysis Performed on: 6/5/2018 2:06 :21 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area uncert. Counts M l 245- 346 252.24 63.02 1 .11 9.97E+001 62. 71 l.28E+002 m 2 245- 346 299.67 74.89 1.12 3.42E+002 192.26 1.58E+002 3 1341- 1358 1349.86 337.66 0.45 1 .81E+001 20.08 2.49E+001 4 1398- 1415 1406.63 351.86 0.79 3.47E+001 20.71 2.23E+001 5 2321 - 2338 2329.74 582.72 1. 03 2.57E+001 13.72 6.30E+OOO 6 2426- 2443 2434.80 608.99 1. 28 4 .95E+001 19.33 1.35E+001 7 4468- 4487 4477.52 1119.49 0.83 2.08E+001 13.53 7.18E+OOO 8 5832- 5851 5841.39 1460.07 0.89 7.67E+001 18.39 2.33E+OOO M : First peak in a multiplet region m :; other peak in a multiplet region F :; Fitted singlet Errors quoted at 2.000 sigma

[70]

Interference Corrected Activity Report 6/5/2018 2:06:21 PM Page 3

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Sample

Title:

B106201AFSFC006GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.999 1460.82* 10.66 9.08030E+005 2.31575E+005 Tl-208 1. 00 0 583. 19* 85.00 2.22066E+004 1.21511E+004 Bi-214 0.743 609.32* 45.49 8.21346E+004 3.35593E+004 1120.29* 14.92 1.49963E+005 9.81825E+004 1764.49 15.30 Pb-214 0 .434 295.22 18 .42 351.93* 35.60 5.18441E+004 3.19019E+004 Am-241 0 .981 59.54* 35.90 1. 17487E+OOS 7.75898E+004

=Energy line found in t he spectrum.

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

[71]

Interference Corrected Activity Report 6/5/2018 2:06:21 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 0.999 9.080298E+005 2.315748E+005 Tl-208 1.000 2.220664E+004 l.215112E+00 4 Bi-214 0.743 8.923017E+004 3.175550E+004 Pb-214 0.434 5. 1 84410E+004 3.190190E+004 Am-241 0.981 l. 1 7 4869E+OOS 7.758984E+004

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

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

- - - - U N I D E N T I F I E D P E AK S **********

Peak Locate Performed on: 6/5/2018 2:06:21 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide m 2 74 .89 5.7043E-001 56.17 3 337.66 3.0097E-002 111 .22 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[72]

Nucl ide MDA Report 6/5/2018 2:06:22 PM Page 5

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

Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC006GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2) (pCi/MA2 ) (pCi/M"'2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 l.411E+005 1.41E+005 9.080E+OOS S.453E+004 Co-60 1173.23 99.85 3.021E+004 2.73E+004 -5.656E+003 1.361E+004 1332.49 99.98 2.725E+004 2.252E+004 1.202E+004 Nb-94 702.65 99.81 2.646E+004 2.65E+004 -3.274E+003 1.212E+004 871.09 99.89 3.026E+004 9.108E+003 1.387E+004 Ag-108m 433.90 90.50 3.003E+004 2.85E+004 3.528E+004 1. 410E+004 614.30 89.80 4.296E+004 6.718E+004 2.034E+004 722.90 90.80 2.853E+004 -7.231E+003 1. 302E+004 Cs-134 604.72 97.62 4.149E+004 3.36E+004 6.197E+004 1.970E+004 795.86 85.46 3.358E+004 -8.752E+003 1.539E+004 Cs-137 661.66 85.10 3.503E+004 3.SOE+D04 -8.331E+004 1.625E+004 Eu-152 121.78 28.67 1. 298E+005 1.10E+005 -2.681E+004 6.338E+004 344.28 26.60 1. 210E+005 1. 006E+005 5.783E+004 1408.01 21.07 1. 099E+005 7.009E+004 4 .707E+004 Eu-154 123.07 40.40 9.171E+004 7.46E+004 -4.830E+004 4.478E+004 723.30 20.06 l.292E+OOS 1.159E+OOS 5.896E+004 1274.43 34.80 7.457E+004 -l.246E+004 3.279E+004 Eu-155 86.55 30.70 1.632E+OOS 1.63E+OOS 8.001E+004 8.014E+004 105.31 21.10 l.899E+OOS -1. 967E+OOS 9.290E+004

+ Tl-208 583. 19* 85. 00 1 .547E+004 1.55E+004 2.221E+004 6.568E+003 Bi-212 727.33 6.67 4.08SE+005 4.09E+OOS 2.378E+005 1.873E+OOS Pb-212 238.63 43.60 7.440E+004 7.44E+004 l .024E+005 3.59DE+004

+ Bi-214 609.32* 45.49 4.067E+004 4.07E+004 8.213E+004 1 .809E+004 1120.29* 14.92 1. 378E+OOS 1.SOOE+OOS 5.917E+004 1764.49 15.30 2.063E+OOS 3.783E+004 9.039E+004

+ Pb-214 295.22 18.42 1 .670E+OOS 4.59E+004 1.294E+005 8.000E+004 351. 93

35.60 4.591E+004 5.184E+004 2.093E+004 Ra-226 186.21 3.64 8.894E+005 8.89E+005 1 .485E+005 4.312E+005 Ac-228 338.32 11. 27 2.602E+OOS 1 .38E+005 -3.002E+005 1.239E+OOS 911.20 25.80 1.377E+OOS -6.783E+004 6.384E+004 968.97 15 .80 1.738E+005 -2.666E+004 7.842E+004

+ Am-241 59.54* 35.90 6.532E+004 6.53E+004 1.175E+005 3.107E+004

+ =Nuclide identified during the nuclide identification

= Energy line found in the spectrum

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

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

[73]

- - - - GAMMA S P E C T R U M A N A L Y S I S *****

Filename: 6279 Report Generated On 6/11/2018 9:44:52 AM Sample Title B106201AFSFC007GD Sampl e Description Ul Diesel Oil Fuel Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10. 000 keV Samp le Size 2.830E+001 MA2 Sample Taken On 6/11/2018 9:34:00 AM Acquisition Started 6/11/2018 9:34:50 AM Live Time 600.0 seconds Real Time 600.9 seconds Dead Time 0 , 14 %

Energy Calibration used Done on 6/9/2018 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATAVAUDATED DATE1; .. 4 .. /I' Tl ME a ,ytJ c:iJ/rl? '4.c

[74]

Peak Analysis Report 6/11/2018 9:44:52 AM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSFC007GD Peak Analysis Performed on: 6/11/2018 9:44:52 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area uncert. Counts 1 287- 305 300 .26 75.19 0.68 l.45E+002 68.88 3.07E+002 2 335- 345 339.22 84.93 0.86 3.74E+001 40.70 1. 57E+O 02 3 950- 960 954.12 238.65 0.78 5.65E+001 25.39 4. 35E+001 4 1400- 1414 1406.64 351.77 0.81 5.70E+001 23.46 2.BOE+OOl 5 2325- 2336 2330.51 582.73 0.66 l.62E+001 13 .39 l.08E+001 6 2427- 2443 2435.53 608.98 0.82 5.17E+001 17 .61 8.29E+OOO 7 5833- 5852 5842.94 1460.79 0.46 8.09E+001 19 .94 5.llE+OOO M Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[75]

Interference Corrected Activity Report 6/11/2018 9:44:52 AM Page 3

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

Sample

Title:

B106201AFSFC007GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

t * * * *

I *

I * * * * * * * *

IDENTIFIED NUCLIDES * *. * * * * * * * * * * * *

t, * *

I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%} (pCi/MA2 } Uncertainty K-40 1 .000 1460.82* 10.66 9.58284E+OOS 2.50444E+OOS Eu-155 0.338 86.55* 30.70 4.12668E+004 4 .56190E+004 105.31 21.10 Tl-208 1 . 000 583.19* 85.00 l.39718E+004 1 . 16950E+004 Pb-212 1 . 000 238.63* 43.60 5.41264E+004 2.58262E+004 Bi-214 0 .454 609.32* 45.49 8.57982E+004 3.09862E+004 1120 .29 14.92 1764.49 15.30 Pb-214 0.434 295.22 18.42 351.93* 35.60 8.51700E+004 3.72865E+004

=Energy line found in t he spectrum.

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

[76]

Interference Corrected Activity Report 6/11/2018 9:44:52 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 9.582842E+005 2.504436E+005 Eu-155 0.338 4.126684E+004 4.561896E+004 Tl-208 1 .000 1. 397179E+004 1.169498E+004 Pb-212 1 .000 5.412637E+004 2.582622E+004 Bi-214 0.454 8.579815E+004 3.09862DE+004 Pb-214 0.434 8.517005E+004 3.728653E+004

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

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

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

Peak Locate Performed on: 6/11/2018 9:4 4: 52 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75. 19 2.4086E-001 47.66 M = First peak in a mult iplet region m = Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[77]

Nuclide MDA Report 6/11/2018 9:44:52 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC007GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/MA2) (pCi/M"2 ) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10. 66 1. 997E+005 2.00E+005 9.583E+OOS 8.383E+004 Co-60 1173.23 99.85 2.819E+004 2.53E+004 3.916E+002 1.260E+004 1332.49 99.98 2.527E+004 1. 519E+003 1.103E+004 Nb-94 702.65 99.81 2.139E+004 2.14E+004 8.483E+003 9.S80E+003 871. 09 99.89 2.330E+004 -1. 699E+004 1.039E+004 Ag-108m 433.90 90.50 2.485E+004 2.49E+004 -9.714E+003 1.152E+004 614. 3 0 89.80 3.811E+004 -1.728E+004 1.791E+004 722.90 90.80 2.594E+004 -8.972E+003 1.173E+004 cs-134 604.72 97.62 3.549E+004 3.00E+OD4 2.695E+D03 1.671E+004 795.86 85.46 2.999E+004 -2.31DE+004 1 .360E+004 Cs-137 661.66 85.10 2.965E+004 2.96E+OD4 6.743E+003 1 .356E+OD4 Eu-152 121.78 28.67 9.727E+004 8.58E+004 -7.623E+004 4.712E+004 344.28 26.60 8.582E+004 -6.998E+004 4.024E+004 1408. 01 21.07 1. 311E+005 6.401E+004 5.76SE+004 Eu-154 123.07 40.40 6.892E+004 6.68E+004 -4.736E+OD4 3.338E+004 723.30 20.06 1.192E+005 2.886E+004 5.397E+004 1274.43 34.80 6.683E+004 2.349E+004 2.892E+004

+ Eu-155 86.55* 30.70 7.337E+004 7.34E+004 4 .127E+004 3.519E+004 105.31 21.10 1.468E+005 -5.484E+OD4 7.132E+004

+ Tl-208 583.19* 85.00 1.756E+004 1.76E+004 1.397E+004 7.612E+003 Bi-212 727.33 6.67 3.801E+005 3.80E+005 1.984E+005 1.730E+005

+ Pb-212 238.63* 43.60 3.479E+004 3.48E+004 5.413E+004 1.610E+004

+ Bi-214 609.32* 45.49 3.223E+004 3.22E+004 8.580E+004 1.387E+004 1120.29 14.92 2.062E+005 1.296E+004 9.333E+004 1764.49 15.30 2.616E+005 2.733E+005 1.181E+005

+ Pb-214 295.22 18.42 1. 437E+005 4.81E+004 7.287E+003 6.837E+004 351.93* 35.60 4.815E+004 8.S17E+004 2.205E+004 Ra-226 186.21 3.64 6.628E+005 6.63E+005 5.798E+005 3.179E+005 Ac-228 338.32 11. 27 2.144E+005 1 .15E+005 5.094E+004 1.0lOE+OOS 911.20 25.80 1 .147E+005 8 . 417E+004 5.236E+004 968.97 15.80 2.079E+005 1. 3 74E+005 9.549E+004 Am-241 59.54 35.90 1 .188E+005 1.19E+005 - 8.485E+004 5.772E+004

+=Nuclide identified during the nuclide identification

= Energy line found in the spectrum

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

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

[78]

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

Filename: 6279 Report Generated On 6/11/2018 9:56: 15 AM Sample Title B106201AFSFCOOBGD Sample Description Ul Diesel Fuel Storage Floor sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/11/2018 9:46:00 AM Acquisition Started 6/11/2018 9:46:13 AM Live Time 600.0 seconds Real Time 600.8 seconds Dead Time 0 . 12 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATAVAUDATED DATE.a ... , .. /f TIME /<<"/d a6',~~

[79]

Peak Analysis Report 6/11/2018 9:56:15 AM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSFC008GD Peak Analysis Performed on: 6/11/2018 9:56:15 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 283- 305 300.42 75.23 0.94 2.10E+002 80.27 3.61E+002 2 950- 959 954.26 238.68 0.64 2.34E+001 20.46 3.46E+001 3 1173- 1187 1179.89 295.09 0.93 3.76E+001 20.21 2.24E+001 4 1402- 1415 1408.12 352.14 0.86 5.25E+001 20.73 1.95E+001 5 2327- 2338 2332.53 583.23 0.64 l .44E+001 12.82 1.06E+001 6 2429- 2443 2435.96 609.09 0.42 4.13E+001 17.65 1.27E+001 7 2640- 2652 2645.96 66 1. 58 0.43 3.22E+001 12.23 1.81E+OOO 8 3638- 3651 3644.59 911. 23 0.76 2.08E+001 1 1 .88 5.24E+OOO 9 5833- 5853 5843.17 1 460.84 1. 74 8.SOE+OOl 2 1 .41 8.03E+OOO M ::::. First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[80]

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Sample

Title:

B106201AFSFC008GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"'2 ) Uncertainty K-40 1 . 000 1460.82* 10.66 1.00669E+006 2.68322E+005 Cs-137 1 . 000 661.66* 85.10 3.00464E+004 l .19702E+004 Tl- 208 1 . 000 583.19* 85.00 1.24776E+004 1 .11892E+004 Pb-212 1 . 000 238.63* 43.60 2.24081E+004 1 .99165E+004 Bi-214 0 . 454 609.32* 45.49 6.85445E+004 3.04301E+004 1120.29 14 .92 1764.49 15.30 Pb-214 1 . 000 295.22* 18.42 9.68902E+004 5.43411E+004 351.93* 35.60 7.84495E+004 3.31407E+004

~ Energy line found in the spectrum.

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

[81]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1.000 1.006689E+006 2.683218E+005 Cs-137 1. 000 3.004643E+004 1.197017E+00 4 Tl-208 1.000 1.247756E+004 1.118915E+00 4 Pb-212 1.000 2.240814E+004 1.991651E+00 4 Bi-214 0.454 6.854452E+004 3.043007E+00 4 Pb-214 1.000 8.344883E+004 2.829402E+00 4

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

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

[82]

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Peak Locate Performed on: 6/11/2018 9:56:15 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.23 3.4964E-001 38.26 8 911. 23 3.4599E-002 57.23 Sum M ~ First peak in a multiplet region m ~ Other peak in a multiplet region F: Fitted singlet Errors quoted at 2 1 000 sigma

[83]

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Detector Name: 6279 sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC008GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (% ) (pCi/M"2 ) (pCi/M ... 2 ) (pCi/M ... 2 ) (pCi/M"2 )

+ K-40 1460.82* 10 .66 2.443E+005 2.44E+005 1 .007E+006 1.061E+OOS Co-60 1173.23 99.85 2.819E+004 2.73E+004 2.061E+003 1. 260E+004 1332.49 99.98 2.725E+004 1.318E+004 1.202E+004 Nb-94 702.65 99.81 2.214E+004 2.21E+004 1.658E+004 9.955E+003 871.09 99.89 2.375E+004 -1. 591E+003 1.061E+004 Ag-108m 433.90 90.50 2.398E+004 2.4DE+004 -2.132E+OD3 1.108E+OD4 614.30 89.80 3.875E+004 -6.499E+003 1 .823E+OD4 722.90 90.80 3.057E+004 2.124E+004 1 .404E+004 Cs-134 604.72 97.62 3.549E+004 3.00E+004 4.479E+003 1 .671E+OD4 795.86 85.46 2.999E+004 -1. 799E+004 1 .360E+004

+ Cs-137 661.66* 85.10 9.522E+003 9.52E+003 3.005E+004 3.498E+003 Eu-152 121.78 28.67 1.039E+005 8. 15E+004 1. 771E+004 5.041E+D04 344.28 26.60 8.152E+004 -8.662E+004 3.809E+004 1408.01 21.07 1.279E+005 5.540E+004 5.603E+004 Eu-154 123.07 40.40 7.465E+004 6.03E+004 4.247E+004 3.625E+004 723.30 20.06 1.369E+005 6.498E+004 6.282E+004 1274.43 34.80 6.026E+004 8.155E+003 2.563E+004 Eu-155 86.55 30.70 1 .180E+005 1.18E+005 8.476E+004 5.749E+D04 105. 31 21. 10 1 .517E+OOS 9.175E+004 7.377E+004

+ Tl-208 583.19* 85.00 1 .703E+004 1.70E+004 1.248E+004 7.347E+003 Bi-212 727.33 6.67 3.751E+005 3.75E+005 -3.697E+002 1 .705E+005

+ Pb-212 238.63* 43.60 3.098E+004 3.10E+004 2.241E+004 l .419E+004

+ Bi-214 609.32* 45.49 3.752E+004 3.75E+004 6.854E+004 1.651E+004 1120.29 14.92 2.368E+005 2.102E+004 1.086E+005 1764.49 15.30 2.llSE+OOS 1.696E+005 9.301E+004

+ Pb-214 295.22* 18.42 7.507E+004 4.05E+004 9.689E+004 3.405E+004 351.93* 35.60 4.051E+004 7.845E+004 1.823E+004 Ra-226 186.21 3.64 6.780E+OOS 6.78E+005 2.173E+005 3.255E+OOS Ac-228 338.32 1 1. 27 2.086E+005 l.23E+005 4 .988E+004 9.809E+004 911. 20 25.80 1 .229E+005 1. 314E+005 5.644E+004 968.97 15.80 1.868E+005 3.783E+004 8.491E+004 Am-241 59.54 35.90 1.194E+OD5 1 .19E+005 2.727E+004 5.801E+004

+= Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[84]

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

Filename: 6279 Report Generated On 6/11/2018 10 :08 : 25 AM Sample Title B106201AFSFC009GD Sample Description Ul Diesel Fuel Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On G/l 1 /20l9 9:5 9 : 00 AM Acquisition Started 6 /ll /:2"018 9:5 8 :23 AM Live Time 600.0 seconds Real Time 600.9 seconds Dead Time 0.15 %

Energy Calibration used Done On 6/9/2018 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATA VALIDATED DATE l,i-- t; .. /1 1*1ME l,iJl/:IJ

°"11" AS*

[85]

Peak Analysis Report 6/11/2018 10:08:25 AM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSFC009GD Peak Analysis Performed on: 6/11/2018 10:08:25 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 285- 305 300.66 75.29 0.84 2.15E+002 75.94 3.39E+002 2 741- 753 745.82 186.57 0.56 2.44E+001 27.44 5.76E+001 3 1174- 1185 1179.79 295.06 0.75 1.49E+001 18.33 2.71E+001 4 1400- 1416 1407.59 352.01 1.18 4.80E+001 24.09 3.lOE+OOl 5 2431- 2442 2436.90 609.32 0.58 2.60E+001 14.99 1.20E+001 6 2638- 2652 2646.04 66 1 .60 0.58 3.17E+001 14.54 7.34E+OOO 7 4474- 4487 4480.44 112 0 .18 0.42 2.15E+001 11.16 3.50E+OOO 8 5835- 5853 5843.90 146 1 .03 1. 64 8.53E+001 2 0 .14 4 .75E+OOO 9 7051- 7066 7058.93 1764.77 0.42 1.80E+001 8.49 O.OOE+OOO M ;:: First peak in a multiplet region m Other peak in a multiplet region F ;:: Fitted singlet Errors quoted at 2 . 000 sigma

[86]

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Sample

Title:

B106201AFSFC009GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M ... 2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 1. 01006E+006 2.54269E+005 Cs-137 1. 000 661.66* 85.10 2.95514E+004 1 .40292E+004 Bi-214 1. 000 609.32* 45.49 4.31560E+004 2.54179E+004 1120.29* 14.92 1. 54906E+005 8.13873E+004 1764.49* 15. 30 1. 69645E+005 8.lll78E+004 Pb-214 1 .000 295.22* 18.42 3.82829E+004 4.76271E+004 351.93* 35.60 7.16655E+004 3.75636E+004 Ra-226 1 .000 186.21* 3.64 2.44203E+005 2.7767BE+005

=Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M ... 2 ) Uncertainty K-40 1. 000 1.010058E+006 2.542687E+005 Cs-137 1. 000 2.955140E+004 1.402918E+004 Bi-214 1. 000 6.265810E+004 2.324473E+004 Pb-214 1. 000 5.886336E+004 2.949407E+004 Ra-226 1. 000 2.442035E+005 2.776784E+005

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

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

- - - - U N I D E N T I F I E D P E AK S **********

Peak Locate Performed on: 6/11/2018 10:08:25 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.29 3.5750E-001 35.40 M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[88]

Nuclide MDA Report 6/11/2018 10: 08:26 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC009GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1 4 6 0 .82* 10 .66 1.889E+005 1.89E+005 1.010E+006 7.842E+004 Co-60 1173.23 99.85 3.069E+004 1.98E+004 1.520E+004 1. 385E+004 1332.49 99.98 l.976E+004 -5.269E+003 8.274E+003 Nb-94 702.65 99. 81 2.390E+004 2.39E+004 -9.400E+003 1. 084E+004 871.09 99.89 2.461E+004 -1.958E+004 1. 105E+004 Ag-108m 433.90 90.50 2.842E+004 2.84E+004 8.953E+003 1. 330E+004 614.30 89.80 3.325E+004 -3.620E+004 1. 548E+004 722.90 90.80 3.246E+004 1.704E+004 1. 499E+004 Cs-134 604.72 97.62 3.140E+004 2.96E+004 3.519E+004 l. 466E+004 795.86 85.46 2.957E+004 1.121E+004 1. 338E+004

+ Cs-137 661.66* 85.10 1 .667E+004 1.67E+004 2.955E+004 7.070E+003 Eu-152 121. 78 28.67 1 .047E+005 9.33E+004 2.614E+004 5.081E+004 344.28 26.60 9.331E+004 -4.151E+004 4.399E+004 1408.01 21. 07 l .059E+005 6.425E+004 4.507E+004 Eu- 154 123.07 40.40 7.282E+004 6.89E+004 -1.756E+004 3.533E+004 723.30 20.06 l .484E+OOS 7.863E+004 6.854E+004 1274.43 34 .80 6.886E+004 -2.802E+004 2.993E+004 Eu-155 86.55 30.70 1 .209E+005 1. 21E+005 -1.814E+004 5.895E+004 105.31 21.10 l .430E+005 -8.642E+003 6.944E+004 Tl-208 583.19 85.00 3.402E+004 3 .40E+O 04 1.523E+OD4 1. 584E+004 Bi-212 727.33 6.67 4.393E+005 4.39E+005 3.606E+005 2.026E+005 Pb-212 238.63 43.60 6.349E+004 6.35E+004 6.101E+004 3.045E+004

+ Bi-214 609.32* 45.49 3.449E+004 2.55E+004 4.316E+004 l. 500E+004 1120 .29* 14 .92 9.317E+004 l .549E+005 3.683E+004 1764.49* 15.30 2.550E+004 1 .696E+005 O.OOOE+OOO

+ Pb-214 295.22* 18 .42 7.746E+004 5.25E+004 3.828E+004 3.524E+004 351.93* 35.60 5.250E+004 7.167E+004 2.423E+004

+ Ra-226 186.21* 3.64 4.483E+005 4.48E+005 2.442E+005 2.106E+005 Ac-228 338.32 11. 27 2.027E+005 1. 12E+OOS -5.117E+004 9.512E+004 911.20 25.80 1.119E+005 -l .876E+003 5.092E+004 968.97 15.80 2.034E+005 1 .193E+005 9.324E+004 Am-241 59.54 35.90 l.190E+005 1. 19E+OOS -6.702E+003 5.779E+004

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[89]

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

Filename: 6279 Report Generated on 6/11/2018 12:40:00 PM Sample Title B106201AFSFC010GD Sample Description Ul Diesel Fuel Storage Floor sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/11/2018 12: 29: 00 PM Acquisition Started 6/11/2018 12:29:57 PM Live Time 600. 0 seconds Real Time 600.9 seconds Dead Time 0 . 15 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP lIN

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Detector Name: 6279 Sample

Title:

B106201AFSFC010GD Peak Analysis Performed on: 6/11/2018 12:39:59 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 233- 240 236.70 59.30 0.54 -1.02E+OOO 26.88 8.90E+001 2 285- 305 300.72 75. 31 0.78 1.51E+002 73.05 3.26E+002 3 951- 960 955.20 238.92 0.35 3.76E+001 2 1. 48 3.44E+001 4 1175- 1187 1180.70 295.29 1. 33 2.51E+001 19.30 2.59E+001 5 1402- 1415 1407 .79 352.06 0.85 5.12E+001 20.29 1.88E+001 6 2327- 2339 2333.88 583.57 0.30 2.43E+001 10.75 1.66E+OOO 7 2432- 2445 2437.76 609.54 0.64 3.98E+001 16.79 1.12E+001 8 4477- 4490 4483.55 1120.96 0.50 1 .73E+001 12.00 6.71E+OOO 9 5839- 5857 5848.26 1462.12 1. 08 8.90E+001 18.87 O.OOE+OOO M = Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2 . 000 sigma

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Sample

Title:

B106201AFSFC010GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertainty K-40 0.997 1460. 82* 10.66 1.05504E+006 2.41704E+005 Tl-208 1 .000 583.19* 85. 00 2.10512E+004 9.63517E+003 Pb-212 1 .000 238.63* 43.60 3.60505E+004 2.13862E+004 Bi-214 0.743 609.32* 45.49 6.60907E+004 2.89850E+004 1120 .29* 14.92 1.24635E+005 8.70586E+004 1764 .49 15.30 Pb-214 1 . 000 295.22* 18.42 6.48148E+004 5.08255E+D04 351.93* 35.60 7.64887E+004 3.2 4 1 42E+D04 Am-241 1.000 59.54* 35.90 -1.28207E+OD3 3.36953E+004

=Energy line found in the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.997 1 .055040E+006 2.417040E+005 Tl-208 1.000 2.105117E+004 9.635166E+003 Pb-212 1.000 3.605049E+004 2.138619E+00 4 Bi-214 0.743 7.193260E+004 2.750083E+004 Pb-214 1.000 7.311338E+004 2.732939E+004 Am-241 1.000 -1 .282068E+003 3.369532E+004

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

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

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

Peak Locate Performed on: 6/11/2018 12:39:59 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 2 75 . 31 2.5097E-001 48.51 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

Bl06201AFSFC010GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2)

.. K-40 1460.82* 10.66 3.208E+004 3.21E+OD4 1 .055E+OD6 O.OOOE+OOO Co-60 1173.23 99.85 2.482E+004 2.15E+004 1 ;202E+OD4 l.091E+004 1332.49 99.98 2.15DE+004 -7.005E+003 9.147E+003 Nb-94 702.65 99.81 2.250E+004 2.25E+004 -9.250E+003 1.014E+004 871.09 99.89 2.815E+004 6.984E+003 1.282E+004 Ag-108m 433.90 90.50 2.590E+004 2.59E+004 -3.990E+003 1.204E+004 614. 3 0 89.80 3.518E+004 3.507E+004 1.645E+004 722.90 90.80 2.888E+004 1.058E+004 1.320E+004 Cs-134 604.72 97.62 3.412E+004 3.08E+004 -4.244E+004 1.602E+004 795.86 85.46 3.083E+004 6.838E+003 1 .402E+004 Cs-137 661.66 85. 1 0 2.858E+004 2.86E+004 1.042E+004 1 .303E+004 Eu-152 121.78 28.67 9.492E+D04 9.28E+004 9.897E+003 4.594E+004 344.28 26.60 9.283E+004 -7.365E+002 4.375E+004 1408.01 21.07 1. 211E+OOS 4 .906E+004 5.263E+004 Eu-154 123.07 40.40 6.778E+004 6.78E+004 1.295E+004 3.281E+004 723.30 20.06 1.323E+005 S.208E+004 6.053E+004 1274.43 34.80 7.272E+004 -2.883E+004 3.187E+004 Eu-155 86.55 30.70 1.218E+005 1 .22E+005 1 .403E+005 5.944E+004 105.31 21.10 1.372E+005 4.733E+003 6.655E+004

+ Tl-208 583.19* 85.00 8.406E+003 8.41E+OD3 2.105E+004 3.033E+003 Bi-212 727.33 6.67 3.751E+005 3.75E+005 -3.094E+D05 1.705E+005

+ Pb-212 238.63* 43.60 3.038E+004 3.04E+004 3.605E+004 1.389E+004

+ Bi-214 609.32* 45.49 3.474E+OD4 3.47E+004 6.609E+004 1.512E+D04 1120.29* 14.92 1.221E+005 1.246E+005 5.127E+004 1764.49 15.30 2.009E+005 9.100E+004 8.769E+004

+ Pb-214 295.22* 18.42 7.691E+004 3.94E+004 6.481E+004 3.497E+004 351.93* 35.60 3.942E+004 7.649E+004 1 .769E+004 Ra-226 186.21 3.64 6.543E+D05 6.54E+005 -6.757E+005 3.136E+005 Ac-228 338.32 11. 27 2.265E+OOS 1.2DE+005 -6.220E+004 1.070E+005 911.20 25.80 1. 202E+005 1 .712E+004 5.512E+004 968.97 15.80 1. 764E+005 1 .982E+004 7.976E+004

+ Am-241 59. 54* 35.90 5.898E+OD4 S.9DE+004 -l .282E+003 2.779E+OD4

+ =Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[94]

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

Filename: 6279 Report Generated On 6/5/2018 2: 18 :44 PM Sample Title B106201AFSFC011GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range {in channels) 85 - 8192 Identification Energy Tolerance 10 . 000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/5/2018 2:08:00 PM Acquisition Started 6/5/2018 2: 08: 43 PM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0. 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP lIN DATAVAUDATED DATE J.2 .. ~ ./r TIMEa1'(J

'2"')e+

[95]

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Detector Name: 6279 Sample

Title:

B106201AFSFC011GD Peak Analysis Performed on: 6/5/2018 2:18: 44 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 179- 194 186.38 46.53 0.38 3.56E+001 33.42 8.04E+001 2 285- 310 298.89 74.69 0.84 2.12E+002 79.29 3.19E+002 3 946 - 963 954.03 238.63 0.84 3.97E+001 26.68 4.13E+001 4 1172 - 1189 1180.82 295.37 1.44 3.21E+001 24.42 3.59E+001 5 1398- 1415 1406.82 35 1 .90 0.79 4.80E+001 19.79 1.SOE+OOl 6 2034- 2051 2042.42 510.88 0.28 1.84E+001 18.96 2.16E+001 7 2188- 2205 2196. 21 549.33 0.25 1.59E+001 9.56 2.13E+OOO 8 2324- 2341 2332.59 583.43 0.85 2.62E+001 13.92 6.77E+OOO 9 2428- 2445 2436.93 609.52 0.80 4 .90E+001 18.46 l.lOE+OOl 10 4471- 4490 4480.80 1120.31 0.27 2.16E+001 11 .00 2.44E+OOO 11 5835- 5854 5844.27 1460.78 0.95 6.74E+001 17.53 2.59E+OOO M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[96]

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Sample

Title:

B106201AFSFC011GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES . ... .......... . - .. " " - "

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1. 000 1460.82* 10 .66 7.98560E+005 2.18950E+005 Tl- 208 1. 000 583.19* 85.00 2.26834E+004 l.23461E+004 Pb-212 1. 000 238.63* 43.60 3.79591E+004 2.62662E+004 Bi-214 0.743 609.32* 45.49 8.13074E+004 3.21734E+004 1120.29* 14.92 1. 55366E+OOS 8.02197E+004 1764.49 15.30 Pb-214 1.000 295.22* 18 .42 8.26595E+004 6.43363E+004 351.93* 35.60 7.16643E+004 3. 14489E+004

~ Energy line found in t he spectrum.

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

[97]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1. 000 7.985599E+005 2.189498E+OOS Tl-208 1. 000 2.268345E+004 1.234611E+004 Pb-212 1.000 3.795912E+004 2.626620E+004 Bi-214 0.743 9. 1 56933E+004 2.986123E+004 Pb-214 1 .000 7.378486E+004 2.825397E+004

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

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

[98]

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Peak Locate Performed on: 6/5/2018 2:18: 44 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second % Uncertainty Type Nuclide 1 46.53 5.9332E-002 93.89 2 74.69 3.5329E-001 37. 41 6 510.88 3.0625E-002 103.17 7 549.33 2.6458E-002 60.24 M "" First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[99]

Nuclide MDA Report 6/5/2018 2:18:44 PM Page 6

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC011GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) {pCi/MA2 } (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2)

+ K-40 1460.82* 10 .66 1.517E+005 1. 52E+005 7.986E+OOS 5.982E+004 Co-60 1173.23 99.85 2.871E+004 2.59E+004 - 3.322E+004 1 .286E+004 1332.49 99.98 2.595E+004 - 3.844E+004 1 .137E+004 Nb-94 702 . 65 99.81 2.585E+004 2.58E+004 4.979E+003 1 .181E+004 8 71. 09 99.89 2.625E+004 8.226E+002 1.187E+004 Ag-108m 433.90 90.50 3.301E+004 3.25E+004 2.677E+004 1.559E+004 614.30 89.80 4.141E+004 4.461E+004 1.956E+004 722.90 90.80 3.246E+004 -2.761E+003 1.499E+004 Cs- 134 604.72 97.62 3.965E+004 3.43E+004 6.910E+004 1 .878E+004 795.86 85.46 3.432E+004 -1.989E+004 l. 576E+004 Cs-137 661.66 85. 10 3.645E+004 3.64E+004 3.721E+004 1.696E+004 Eu-152 121. 78 28.67 1.326E+005 1.24E+005 8.303E+003 6.476E+004 344.28 26.60 1.239E+005 l.398E+004 5.927E+004 1408.01 21. 07 1.403E+005 1. 22 7E+O 05 6.227E+004 Eu-154 123.07 40.40 9.429E+004 8.15E+004 8.089E+003 4.606E+004 723.30 20.06 1 .484E+005 1.219E+005 6.854E+004 1274.43 34.80 8.149E+004 7.309E+004 3.625E+004 Eu-155 86.55 30.70 1 .532E+005 1. 53E+005 -2.220E+OOS 7.511E+004 105.31 21.10 1. 949E+005 2.325E+004 9.539E+004

+ Tl-208 583.19* 85.00 l.576E+004 1.58E+004 2.268E+004 6.708E+003 Bi-212 727.33 6.67 4 .558E+005 4.56E+OOS 9.138E+004 2.109E+005

+ Pb-212 238.63* 43.60 3.963E+004 3.96E+004 3.796E+004 1 .852E+004

+ Bi-214 609.32* 45.49 3.738E+004 3.74E+004 8.131E+004 l .644E+004 1120 .29* 14.92 8.934E+004 1 .554E+OOS 3.492E+004 1764.49 15.30 2.216E+005 1 .885E+005 9.804E+004

+ Pb-214 295.22* 18 .42 9.874E+004 3.88E+004 8.266E+004 4.58BE+004 351.93* 35.60 3.877E+004 7.166E+004 1.736E+004 Ra-226 186.21 3.64 8.404E+005 8.40E+005 2.251E+005 4.067E+005 Ac-228 338.32 11. 27 2.556E+005 1. 33E+005 -7.607E+004 1 .216E+OOS 911.20 25.80 1.330E+005 1.143E+005 6.147E+004 968.97 15.80 1.988E+005 1. 740E+005 9.094E+004 Am-241 59.54 35.90 1. 537E+005 1.54E+005 -4.101E+004 7.515E+004

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[100]

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

Filename: 6279 Report Generated On 6/5/2018 1 : 40: 46 PM Sample Title B106201AFSFC012GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/5/2018 1:30:00 PM Acquisition Started 6/5/2018 1:30:45 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP lIN DATA VALIDATED DATE 1.2- ,-1.r TIME~

Q,,_~ _,

[101]

Peak Analysis Report 6/5/2018 1 : 40 ~ 46 PM Page 2

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Detector Name: 6279 sample

Title:

B106201AFSFC012GD Peak Analysis Performed on: 6/5/2018 1:40:46 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuu m No. start end centroid (keV) (keV) Area Uncert. Counts M 1 293- 378 300.39 75.07 0.72 l.16E+001 175.31 1. 66E+002 m 2 293- 378 369.40 92.34 0.73 3.69E+OOO 55.62 8.17E+001 3 946- 963 954.56 238.76 0.34 3.03E+001 30. 18 6.07E+001 4 1397- 1414 1405 .25 351.51 0.42 2.0lE+OOl 22. 51 3.19E+001 5 2322- 2339 2330.20 582.84 0.60 2.0lE+OOl 17.18 1.59E+001 6 2426- 2443 2434.99 609.04 1.14 4 .03E+001 19. 11 1.57E+001 7 5831- 5850 5840.75 1459.91 0.47 9.24E+001 20.16 2.56E+OOO M Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2 . 000 sigma

[102]

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Sample

Title:

Bl06201AFSFC012GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

e 11 .. 11 *

IDENTIFIED NUCLIDES * * * ' * * * * * * * * * !II I * * * * '

Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.999 1460.82* 10.66 l .09462E+006 2.57001E+005 Eu-155 0.309 86.55* 30.70 3.97481E+003 5.98635E+004 105 . 31 21.10 Tl-208 1.000 583. 19* 85 .00 1. 73407E+004 1. 49951E+004 Pb-212 1. 000 238.63* 43.60 2.89647E+004 2.92736E+004 Bi-214 0.454 609.32* 45.49 6.69006E+004 3.27102E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.434 295.22 18.42 351.93* 35.60 3.00042E+004 3.39126E+004

=Energy line found i n t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.999 1. 09 4621E+006 2.570012E+005 Eu-155 0.309 3.974807E+003 5.986345E+004 Tl-208 1. 000 1.734074E+004 1.499508E+004 Pb-212 1. 000 2.896466E+004 2.927364E+004 Bi-214 0.454 6.690055E+004 3.271021E+004 Pb-214 0.434 3. 00 0422E+004 3.391264E+004

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

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

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

Peak Locate Performed on: 6/5/2018 1 :40:46 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide M 1 75.07 1. 9407E-002 1505.55 M '"' First peak in a multiplet region m = Other peak in a multiplet region F -= Fitted singlet Errors quoted at 2 . 000 sigma

[104]

Nuclide MDA Report 6/5/2018 1 :40:46 PM Page 5

**** N U C L I D E MD A REPORT *****

Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC012GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 1.503E+D05 1. 5DE+005 1. 095E+OD6 5.911E+OD4 Co-60 1173.23 99.85 3.117E+D04 2.07E+004 1.146E+004 l. 409E+004 1332.49 99.98 2.065E+004 -1.808E+OD3 8.721E+003 Nb- 94 702.65 99. 81 2.905E+004 2.89E+004 -2.D88E+003 1.341E+004 871. 09 99.89 2.887E+004 8.179E+OD1 1.318E+004 Ag-108m 433.90 90.50 3.237E+004 3.02E+OD4 1 .155E+OD4 1 .527E+004 614.30 89.80 4. 296E+004 6.297E+004 2.034E+004 722.90 90.80 3.024E+004 -1. 768E+OD4 1.387E+004 Cs-134 604.72 97.62 4.033E+OD4 3.36E+D04 5.188E+OD4 1.912E+004 795.86 85.46 3.358E+D04 -3.929E+004 1.539E+004 Cs-137 661. 66 85.10 3 . 166E+004 3.17E+D04 -7.473E+003 1 .457E+004 Eu-152 121. 78 28.67 l.258E+D05 1.06E+005 5.441E+004 6.14DE+004 344.28 26.60 1 .154E+005 4.027E+004 5.5D3E+004 1408.01 21.07 1.059E+005 -6.571E+004 4.507E+004 Eu-154 123.07 40. 40 8.835E+OD4 8.31E+004 -2 .247E+004 4 .309E+004 723.30 20.06 1. 354E+D05 -1 .367E+OD5 6.207E+004 1274.43 34.80 8.312E+004 -7.136E+004 3.707E+004

+ Eu-155 86.55* 30.70 4.816E+D04 4 .82E+004 3.975E+003 2.263E+OD4 105.31 21.10 1.854E+005 1. 378E+005 9.063E+OD4

+ Tl-208 583.19* 85.00 2.318E+004 2.32E+D04 1. 734E+004 1 .042E+OD4 Bi-212 727.33 6.67 4.220E+005 4.22E+005 3.143E+004 l .94DE+005

+ Pb-212 238.63* 43.60 4.686E+OD4 4 .69E+004 2.896E+004 2.213E+OD4

+ Bi-214 609.32* 45.49 4.346E+004 4.35E+004 6.690E+004 1.949E+004 1120.29 14.92 2.589E+OD5 2.961E+OOS l.197E+005 1764.49 15.30 1. 896E+O 05 -8.717E+OD4 8.203E+004

+ Pb-214 295.22 18.42 1. 587E+005 5. 48E+OD4 -4.728E+004 7.585E+OD4 351.93* 35.60 5.476E+D04 3.000E+004 2.536E+D04 Ra-226 186.21 3.64 8.390E+005 8.39E+005 -l.495E+D05 4.06DE+005 Ac-228 338.32 11. 27 2.574E+005 1 .28E+D05 2.246E+005 l.225E+OD5 911. 20 25.80 l .28DE+005 1 .739E+D05 5.901E+OD4 968.97 15 .80 1 .988E+005 1.111E+005 9.094E+D04 Am-241 59.54 35.90 1.496E+005 1 .5DE+005 8.592E+004 7.311E+D04

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[105]

~***********************************************************************

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

Filename: 6279 Report Generated On 6/b/201S l: 00: 33 PM Sample Title B106201AFSFC013GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/5/2018 12:50: 00 PM Acquisition Started 6/5/2018 12:50:32 PM Live Time 600. 0 seconds Real Time 600.4 seconds Dead Time 0 .07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP lIN DATA VALIDATED DATE /d ... to -Ir QTIM~ o

~I' A.

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Detector Name: 6279 Sample

Title:

B106201AFSFC013GD Peak Analysis Performed on: 6/5/2018 1 :00:33 PM Peak Analysis From Channel: BS Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 179- 195 187. 10 46.71 0.25 3.92E+001 33.95 7.88E+001 M 2 249- 315 256. 14 63.99 1. 09 3.02E+001 19.98 1. 15E+O 02 m 3 249- 315 300.22 75.02 1.10 1.44E+002 32 .04 1 .35E+002 4 1170- 1187 1178.94 294.90 0.73 l.93E+001 27.21 4.87E+001 s 1398- 1415 1406.48 351.82 0.53 5.60E+001 24.54 2.80E+001 6 2031- 2048 2039.33 51 0 . 10 0.90 2.41E+001 17.33 1.49E+001 7 2320- 2337 2328.49 582.41 1. 59 2.98E+001 14.20 6.19E+OOO 8 2425- 2442 2433.92 608.77 1. 04 4.40E+001 17.90 1 . lOE+OOl 9 5829- 5848 5838.33 1459.30 1.60 8.74E+001 20.31 4.64E+OOO M - First peak in a multiplet region m ""- Other peak in a multiplet region F ::: Fitted singlet Errors quoted at 2.000 sigma

[107]

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

Sample

Title:

B106201AFSFC013GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

* * * * * * * *

I * * * * * * * *

IDENTIFIED NUCLIDES * * * * * * * * * * * * *

t I * * *

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.996 1460.82* 10 .66 1. 03419E+006 2.56649E+005 Tl-208 0.999 583.19* 85 .00 2.57563E+004 l .26514E+004 Bi-214 0.454 609.32* 45. 49 7.30527E+004 3.09593E+004 1120 .29 14 .92 1764.49 15.30 Pb-214 1.000 295.22* 18.42 4.97561E+004 7.05396E+004 351.93* 35.60 8.36310E+004 3.87417E+004 Am-241 0 .969 59.54* 35.90 3.50828E+004 2.42896E+004

=Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 .30 Errors guoted at 2. 000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.996 1. 034186E+006 2.566485E+005 Tl-208 0.999 2.575633E+004 1.26S141E+004 Bi-214 0.454 7.305267E+004 3.095926E+00 4 Pb-214 1 .000 7.578087E+004 3.395727E+00 4 Am-241 0.969 3.508283E+004 2.428956E+004

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

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

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

Peak Locate Performed on: 6/5/2018 1: 00:33 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak To l.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 46.71 6.5254E-002 86.72 m 3 75.02 2.4070E-001 22.18 6 Sl0.10 4. 0085E-002 72.07 M = First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma

[109]

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC013GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"'2 ) (pCi/MA2 ) (pCi/M"'2 ) (pCi/M"'2 )

+ K-40 1460.82* 10 .66 1 .866E+005 1.87E+005 1. 034E+006 7.729E+004 Co-60 1173.23 99.85 3.163E+004 2.31E+004 -1. 515E+004 l.432E+004 1332.49 99.98 2. 310E+004 l.541E+004 9.944E+003 Nb-94 702.65 99.81 2.850E+004 2.85E+004 -2.041E+004 l.313E+004 8 71. 09 99.89 2.992E+004 -1. 067E+004 1 .370E+004 Ag-108m 433.90 90.50 2.950E+004 2.95E+004 -1. 456E+004 1.384E+004 614.30 89.80 3.917E+004 1.316E+004 l.844E+004 722.90 90.80 3.307E+004 -1.035E+004 1.529E+004 Cs-134 604.72 97.62 3.644E+004 3.64E+004 5.752E+004 1.718E+004 795.86 85.46 3.747E+004 2.881E+002 1 .734E+004 Cs-137 661.66 85.10 3.589E+004 3.59E+004 2.715E+004 1 .668E+004 Eu-152 121.78 28.67 1. 231E+005 1 .23E+005 -2.763E+004 6.005E+004 344.28 26.60 1.328E+005 5.155E+004 6.371E+004 1408 . 01 21. 07 1.403E+005 1.227E+OOS 6.227E+004 Eu-154 123.07 40.40 8.706E+004 8.71E+004 3.688E+004 4.245E+004 723.30 20.06 1. 524E+005 1. 314E+005 7.057E+004 1274. 43 34.80 8.781E+004 1.412E+004 3.941E+004 Eu-155 86.55 30.70 l.544E+005 1 .54E+005 1.955E+005 7.571E+004 105.31 21.10 1.810E+005 -3.144E+004 8.843E+004

+ Tl-208 583.19* 85.00 1.523E+004 l.52E+004 2.576E+004 6.448E+003 Bi-212 727.33 6.67 4.795E+005 4.79E+005 -3.133E+005 2.227E+005 Pb-212 238.63 43.60 7.467E+004 7.47E+004 -3.876E+003 3.604E+004

+ Bi-214 609.32* 45.49 3.725E+004 3.72E+004 7.305E+004 1.638E+004 1120.29 14.92 2.178E+005 1.763E+005 9.917E+004 1764.49 15. 30 2.063E+005 1. 6 02E+O 05 9.039E+004

+ Pb-214 295.22* 18.42 1 .161E+005 5.18E+004 4.976E+004 5.456E+004 351.93* 35.60 5.185E+004 8.363E+004 2.390E+004 Ra-226 186.21 3.64 8.457E+005 8.46E+005 -1.638E+005 4.093E+005 Ac-228 338.32 11. 27 2.546E+005 1. 29E+005 -2.071E+OOS 1.211E+005 911.20 25.80 l. 293E+005 -5.457E+004 5.964E+004 968.97 15.80 1.988E+005 -3.098E+004 9.094E+004

+ Am-241 59.54* 35.90 6.106E+004 6. 11E+004 3.508E+004 2.896E+004

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[110]

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

Filename: 6279 Report Generated On 6/5/2018 10:18:29 AM Sample Title Bl06201AFSFC014GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 6/5/2018 10:08:00 AM Acquisition Started 6/5/2018 10:08:28 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP lIN DATA VALIDATED DATE1J-, ..1r w" af:,c.

TIMEaw

[111]

Peak Analysis Report 6/5/2018 10 : 18 :29 AM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSFC014GD Peak Analysis Performed on: 6/5/2018 10:18:29 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 293- 316 300.79 75.17 0.45 8.93E+001 75.68 3.20E+002 2 490- 505 497.33 124.35 0.38 6.57E+001 35. 10 8.03E+001 3 946- 963 954. 10 238.65 0 .45 -2.23E+OOO 30.08 6.92E+001 4 1072- 1089 1080.69 270.32 0.79 4.87E+OOO 22.78 3.BlE+OOl 5 1398- 1415 1406.63 35 1. 86 0.58 3.75E+001 2 1 .07 2.25E+001 6 2323- 2340 2331.47 583.15 0.46 2.59E+001 15.73 l.llE+OOl 7 2427- 2444 2435.86 609.26 0.71 4.19E+001 17.94 l.llE+OOl 8 5832- 5851 5841. 20 1 46 0 .02 2.07 6.80E+001 16.49 O.OOE+OOO M First peak in a multiplet region m ; Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[112]

Interference Corrected Activity Report 6/5/2018 10 : 18:29 AM Page 3

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Sample

Title:

B106201AFSFC014GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

* * * * * * * * !ti I' * * *

I e

I I IDENTIFIED NUCLIDES * * * * * * * * * * * * "

II *

ii * ,.

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M ... 2 ) Uncertainty K-40 0.999 1460.82* 10.66 8.05287E+005 2.07452E+005 Eu- 152 0.679 121.78* 28.67 7.38207E+004 4.21029E+004 344.28* 26.60 7.49804E+004 4.36865E+004 1408. 01 21. 07 Tl- 208 1.000 583.19* 85.00 2.24101E+004 1. 38660E+004 Pb-212 1. 000 238.63* 43.60 -2.13214E+003 2.87887E+004 Bi-214 0.454 609.32* 45.49 6.94896E+004 3.09305E+004 1120.29 14 .92 1764.49 15.30 Pb-214 0.434 295.22 18.42 351.93* 35.60 5.60247E+004 3.25749E+004

=Energy line found in t he spectrum.

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

[113]

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pci/MA2 ) Uncertainty K-40 0.999 8.052874E+005 2.074518E+005 Eu-152 0.679 7.382066E+004 4.209580E+004 X Eu-154 0.307 Tl-208 1.000 2.241012E+004 1.386597E+004 Pb-212 1.000 -2.132141E+003 2.878871E+004 Bi - 214 0 . 454 6.948958E+004 3.093045E+004 Pb-214 0.434 8.665629E+002 4.528140E+004

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

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

[114]

Interference Corrected Activity Report 6/5/2018 10:18:29 AM Page S

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Peak Locate Performed on: 6/5/2018 10 :18:29 AM Peak Locate From Channel : 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV} Counts per Second % Uncertainty Type Nuclide 1 75.17 1.4879E - 001 84.77 4 270.32 8.1202E-003 467.46 M ~ First peak in a multiplet region m ; Other peak in a multiplet region F; Fitted singlet Errors quoted at 2. 000 sigma

[115]

Nuclide MDA Report 6/5/2018 10: 18 :29 AM Page 6

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Detector Name: 6279 Sample Geometry: 3M90D CP lIN Sample

Title:

B106201AFSFC014GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yie ld Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M ... 2 ) (pCi/M"2 ) (pCi/M ... 2 ) (pCi/M ... 2 )

+ K-40 1460.82* 10 .66 3.205E+004 3.20E+004 8.053E+005 O. OOOE+OOO Co-60 1173 .23 99.85 3.209E+004 2.73E+004 -2.648E+004 1. 455E+004 1332.49 99.98 2.72SE+004 2.252E+004 1. 2 02E+O 04 Nb-94 702.65 99.81 2.554E+004 2.55E+004 -l.216E+004 l.165E+004 871.09 99.89 2.741E+004 l.143E+003 1.244E+004 Ag-108m 433.90 90.50 3.155E+004 3.16E+004 7.795E+003 l.487E+OD4 614.30 89.80 3.959E+004 4.072E+004 l .865E+004 722.90 90.80 3.184E+004 2.599E+003 1 .468E+004 Cs-134 604.72 97.62 3.790E+004 3.08E+004 3.022E+004 1.791E+004 795.86 85.46 3.083E+004 2.773E+003 l.402E+004 Cs-137 661 . 66 85.10 3.754E+004 3.75E+004 8.544E+002 1 .751E+004

+ Eu-152 121 .78* 28.67 6.055E+004 6.06E+004 7.382E+004 2.876E+004 344.28* 26.60 6.180E+004 7.498E+004 2.819E+004 1408. 01 21.07 1. 311E+005 4.876E+004 5.765E+004 Eu-154 123.07* 40 . 40 4.297E+004 4.30E+004 5.239E+004 2.041E+004 723.30 20.06 l.456E+005 -3.066E+004 6.716E+004 1274.43 34.80 7.457E+004 5.980E+004 3.279E+004 Eu-155 86.55 30.70 1 .539E+005 1 .54E+005 l .579E+OOS 7.546E+004 105.31 21. 10 1 .816E+005 -7.809E+004 8.872E+004

+ Tl-208 583.19* 85.00 l.940E+004 l.94E+004 2.241E+004 8.528E+003 Bi-212 727. 3 3 6.67 4 . 476E+005 4.48E+OD5 2.87BE+OOS 2.068E+005

+ Pb-212 238.63* 43.60 5.018E+004 5.02E+OD4 -2.132E+003 2.379E+004

+ Bi-214 609.32* 45.49 3.843E+004 3.84E+004 6.949E+004 1 .697E+004 1120.29 14.92 2.493E+005 -4.457E+D04 l. 149E+005 1764.49 15.30 2.166E+005 8.097E+004 9.556E+004

+ Pb-214 295.22 18 .42 l.656E+OOS 4.62E+004 1.241E+005 7.933E+004 351.93* 35.60 4 .618E+004 S.602E+004 2.107E+OD4 Ra-226 186.21 3.64 8.601E+005 8.60E+005 7.514E+OOS 4.165E+005 Ac-228 338.32 11. 27 2.639E+005 1. 15E+005 1 .49SE+004 1.257E+005 911. 2 0 25.80 1.147E+005 1. 952E+O 04 5.236E+OD4 968.97 15. 80 2.101E+005 l.424E+005 9.659E+004 Am-241 59.54 35.90 l.504E+005 1.50E+005 7.884E+004 7.351E+004

+ =Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[116]

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

Filename: 6279 Report Generated On 6/5/2018 9: 41 :01 AM Sample Title B106201AFSFC015GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3. 00 Peak L ocate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"'2 Sample Taken On 6/5/2018 9:30 : 00 AM Acquisition started 6/5/2018 9:31 :00 AM Live Time 600 . 0 seconds Real Time 600.S seconds Dead Time 0 .08 %

Energy Calibra.tion Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP lIN DATA VALIDATED DATE IJ.. ,.-11 TIME..Mt12 Ch°'j"4

[117]

Peak Analysis Report 6/5/2018 9:41: 01 AM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSFC015GD Peak Analysis Performed on: 6/5/2018 9:41:01 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 291- 346 300.33 75.05 1. 28 - l.25E+OOO 168.05 8.38E+002 2 727- 742 734.26 183.64 0.98 8.06E+OOO 3 1. 24 7.69E+001 3 944- 961 952.89 238.34 1. 08 1. 45E+001 3 1 .19 6.95E+001 4 1171- 1188 1179.68 295.08 1. 01 4.55E+001 2 1 .79 2.25E+001 5 1397- 1414 1405 .86 351.66 0.66 3.41E+D01 23.99 3.29E+001 6 2032- 2049 2040.23 510.33 0.39 3.15E+001 18.37 1. 55E+O 01 7 2424- 2442 2433.42 608.64 0.79 6.15E+001 19. 35 9.50E+OOO 8 4467- 4486 4476.62 1119.26 0.49 1.70E+001 11.76 5.00E+OOO 9 5829- 5849 5838.60 1459.37 1.20 7.48E+001 19.37 5.25E+OOO M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[118]

Interference Corrected Activity Report 6/5/2018 9:41:01 AM Page 3

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Sample

Title:

B106201AFSFC015GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

* * * * * * *

f * * * * * ' .. * ~ " IDENTIFIED NUCLIDES . . .... . ................

Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.997 1460.82* 10.66 8.84948E+005 2.41881E+005 Pb-212 1. 000 238.63* 43 .60 1 .38479E+004 2.99096E+004 Bi-214 0.743 609.32* 45.49 1 .02010E+005 3.43586E+004 1120 .29* 14 .92 l .22426E+005 8.52672E+004 1764 .49 15.30 Pb-214 1 .000 295.22* 18.42 1. l 7247E+005 5.91967E+004 35 1.93* 35.60 5.09057E+004 3.66357E+004 Ra-226 0.989 186.21* 3.64 8.00583E+004 3.10615E+005

=Energy line found in the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2) Uncertainty K-40 0 .997 8.849477E+005 2.418813E+005 Pb-212 1. 000 1. 384795E+004 2.990965E+004 Bi-214 0.743 1. 048623E+005 3.186863E+004 Pb-214 1.000 6.927831E+004 3.115237E+004 Ra-226 0.989 8.005831E+004 3.106154E+005

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

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

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

Peak Locate Performed on: 6/5/2018 9:4 1 : 01 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size J.Il Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.05 -2.0809E-003 -13459.

6 510.33 5.2438E-002 58.39 M = First peak in a mult iplet region m = Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[120]

Nuclide MDA Report 6/5/2018 9:41: 01 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC015GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/M"'2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2)

+ K-40 1460.82* 10.66 2.022E+005 2.02E+005 8.849E+005 8.506E+004 Co-60 1173.23 99. 85 3.299E+004 2.46E+004 1 .512E+003 l .500E+OD4 1332.49 99.98 2.457E+004 6.421E+OD3 1 .D68E+004 Nb-94 702.65 99. 81 2.850E+004 2.54E+004 -6.304E+003 1.313E+OD4 8 71. 09 99.89 2.545E+004 -1. 314E+003 l.146E+D04 Ag-108m 433.90 90.50 3.037E+004 3.04E+004 9.615E+D03 1.428E+004 614. 3 0 89.80 4.371E+004 5.412E+004 2.071E+004 722.90 90 .80 3.153E+004 -4.327E+004 l.452E+004 Cs-134 604.72 97.62 4.149E+004 3.28E+004 4.389E+004 l.970E+004 795.86 85.46 3.282E+004 -2.089E+004 1.S01E+OD4 Cs-137 661.66 85. 1 0 3.727E+004 3.73E+OD4 -6.629E+003 l .737E+004 Eu-152 121. 78 28.67 1.246E+005 1.21E+005 -8.162E+004 6.079E+004 344.28 26.60 1 .214E+005 6.503E+004 5.801E+D04 1408.01 21.07 1 .373E+005 -4.614E+D04 6.077E+004 Eu-154 123.07 40.40 8.698E+004 7.46E+004 -7.527E+004 4.241E+004 723.30 20.06 1. 413E+005 -2.434E+OOS 6.502E+004 1274.43 34.80 7.457E+004 -1.246E+004 3.279E+004 Eu-155 86.55 30.70 1 .498E+005 1.SOE+005 1.291E+005 7.340E+004 105.31 21.10 1.833E+005 3.266E+OOS 8.957E+OD4 Tl-208 583.19 85.00 3.718E+D04 3.72E+004 -1.410E+OD4 1 .742E+OD4 Bi-212 727.33 6.67 4.435E+D05 4.43E+005 -1.666E+005 2.047E+005

+ Pb-212 238.63* 43.60 5.017E+004 5.D2E+004 1. 385E+D04 2.379E+004

+ Bi-214 609.32* 45.49 3.541E+OD4 3.54E+004 1. 020E+005 1.546E+004 1120 .29* 14 .92 1.188E+005 1. 224E+005 4.968E+004 1764.49 15.30 2.009E+005 -3.681E+004 8.769E+004

+ Pb-214 295.22* 18.42 7.949E+004 5.55E+004 l.172E+005 3.626E+004 351.93* 35.60 5.554E+004 5.D91E+004 2.575E+004

+ Ra-226 186.21* 3.64 5.288E+005 5.29E+OD5 8.D06E+004 2.51DE+005 Ac-228 338.32 11. 27 2.400E+D05 1.24E+OOS -2.772E+005 1 .138E+D05 911. 20 25.80 1.242E+005 8.602E+004 5.71DE+004 968.97 15.80 1. 941E+D05 3.908E+004 8.857E+004 Am-241 59.54 35.90 l.502E+005 1 .SOE+OOS 5.506E+004 7.340E+004

+ = Nuclide identified during the nuclide identification

= Energy line found in the spectrum

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

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

[121]

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

Filename: 6279 Report Generated On 6/1/20 1 8 J; ll :57 PM Sample Title B106201AFSFC016GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/4/2018 3:01:00 PM Acquisition Started 6/4/2018 3: 01 :56 PM Live T ime 600.0 seconds Real Time 600.5 seconds Dead Time 0 . 08 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP lIN DATA VALIDATED DATE/J-&*H TIME /Ji'~

~y. ~~.

[122]

Peak Analysis Report 6/4/2018 3:11:58 PM Page 2

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Detector Name : 6279 Sample

Title:

B106201AFSFC016GD Peak Analysis Performed on: 6/4/2018 3:11:57 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 291- 306 298.22 74.52 0 .71 1. 04E+002 56.33 2.26E+002 2 947- 964 955. 10 238.90 0 .37 2.79E+001 30.35 6. 21E+001 3 1398- 1415 1406.34 35 1 .79 0 .46 4.67E+001 22.15 2.33E+001 4 2323- 2340 2331.78 583 . 23 0 .33 4.81E+OOO 17.01 2.02E+001 5 2428- 2445 2436.27 609.36 0 .61 3.24E+D01 20.09 2.06E+OD1 6 4471- 4490 4480.97 1120.35 0 .39 1 .50E+001 11.41 5.00E+OOO 7 5833- 5852 5842.96 1460.46 0 .81 7.00E+OOl 16.73 O.OOE+OOO M == First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 , 000 sigma

[123]

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Sample

Title:

B106201AFSFC016GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1 . 000 1460.82* 10.66 8.29147E+005 2.10876E+005 Tl-208 1 . 000 583.19* 85.00 4.15919E+003 1.47191E+004 Pb-212 1 . 000 238.63* 43.60 2.67319E+004 2.93886E+004 Bi-214 0 .744 609.32* 45.49 5.3852BE+004 3.39734E+004 1120.29* 14. 92 1.08083E+005 8.26674E+004 1764.49 15.30 Pb-214 0.434 295.22 18.42 351 .93* 35.60 6.97281E+004 3.46979E+004

~ Energy line found in t he spectrum.

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

[124]

Interference Corrected Activity Report 6/4/2018 3: 11: 58 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 8.291469E+005 2.108763E+005 Tl-208 1.000 4.159189E+003 1 .471905E+004 Pb-212 1.000 2.673189E+004 2.938860E+004 Bi-214 0 .744 6.168856E+004 3.142333E+00 4 Pb-214 0.434 6.972806E+004 3.469793E+00 4

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

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

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

Peak Locate Performed on: 6/4/2018 3: 11: 57 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 74.52 1.7395E-001 53.97 M ; First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma

[125]

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC016GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M ... 2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"'2 )

+ K-40 1460.82* 10.66 3.205E+004 3.21E+004 8.291E+005 O.OOOE+OOO Co-60 1173 .23 99.85 3.342E+004 2.59E+004 3.870E+004 l.522E+004 1332.49 99.98 2.595E+004 6.694E+003 1.137E+004 Nb-94 702.65 99. 81 2.676E+004 2.SOE+004 -1 .602E+003 1. 227E+004 871. 09 99.89 2.503E+004 -3.802E+003 1. 126E+004 Ag-108m 433.90 90.50 3.285E+004 3.28E+004 -2.079E+004 1.551E+004 614.30 89.80 4.101E+004 4.135E+004 1.936E+004 722.90 90.80 3.277E+004 -1. 956E+004 1.514E+004 Cs-134 604.72 97.62 3.681E+004 3.36E+004 4. 728E+004 1.736E+004 795.86 85.46 3.358E+004 -1. 043E+004 1.539E+004 Cs-137 661.66 85.10 3.473E+004 3.47E+004 l. 260E+004 1.610E+004 Eu-152 121. 78 28.67 1. 311E+005 1. 28E+005 8.200E+004 6.402E+004 344.28 26.60 l. 291E+OOS 1.317E+003 6.187E+004 1408.01 21.07 1. 279E+OOS -1.649E+004 5.603E+004 Eu-154 123.07 40. 40 9.278E+004 7.46E+004 9.856E+004 4.531E+004 723.30 20.06 l.511E+005 5.609E+003 6.990E+004 1274.43 34.80 7.457E+004 -4 .554E+004 3.279E+004 Eu-155 86.55 30.70 1.572E+OOS 1.57E+005 1 .594E+004 7.712E+004 105.31 21.10 1.877E+005 -1 .922E+005 9.180E+004

+ Tl-208 583.19* 85.00 2.572E+004 2.57E+004 4.159E+003 1 .169E+004 Bi-212 727.33 6.67 4.517E+OOS 4.52E+OOS 2.480E+005 2.089E+005

+ Pb-212 238.63* 43.60 4.742E+004 4.74E+004 2.673E+004 2.241E+004

+ Bi-214 609.32* 45 .49 4.968E+004 4.97E+004 S.385E+004 2.260E+004 1120.29* 14.92 1.188E+OOS 1. 081E+005 4.965E+004 1764.49 15.30 1.896E+005 1. 319E+005 8.203E+004

+ Pb-214 295.22 18.42 1. 647E+OOS 4.69E+004 -3.643E+004 7.887E+004 351.93* 35.60 4.689E+004 6.973E+004 2.142E+004 Ra-226 186.21 3.64 8.614E+005 8.61E+005 5.743E+005 4.172E+005 Ac-228 338.32 11.27 2.648E+OOS 1 .24E+OOS 2.493E+004 1 .262E+005 911.20 25.80 1.242E+005 5.035E+004 5.710E+004 968.97 15.80 2.123E+OOS 7.139E+004 9.768E+004 Am-241 59.54 35.90 1.528E+OOS 1.53E+OOS 1.241E+003 7.470E+004

+= Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[126]

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

Filename: 6279 Report Generated On 6/4/2018 2:59: 1 6 PM Sample Title Bl06201AFSFC017GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3 .00 Peak Locate Range (in channels} 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/4/2018 2:49:00 AM Acquisition Started 6/4/2018 2:49:15 PM Live Time 600 , 0 seconds Real Time 600.5 seconds Dead Time 0 , 08 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP lIN DATAVAUDA1ED DATEM-i*Ll TIME~

G1T

[127]

Peak Analysis Report 6/4/2018 2:59:16 PM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSFC017GD Peak Analysis Performed on: 6/4/2018 2:59:16 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 283- 309 290.65 72.63 0.68 1.53E+OG2 84.97 3.75E+002 2 1171- 1188 1179.84 295.12 1 .51 2.90E+001 23.72 3.40E+001 3 1399- 1416 1407.16 351. 99 0.61 2.46E+001 24.53 3.84E+001 4 2323- 2340 2331. 38 583.13 0.63 2.38E+001 16.00 1 .12E+001 5 2427- 2444 2435.42 609.15 1.19 4.90E+001 19.61 1 .40E+001 6 3634- 3651 3642.90 910.96 0.72 2.13E+001 14.14 8.73E+OOO 7 5832- 5852 5841.84 1460.18 0.43 7.8SE+001 18.71 2.53E+OOO M First peak in a multiplet region m == Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[128]

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Sample

Title:

B106201AFSFC017GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

* * * * * * *

lll t ** I It,* * *

IDENTIFIED NUCLIDES . ... ............. . ,. ......

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0 .999 1460.82* 10.66 9.29375E+005 2.35796E+005 Tl-208 1 . 000 583.19* 85.00 2.05961E+004 1.40494E+004 Bi-214 0.454 609.32* 45.49 8.13969E+004 3.39841E+004 1120.29 14.92 1764 .49 15.30 Pb-214 1 . 000 295.22* 18.42 7.48474E+004 6.22804E+004 351.93* 35.60 3.67363E+004 3.70614E+004

=Energy line found in the spectrum.

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

[129]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 9.293751E+OOS 2.357965E+OOS Tl-208 1.000 2.059611E+004 l .404939E+004 Bi-214 0.454 8.139694E+004 3.398414E+004 Pb-214 1. 000 4.670266E+004 3.184887E+004

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

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

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

Peak Locate Performed on ; 6/4/2018 2:59:16 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 72.63 2.5461E- 001 55.62 6 910.96 3.5444E-002 66.47 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 .000 sigma

[130]

Nuclide MDA Report 6/4/2018 2:59:16 PM Page 5

NUCLID E MD A R E P O R T *****

Detector Name: 6279 Sample Geometry: 3M90D CP lIN Sample

Title:

Bl06201AFSFC017GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10 .66 1. 491E+005 l.49E+005 9.294E+005 5.850E+004 Co-60 1173.23 99.85 3.255E+004 2.15E+004 3.649E+004 1.478E+004 1332.49 99.98 2. 151E+004 -8.354E+003 9.148E+003 Nb-94 702.65 99. 81 3.065E+004 3.06E+004 1.032E+004 l. 421E+004 871.09 99.89 3.060E+004 2.760E+004 1.404E+004 Ag-108m 433.90 90.50 3.172E+004 3. 17E+004 -3.223E+004 1.49SE+004 614. 3 0 89.80 4.200E+004 4 .620E+004 1.985E+004 722.90 90.80 3.593E+004 2.659E+004 1.672E+004 Cs - 134 604.72 97.62 3.915E+004 3.36E+004 5.122E+004 1.853E+004 795.86 85.46 3.360E+004 -1 .033E+004 l. 540E+004 Cs-137 661. 66 85.10 3.414E+004 3.41E+004 - 1.702E+004 1 .581E+004 Eu-152 121.78 28.67 1.290E+005 1 .17E+005 -2.420E+OOS 6.300E+004 344.28 26.60 1. 246E+005 -8.586E+003 5.962E+004 1408.01 21. 07 1 .175E+005 8.178E+004 S.085E+004 Eu-154 123.07 40. 40 9 . 134E+004 8.93E+004 -4.778E+003 4.459E+004 723.30 20.06 1.627E+OOS l .221E+005 7.572E+004 1274.43 34.80 8.932E+004 5.470E+004 4.016E+004 Eu-155 86.55 30.70 1.585E+005 1 .58E+005 -1.101E+004 7.776E+004 105. 31 21.10 1. 947E+005 -9.755E+004 9.527E+004

+ Tl-208 583.19* 85.00 2.036E+004 2. 04E+004 2.060E+004 9.011E+003 Bi-212 727.33 6.67 4.717E+005 4.72E+005 -7.857E+004 2.189E+005 Pb-212 238.63 43.60 7.426E+004 7.43E+004 -2.756E+004 3.583E+004

+ Bi-214 609.32* 45.49 4.196E+004 4 .20E+004 8.140E+004 1.874E+004 1120.29 14.92 2.518E+005 1.941E+005 1.161E+005 1764.49 15 .30 2.166E+005 1. 791E+005 9.556E+004

+ Pb-214 295.22* 18 .42 9.653E+004 5.92E+004 7.485E+004 4.478E+004 351.93* 35.60 5.919E+004 3.674E+004 2.757E+004 Ra-226 186.21 3.64 8.768E+OOS 8.77E+OOS 4. 372E+OOS 4.249E+005 Ac-228 338.32 1 1. 27 2.556E+005 1.33E+005 l . 837E+004 1.216E+005 911. 2 0 25.80 1.330E+005 1. 510E+005 6.147E+001 968.97 15.80 2.034E+005 5.282E+004 9.324E+004 Am-241 59.54 35.90 1. 473E+005 l .47E+005 -5.915E+004 7.196E+004

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[131]

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

Filename: 6279 Report Generated On 6/5/2018 9:52:37 AM Sample Title B106201AFSFC018GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels} 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M... 2 Sample Taken On 6/5/2018 9:42:00 AM Acquisition Started 6/5/2018 9:42:35 AM Live Time 600. 0 seconds Real Time 600.4 seconds Dead Time 0 .07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATA VAUDAlED DATE/3*' .. /f TIME~

Wt-b?J, '

[132]

Peak Analysis Report 6/5/2018 9:52:37 AM Page 2

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Detector Name: 6279 Sample

Title:

Bl06201AFSFC018GD Peak Analysis Performed on: 6/5/2018 9:52:36 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 179- 194 186.13 46.47 0.43 2.94E+001 30.10 6.56E+001 2 285- 308 299.12 74.75 0.63 l .32E+002 75.25 3.21E+002 3 944- 961 952.45 238.23 0.72 2.23E+001 3 4 .01 8.07E+001 4 1170- 1187 1178.02 294.67 0.55 3.7SE+001 2 1. 08 2.25E+001 5 1397- 1414 1405.63 351. 61 0.60 4.19E+001 23.40 2.91E+001 6 2425- 2442 2433.53 608.67 1. 08 3.99E+001 20 . 57 2.0lE+OOl 7 5827- 5846 5836.75 1458.91 1. 39 8.00E+OOl 19.75 5.00E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[133]

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Sample

Title:

Bl06201AFSFC018GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENT IFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.994 1460 . 82* 10.66 9.46891E+005 2.47786E+005 Pb-212 1.000 238.63* 43.60 2.13367E+004 3.27012E+004 Bi-214 0.453 609.32* 45.49 6.61843E+004 3.50371E+004 1120.29 14.92 1764 .49 15.30 Pb - 214 1. 000 295.22* 18.42 9.65064E+004 5.64258E+004 351.93* 35.60 6.25820E+004 3.61767E+004

~ Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M2 ) Uncertainty K-40 0 .994 9.468909E+005 2.477862E+005 Pb-212 1 .000 2. 1 33668E+004 3.27012SE+004 Bi-214 0 .453 6.618430E+004 3.503715E+004 Pb - 214 1 .000 7.246456E+004 3.045487E+004

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

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

- - - - U N I D E N T I F I E D PE AK S **********

Peak Locate Performed on: 6/5/2018 9:52:36 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. . (keV) Counts per Second % Uncertainty Type Nuclide 1 46.47 4.9004E-002 102.36 2 74.75 2.2042E-001 56.90 M = First peak in a multiplet region m = Other peak in a multiplet region F "' Fitted singlet Errors quoted at 2 . 000 sigma

[135]

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC018GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 l .949E+OOS 1.95E+005 9.469E+005 8.145E+004 Co - 60 1173 .23 99.85 2.972E+004 2 . 59E+004 -2 . 731E+004 l .336E+004 1332.49 99.98 2.595E+004 -2.00SE+004 l.137E+004 Nb-94 702.65 99.81 2.793E+004 2.54E+004 2.855E+004 1.285E+004 871. 09 99.89 2.54SE+004 -6.926E+003 1.146E+004 Ag-108m 433.90 90.50 3.301E+004 3.02E+004 -1.353E+004 l .559E+004 614.30 89.80 4.352E+004 3.090E+004 2.062E+004 722.90 90.80 3.024E+004 - 4.711E+002 1.387E+004 Cs-134 604.72 97.62 3.948E+004 3.12E+004 2.474E+004 1.870E+004 795.86 85.46 3.124E+004 -3.752E+004 l.422E+004 Cs-137 661. 66 85 .10 3.560E+004 3.56E+004 -2. 400E+004 1 .654E+004 Eu-152 121. 78 28.67 1.278E+005 1.14E+OOS -3.301E+004 6.240E+004 344.28 26.60 1.284E+005 9.609E+004 6.153E+004 1408. 01 21.07 l.138E+OOS 7.593E+004 4.899E+004 Eu-154 123.07 40.40 9.133E+004 6.68E+004 6.354E+004 4 .458E+004 723.30 20.06 1. 413E+005 1.010E+005 6.502E+004 1274. 43 34.80 6.683E+004 7.178E+003 2.892E+004 Eu-155 86.55 30.70 1.548E+OOS 1.SSE+005 -5.544E+004 7.593E+004 105.31 21. 10 1. 838E+005 -9.586E+004 8.985E+004 Tl-208 583.19 85. 00 3.671E+004 3.67E+004 1.177E+004 l.719E+004 Bi-212 727.33 6.67 4 . 264E+005 4.26E+005 -8.507E+004 l .962E+005

+ Pb-212 238.63* 43.60 5.398E+004 5.40E+004 2.134E+004 2.569E+004

+ Bi-214 609.32* 45.49 4 .879E+004 4.88E+004 6.618E+004 2.215E+004 1120 . 29 14.92 2.542E+005 3.963E+004 l.173E+OOS 1764.49 15.30 2.57SE+005 2.639E+005 1.160E+005

+ Pb-214 295.22* 18.42 7.963E+004 5.19E+004 9.651E+004 3.633E+004 351.93* 35.60 5.192E+004 6.258E+004 2.394E+004 Ra-226 186.21 3.64 8.430E+005 8.43E+OOS 2.353E+005 4.080E+OOS Ac-228 338.32 11. 27 2.556E+005 1. 27E+005 -3.357E+005 1.216E+005 911. 20 25.80 1.268E+005 S. 681E+ 004 5. 838Ei 004 968.97 15.80 1.868E+005 1. 062E+005 8.491E+004 Am-241 59.54 35.90 1. 4 74E+005 l.47E+005 4.860E+004 7.201E+004

+ ; Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[136]

- - - - GAMM A SPECTRUM A N A L Y S I S *****

Filename : 6279 Report Generated On 6/5/2018 10 :04:20 AM Sample Title B106201AFSFC019GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Samp le Taken On 6/5/2018 9: 54 : 00 AM Acquisition Started 6/5/2018 9:54:18 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP lIN DATA VALIDATED DATEa-4'-/f TIME h{l<I()

~7+

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Peak Analysis Report 6/5/2018 10 : 04 :20 AM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSFC019GD Peak Analysis Performed on: 6/5/2018 10:04:19 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 291- 347 300.07 74.99 0.90 1.85E+002 152.28 6.88E+002 2 944- 961 952.97 238.36 1. 37 3.46E+001 29.58 5.64E+001 3 1171- 1188 1179.17 294.96 0.35 2.69E+001 24.57 3.81E+001 4 1398- 1415 1406.43 351.81 1.12 4.17E+001 1 9.14 1.53E+001 5 2426- 2443 2434.08 60 8 .81 0.88 5.20E+001 17. 37 6.97E+OOO 6 3634- 3651 3642.20 91 0 .79 1. 08 1.71E+001 12.69 6.92E+OOO 7 5831- 5850 5840.64 1459.88 0.37 8.70E+001 18.65 O.OOE+OOO 8 7046- 7065 7055.68 1763.11 0.50 1.50E+001 7.75 O.OOE+OOO M = Fi rst peak in a multiplet region m = other peak in a multiplet region F Fi tted singlet Errors quoted at 2 . 000 sigma

[138]

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Sample

Title:

B106201AFSFC019GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB r * * * * * * * * * * * *

I * * ,.

r IDENTIFIED NUCLIDES . . . . .......... .......

Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0 .999 1460.82* 10.66 1.03022E+006 2.38331E+005 Pb-212 1 .000 238.63* 43.60 3.31001E+004 2.87959E+004 Bi-214 0 .709 609.32* 45.49 8.63164E+004 3.06293E+004 1120.29 14.92 1764.49* 15 .30 1. 41278E+005 7.38282E+004 Pb-214 1. 000 295.22* 18.42 6.92693E+004 6.42481E+004 351.93* 35.60 6.23093E+004 3.00680E+004

= Energy line found in the spectrum.

@ - Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 .30 Errors quoted at 2. 000 sigma

[139]

Interference Corrected Activity Report 6/5/2018 10:04:20 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.999 1. 030225E+006 2.383307E+005 Pb-212 1.000 3.310013E+004 2.879593E+004 Bi-214 0 .709 9. 4 38728E+004 2.829118E+00 4 Pb-214 1 .000 6.355981E+004 2.723324E+004

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

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

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

Peak Locate Performed on: 6/5/2018 10 :04:19 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 74.99 3.0906E-001 82.12 6 910.79 2.8472E-002 74.31 Sum M First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma

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Nuclide MDA Report 6/5/2018 10:04:20 AM Page 5

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC019GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/M ... 2 ) (pCi/MA2)

+ K-40 1460.82* 10 .66 3.204E+004 3.20E+004 1.030E+006 O. OOOE+OOO Co-60 1173.23 99.85 2.972E+004 2.85E+004 -2.157E+OD4 1 .336E+OD4 1332.49 99.98 2.848E+004 -1.482E+OD3 1.264E+004 Nb-94 702.65 99.81 2.959E+004 2.85E+004 7 . 537E+003 1.368E+004 871. 09 99.89 2.852E+004 -3.205E+004 l.300E+OD4 Ag-108m 433.90 90.50 2.709E+004 2.71E+004 9.205E+OD3 1 .263E+OD4 614.30 89.80 4.081E+004 4.559E+004 1 .926E+004 722.90 90.80 2.991E+004 -2.489E+004 1.371E+004 Cs-134 604.72 97.62 3.999E+004 3.54E+OD4 6.886E+004 1.895E+004 795.86 85.46 3.541E+004 -l .353E+004 1.630E+004 Cs-137 661. 66 85.10 3.645E+004 3.64E+004 8.370E+003 1.696E+004 Eu-152 121. 78 28.67 1 .242E+005 l. 14E+005 3.653E+003 6.056E+004 344.28 26.60 1 .139E+005 -6.145E+004 S.426E+004 1408.01 21. 07 1.279E+OD5 3.307E+004 5.603E+004 Eu-154 123.07 40. 40 8.690E+004 8.15E+OD4 -8.466E+004 4.237E+OD4 723.30 20.06 1. 369E+D05 -1 .060E+OOS 6.282E+004 1274.43 34.80 8.149E+004 8.306E+002 3.625E+004 Eu-155 86.55 30.70 1.507E+005 1.51E+OOS -6.360E+004 7.389E+004 105.31 21. 10 1.823E+005 -2.065E+OD5 8.908E+004 Tl-208 583.19 85.00 3.624E+004 3.62E+004 -4.628E+OD2 1.695E+004 Bi-212 727.33 6.67 4.35DE+005 4.35E+OOS 1. 666E+005 2.00SE+OOS

+ Pb-212 238.63* 43.60 4.529E+004 4.53E+004 3.310E+OD4 2.135E+004

+ Bi-214 609.32* 45.49 3.09DE+004 2.55E+004 8.632E+OD4 1.320E+004 1120.29 14. 92 2.315E+005 2.117E+005 l.060E+005 1764.49* 15.30 2.549E+004 1. 413E+005 O.OOOE+OOO

+ Pb-214 295.22* 18.42 l. 013E+005 3.87E+004 6.927E+004 4.719E+004 351. 93* 35.60 3.873E+OD4 6.231E+004 1 .735E+004 Ra-226 186.21 3.64 8.161E+005 8.16E+OD5 -4.951E+OOS 3.945E+005 Ac-228 338.32 11. 27 2.450E+OOS 1 .31E+005 1.405E+005 1.163E+OD5 911.20 25.80 1. 305E+005 1. 04SE+O OS 6.025E+004 968.97 15.80 2.101E+OOS 7.244E+004 9.659E+004 Am-241 59. 54 35.90 1.446E+OOS l.45E+OOS 8.405E+004 7.060E+004

+ ~ Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[141]

- - - - i******************************************************************

- - - - GAMM A SPECTRUM A N A L Y S I S *****

Filename: 6279 Report Generated On 6/5/2018 1 :13:50 PM Sample Title B106201AFSFC020GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"'2 Sample Taken On 6/5/2018 1:03:00 PM Acquisition Started 6/5/2018 1:03:49 PM Live Time 600. 0 seconds Real Time 600 .4 seconds Dead Time 0.07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATA VALIDATED OATElN*i,*/C-TIME 1-11/tJ Q.njd;~

[142]

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Detector Name: 6279 Sample

Title:

B106201AFSFC020GD Peak Analysis Performed on: 6/5/2018 1 :13 :50 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 291- 350 299.69 74.89 0.96 1.34E+002 164. 41 7.82E+002 2 945- 962 953.79 238.57 0.67 3.58E+001 30.53 6.02E+001 3 1398- 1415 1406 .48 351.82 0.39 4 .12E+001 27.81 4.68E+001 4 2322- 2339 2330.54 582.92 0.42 1 .45E+001 18.78 2.25E+001 5 2425- 2444 2434.65 608.95 0.92 6 .50E+001 16.12 O.OOE+OOO 6 2634- 2651 2642.53 660.92 0.46 1 .17E+001 8.92 2.34E+OOO 7 5831- 5850 5840.46 1459.83 1. 50 6.37E+001 18.87 7.32E+OOO M ""- First peak in a multiplet region m Other peak in a multiplet region F - Fitted singlet Errors quoted at 2 . 000 sigma

[143]

Interference Corrected Activity Report 6/5/2018 1:13:50 PM Page 3

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Sample

Title:

Bl06201AFSFC020GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB

. ....... .. ....... ..... - IDENTIFIED NUCLIDES . . . ... ........ ' - " ... ' -

Nuclide Id Energy Yield Activity Activity Name Confidence {keV) {%) (pCi/M"2 ) Uncertainty K-40 0.998 1460.82* 10.66 7.54056E+005 2.32892E+005 Cs-137 0.999 661.66* 85. 10 l.08771E+004 8.42525E+003 Tl-208 1. 000 583.19* 85. 00 l.25340E+004 1.63075E+004 Pb-212 1.000 238.63* 43.60 3.42559E+004 2.97392E+004 Bi-214 0.454 609.32* 45.49 1 .07849E+005 2.97297E+004 1120 .29 14.92 1764.49 15. 30 Pb-214 0.434 295.22 18.42 351.93* 35.60 6.15508E+004 4.25604E+004

=Energy line found in the spectrum.

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

[144]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0. 998 7.540556E+005 2.328921E+OOS Cs-137 0. 999 1. 087712E+004 8.42524SE+003 Tl-208 1.000 l. 253399E+004 l .630753E+004 Pb-212 1. 000 3.425588E+004 2.973923E+004 Bi-214 0.454 1.078494E+OOS 2.972968E+004 Pb-214 0.434 6.155076E+004 4.256045E+004

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

~ c Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2.000 sigma

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

Peak Locate Performed on : 6/5/2018 1:13:50 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 74.89 2.2337E-001 122.68 M = First peak in a multip let region m ~ Other peak in a multip let region F : Fitted singlet Errors quoted at 2 , 000 sigma

[145]

Nucl ide MDA Report 6/5/2018 1 :13:50 PM Page 5

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC020GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (l:eV) ( %) (pCi/M"2 ) (pCi/M"2 } (pCi/M"2 } (pCi/M"2 }

+ K-40 1460.82* 10. 66 2.283E+005 2.28E+005 7.541E+005 9.813E+004 Co-60 1173.23 99.85 3.386E+004 2.79E+004 3.501E+003 1 .543E+004 1332.49 99.98 2.787E+004 6.742E+003 1 .233E+004 Nb-94 702.65 99.81 2.706E+004 2.63E+004 9.10BE+003 1 .242E+004 871.09 99.89 2.625E+004 -1. 071E+004 1.187E+004 Ag-108m 433.90 90.50 2.950E+004 2.78E+004 -8.763E+003 l.384E+004 614.30 89.80 4.200E+004 1.519E+004 1.985E+004 722.90 90.80 2.782E+004 2.140E+004 1. 267E+004 Cs-134 604.72 97.62 3.826E+004 3.20E+004 -8.404E+003 1 .809E+004 795.86 85. 46 3.204E+004 -3.066E+004 1 .462E+004

+ Cs-137 661.66* 85.10 1 . 134E+004 1 .13E+004 1.088E+004 4.406E+003 Eu-152 121. 78 28.67 1.298E+005 l .30E+005 6.741E+004 6.33BE+004 344.28 26.60 l.331E+005 -1 .089E+004 6.388E+004 1408.01 21. 07 1 .570E+005 -1 .839E+003 7.061E+004 Eu-154 123.07 40.40 9.12SE+004 7.08E+004 5.606E+004 4 .455E+004 723.30 20.06 1.243E+OOS 9.335E+004 5.652E+004 1274.43 34.80 7.082E+004 1.853E+004 3.092E+004 Eu - 155 86.55 30.70 1.549E+005 l .SSE+005 -7.115E+004 7.597E+004 105.31 21 . 10 1.840E+005 -4 .626E+004 8.992E+004

+ Tl-208 583.19* 85.00 2.676E+004 2.68E+004 1 .253E+004 1.221E+004 Bi-212 727.33 6.67 3.801E+005 3.BOE+OOS -1 .139E+005 1.730E+OOS

+ Pb-212 238.63* 43.60 4.681E+004 4.68E+004 3.426E+004 2.211E+004

+ Bi-214 609.32* 45.49 4.490E+003 4 .49E+003 1.078E+005 O.OOOE+OOO 1120. 29 14.92 1.767E+005 1.585E+OOS 7.862E+004 1764.49 15.30 2.166E+005 8.221E+004 9.556E+004

+ Pb-214 295.22 18.42 1. 661E+005 6.47E+004 1. 0 76E+005 7.955E+004 351.93* 35.60 6.468E+004 6.155E+004 3.032E+004 Ra-226 186.21 3.64 8.483E+005 8.4BE+OOS -4.9SOE+OOS 4.106E+005 Ac-228 338.32 11.27 2.64BE+005 1.37E+OOS -2.080E+004 1.262E+OOS 911. 2 0 25.80 1.365E+005 4 . 625E+004 6.325E+004 968.97 15.80 2.101E+OOS 3.770E+004 9.659E+004 Am-241 59.54 35.90 1.469E+005 1. 47E+005 1.767E+OOS 7.178E+004

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[146]

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

Filename: 6279 Report Generated On 6/5/2018 1 :28:36 PM Sample Title B106201AFSFC021GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identi fication Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/5/2018 1:18: 00 PM Acquisition Started 6/5/2018 1:1 8 : 34 PM Live Time 600. 0 seconds Real Time 600. 4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATA VALIDATED DATE/2 .. ,-/f Ci)?Hj TIME~

,(

[147]

Peak Analysis Report 6/5/2018 1: 28: 36 PM Page 2

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Detector Name: 6279 Sample

Title:

Bl06201AFSFC021GD Peak Analysis Performed on: 6/5/2018 1: 28:35 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 285- 347 338.42 84.58 0.59 l.59E+002 172.72 8.01E+002 2 945- 962 953.21 238.43 0.40 2.85E+001 30.90 6.35E+001 3 1171- 1188 1179.80 295. 11 0.74 1.85E+001 22.03 3.15E+001 4 1398- 1415 1406.53 35 1. 83 0.98 2.45E+001 23.14 3.3SE+001 5 2427- 2444 2435.24 609.10 0.89 4.18E+001 15.75 6.19E+OOO 6 3634- 3651 3642.17 910.78 0.40 l .91E+001 12.16 4.88E+OOO 7 5832- 5851 5841.84 146 0 . 18 1. 05 8.66E+001 19 .46 2.37E+OOO 8 7047- 7066 7056 . 98 1763.44 0 .50 1.20E+001 6.93 O.OOE+OOO M "" Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2 . 000 sigma

[148]

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

Sample

Title:

B106201AFSFC021GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB 4

e * * * *

f I

o, * * * * !

I I IDENTIFIED NUCLIDES * '

I "' f * * * * * * * *

ft * * *

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10 .66 1. 02602E+006 2.47116E+005 Eu-155 0.336 86.55* 30.70 1. 75849E+005 1 .93864E+005 105.31 21 .10 Pb-212 1. 000 238.63* 43.60 2.72424E+004 2.98835E+004 Bi-214 0.710 609.32* 45.49 6.93867E+004 2.74301E+004 1120.29 14.92 1764.49* 15.30 1.13037E+005 6.58871E+004 Pb-214 1.000 295.22* 18.42 4.76747E+004 5.72809E+004 351. 93

35.60 3.65818E+004 3.49960E+004

=Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA 2 ) Uncertainty K-40 0 .999 1.026015E+006 2.471160E+005 Eu-155 0.336 1.758495E+OOS 1. 938644E+005 Pb-212 1. 000 2.724236E+004 2.988351E+00 4 Bi-214 0 .710 7.583473E+004 2.532323E+004 Pb-214 1 .000 3.959691E+004 2.986354E+004

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

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

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

Peak Locate Performed on: 6/5/2018 1:28:35 PM Peak Locate From Channel : 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 6 910.78 3.1875E-002 63.59 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma

[150]

Nuclide MDA Report 6/5/2018 1 :28:36 PM Page 5

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Detector Name: 6279 Sample Geometry: 3M90D CP lIN Sample

Title:

B106201AFSFC021GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/M ... 2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 l .427E+005 1 .43E+005 1.026E+006 5.531E+004 Co-60 1173.23 99.85 2.871E+004 2.66E+004 -7.286E+003 1.286E+004 1332.49 99.98 2.661E+004 2.134E+004 l.170E+004 Nb-94 702.65 99.81 3.090E+004 3.09E+004 2.064E+004 1 .434E+004 871.09 99.89 3.254E+004 8.890E+003 1 .501E+004 Ag-108m 433.90 90.50 3.055E+004 3.0SE+004 -4.360E+004 l.436E+004 614.30 89.80 3.565E+004 3.788E+003 1.668E+004 722.90 90.80 3 .121E+004 -5.608E+004 1.436E+004 Cs-134 604 . 72 97.62 3.331E+004 3.33E+004 -7.142E+003 1.561E+004 795.86 85.46 3.645E+004 -5.557E+003 1. 683E+004 Cs-137 661.66 85. 10 3.503E+004 3.50E+004 -5.834E+003 1 .625E+004 Eu-152 121.78 28.67 1. 261E+005 9.73E+004 -l.025E+OOS 6.152E+004 344.28 26.60 1.188E+005 2.449E+004 5.673E+004 1408.01 21.07 9.734E+004 -1. 639E+004 4.076E+004 Eu-154 123.07 40.40 8.977E+004 7.46E+004 l.491E+005 4.381E+004 723.30 20.06 l.442E+005 7.713E+003 6.645E+004 1274.43 34.80 7.457E+004 -4.840E+004 3.279E+004

+ Eu- 155 86.55* 30.70 3.132E+OOS 1 .88E+005 1.758E+005 1.551E+005 105.31 21.10 l.884E+OOS 9.362E+004 9.215E+004 Tl-208 583.19 85.00 3.718E+004 3.72E+004 -3.356E+004 1 .742E+004 Bi-212 727.33 6.67 4 .393E+005 4 .39E+005 -6.107E+005 2.026E+005

+ Pb-212 238.63* 43.60 4.822E+004 4.82E+004 2.724E+004 2.281E+004

+ Bi-214 609.32* 45.49 2.902E+004 2.55E+004 6.939E+004 l.226E+004 1120 .29 14.92 2.393E+005 8.102E+004 1.099E+005 1764.49* 15.30 2.549E+004 l .130E+005 O.OOOE+OOO

+ Pb-214 295.22* 18.42 9.295E+004 5.54E+004 4.767E+004 4.299E+004 351.93* 35.60 5.544E+004 3.658E+004 2.570E+004 Ra-226 186.21 3.64 8.522E+OOS 8.52E+005 -3.846E+004 4.126E+005 Ac-228 338.32 11. 27 2.546E+005 1 .34E+005 -1.836E+005 1.211E+005 911.20 25.80 1.342E+005 3.885E+004 6.207E+004 968.97 15.80 2.057E+OOS 7.142E+004 9.437E+004 Am-241 59.54 35.90 l. 476E+005 1. 48E+O 05 1.368E+005 7.213E+004

+ Nuclide identified during the nuclide identification

: Energy line found in the spectrum

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

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

[151]

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

Filename : 6279 Report Generated On 6/5/2018 2: 30: 00 PM Sample Title Bl06201AFSFC022GD Sample Description Ul Diesel Fuel Oil Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/5/2018 2: 19 : 00 PM Acquisition Started 6/5/2018 2:19:59 PM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 , 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATA VALIDATED DATE/,/-'-/I TIME4d a~

[152]

Peak Analysis Report 6/5/2018 2:30: 00 PM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSFC022GD Peak Analysis Performed on: 6/5/2018 2: 30: 00 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 286- 314 298.95 74 .71 0.98 2.36E+002 8 1. 59 3.09E+002 2 946- 963 954.13 238.65 0.30 3.59E+001 27.51 4.71E+001 3 1173- 1190 1181.02 295.42 0.49 3.65E+001 20.41 2.05E+001 4 1399- 1416 1407.68 352. 12 0.82 4.05E+001 25.00 3.55E+001 5 2428- 2445 2436.43 609 .40 0. 35 4.04E+001 18.09 1.16E+001 6 5836- 5855 5845.27 146 1 . 04 0.85 6.46E+001 17.07 2.39E+OOO M "" First peak in a multiplet region m = Other peak in a multiplet region F ,; Fitted singlet Errors quoted at 2 . 000 sigma

[153]

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Sample

Title:

B106201AFSFC022GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. . . . . . . . . . . . .. .. . . . . . IDENTIFIED NUCLIDES . ' . . . . . . . . .. . . . .. ~ ' . . ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"'2 ) Uncertainty K-40 1. 000 1460.82* 10.66 7.65494E+005 2.12874E+005 Pb-212 1.000 238.63* 43.60 3.43828E+004 2.69141E+004 Bi-214 0.454 609.32* 45.49 6.70453E+004 3.10952E+004 1120.29 14.92 1764.49 15.30 Pb-214 1. 000 295.22* 18.42 9.41876E+004 S.47452E+004 351.93* 35.60 6.05753E+004 3.84488E+OD4

= Energy line found in t he spectrum.

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

[154]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 7.654939E+005 2.128742E+005 Pb-212 1. 000 3.438278E+004 2.691405E+004 Bi-214 0.454 6.704529E+004 3.109521E+004 Pb-214 1.000 7. 16 7823E+004 3.146414E+004

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

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

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

Peak Locate Performed on : 6/5/2018 2: 30: 00 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second % Uncertainty Type Nuclide 1 74. 71 3.9392E-001 3 4.52 M = First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[155]

Nuclide MDA Report 6/5/2018 2: 30: 00 PM Page 5

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC022GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 1.438E+005 l.44E+005 7.65SE+OOS 5.589E+004 Co-60 1173.23 99.85 3.163E+004 2.97E+004 9.077E+003 1 .432E+004 1332.49 99.98 2.966E+004 -2.549E+004 1 .323E+004 Nb-94 702.65 99.81 2.490E+004 2.49E+004 -5.353E+003 l .133E+004 871. 09 99.89 2.815E+004 2.488E+004 1 .282E+004 Ag-108m 433.90 90.50 3.188E+004 3.19E+004 1.09SE+004 1 .503E+004 614.30 89.80 4.000E+004 1. 642E+O 04 1 .886E+004 722.90 90.80 3.366E+004 -5.799E+003 1.559E+004 Cs-134 604.72 97.62 3.530E+004 3.47E+004 4 .440E+004 1.661E+004 795.86 85.46 3.469E+004 -3.611E+003 1.595E+004 Cs-137 661.66 85.10 3.503E+004 3.50E+004 3.290E+004 1.625E+004 Eu-152 121. 78 28.67 1.218E+005 1. 20E+005 2.719E+004 5.937E+004 344.28 26.60 1.195E+005 -6.160E+004 5.710E+004 1408. 01 21.07 1.245E+005 5.047E+004 5.435E+004 Eu-154 123.07 40.40 8.592E+004 5.54E+004 -4.397E+004 4 .188E+004 723.30 20.06 l.497E+005 -1 .562E+OOS 6.922E+004 1274.43 34.80 5.536E+004 -6.552E+003 2.319E+004 Eu-155 86.55 30.70 1 .507E+OOS 1.51E+005 4.048E+004 7.384E+004 105.31 21. 10 1 .838E+005 8.221E+004 8.985E+004 Tl-208 583. 19 85.00 3.787E+004 3.79E+004 3.323E+004 1. 777E+004 Bi-212 727.33 6.67 4.476E+OOS 4.48E+005 1.426E+005 2.068E+005

+ Pb-212 238.63* 43.60 4.158E+004 4.16E+004 3.438E+004 1.950E+004

+ Bi-214 609.32* 45.49 3.965E+004 3.96E+004 6.705E+004 1.758E+004 1120.29 14 .92 2.393E+005 -2.475E+OOS 1.099E+005 1764.49 15. 30 2.063E+005 1 .602E+OOS 9.039E+004

+ Pb-214 295.22* 18.42 7.674E+004 5.69E+004 9.419E+004 3.488E+004 351.93* 35.60 5.694E+004 6.058E+004 2.645E+004 Ra-226 186.21 3.64 8.614E+005 8.61E+005 5.732E+005 4 .172E+005 Ac-228 338.32 11 .27 2.254E+005 1 .2SE+OOS -2.638E+004 1.065E+005 911. 20 25.80 1. 255E+005 1 .279E+005 5.774E+004 968.97 15.80 2.166E+005 S.137E+004 9.983E+004 Am-241 59.54 35.90 1. 516E+005 1.52E+005 8.627E+004 7.414E+004

+=Nuclide identified during the nuclide identification

- Energy line found in the spectrum

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

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

[156]

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

Filename: 54 52A Report Generated On 6/7/2018 3:14:10 PM Sample Title B106201AFSFC023GD Sample Description Ul Diesel Fuel Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/7/2018 3:04:00 PM Acquisition Started 6/7/2018 3:04:09 PM Live Time 600 . 0 seconds Real Time 600. 4 seconds Dead Time 0.07 %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 6/7/2018 Efficiency ID 3M90D CP lIN DATA VALIDATED DATE1c2. . 4>-/f THVIE I o'l ,yd

~#*-",...

[157]

Peak Analysis Report 6/7/2018 3: 14 :10 PM Page 2

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

Detector Name: 5452A Sample

Title:

B106201AFSFC023GD Peak Analysis Performed on: 6/7/2018 3: 14 : 10 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 1399- 1417 1407. 04 351.76 1.18 8.04E+001 27.33 3.16E+001 2 2428- 2444 2435.22 608.80 0.93 6.20E+001 20.92 1.50E+001 3 3639- 3652 3645.62 911.41 0.78 1 .86E+001 14. 93 1.34E+001 4 4473- 4486 4479.27 1119.82 0.52 2.24E+001 15.35 l.26E+001 5 5832- 5853 5842.96 1460.74 1. 87 l.47E+002 25.74 5.17E+OOO 6 7051- 7066 7058. 11 1764.53 0.64 1 .90E+001 11.76 5.00E+OOO M First peak in a multiplet region m

F Other peak in a multiplet region Fitted singlet Errors quoted at 2 . 000 sigma

[158]

Interference Corrected Activity Report 6/7/2018 3:14:10 PM Page 3

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

Sample

Title:

B106201AFSFC023GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. ................... - . . IDENTIFIED NUCLIDES * ...... .............. . . . P' ... "".

Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M.,..2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.09288E+006 2.13792E+005 Bi-214 1. 000 609.32* 45.49 7.35379E+004 2.63515E+004 1120.29* 14.92 l.04869E+005 7.24825E+004 1764.49* 15.30 1. 09684E+'005 6.84738E+004 Pb-214 0 .440 295.22 18.42 351.93* 35.60 9.5368BE+004 3.58279E+004

~ Energy line found in the spectrum.

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

[159]

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2) Uncertainty K-40 1.000 1. 0 928 83E+O 06 2.137925E+OOS Bi-214 1.000 8.095395E+004 2.328912E+00 4 Pb-214 0.440 9.536884E+004 3.582786E+004

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

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

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

Peak Locate Performed on: 6/7/2018 3: 14 : 10 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 3 911.41 3.1016E-002 80. 21 Tol. Ac-228 M ~ First peak in a multiplet region m = Other peak in a multipl et region F = Fitted singlet Errors quoted at 2 . 000 sigma

[160]

Nuclide MDA Report 6/7/2018 3:14: 10 PM Page 5

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

Detector Name: 5452A Sample Geometry: 3M90D CP 1IN sample

Title:

B106201AFSFC023GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yie ld Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 1.263E+005 1 .26E+005 1.093E+006 5.307E+004 Co-60 1173 .23 99.85 2.075E+004 2.00E+004 6.524E+003 9.409E+003 1332.49 99.98 1.997E+004 1.472E+004 8.961E+003 Nb- 94 702.65 99.81 2.065E+004 1 .77E+004 -1.202E+004 9.549E+003 871.09 99.89 1.768E+004 1.402E+004 7.989E+003 Ag- 108m 433.90 90.50 1.972E+004 1 .97E+004 l.400E+003 9.167E+003 614.30 89.80 2.871E+004 -2.291E+004 1.354E+004 722.90 90.80 2.457E+004 3.237E+003 1.142E+004 Cs-134 604.72 97.62 2.714E+004 2.27E+004 -1.247E+004 1.282E+004 795.86 85.46 2.270E+004 1.766E+002 1.039E+004 Cs-137 661.66 85.10 2.607E+004 2.61E+004 3.767E+004 1.215E+004 Eu-152 121 .78 28.67 9.636E+004 7.37E+004 4.167E+004 4.677E+004 344.28 26.60 7.367E+004 -4.433E+004 3.471E+004 1408 .01 21.07 7.427E+004 5.169E+004 3.214E+004 Eu-154 123.07 40.40 6.621E+004 5.53E+004 -6.433E+004 3.210E+004 723.30 20.06 1.130E+005 4 .384E+004 5.258E+004 1274.43 34.80 5.526E+004 1.902E+004 2.475E+004 Eu-155 86.55 30.70 1.096E+005 1 .10E+005 8.332E+002 5.342E+004 105.31 21.10 1.461E+005 2.910E+004 7.110E+004 Tl-208 583.19 85.00 2.826E+004 2.83E+004 -6.793E+003 1.329E+004 Bi-212 727.33 6.67 3.246E+005 3.25E+005 -3.293E+OOS 1.505E+005 Pb-212 238.63 43.60 5.679E+004 5.68E+004 6.556E+004 2.729E+004

+ Bi-214 609.32* 45.49 3.010E+004 3.01E+004 7.354E+004 1.345E+004 1120 .29* 14.92 1.060E+005 1.049E+005 4.664E+004 1764.49* 15.30 9.062E+004 1.097E+005 3.7SOE+004

+ Pb-214 295.22 18.42 1.183E+005 4.34E+004 -5.971E+004 5.626E+004 351.93* 35.60 4.344E+004 9.537E+004 2.012E+004 Ra-226 186.21 3.64 6.385E+005 6.39E+005 -5.942E+005 3.073E+005 Ac-228 338.32 11. 27 1.805E+OOS 9.46E+004 -5.003E+004 8.525E+004 911.20 25.80 9.457E+004 5.371E+004 4.393E+004 968.97 15.80 1.411E+OOS 6.862E+004 6.490E+004 Am-241 59.54 35.90 1.160E+005 1 .16E+005 -1.095E+004 5.643E+004

+ =Nuclide identified during the nuclide identification

~ Energy line found in the spectrum

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

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

[161]

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

Filename: 5452A Report Generated On 6/7/2018 3: 27: 54 PM Sample Title B106201AFSFC024GD Sample Description Ul Diesel Fuel Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M... 2 Sample Taken On 6/7/2018 3:17:00 PM Acquisition Started 6/7/2018 3:17:53 PM Live Time 600 . 0 seconds Real Time 600.9 seconds Dead Time 0 , 15 %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 6/7/2018 Efficiency ID 3M90D CP 1IN DATA-VALIDATED DATE le<*& ../f

@!;~

[162]

Peak Analysis Report 6/7/2018 3:27:54 PM Page 2

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

Detector Name: 5452A Sample

Title:

B1062D1AFSFC024GD Peak Analysis Performed on: 6/7/2018 3:27 :54 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 284- 304 291.25 72.81 0.84 1.60E+002 80.20 3.98E+002 2 949- 960 953.80 238.45 0.64 2.41E+001 27.21 6.39E+001 3 1176- 1189 1181.52 295.38 1. 06 4.llE+OOl 22.00 2.89E+001 4 1398- 1413 1406.64 351.66 1. 39 6.69E+001 28.25 4.41E+001 5 2429- 2445 2436.30 609.08 1.18 7.75E+001 2 4 .54 2.35E+001 6 2635- 2653 2645.17 661. 29 1.16 1.34E+002 25.72 9.42E+OOO 7 3637- 3650 3643.51 910.88 0.76 1.63E+001 13 .70 1.07E+001 8 5830- 5852 5842. 10 1460.53 1. 98 1.46E+002 27.68 l.15E+001 9 7050- 7065 7057. 44 1764.36 0.93 2.42E+001 10 .85 1.79E+OOO M

m

-= First peak in a multiplet region Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[163]

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Sample

Title:

B106201AFSFC024GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

* * * * * * * ' I * * *

1 * '"' * ..,

IDENTIFIED NUCLIDES . . .... ........ ......... .,.. ..... "

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 1.09002E+006 2.26718E+OOS Cs-137 1.000 661.66* 85. 10 8.78484E+004 1 .99339E+004 Pb-212 1. 000 238.63* 43.60 1 .96852E+004 2.24121E+004 Bi-214 0 .703 609.32* 45.49 9.19134E+004 3.11439E+004 1120.29 14.92 1764.49* 15.30 1 .39763E+OOS 6.36011E+004 Pb-214 1 . 000 295.22* 18.42 8.71945E+004 4.87284E+004 351.93* 35.60 7.93758E+004 3.58333E+004

. Energy line found in t he spectrum.

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

[164]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1.000 l.090018E+006 2.267184E+005 Cs-137 1.000 8.784845E+004 1. 993394E+004 Pb-212 1.000 1.968516E+004 2.241214E+004 Bi-214 0.703 1. 011678E+005 2.797047E+004 Pb-214 1. 000 8.211994E+004 2.886810E+004

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

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

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

Peak Locate Performed on: 6/7/2018 3:27:54 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 72.81 2.6626E-001 50.20 7 910.88 2.7099E-002 84.23 Sum M First peak in a multiplet region m . Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[165]

Nuclide MDA Report 6/7/2018 3: 27 : 54 PM Page 5

- - *

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

Detector Name: 5452A Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC024GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

K-40 1460.82* 10.66 1. 846E+O 05 1.8SE+005 1.090E+006 8.222E+004 Co-60 1173.23 99.85 2.133E+004 1.85E+004 7.828E+003 9.699E+003 1332.49 99.98 1. 853E+O 04 1.070E+004 8.243E+003 Nb-94 702.65 99.81 1. 868E+O 04 1.87E+004 -6.063E+003 8.562E+003 871.09 99.89 2.060E+004 l.790E+004 9.453E+003 Ag-108m 433.90 9 0 .50 2.326E+004 1.93E+004 -5.808E+003 1 .094E+004 614. 3 0 89.80 3.302E+004 l.446E+003 1 .569E+004 722.90 90.80 1.932E+004 -5.141E+003 8.797E+003 Cs-134 604.72 97.62 3.216E+004 2.32E+004 -1.599E+004 1 .534E+004 795.86 85 .46 2.321E+004 -2.39SE+004 1 .065E+004

+ cs-137 661.66* 85.10 1.398E+004 1.40E+004 8.785E+004 6.098E+003 Eu-152 121.78 28.67 1.009E+005 8.08E+004 1.096E+004 4 .905E+004 344.28 26.60 8.638E+004 -8.005E+004 4.106E+004 1408.01 21. 07 8.082E+004 -5.413E+004 3.542E+004 Eu-154 123.07 40. 40 7.164E+004 5.11E+004 2.791E+004 3.482E+004 723.30 20.06 8.862E+004 2.412E+003 4.039E+004 1274.43 34.80 5.113E+004 2.939E+004 2.269E+004 Eu-155 86.55 30.70 1.202E+005 1. 20E+005 -1.483E+003 5.872E+004 105.31 21.10 1.520E+005 -3.090E+004 7.406E+004 Tl-208 583.19 85.00 2.762E+004 2.76E+004 1.807E+004 l .297E+004 Bi-212 727.33 6.67 2.928E+005 2.93E+005 2.116E+005 1 .346E+005

+ Pb-212 238.63* 43.60 3.624E+004 3.62E+004 l.969E+004 1 .702E+004

+ Bi-214 609.32* 45.49 3.658E+004 3.66E+004 9.191E+004 l .669E+004 1120.29 14.92 1.789E+005 1.646E+005 8.309E+004 1764.49* 15 . 30 5.891E+004 l.398E+005 2.165E+004

+ Pb-214 295.22* 18.42 6.816E+004 4.81E+004 8.719E+004 3.121E+004 351.93* 35.60 4.814E+004 7.938E+004 2.247E+004 Ra-226 186.21 3.64 6.782E+005 6.78E+OOS -2.070E+005 3.272E+005 Ac-228 338.32 11 .27 2.098E+005 8.91E+004 1.284E+005 9.992E+004 911.20 25.80 8.910E+004 -3.336E+004 4.119E+004 968.97 15.80 1.467E+005 8.525E+004 6.772E+004 Am-241 59.54 35.90 1. l 78E+005 1.18E+005 -4.743E+004 5.729E+004

+ ~ Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[166]

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

Filename: 6279 Report Generated On 6/11/2018 10:22:09 AM Sample Title B106201AFSFC025GD Sample Description Ul Diesel Fuel Storage Floor sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2 , 830EHJ0l M"' 2 Sample Taken On 6/11/2018 10:12:00 AM Acquisition Started 6/11/2018 10:12:07 AM Live Time 600. 0 seconds Real Time 601. 0 seconds Dead Time 0.16 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M9 0D CP lIN DATA VALIDATED DATE1..z.. , ../1' TIME/c7¥5

~~~

[167]

Peak Analysis Report 6/11/2018 10:22:09 AM Page 2

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

Detector Name: 6279 sample

Title:

B106201AFSFC025GD Peak Analysis Performed on: 6/11/2018 10: 22:08 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts l 285- 305 299.86 75.09 0.83 1.22E+002 82.30 4.32E+002 2 330- 343 338.87 84.84 0.57 3.27E+001 52.26 2.35E+002 3 413- 424 419.13 104.91 0.54 2.09E+001 38.99 1.43E+002 4 951- 962 955.13 238.90 1. 07 3.27E+001 24.20 4.43E+001 5 2327- 2338 2332.40 583.20 0.39 2.lOE+OOl 13.24 9.00E+OOO 6 2427- 2443 2436.34 609.18 0.44 5.42E+001 19.46 1.28E+001 7 2637- 2653 2645.43 66 1. 45 1. 59 1.77E+002 30. 75 1.90E+001 8 3636- 3649 3642.08 910.60 0.74 1.90E+001 13.37 9.00E+OOO 9 4475- 4488 4481.10 1120.34 0.58 2.76E+001 13.42 6.38E+OOO 10 5836- 5851 5843.39 1460.90 1. 26 5.09E+001 19.32 1.41E+001 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2 . 000 sigma

[168]

Interference Corrected Activity Report 6/11/2018 10:22:09 AM Page 3

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

Sample

Title:

B106201AFSFC025GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10.66 6.03492E+005 2.34852E+005 Cs-137 1.000 661.66* 85. 10 1.65192E+005 3.48849E+004 Eu-155 0.997 86.55* 30.70 3.60897E+004 5.80865E+004 105.31* 21. 10 3.19549E+004 5.99912E+004 Tl- 208 1. 000 583.19* 85. 00 1.81580E+004 1. 16577E+O 04 Pb-212 1. 000 238.63* 43.60 3.13385E+004 2.37269E+004 Bi-214 0 .743 609.32* 45.49 8.99161E+004 3.40632E+004 1120.29* 14 .92 1.99000E+OOS 9.80084E+004 1764.49 15 .30

~ Energy line found i n the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence ( pCi/MA2 ) Uncertainty K-40 1.000 6.034916E+005 2.348517E+005 Cs-137 1. 000 1 .651917E+005 3.488490E+004 Eu-155 0.997 3.408897E+004 4 .173046E+004 Tl-208 1. 000 1 .815796E+004 1.165772E+004 Pb-212 1.000 3.133854E+004 2.372693E+004 Bi-214 0.743 1 .016726E+005 3.217527E+004

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

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

[170]

Interference Corrected Activity Report 6/11/2018 10 :22:09 AM Page 5

- - - - UN I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 6/11/2018 10 :22:08 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % uncertainty Type Nuclide 1 75.09 2.0340E-001 67.44 8 910.60 3.1667E-002 70.35 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[171]

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- - - - NUCLIDE MD A R E P O R T *****

Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC025GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yie ld Line MDA Nuclide MDA Activity Dec. Level Name (keV) (% ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

K-40 1460.82* 10.66 2.859E+005 2.86E+005 6.035E+OOS 1.269E+005 Co-60 1173.23 99. 85 3.021E+004 3.02E+004 l.410E+004 1.361E+004 1332.49 99.98 3.239E+004 2.378E+004 1.459E+004 Nb-94 702.65 99.81 2.356E+004 2.36E+004 3.819E+003 1.067E+004 871. 09 99.89 2.545E+004 1. 224E+004 1.146E+004 Ag-108m 433.90 90.50 3.037E+004 2.7SE+004 -l.660E+004 1.428E+004 614. 3 0 89.80 3.938E+004 -7.241E+003 1.855E+004 722.90 90.80 2.746E+004 l.854E+003 1.248E+004 Cs-134 604.72 97.62 3.607E+004 3.32E+004 -l.909E+004 1.699E+004 795.86 85.46 3.320E+004 -l .292E+003 1.520E+004

+ Cs-137 661.66* 85.10 2.618E+004 2.62E+004 l .652E+005 1.183E+004 Eu-152 121. 78 28.67 1.059E+OOS 1.03E+OOS 3.090E+004 5.141E+004 344.28 26.60 1.028E+005 -4.024E+004 4.875E+004 1408. 01 21.07 1.138E+OOS 3.066E+004 4 .899E+004 Eu-154 123.07 40.40 7.360E+004 7.27E+004 -l .330E+004 3.572E+004 723. 3 0 20.06 1.243E+005 -2.396E+004 5.652E+004 1274 .43 34.80 7.272E+004 5.814E+003 3.187E+004

+ Eu-155 86.55* 30.70 9.550E+004 9.55E+004 3.609E+004 4 .626E+004 105.31* 21 .10 9.950E+004 3.195E+004 4 .768E+004

+ Tl-208 583.19* 85.00 1.594E+004 1 .59E+004 1 .816E+004 6.799E+003 Bi-212 727.33 6.67 3.898E+005 3.90E+005 1 .193E+005 1.779E+005

+ Pb-212 238.63* 43.60 3.619E+004 3.62E+004 3.l34E+004 1.680E+004

+ Bi-214 609.32* 45.49 3.925E+004 3.93E+004 8.992E+004 1.738E+004 1120.29* 14.92 1.184E+OOS 1.990E+005 4 .946E+004 1764.49 15.30 2.264E+OOS 1.979E+005 1.00SE+OOS Pb-214 295.22 18.42 1.665E+OOS 9.06E+004 1.083E+005 7.978E+004 351.93 35.60 9.060E+004 4.736E+004 4 .328E+004 Ra-226 186.21 3.64 7.473E+OOS 7.47E+OOS 1.791E+005 3.601E+005 Ac-228 338.32 11 .27 2.518E+OOS 1 .32E+005 2.128E+005 1.197E+005 911. 20 25.80 1. 317E+005 1.323E+005 6.086E+004 968.97 15.80 1. 892E+005 1.173E+005 8.615E+004 Am-241 59.54 35.90 1. 272E+005 1. 27E+005 9.005E+004 6.193E+004

+ ~ Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[172]

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Filename: 5452A Report Generated On 6/7/2018 2: 35: 37 PM Sample Title Bl06201AFSFC026GD Sample Description Ul Diesel Fuel Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10 . 000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/7/2018 2:25: 00 PM Acquisition Started 6/7/2018 2:25:36 PM Live Time 600. 0 seconds Real Time 600.3 seconds Dead Time 0.05 %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 6/7/2018 Efficiency ID 3M90D CP 1IN DATA VALIDATED DATE /;3-J-/F aME/~

~ A

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Detector Name: 5452A Sample

Title:

B106201AFSFC026GD Peak Analysis Performed on: 6/7/2018 2: 35: 37 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 947- 959 954.54 238.63 0 .70 2.82E+001 25.70 5.18E+001 2 1402- 1417 1407. 71 35 1 .93 0 .86 7.llE+OOl 25.15 2.89E+001 3 2428- 2444 2435.86 608.96 0 .37 6.74E+001 20.67 1 .26E+001 4 2639- 2653 2645.13 661.28 1.42 3.SlE+OOl 17 .98 1 .59E+001 5 3638- 3652 3644.85 911.21 0 .96 3.94E+001 16 .47 9.61E+OOO 6 4473- 4486 4479.59 1119.90 0 .27 2.51E+001 12.98 5.90E+OOO 7 5835- 5854 5843.63 1460.91 1. 07 1 .20E+002 25.82 1 .37E+001 M First peak in a multiplet region m = Other peak in a multiplet region F "" Fitted singlet Errors quoted at 2 . 000 sigma

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Sample

Title:

B106201AFSFC026GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (%} (pCi/MA2 } Uncertainty K-40 1. 000 1460.82* 10.66 8.95580E+005 2.07308E+005 cs-137 1. 000 661.66* 85.10 2.31138E+004 1.21454E+004 Pb-212 1. 000 238.63* 43.60 2.30012E+004 2.1288SE+004 Bi-214 0.729 609.32* 45.49 7.99698E+004 2.63405E+004 1120 .29* 14.92 1.17686E+OOS 6.15696E+004 1764.49 15.30 Pb-214 0. 440 295.22 18.42 351.93* 35.60 8.43078E+004 3.27535E+004

=Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) uncertainty K-40 1 . 000 8.955798E+005 2.073085E+005 Cs-137 1 . 000 2.311382E+004 1.214541E+004 Pb-212 1 . 000 2.300116E+004 2.128852E+004 Bi-214 0.729 8.580490E+004 2.421734E+004 Pb-214 0.440 8.430784E+004 3.275346E+004

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

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

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

Peak Locate Performed on: 6/7/2018 2: 35: 37 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy *Peak Si ze in Peak CPS Peak Tol.

No. (keV) Counts per Second % uncertainty Type Nuclide 5 911. 21 6.5655E-002 41.81 Tol. Ac-228 M := First peak in a multiplet region m "" Other peak in a multiplet region F := Fitted singlet Errors quoted at 2 . 000 sigma

[176]

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Detector Name: 5452A Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC026GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 l.868E+005 l.87E+OOS 8.956E+005 8.332E+004 Co-60 1173.23 99.85 2.189E+004 l.96E+004 l.502E+004 9.980E+003 1332.49 99.98 l.962E+004 2.682E+003 8.787E+003 Nb-94 702.65 99.81 l.782E+004 1.66E+004 -8.932E+002 8.133E+003 871.09 99.89 1.657E+004 3.509E+003 7.438E+003 Ag- 108m 433.90 90.50 2.274E+004 2.17E+004 -4.36SE+003 1 .067E+004 614. 3 0 89.80 2.914E+004 -l. 354E+004 l. 375E+004 722.90 90.80 2.168E+004 -4.883E+003 9.975E+003 Cs-134 604.72 97.62 2.912E+004 2.52E+004 3.579E+003 l.381E+004 795.86 85 .46 2.51SE+004 l. 187E+004 1.162E+004

+ Cs-137 661.66* 85.10 1. 640E+004 1 .64E+004 2.311E+004 7.311E+003 Eu-152 121. 78 28.67 9.367E+004 7.43E+004 -1. 679E+004 4.542E+004 344.28 26.60 7.443E+004 l.068E+003 3.509E+004 1408.01 21. 07 7.427E+004 1.668E+004 3.214E+004 Eu-154 123.07 40.40 6.630E+004 5.53E+004 -2.005E+004 3.215E+004 723.30 20.06 9.816E+004 -3.998E+004 4.516E+004 1274.43 34.80 S.526E+004 -1. 958E+003 2.475E+004 Eu-155 86.55 30.70 l.160E+005 1. 16E+005 l.159E+OOS S.659E+004 105 .31 21.10 1.416E+005 -1. 872E+004 6.884E+004 Tl-208 583.19 85.00 2.612E+004 2.61E+004 8.750E+003 1.221E+004 Bi-212 727.33 6.67 2.959E+OOS 2.96E+005 l.639E+OOS 1.361E+005

+ Pb-212 238.63* 43.60 3.361E+004 3.36E+004 2.300E+004 1. 570E+004

+ Bi-214 609.32* 45.49 2.771E+004 2.77E+004 7.997E+004 1. 22SE+004 1120.29* 14 .92 7.628E+004 l.177E+OOS 3.180E+004 1764.49 15.30 1.676E+005 1.373E+OOS 7.597E+004

+ Pb-214 295.22 18.42 l.325E+005 3.96E+004 l.062E+OOS 6.339E+004 351.93* 35.60 3.965E+004 8.431E+004 l. 822E+004 Ra-226 186 .21 3.64 6.639E+005 6.64E+005 1 .169E+005 3.201E+005 Ac-228 338.32 11. 27 l.698E+005 1.09E+005 -1 .547E+005 7.992E+004 911.20 25.80 l.092E+005 1 .627E+005 5.127E+004 968.97 15.80 l.453E+005 5.660E+004 6.703E+004 Am-241 59.54 35.90 l.164E+005 1. 16E+005 9.462E+004 5.663E+004

+ = Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[177]

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

Filename: 5452A Report Generated On 6/7/2018 2: 48: 23 PM Sample Title B106201AFSFC027GD Sample Description Ul Diesel Fuel Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels} 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/7/2018 2:38:00 PM Acquisition Started 6/7/2018 2:38:21 PM Live Time 600 . 0 seconds Real Time 600.5 seconds Dead Time 0 . 09 %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 6/7/2018 Efficiency ID 3M90D CP 1IN D,\TAVAUDATED DATEL./* k /tf_

4 TIMEL..?¥5"

-~+

[178]

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Detector Name: 5452A Sample

Title:

B106201AFSFC027GD Peak Analysis Performed on: 6/7/2018 2:48:22 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 283- 305 300.28 75.07 0.40 l.15E+002 85.81 4.45E+002 2 738- 749 743.23 185. 81 0.91 2 .41E+001 29. 00 7.39E+001 3 950- 959 954.79 238.70 1. 15 3.16E+001 25.22 5.64E+001 4 1175- 1208 1202.07 30 0 .52 0.57 6.SSE+OOl 42.28 7.lSE+OOl 5 1401- 1415 1407.57 351.89 1. 30 6.21E+001 25.83 3.59E+001 6 2429- 2443 2436.04 609.01 0.81 6.02E+001 2 1 .40 1.88E+001 7 2637- 2654 2645.06 661.27 1.41 1.23E+002 25.81 1.35E+001 8 4686 - 4699 4692.78 1173.20 0.56 1.71E+001 13.10 8.87E+OOO 9 5323- 5336 5329.1 0 1332.27 0.47 1.75E+001 13 .66 1.0SE+OOl 10 5833- 5853 5843. 00 146 0. 75 1. 97 1.33E+002 26.06 1 .03E+001 M ,:: First peak in a multiplet region m "" Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

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Sample

Title:

B106201AFSFC027GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

"' ....... ... ... .......... IDENTIFIED NUCLIDES * * * - * * * * * * * *

a * -

a * -

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 9.87756E+005 2.12077E+005 Co-60 1.000 1173.23* 99.85 l .22505E+004 9. 41 529E+003 1332.49* 99.98 l .32185E+004 l. 03697E+004 Cs-137 1.000 661.66* 85.10 8.05590E+004 1. 95342E+004 Pb-212 1.000 238.63* 43.60 2.57619E+004 2.09884E+004 Bi-214 0.431 609.32* 45.49 7.14540E+004 2.68080E+004 1120.29 14 .92 1764.49 15.30 Pb-214 0 .985 295.22* 18.42 1.39956E+005 9.31197E+004 351.93* 35.60 7.37245E+004 3.28364E+004 Ra-226 1 .00 0 186.21* 3.64 2.12422E+005 2.57518E+005

=Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 .30 Errors quoted at 2. 000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1 .000 9.877556E+005 2.120773E+005 Co-60 1. 000 l.268794E+004 6.970681E+003 Cs-137 1 .000 8. 0 55901E+004 l.953424E+004 Pb-212 1.000 2.576187E+004 2.098838E+004 Bi-214 0.431 7.145405E+004 2.680800E+004 Pb-214 0.985 8.104923E+004 3.096746E+004 Ra-226 1.000 2.124224E+005 2.575181E+005

? Nuclide is part of an undetermined solution x . Nuclide rejected by the interference analysis

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

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Peak Locate Performed on: 6/7/2018 2:48:22 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.07 1.9180E-001 74.57 M ; First peak in a mult iplet region m ~ Other peak in a mult iplet region F - Fitted singlet Errors quoted at 2 . 000 sigma

[182]

Nuclide MDA Report 6/7/2018 2:48:23 PM Page 6

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Detector Name: 5452A Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFSFC027GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yie ld Line MDA Nuclide MDA Activity Dec. Level Name (keV} (% } (pCi/MA2 ) (pCi/MA2 } (pCi/MA2 ) (pCi/MA2 }

+ K-40 1460 .82* 10 .66 1 .692E+005 l. 69E+005 9.878E+005 7.453E+004

+ Co-60 1173.23* 99.85 1 .387E+004 1. 39E+004 1.225E+004 5.968E+003 1332.49* 99.98 l .546E+004 1.322E+004 6.706E+003 Nb-94 702.65 99.81 1 .909E+004 1. 77E+004 3.535E+003 8.768E+003 871. 09 99.89 1.768E+004 1. 881E+004 7.989E+003 Ag-108m 433.90 90.50 2.287E+004 2.29E+004 2.779E+003 1. 074E+004 614.30 89.80 3.081E+004 -2.826E+004 1. 459E+O 04 722.90 90.80 2.399E+004 5.399E+003 1. 113E+004 Cs-134 604.72 97.62 2.876E+004 2.54E+004 - 1.103E+004 1. 363E+004 795.86 85.46 2.538E+004 1. 616E+004 l. 173E+004

+ Cs-137 661.66* 85.10 1.613E+004 1.61E+004 8.056E+004 7.174E+003 Eu- 152 121.78 28.67 1.041E+005 8.74E+004 -4.236E+003 5.06SE+004 344.28 26.60 8.735E+004 -l. 499E+004 4.155E+004 1408.01 21.07 9.926E+004 7.265E+004 4.463E+004 Eu-154 123.07 40.40 7.316E+004 5. 00E+004 l. 431E+004 3.558E+004 723. 3 0 20.06 1. 077E+005 2.502E+004 4.993E+004 1274.43 34.80 5.004E+004 -4.352E+004 2.214E+004 Eu-155 86.55 30.70 1 .191E+005 1.19E+005 3.289E+004 5.818E+004 105. 31 21.10 1 .494E+005 4.766E+004 7.276E+004 Tl-208 583.19 85.00 2.663E+004 2.66E+004 1.707E+004 1 .247E+004 Bi-212 727.33 6.67 3.246E+OOS 3.25E+005 2.201E+004 1 .SOSE+OOS

+ Pb-212 238.63* 43.60 3.250E+004 3.25E+004 2.576E+004 1 .515E+004

+ Bi-214 609.32* 45.49 3.197E+004 3.20E+004 7.145E+004 1 .438E+004 1120.29 14.92 1. 745E+O 05 1.864E+OOS 8.092E+004 1764.49 15. 30 1. 577E+O 05 1.135E+005 7.106E+004

+ Pb-214 295.22* 18.42 l.431E+005 4.31E+004 1.400E+005 6.868E+004 351.93* 35.60 4.314E+004 7.372E+004 1.996E+004

+ Ra-226 186.21* 3.64 4.188E+005 4.19E+005 2.124E+005 1.975E+005 Ac-228 338.32 11. 27 2.113E+005 9.53E+004 -3.876E+003 1.006E+005 911. 2 0 25.80 9.532E+004 9.402E+004 4.431E+004 968.97 15.80 l.425E+005 7.278E+004 6.562E+004 Am-241 59.54 35.90 1. 216E+005 1. 22E+O 05 5.909E+004 5.923E+004

+ = Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[183]

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Filename: 5452A Report Generated On 6/7/2018 3:00:16 PM Sample Title B106201AFSFC028GD Sample Description Ul Diesel Fuel Storage Floor Sample Identification Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"'2 Sample Taken On 6/7/2018 2:50:00 PM Acquisition Started 6/7/2018 2:50: 14 PM Live Time 600 . 0 seconds Real Time 600.6 seconds Dead Time Orll %

Energy Calibration Used Done On 3/15/2018 Efficiency Calibration Used Done On 6/7/2018 Efficiency ID 3M90D CP 1IN DATAVAUDATED DATE/,/.. ' ./J>

TIME/;¥5

~~**

[184]

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- - - - PE AK AN ALYS IS REPORT *****

Detector Name: 5452A Sample

Title:

B106201AFSFC028GD Peak Analysis Performed on: 6/7/2018 3:00:16 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 284- 306 300.35 75.09 0.38 1 .34E+002 90.50 4.92E+002 2 949- 960 955. 11 238.78 0.67 4.94E+001 30.61 7.26E+001 3 1176- 1187 1180.79 295.20 0.58 1.58E+001 26.27 6.22E+001 4 1264- 1273 1268.99 317.25 0.56 l.46E+001 17.28 2.64E+001 5 1399- 1415 1407 .39 351.85 1. 87 6.92E+001 27.84 3.98E+001 6 2037- 2050 2042.94 510.73 0.89 4.78E+001 20.87 2.22E+001 7 2428- 2444 2435.13 608.78 0.95 5.98E+001 24.07 2.72E+001 8 2632- 2656 2645.76 66 1 .44 1.41 4.27E+002 44 .94 1. 88E+001 9 5832- 5854 5843.26 1460.81 1. 09 1.45E+002 27.40 1. llE+OOl 10 7053- 7068 7060.62 1765.15 0.49 1. 69E+001 9.76 2.13E+OOO M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[185]

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

Sample

Title:

B106201AFSFC028GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB

" * * * * * * *

o, " * * ,t *

t I

IDENTIFIED NUCLIDES Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1 .000 1460.82* 10.66 l.07863E+006 2.24450E+005 cs-137 1 .000 661.66* 85.10 2.81003E+005 4.48583E+004 Pb- 212 1 .000 238.63* 43.60 4.03159E+004 2.58014E+004 Bi-214 0.702 609.32* 45.49 7.09211E+004 2.98010E+004 1120.29 14.92 1764.49* 15. 30 9.73980E+004 5.68873E+004 Pb-214 1 .000 295.22* 18.42 3.35300E+004 5.59704E+004 351.93* 35.60 8.21140E+004 3.55521E+004

- Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1. 078633E+006 2.244504E+005 Cs-137 1. 000 2.810026E+005 4 .485834E+00 4 Pb-212 1. 000 4 .031589E+004 2.580136E+00 4 Bi-214 0.702 7.662252E+004 2.639809E+00 4 Pb-214 1. 000 6.814702E+004 3.000983E+00 4

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

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

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Peak Locate Performed on: 6/7/2018 3 :00 :16 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Si ze in Peak CPS Peak Tol.

No . (keV) Counts per Second % Uncertainty Type Nuclide 1 75.09 2.2362E-001 67.45 4 317 .25 2.4339E-002 118 .34 6 510 .73 7.9625E-002 43.69 M First peak in a multip let region m = Other peak in a multip let region F ~ Fitted singlet Errors quoted at 2 . 000 sigma

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Nuclide MDA Report 6/7/2018 3:00: 17 PM Page 6

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Detector Name: 5452A Sample Geometry: 3M90D CP lIN Sample

Title:

B106201AFSFC028GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV} (% } (pCi/M"2 } (pCi/MA2 ) (pCi/MA2 } (pCi/MA2 }

+ K-40 1460.82* 10. 66 1. 804E+OD5 1.8DE+005 1 .079E+D06 8.013E+004 Co-60 1173.23 99.85 2.297E+004 2.00E+004 1 .259E+D04 1.D52E+004 1332.49 99.98 1. 997E+004 2.07DE+003 8.961E+003 Nb-94 702.65 99.81 2.028E+004 1.85E+D04 1 .287E+OD4 9.360E+003 871.09 99.89 1. 846E+004 7.082E+003 8.379E+003 Ag-108m 433.90 90.50 2.365E+OD4 2.12E+004 2.437E+OD3 1 .113E+004 614.30 89.80 3.20DE+004 -2.13BE+004 1 .518E+004 722.90 90.80 2.123E+004 6.842E+003 9.751E+003 Cs-134 604.72 97.62 3.017E+OD4 2.22E+004 -2.384E+003 1 .434E+004 795.86 85.46 2.217E+004 1 .271E+004 1 .013E+004

+ Cs-137 661.66* 85.10 2.D84E+004 2.08E+004 2.810E+005 9.528E+003 Eu-152 121. 78 28.67 1.044E+005 8.29E+004 -3.978E+004 5.077E+004 344.28 26.60 8.768E+004 -4.223E+004 4.171E+004 1408.01 21.07 8.288E+004 4.533E+004 3.644E+004 Eu-154 123.07 40.40 7.433E+OD4 4.7BE+004 -2.771E+004 3.616E+004 723.30 20.06 9.816E+004 1.6DOE+004 4.516E+004 1274.43 34.80 4.776E+004 -1.070E+004 2.10DE+004 Eu-155 86.55 30.70 1.242E+005 1. 24E+005 1.016E+004 6.073E+004 105.31 21.10 1.628E+005 1.063E+OD5 7.944E+004 Tl-208 583.19 85.00 3.053E+OD4 3.05E+004 2.962E+004 1.442E+OD4 Bi-212 727.33 6.67 2.835E+005 2.83E+005 1.265E+005 1.299E+005

+ Pb-212 238.63* 43.60 3.868E+004 3.87E+004 4.032E+004 1.824E+004

+ Bi-214 609.32* 45.49 3.921E+OD4 3.92E+004 7.092E+004 1.800E+OD4 1120.29 14. 92 1 .654E+005 8.677E+004 7.638E+004 1764.49* 15.30 6.568E+004 9.740E+OD4 2.503E+004

+ Pb-214 295.22* 18.42 9.309E+OD4 4.68E+004 3.353E+004 4.367E+OD4 351.93* 35.60 4.678E+004 8.211E+004 2.179E+004 Ra-226 186.21 3.64 7.694E+005 7.69E+005 3.502E+D05 3.728E+005 Ac-228 338.32 11. 27 2.038E+OD5 9.61E+004 3.436E+004 9.693E+004 911.20 25.80 9.607E+D04 2.627E+004 4.468E+004 968.97 15.80 1.534E+D05 7.896E+004 7.109E+004 Am-241 59.54 35.90 1.196E+OD5 1.20E+OOS 1.185E+OD5 5.82DE+004

+=Nuclide identified during the nuclide identification

- Energy line found in the spectrum

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

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

[189]

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

Filename: 6279 Report Generated On 6/6/2018 3 : 04:47 PM Sample Title B106201AFSWC029GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.030E+001 MA2 Sample Taken On 6/6/2018 2:54:00 PM Acquisition Started 6/6/2018 2:54:46 PM Live Time 600 . 0 seconds Real Time 600. 4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP 1IN DATA VALIDATED DATE/3* ' .. Jp o::;~c

[190]

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

Detector Name: 6279 Sample

Title:

B106201AFSWC029GD Peak Analysis Performed on: 6/6/2018 3:04:47 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts M 1 284- 349 299.69 74.89 1. 23 9.llE+OOl 30.57 1.98E+002 m 2 284- 349 339.91 84.96 1. 24 7.47E+001 28.41 1.80E+002 3 640- 655 647.56 161. 95 1. 12 3.18E+001 30.01 6.42E+001 4 1171- 1188 1179. 01 294.92 0.87 2.47E+001 19.84 2.23E+001 5 1397- 1414 1405.16 351. 49 0.73 2.31E+001 22.37 2.99E+001 6 2031- 2048 2039.66 510 .19 0.71 4.41E+001 17.28 8.92E+OOO 7 2320- 2337 2328.42 582.39 0.36 1.56E+001 18.59 2. 0 4E+001 8 2423 - 2440 2431.88 608.26 0.67 3.25E+001 13.73 4.50E+OOO 9 2633 - 2650 2641.76 660.73 0.67 4. 95E+001 16.02 4.50E+OOO 10 3242 - 3259 3250.52 812.90 0.72 9.29E+OOO 10.37 4.71E+OOO 11 3631- 3648 3639.59 910 .14 0.31 l. 69E+001 9.72 2.07E+OOO 12 5824- 5846 5835.89 1458.69 0.43 9.62E+001 20.69 2.81E+OOO M = First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[191]

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Sample

Title:

B106201AFSWC029GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

* * * .. , * * * ~ * * *

t * * *

I IDENTIFIED NUCLIDES * * * 't' * * * * ***** * .. II *

ti Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0 .993 1460.82* 10.66 1. 14689E+006 2.65979E+005 Cs-137 0 .999 661.66* 85.10 4.67002E+004 1 . 61171E+004 Eu-155 0 .337 86.55* 30.70 8.40301E+004 3.60974E+004 105.31 21.10 Tl-208 0 .999 583.19* 85.00 1.36122E+004 1.63261E+004 Bi-214 0 .452 609.32* 45.49 5.45098E+004 2.39419E+004 1120.29 14.92 1764.49 15.30 Pb-214 1.000 295.22* 18.42 6.45571E+004 5.28097E+004 351. 93* 35.60 3.48714E+004 3.42197E+004

= Energy line found in t he spectrum.

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

[192]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.993 1.146885E+006 2.659791E+OD5 Cs-137 0.999 4 .670024E+004 1 .611706E+00 4 Eu-155 0.337 8.403007E+004 3.609743E+004 Tl-208 0.999 1 .361222E+004 1 .632607E+004 Bi-214 0.452 5.450978E+004 2.394193E+004 Pb-214 1.000 4.364992E+004 2.871774E+004

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

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

[193]

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- - - - UN I D E N T I F I E D P E AK S * *********

Peak Locate Performed on: 6/6/2018 3:04: 47 PM Peak Locate From Channel: BS Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak To l.

No. (keV) Counts per Second % Uncertainty Type Nuclide M 1 74 . 89 1. 5177E-001 33.57 3 161.95 S.3038E-002 94 .31 Sum 6 510.19 7.3459E-002 39.20 10 812.90 1. 5476E-002 111. 64 11 910 .14 2.8224E-002 57. 39 Sum M ~ First peak in a multiplet region m ~ Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2 . 000 sigma

[194]

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Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC029GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10 .66 1.611E+005 1 .61E+005 1 .147E+006 6.44DE+004 Co-60 1173.23 99.85 3.145E+004 2.93E+004 -3.142E+003 1 .422E+004 1332.49 99.98 2.929E+004 -2.98SE+002 1 .303E+D04 Nb-94 702.65 99.81 2.851E+004 2.84E+004 -1 .352E+004 1 .313E+004 871.09 99.89 2.843E+004 -6.114E+003 1.294E+004 Ag-108m 433.90 90.50 2.894E+004 2.89E+004 -3.574E+003 l.355E+D04 614.30 89.80 3. 511E+004 4.639E+004 1.640E+004 722.90 90.80 2.987E+004 -2 . 919E+004 1.368E+004 Cs-134 604.72 97.62 3.285E+004 3.29E+004 3.381E+OD4 1.537E+004 795.86 85.46 3.917E+D04 7.745E+003 1.817E+004 Cs-137 661.66* 85.10 1.442E+004 1.44E+004 4.670E+004 5.935E+003 Eu-152 121. 78 28.67 1.339E+005 1.18E+005 -1.816E+004 6.541E+004 344.28 26.60 1.176E+005 -3.30SE+004 5.612E+004 1408.01 21. 07 1.220E+005 -4.31SE+003 5.302E+004 Eu-154 123.07 40.40 9.456E+004 7.33E+004 7.161E+004 4.618E+004 723.30 20.06 1.383E+005 1.193E+004 6.346E+004 1274.43 34.80 7.330E+004 S.692E+004 3.212E+004

+ Eu-155 86.55* 30.70 7.333E+004 7.33E+004 8.403E+004 3.514E+OD4 105.31 21. 10 l.992E+005 3.300E+004 9.749E+004

+ Tl-208 583.19* 85.00 2.656E+004 2.66E+004 1.361E+004 1.210E+004 Bi-212 727.33 6.67 3.889E+005 3.89E+005 1.937E+005 1.773E+D05 Pb-212 238.63 43.60 7.159E+004 7.16E+004 6.935E+004 3.448E+004

+ Bi-214 609.32* 45.49 2.564E+004 2.56E+004 5.451E+004 1 .055E+004 1120.29 14.92 2.310E+005 4.494E+OD4 1 .D57E+005 1764.49 15.30 1 .722E+005 1 .044E+005 7.323E+004

+ Pb-214 295.22* 18.42 8.078E+OD4 5.43E+004 6.456E+004 3.686E+004 351.93* 35.60 5.433E+D04 3.487E+004 2.512E+004 Ra-226 186.21 3.64 9.164E+005 9.16E+005 7.346E+005 4.445E+005 Ac-228 338.32 11. 27 2.520E+005 1. 20E+005 -1.860E+005 1.197E+005 911. 2 0 25. 80 1.201E+005 7.194E+004 5.498E+004 968.97 15 .80 1.886E+005 -1.196E+005 8.575E+004 Am-241 59.54 35.90 l.614E+005 1. 61E+005 1.275E+004 7.898E+004

+ Nuclide identified during the nuclide identification

= Energy line found in the spectrum

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

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

[195]

- - - - GAMMA S P E C T R U M A N A L Y S I S *****

Filename: 6279 Report Generated On 6/6/2018 2:52:19 PM Sample Title B106201AFSWC030GD Sample Description Ul Diesel Fuel* Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP 1IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.030E+001 M"2 Sample Taken On 6/6/2018 2:42:00 PM Acquisition started 6/6/2018 2:42:18 PM Live Time 600.0 seconds Real Time 600.S seconds Dead Time 0 . 08 %

Energy Calibration Used Done On.' 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP lIN DATA VALIDATED DATE /-7* '*I 1 TIME/,1¥5 l2m;t-4

[196]

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Detector Name: 6279 Sample

Title:

B106201AFSWC030GD Peak Analysis Performed on: 6/6/2018 2:52:19 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 292- 307 299.75 74.90 0.46 2.51E+001 6 1 .96 3.10E+002 2 945- 962 953.50 238.50 0.66 2.68E+001 28.95 5.62E+001 3 1396- 1414 1404.97 351.44 0.43 2.04E+001 25.01 3.86E+001 4 2030- 2047 2038.13 509.80 0.48 2.lOE+OOl 20.32 2.SOE+OOl 5 2424- 2441 2432.68 608.46 1. 01 2.22E+001 18.65 1.98E+001 6 5826- 5845 5835. 14 1458 .51 0.84 7.40E+001 17.20 O.OOE+OOO 7 7039- 7058 7048.80 176 1. 40 0.46 1 .80E+001 8.49 O.OOE+OOO M Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2 . 000 sigma

[197]

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Sample

Title:

Bl06201AFSWC030GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB I * * * * * * *

1 * * * * * ., * * * " IDENTIFIED NUCLIDES * * "' * * * * * * * * * * .. 1 ,t * + ._ I Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.991 1460.82* 10 .66 8.82214E+005 2.18950E+005 Pb-212 1.000 238.63* 43.60 2.60016E+004 2.84131E+004 Bi-214 0.706 609.32* 45. 49 3.72958E+004 3.16140E+004 1120 .29 14.92 1764.49* 15.30 l.70637E+OOS 8.15921E+004 Pb- 214 0.434 295.22 18.42 351.93* 35.60 3.08420E+004 3.80863E+004

=Energy line found in the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M""2 ) Uncertainty K-40 0 .991 8.822138E+005 2.189500E+005 Pb-212 1 . 000 2.600162E+004 2.841309E+004 Bi-214 0 .706 5.470116E+004 2.947856E+004 Pb - 214 0.434 3.084199E+004 3.808633E+004

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

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

- - - - UN I D E N T I F I E D P E A K S **********

Peak Locate Performed on: 6/6/2018 2:52:19 PM Peak Locate From Channel : 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak To l.

No . (keV) Counts per Second % Uncertainty Type Nuclide 1 74. 90 4.1765E-002 247.25 4 509.80 3.5082E-002 96.52 M = First peak in a multiplet region m - Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[199]

Nuclide MDA Report 6/6/2018 2:52:19 PM Page 5

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Detector Name: 6279 Sample Geometry: 4M90D CP lIN Sample

Title:

B106201AFSWC030GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yie ld Line MDA Nuclide MDA Activity Dec. Level Name (keV) (% ) (pCi/MA2 ) (pci/M ... 2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10 .66 3.226E+004 3.23E+004 8.822E+005 O.OOOE+OOO Co-60 1173.23 99.85 2.737E+004 2.74E+004 -2.399E+004 1. 217E+004 1332.49 99.98 2.745E+004 -1 .804E+004 1.211E+004 Nb- 94 702.65 99.81 2.990E+004 2.44E+004 -1. 958E+002 1.382E+D04 871.09 99.89 2.443E+004 -1.552E+004 1.094E+004 Ag- 108m 433.90 90.50 2.819E+004 2.82E+004 -1. 308E+004 l .317E+004 614.30 89.80 3.811E+004 4 .626E+004 1 .79DE+004 722.90 90.80 3.401E+004 3.894E+004 1.574E+004 Cs-134 604.72 97.62 3.610E+004 2.94E+004 6.174E+004 1.70DE+004 795.86 85.46 2.943E+004 -2.281E+004 1 .330E+OD4 Cs-137 661.66 85. 10 3.630E+004 3.63E+004 -l.269E+004 1 .687E+004 Eu-152 121.78 28.67 1. 344E+OOS l.18E+005 1.409E+004 6.563E+004 344.28 26.60 1. 199E+005 8.612E+004 5.726E+D04 1408. 01 21. 07 1.184E+005 3.279E+004 5.122E+OD4 Eu-154 123. 07 40.40 9.331E+004 7.52E+004 -9.183E+004 4 .556E+004 723.30 20.06 l.540E+005 2.231E+005 7.129E+004 1274.43 34.80 7.516E+004 -8.538E+004 3.305E+004 Eu-155 86.55 30.70 1 .574E+OOS l.57E+OOS -2.063E+005 7.719E+004 105.31 21.10 1. 937E+OOS -2.878E+005 9.475E+OD4 Tl-208 583. 19 85.00 3.518E+004 3.52E+004 3.955E+004 1.640E+004 Bi-212 727.33 6.67 4 .60SE+005 4.6DE+005 5.098E+OOS 2.131E+005

+ Pb-212 238.63* 43.60 4.580E+004 4.58E+OD4 2.600E+004 2.158E+D04

+ Bi-214 609.32* 45.49 4.896E+004 2.57E+004 3.730E+004 2.221E+004 1120.29 14.92 1. 784E+005 -3.145E+OOS 7.936E+004 1764.49* 15.30 2.565E+004 1. 706E+005 0.000E+OOO

+ Pb-214 295.22 18.42 1 .569E+005 6.21E+004 -1. 014E+OOS 7.491E+004 351.93* 35.60 6.208E+004 3.084E+004 2.90DE+004 Ra-226 186.21 3.64 8.766E+OOS 8.77E+OOS 7.749E+004 4.246E+005 Ac-228 338.32 11.27 2.461E+005 1. 21E+O 05 2.329E+003 1.167E+005 911. 20 25.80 1. 214E+005 1. 532E+005 5.567E+004 968.97 15.80 2.008E+005 1.122E+OOS 9.184E+004 Am-241 59. 54 35.90 1.590E+005 1.59E+005 1 .670E+005 7.780E+004

+ : Nuclide identified during the nuclide identification

~ Energy line found in the spectrum

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

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

[200]

- - - - GAMM A SPECTRUM A N A L Y S I S *****

Filename: 6279 Report Generated On 6/5/2018 2:59:38 PM Sample Title B106201AFSWC031GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP 1IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample size 5.027E+001 M"2 Sample Taken On 6/5/2018 2:49: 00 PM Acquisition Started 6/5/2018 2:49:37 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0. 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP 1IN DATA VALIDATED DATE/3 ... , -If

&;~:

[201]

Peak Analysis Report 6/5/2018 2:59:38 PM Page 2

**** P E A K ANALYSIS R E P O R T *****

Detector Name: 6279 Sample

Title:

B106201AFSWC031GD Peak Analysis Performed on: 6/5/2018 2:59:38 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 177- 192 184.83 46.14 0.79 l.94E+001 34.92 9.46E+001 2 2 86- 309 299.87 74.94 1 .09 1.49E+002 75.12 3.13E+002 3 946- 963 954.75 238.81 0.70 4.09E+001 30. 14 5.51E+001 4 13 99- 1416 1407.46 352.06 0.38 3.74E+001 25.79 3.96E+001 5 2429- 2446 2437.42 609.64 0.76 4.33E+001 15.45 4.72E+OOO 6 3636- 3653 3644.69 911.41 0.36 1.36E+001 10. 71 4.36E+OOO 7 5838- 5857 5847.22 1461.52 1.61 6.47E+001 17. 01 2.29E+OOO M "' First peak in a multiplet region m :: Other peak in a multiplet region F :: Fitted singlet Errors quoted at 2. 000 sigma

[202]

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Sample

Title:

B106201AFSWC031GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10.66 7.73070E+OOS 2.14028E+005 Pb-212 1 .000 238.63* 43.60 3.97530E+004 2.99954E+004 Bi-214 0.453 609.32* 45.49 7.27375E+004 2.7391SE+004 1120.29 14.92 1764.49 15.30 Pb-214 0.434 295.22 18 .42 351.93* 35.60 5.67081E+004 3.99658E+004

= Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.999 7 .730701E+005 2.140285E+005 Pb-212 1.000 3.975304E+004 2.999542E+004 Bi-214 0.453 7.273754E+004 2.739153E+004 Pb-214 0.434 5.670807E+004 3.996578E+00 4

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

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

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

Peak Locate Performed on: 6/5/2018 2:59:38 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 46 .14 3.2281E-002 180.30 2 74.94 2.4847E-001 50.39 6 911.41 2.2731E-002 78.54 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC031GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (% ) (pCi/M"2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 1. 410E+005 l.41E+005 7.731E+005 5.431E+004 Co-60 1173.23 99.85 3.240E+004 2.87E+004 -1 .252E+004 1 .469E+004 1332.49 99.98 2.871E+004 -3.624E+004 l . 274E+004 Nb-94 702.65 99 . 81 2.852E+004 2.77E+004 -1 .444E+004 1.314E+004 8 71. 09 99.89 2.770E+004 -7.999E+003 1.258E+004 Ag-108m 433.90 90.50 3.127E+004 3.02E+004 -9.112E+003 1.471E+004 614 .30 89.80 3.655E+004 3.948E+004 1.712E+004 722.90 90.80 3.023E+004 -1.129E+003 1.386E+004 Cs-134 604.72 97.62 3.534E+004 3.36E+004 l .812E+004 l.661E+004 795 . 86 85.46 3.356E+004 -2.324E+004 1 .537E+004 Cs-137 661.66 85.10 3.575E+004 3.57E+004 2.486E+004 1 .659E+004 Eu-152 121.78 28.67 1. 363E+005 1.26E+005 9.384E+004 6.658E+004 344.28 26.60 1. 255E+005 -7.820E+004 6.005E+004 1408.01 21.07 1.473E+005 7.258E+004 6.569E+004 Eu-154 123.07 40.40 9.599E+004 8.54E+004 2.114E+004 4 .690E+004 723.30 20.06 1 .384E+005 8.950E+004 6.350E+004 1274.43 34.80 8.543E+004 7.538E+003 3.818E+004 Eu-155 86.55 30.70 1.628E+005 l. 63E+005 1 .194E+OOS 7.991E+004 105.31 21.10 1.952E+005 -1.732E+OOS 9.550E+004 Tl-208 583.19 85.00 3.787E+004 3.79E+004 1. 335E+004 l.775E+004 Bi-212 727.33 6.67 4 .083E+005 4.08E+005 9.610E+004 1.870E+005

+ Pb-212 238.63* 43.60 4.627E+004 4.63E+004 3.975E+004 2.182E+004

+ Bi-214 609.32* 45.49 2.692E+004 2.69E+004 7.274E+004 l.118E+004 1120. 29 14. 92 2.391E+005 1 . 435E+OOS 1.097E+005 1764.49 15.30 1.910E+005 1. 330E+OOS 8.267E+004

+ Pb-214 295.22 18.42 1. 609E+005 6.06E+004 -1.872E+005 7.690E+004 351.93* 35.60 6.065E+004 5.671E+004 2.827E+004 Ra-226 186.21 3.64 8.585E+005 8.59E+005 -3.450E+005 4.155E+005 Ac-228 338.32 11. 27 2.380E+005 1.19E+005 4 .079E+003 1.127E+005 911.20 25.80 1.188E+005 -3.883E+004 5.432E+004 968.97 15.80 1.985E+005 l .059E+005 9. 071E+004 Am-241 59.54 35.90 1.572E+OOS l .57E+005 6.648E+004 7.688E+004

+ ; Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[205]

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

Filename : 6279 Report Generated On 6/6/2018 10:30:58 AM Sample Title B106201AFSWC032GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.030E+001 M"2 Sample Taken On 6/6/2018 10:20:00 AM Acquisition Started 6/6/2018 10:20:56 AM Live T ime 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP lIN DATA VAUDAlED OATELi-, ./f TIMEL2~5 a~1:it;,.

[206]

Peak Analysis Report 6/6/2018 10: 30:58 AM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSWC032GD Peak Analysis Performed on: 6/6/2018 10 :30:57 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 286- 347 299.83 74.93 1. 10 1 .03E+002 168.01 7.91E+002 2 946- 963 954.26 238.69 0.77 4.98E+001 26.87 4.02E+001 3 1398- 1416 1407 .12 351.98 0.42 3. 44E+001 22.95 2.86E+001 4 2035- 2052 2043.97 511.26 0.31 1. 81E+001 17.75 l.79E+001 5 2428- 2445 2436.37 609.38 0.55 3.70E+001 17.78 1. 30E+001 6 5834- 5854 5844.28 1460.79 1. 49 8.48E+001 20.38 5.25E+OOO 7 7052- 7071 7061.50 1764.56 0 .38 l. 40E+001 7.48 O.OOE+OOO M :: First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[207]

Interference Corrected Activity Report 6/6/2018 10:30:58 AM Page 3

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Sample

Title:

Bl06201AFSWC032GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

* * * * * * * .,. * * * * * * ~ ,.. r *

IDENTIFIED NUCLIDES I P

I I I * * * * * * *

4 - * *

ti Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M~2 ) Uncertainty K-40 1 .000 1460.82* 10 .66 l. 01148E+006 2.58561E+005 Pb-212 1 .000 238.63* 43.60 4.83428E+004 2.72404E+004 Bi-214 0.710 609.32* 45.49 6.21279E+004 3.07781E+004 1120.29 14.92 1764.49* 15.30 1. 32885E+005 7. 18 231E+004 Pb-214 0 .434 295.22 18.42 351.93* 35.60 5.20425E+004 3.55860E+004

. Energy line found in t he spectrum.

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

[208]

Interference Corrected Activity Report 6/6/2018 10:30:58 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1 . 000 1 .011480E+006 2.585612E+OD5 Pb-212 1 . 000 4.834284E+OD4 2.724042E+00 4 Bi-214 0 . 710 7.310549E+OD4 2.829001E+00 4 Pb-214 0 .434 5.204246E+OD4 3.558597E+004

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

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

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

Peak Locate Performed on : 6/6/2018 10:3 0 :57 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 74 .93 1. 7083E-0 01 163.91 4 511 .26 3.0093E-002 98.32 M ~ First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[209]

Nuclide MDA Report 6/6/2018 10 : 30:58 AM Page 5

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

Detector Name: 627 9 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC032GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 2.037E+005 2.04E+005 1. 011E+006 8.568E+D04 Co-60 1173.23 99.85 2.565E+004 1.99E+004 -2.733E+OD4 1.131E+004 1332.49 99.98 1.990E+004 -4.322E+D04 8.333E+OD3 Nb-94 702.65 99.81 3.096E+004 2.73E+004 3.753E+OD4 1 .435E+004 8 71. 09 99.89 2.730E+004 -2.845E+004 1. 238E+004 Ag-108m 433.90 90.50 2.949E+004 2.95E+004 2.51DE+004 1.382E+004 614.30 89.80 3.983E+004 3.481E+OD4 1.876E+004 722.90 90.80 3.341E+004 -1.34DE+003 1.544E+OD4 Cs-134 604.72 97.62 3.667E+004 2.81E+004 1.048E+004 1 .728E+004 795.86 85.46 2.806E+004 1. 639E+004 1 .262E+004 Cs-137 661. 66 85.10 3.069E+004 3.07E+004 -1 .423E+OD4 1.407E+D04 Eu-152 121. 78 28.67 1.322E+005 1.18E+005 1.815E+005 6.454E+D04 344.28 26.60 1. 18 OE+005 9.248E+003 5.631E+004 1408. 01 21.07 1.220E+005 9.121E+OD3 5.302E+OD4 Eu-154 123.07 40. 40 9.339E+004 7.70E+004 8.138E+D04 4.56DE+004 723.30 20.06 1. 513E+005 -2.21DE+004 6.993E+004 1274.43 34.80 7.697E+004 6.362E+OD4 3.395E+004 Eu-155 86.55 30.70 1.532E+005 1.53E+OOS 5.406E+004 7.510E+004 105.31 21.10 1. 888E+005 -1.403E+004 9.229E+004 Tl-208 583.19 85.00 3.171E+004 3.17E+004 1 .232E+D03 l.467E+004 Bi-212 727.33 6.67 4 . 564E+005 4.56E+OD5 1.2D6E+005 2.llOE+OOS

+ Pb-212 238.63* 43.60 3.916E+004 3.92E+004 4.834E+D04 1. 827E+004

+ Bi-214 609.32* 45.49 4 .037E+004 2.57E+004 6.213E+OD4 1. 791E+D04 1120.29 14.92 2.141E+005 2.400E+OD5 9.719E+004 1764.49* 15.30 2.569E+OD4 1. 329E+005 O.OOOE+OOO

+ Pb-214 295.22 18.42 1.728E+005 5.32E+004 9.836E+D03 8.286E+D04 351.93* 35.60 5.319E+004 5.204E+D04 2.455E+D04 Ra-226 186.21 3.64 8.660E+005 8.66E+005 2.336E+005 4.193E+OOS Ac-228 338.32 11. 27 2.430E+005 1 .27E+005 3.525E+D04 1.152E+005 911.20 25.80 1.268E+005 4.381E+OD3 5.832E+004 968.97 15.80 2.031E+OOS 2.529E+D05 9.301E+OD4 Arn-241 59.54 35.90 l. 467E+005 1.47E+005 -1.549E+OOS 7.164E+004

+ ~ Nuclide identified during the nuclide identification

= Energy line found in the spectrum

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

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

[210]

***

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

Filename: 6279 Report Generated On 6/6/2018 10:03 ; 14 AM Sample Title B106201AFSWC033GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.030E+001 MA2 Sample Taken On 6/6/2018 9:53:00 AM Acquisition Started 6/6/2018 9:53:13 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 , 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP lIN DATA VALIDATED DATE/2--' -Lf

~~

[211]

Peak Analysis Report 6/6/2018 10:03:14 AM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSWC033GD Peak Analysis Performed on: 6/6/2018 10:03:14 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 281- 348 299.50 74 .84 1. 25 3.89E+002 161.22 6.34E+002 2 944- 961 952.71 238.30 0 .38 2.95E+001 3 1 .62 6.45E+001 3 1396- 1414 1405.39 351.55 0.42 3.25E+001 2 1 .93 2.55E+001 4 2033- 2050 2041.20 51 0 .57 0.45 3.60E+001 16.93 1. lOE+O 01 5 2321- 2338 2329.41 582.64 0.50 1.85E+001 16.08 1. 25E+O 01 6 2426- 2443 2434.26 608.85 0.65 3.04E+001 16.99 1 .26E+001 7 3631- 3648 3639.94 910.22 1. 32 1.22E+D01 11.79 6.80E+OD0 8 5830- 5849 5839.21 1459.52 1. 26 7.80E+001 17.66 O.OOE+OOO M = Fi rst peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[212]

Interference Corrected Activity Report 6/6/2018 10 :03:14 AM Page 3

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Sample

Title:

B106201AFSWC033GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL. NLB

.. . . . . . . . . . . . .. ... ~ ., "' .. " IDENTIFIED NUCLIDES . ., ..... ......... ....... " ........

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0.997 1460.82* 10.66 9.30355E+005 2.25642E+005 Tl- 208 1 .000 583.19* 85.00 1.61432E+004 l . 41879E+004 Pb-212 1.000 238.63* 43.60 2.86062E+004 3.10271E+004 Bi-214 0. 453 609.32* 45.49 5.09911E+004 2.91700E+004 1120.29 14 .92 1764.49 15.30 Pb-214 0.434 295.22 18 .42 351.93* 35.60 4. 91391E+004 3.39618E+004

= Energy line found in t he spectrum.

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

[213]

Interference Corrected Activity Report 6/6/2018 10:03:14 AM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.997 9.303551E+005 2.256424E+005 Tl-208 1.000 1.614322E+004 1.418792E+004 Pb-212 1. 000 2.860623E+004 3.102713E+00 4 Bi-214 0.453 5.099106E+004 2.916997E+00 4 Pb-214 0.434 4.913909E+004 3.396178E+004

? Nuclide is part of an undetermined solution x ~ Nuclide rejected by the interference analysis

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

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

Peak Locate Performed on: 6/6/2018 10:03:14 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % uncertainty Type Nuclide 1 74.84 6.4883E-001 41.41 4 510.57 5.9973E-002 47.06 7 910.22 2.0329E-002 96.65 Tol. Ac-228 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[214]

Nuclide MDA Report 6/6/2018 10:03:14 AM Page 5

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Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC033GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yie ld Line MDA Nuclide MDA Activity Dec . Level Name (keV) (% ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA 2 )

+ K-40 1460 .82* 10.66 3 . 228E+004 3.23E+004 9.304E+005 O.OOOE+OOO Co-60 1173 .23 99.85 2.897E+004 l.99E+004 3.626E+003 l.29BE+004 1332.49 99.98 1.990E+004 1.075E+004 8.333E+003 Nb-94 702.65 99. 81 3.173E+004 2.92E+004 3.028E+004 1 .474E+004 871. 09 99.89 2.916E+004 -3.246E+004 l.331E+004 Ag- 108m 433.90 90.50 3.292E+004 2.81E+004 1 .196E+004 1.554E+004 614.30 89.80 3.983E+004 5.579E+004 l.876E+004 722.90 90.80 2.811E+004 -2.394E+004 l .279E+004 Cs-134 604.72 97.62 3.492E+004 3.49E+004 1.811E+004 l .641E+004 795.86 85.46 3.884E+004 3.57SE+004 l.801E+004 Cs-137 661. 66 85. 10 3. 601E+004 3.60E+004 -l .27BE+004 1.673E+004 Eu-152 121. 78 28.67 l .263E+OOS 1.03E+OOS -l .187E+003 6.162E+004 344.28 26.60 1 .169E+005 -3.094E+004 5.573E+004 1408. 01 21.07 1.025E+005 -5.679E+004 4.329E+004 123.07 40.40 8.915E+004 8.91E+004 2.029E+003 4.348E+004 723.30 20.06 1. 289E+005 6 .419E+004 5.875E+004 1274.43 34.80 9.150E+004 4.921E+004 4.122E+004 Eu-155 86.55 30.70 l .549E+005 l .SSE+OOS 2.563E+003 7.595E+004 105.31 21.10 l .858E+OOS -8.194E+004 9.078E+004

+ Tl-208 583.19* 85.00 2.190E+004 2.19E+004 1.614E+004 9.770E+003 Bi-212 727.33 6.67 3.889E+005 3.89E+OOS -3.334E+OOS 1. 773E+005

+ Pb-212 238.63* 43.60 5.003E+004 5.00E+004 2.861E+004 2.370E+004

+ Bi-214 609.32* 45.49 4 .024E+004 4.02E+004 5.099E+004 l.785E+004 1120.29 14 .92 2.25SE+OOS 2.691E+OOS 1.029E+OOS 1764.49 15. 30 2.023E+005 l.519E+OOS 8.832E+004

+ Pb-214 295.22 18.42 l.608E+005 5.07E+004 1.661E+OOS 7.685E+004 351.93* 35.60 5.06BE+004 4 .914E+004 2.329E+004 Ra-226 186.21 3.64 8.334E+OOS 8.33E+OOS 8.165E+004 4.030E+OOS Ac-228 338.32 11. 27 2.400E+005 l .17E+OOS -l .595E+OOS 1.137E+005 911. 20 25.80 l. 173E+005 6.446E+004 5.359E+004 968.97 15.80 1.984E+OOS 1.807E+005 9.065E+004 Am-241 59.54 35.90 l.414E+005 1. 41E+O OS 5.729E+004 6.895E+004

+ = Nuclide identified during the nuclide identification

Energy line found in the spectrum

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

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

[215]

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

Filename: 6279 Report Generated On 6/5/201B 3 : .12:4.7 PM Sample Title B106201AFSWC034GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 6/5/2018 3:02:00 PM Acquisition Started 6/5/2018 3:02:46 PM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0.07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration used Done On 6/2/2018 Efficiency ID 4M90D CP 1IN DATAVAUDATED DATEI.Z* , *11 TIME1t2'1£

~~

[216]

Peak Analysis Report 6/5/2018 3:12:47 PM Page 2

P E A K A N A L Y S I S REPORT *****

Detector Name: 6279 Sample

Title:

B106201AFSWC034GD Peak Analysis Performed on: 6/5/2018 3:12:46 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts M 1 247- 308 255.05 63.72 0.79 2.98E+OOO 38.63 1.04E+002 m 2 247- 308 300.21 75.02 0.80 9.98E+OOO 129. 35 1.80E+002 3 946- 963 954.15 238.66 1. 07 1.15E+001 30 . 47 6.75E+001 4 1171- 1188 1179.64 295.07 0.49 1.77E+001 22.82 3.23E+001 5 1397- 1416 1406.65 351.86 0.55 4 .67E+001 23.88 2.73E+001 6 2035- 2052 2043.66 511 .18 0.78 2.53E+001 17.47 1 .57E+001 7 2428- 2445 2436.80 609.49 0.80 3.53E+001 18.36 1. 47E+001 8 5837- 5856 5846.42 1461.32 1. 84 7.70E+001 17.55 O.OOE+OOO 9 7053- 7072 7062.89 1764.91 0.59 9.00E+OOO 10.30 5.00E+OOO M = First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2.000 sigma

[217]

I nt erference Corrected Activity Report 6/5/2018 3: 12 : 47 PM Page 3

** *

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

Sample

Title:

B106201AFSWC034GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENT IFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10 .66 9.19768E+005 2.24334E+005 Pb-212 1.000 238.63* 43.60 1.11744E+004 2.96623E+004 Bi-214 0.710 609.32* 45.49 5.93572E+004 3.16645E+004 1120.29 14.92 1764.49* 15.30 8.54889E+004 9.80364E+004 Pb-214 1.000 295.22* 18.42 4.62141E+004 6. 00 819E+004 351.93* 35.60 7.07422E+004 3.76640E+004 Am-241 0.972 59.54* 35.90 3.55594E+003 4. 61123E+004

=Energy line found in t he spectrum.

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

[218]

Ir.~erference Corrected Activity Report 6/5/2018 3:12:47 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name confidence (pCi/M"2 } Uncertainty K-40 1.000 9.197685E+OOS 2.243340E+OOS Pb-212 1. 000 1 .117439E+004 2.966234E+004 Bi-214 0.710 6.182572E+004 3.013179E+004 Pb-214 1 .000 6.382249E+004 3.191207E+004 Am-241 0.972 3.555943E+003 4.611231E+004

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

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

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

Peak Locate Performed on: 6/5/2018 3: 12 :46 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV} Counts per Second % Uncertainty Type Nuclide m 2 75.02 l .6634E-002 1296.02 6 511.18 4.2215E-002 68.96 M = First peak in a multiplet region m = Other peak in a multiplet region F ~ Fitted singlet Errors quoted at 2.000 sigma

[219]

Nuclide MDA Report 6/5/2018 3: 12: 47 PM Page 5

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

Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC034GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M"'2 ) (pCi/M"'2 ) (pci/M ... 2 ) (pCi/MA2 )

+ K-40 1460.82* 1 0.66 3.232E+004 3.23E+004 9.198E+OOS O.OOOE+OOO Co-60 1173 .23 99.85 2.899E+004 2.33E+004 -8.484E+003 1.29BE+004 1332.49 99.98 2.328E+004 1.553E+004 1 .002E+004 Nb-94 702.65 99.81 2.909E+004 2.88E+004 5.411E+003 1 .342E+004 8 71. 09 99.89 2.882E+004 -1.404E+004 1. 314E+004 Ag-108m 433.90 90.50 2.801E+004 2.80E+004 -9.558E+003 1.308E+004 614.30 89.80 3.857E+004 1. 903E+004 1.813E+004 722.90 90.80 3.281E+004 1. 049E+003 1.515E+004 Cs- 134 604.72 97.62 3.782E+004 3.32E+004 5.839E+004 1.785E+004 795.86 85.46 3.317E+004 1.271E+004 1.517E+004 Cs-137 661.66 85.10 3.333E+004 3.33E+004 -2.160E+003 1.539E+004 Eu-152 121. 7 8 28.67 1. 301E+005 1.22E+005 -6.855E+004 6.353E+004 344.28 26.60 1. 255E+005 2.892E+004 6.005E+004 1408. 01 21. 0 7 1. 220E+005 3.199E+004 5.305E+004 Eu-154 123.07 40.40 9. 171E+004 7.52E+004 -5.513E+004 4.476E+004 723.30 20.06 1.513E+OOS 7.697E+004 6.997E+004 1274.43 34.80 7.520E+004 -4.286E+004 3.307E+004 Eu-155 86.55 30.70 1. 506E+005 1.51E+005 -1 .198E+005 7.378E+004 105.31 21.10 1.891E+005 - 1. 261E+005 9.242E+004 Tl-208 583.19 85.00 3.644E+004 3.64E+004 8.095E+003 1.703E+004 Bi-212 727.33 6.67 4.689E+005 4.69E+005 5.466E+005 2.172E+005

+ Pb-212 238.63* 43.60 S.011E+004 5.01E+004 1.117E+004 2.374E+004

+ Bi-214 609.32* 45.49 4 .322E+004 4 .32E+004 5.936E+004 1 .934E+004 1120. 29 14. 92 2.567E+005 1.184E+005 1 .185E+005 1764.49* 15.30 1 .564E+005 8.549E+004 6.537E+004

+ Pb-214 295.22* 18.42 9.825E+004 S.28E+004 4.621E+004 4.559E+004 351.93* 35.60 5.284E+004 7.074E+004 2.437E+004 Ra-226 186.21 3.64 8.395E+005 8.39E+005 6.672E+OOS 4.060E+005 Ac-228 338.32 11. 27 2.5BOE+005 1.26E+005 1 .949E+004 1.227E+005 911. 20 25.80 1.255E+005 8.694E+004 5.770E+004 968.97 15 .80 1.912E+OOS 9.370E+004 8.705E+004 Am-241 59.54* 35.90 5.997E+004 6.00E+004 3.S56E+003 2.837E+004

+ = Nuclide identified during the nuclide identification

~ Energy line found in the spectrum

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

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

[220]

~*~**********************************************************************

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

Filename: 6279 Report Generated On 6/5/2Dl8 B:59;52 AM Sample Title B106201AFSWC035GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP lIN Peak Locate Threshold 3 . 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.027E+001 MA2 Sample Taken On 6/5/2018 8:49: 00 AM Acquisition Started 6/5/2018 8:49:51 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2 017 Efficiency Calibration used Done On 6/2/2018 Efficiency ID 4M90D CP 1IN DATA VALIDATED DATELe'*, ..JS' a;;~

[221]

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Detector Name: 6279 Sample

Title:

B106201AFSWC035GD Peak Analysis Performed on: 6/5/2018 8:59:52 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Pe a k Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 291- 311 299.95 74.96 0.96 1.29E+002 6 4 .88 2.54E+002 2 945- 962 953.52 238.50 0.99 3.50E+001 26.95 4.50E+001 3 1171- 1188 1179.83 295.12 0.90 2.60E+001 19.76 2.20E+001 4 1398- 1415 1406.50 35 1 .82 0.73 3.29E+001 22.38 2.81E+001 s 2033- 2050 2 041. 25 51 0 .58 0.51 2.35E+001 18.99 1.85E+001 6 2425- 2442 2433.52 608.67 0.47 3.26E+001 16.77 1.14E+001 7 4468- 4487 4477.37 1119.45 0.39 1. 48E+001 10 .90 4 .18E+OOO 8 5831- 5850 5840.58 1459.86 1. 35 6.37E+001 18.92 7.27E+OOO 9 7047- 7066 7056.99 1763.44 0.50 1. 20E+001 6.93 O.OOE+OOO M First peak in a multiplet region m Other peak in a multiplet region F ,: Fitted singlet Errors quoted at 2.000 sigma

[222]

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Sample

Title:

B106201AFSWC035GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10.66 7.60754E+005 2.35352E+005 Pb-212 1 .000 238.63* 43.60 3.39956E+004 2.67473E+004 Bi- 214 0.999 609.32* 45.49 5.47176E+004 2.89121E+004 1120.29* 14.92 1.07766E+005 7.97317E+004 1764.49* 15.30 l.13919E+005 6.64008E+004 Pb-214 1.000 295.22* 18.42 6.78483E+004 5.27609E+004 351.93* 35.60 4.97331E+004 3.46850E+004

=Energy line found in the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0 .999 7.607544E+005 2.353520E+005 Pb-212 1. 000 3.399555E+004 2.674728E+00 4 Bi-214 0.999 6.849369E+004 2.515448E+004 Pb-214 1. 000 5.519955E+004 2.898300E+004

?

X .. Nuclide

"'- is part of an undetermined solution Nuclide rejected by the interference analysis Nuclide contains energy lines not used in weighted Mean Activity

@ =

Errors quoted at 2.000 sigma

- - - - U N I D E N T I F I E D P E AK S **********

Peak Locate Performed on : 6/5/2018 8:59:52 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 74 .96 2.1532E-001 50.22 5 510 .58 3.9107E-002 80.94 M = First peak in a multip let region m = Other peak in a multip let region F = Fitted singlet Errors quoted at 2 . 000 sigma

[224]

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Detector Name: 6279 Sample Geometry: 4M90D CP lIN Sample

Title:

B106201AFSWC035GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/M"2 ) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 2.318E+005 2.32E+005 7.608E+005 9.973E+004 Co-60 1173.23 99.85 2.950E+004 2.62E+004 2.054E+004 1.324E+004 1332.49 99.98 2.615E+004 -3.285E+004 1 .146E+004 Nb-94 702.65 99.81 2.824E+004 2.82E+004 -1.638E+004 1 .299E+004 871.09 99.89 2.918E+004 2.597E+004 1.332E+004 Ag-108m 433.90 90.50 2.840E+004 2.84E+004 5.013E+003 1.327E+004 614.30 89.80 3.813E+004 -6.249E+003 1.791E+004 722.90 90.80 3.090E+004 4.705E+002 l.419E+004 Cs-134 604.72 97.62 3.688E+004 3.51E+004 4.716E+004 1 .739E+004 795.86 85.46 3.506E+004 1.223E+004 1 .612E+004 Cs-137 661.66 85.10 3.364E+004 3.36E+004 3.678E+004 1.554E+004 Eu- 152 121.78 28.67 1.224E+005 1.15E+005 9.460E+004 5.967E+004 344.28 26.60 1.222E+005 4 .395E+004 5.841E+004 1408.01 21. 07 1.147E+005 -7.541E+004 4 .939E+004 Eu - 154 123.07 40.40 8.611E+004 8.22E+004 -3.673E+004 4.196E+004 723.30 20.06 1 .414E+005 l.053E+004 6.499E+004 1274.43 34.80 8.218E+004 4.310E+004 3.656E+004 Eu-155 86 . 55 30.70 l.487E+005 1.49E+005 -3.319E+004 7.285E+004 105 .31 21.10 1.762E+005 -5.337E+004 8.600E+004 Tl-208 583. 19 85. 00 3.338E+004 3.34E+004 -2.116E+004 1.551E+004 Bi-212 727.33 6.67 4 .083E+005 4.08E+005 -1 .534E+005 l. 870E+005

+ Pb-212 238.63* 43.60 4.132E+004 4.13E+004 3.400E+004 1. 934E+004

+ Bi-214 609.32* 45.49 3.846E+004 2.57E+004 S.472E+004 l.696E+004 1120.29* 14.92 1.120E+005 1.078E+005 4.614E+004 1764.49* 15.30 2.569E+004 1.139E+005 O.OOOE+OOO

+ Pb-214 295.22* 18 .42 7.984E+004 5.20E+004 6.785E+004 3.638E+004 351.93* 35.60 5.196E+004 4.973E+004 2.393E+004 Ra-226 186.21 3.64 8.381E+005 8.38E+005 -7.663E+005 4.053E+005 Ac-228 338.32 11 .27 2.512E+005 1.20E+005 l.199E+005 1 .193E+005 911.20 25.80 1.202E+005 7.740E+004 5.502E+004 968.97 15.80 2.056E+005 -2.418E+004 9.422E+004 Am-241 59.54 35.90 1. 443E+005 l. 44E+005 l.232E+005 7.044E+004

+= Nuclide identified during the nuclide identification

- Energy line found in the spectrum

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

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

[225]

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

Filename: 6279 Repo~t Generated On 6/5/2018 8:47:43 AM Sampl e Title B106201AFSWC036GD Sampl e Description Ul Diesel Fuel Oil Storage Wall Sampl e Identification Sample Type Gamma Direct Sample Geometry 4M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.027E+001 M"2 Sample Taken On 6/5/2018 8:37:00 AM Acquisition Started 6/5/2018 8:37:42 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 06 %

Energy Cal.ibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP lIN DATA VALIDATED DATE/,z .. 4-/Y TIME/Ja<J Q,.*1'4

[226]

Peak Analysis Report 6/5/2018 8:47:43 AM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSWC036GD Peak Analysis Performed on: 6/5/2018 8:47:42 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 178- 193 185.80 46.39 0.62 1. 31E+001 29.07 6.59E+001 2 283- 308 297.94 74.45 0.63 1. 40E+002 78. 01 3.2SE+002 3 945- 962 953.34 238.46 0.77 2.32E+001 25.52 4.28E+001 4 1171- 1188 1179.32 294.99 1.21 3.45E+001 20.79 2.25E+001 5 1341- 1358 1349.65 337.60 1. 12 3.llE+OOl 15.53 8.89E+OOO 6 1399- 1416 1407.26 352.02 0.89 3.88E+001 20.02 1.82E+001 7 1527- 1544 1535.88 38 4 .19 0.77 1. 26E+001 15.06 1.34E+001 8 2032- 2049 2040.65 51 0 .43 0.39 2.98E+001 15 .57 9.15E+OOO 9 2426- 2443 2434.39 608.89 0.50 2.30E+001 16.38 1 .30E+001 10 5831 - 5850 5840.30 1459.79 0.46 6.34E+001 17.10 2.64E+OOO M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Sample

Title:

B106201AFSWC036GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB R * * * * *

ill ... * ~ *

ill ,a ... * * * ** IDENT IFIED NUCLIDES . .......... - - .... .. . . . .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 0.998 1460.82* 10 .66 7.56282E+005 2.14394E+005 Pb-212 1.000 238.63* 43.60 2.24956E+004 2.50499E+004 Bi-214 0.453 609.32* 45.49 3.85771E+004 2.78975E+004 1120.29 14. 92 1764.49 15. 30 Pb-214 1. 000 295.22* 18. 42 9.01146E+004 5.61897E+004 351.93* 35.60 5.87076E+004 3.15625E+004

= Energy line found in t he spectrum.

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

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0 .998 7.562824E+005 2.143938E+005 Pb-212 1.000 2.249557E+004 2.504992E+00 4 Bi-214 0.453 3.857705E+004 2.789755E+004 Pb - 214 1.000 6.624042E+004 2.751832E+004

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

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

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

Peak Locate Performed on: 6/5/2018 8:47:42 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 46.39 2.1915E-002 221. 05 2 74. 45 2.3335E-001 55.71 5 337.60 5.1854E-002 49.91 Tol. Eu-152 Ac-228 7 384.19 2.1026E-002 119.38 8 510.43 4.9744E-002 52. 16 M :: First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma

[229]

Nuclide MDA Report 6/5/2018 8:47:43 AM Page 5

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Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC036GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 } (pCi/MA2)

+ K-40 1460.82* 10.66 l. 548E+005 1 .55E+005 7.563E+005 6.124E+004 Co-60 1173.23 99. 85 2.950E+004 2.33E+004 1.695E+004 1.324E+004 1332.49 99.98 2.328E+004 -2.723E+004 1.002E+004 Nb-94 702.65 99.81 2.736E+004 2.69E+004 -1.161E+004 1.255E+004 871.09 99.89 2.693E+004 -l.526E+003 1 .219E+004 Ag-108m 433.90 90.50 2.763E+004 2.76E+004 1.180E+004 1 .289E+004 614. 3 0 89.80 3.791E+004 -8.553E+002 l.780E+004 722.90 90.80 3.741E+004 6.046E+004 1.745E+004 Cs-134 604.72 97.62 3.454E+004 3.28E+004 5.954E+003 1.621E+004 795.86 85.46 3.278E+004 1.781E+004 l.498E+004 Cs-137 661.66 85.10 3.426E+004 3.43E+004 9.421E+003 1.585E+004 Eu-152 121. 78 28.67 1. 248E+005 1.15E+005 -2.597E+003 6.085E+004 344.28 26.60 l .154E+005 1 .125E+005 5.498E+004 1408.01 21. 07 l .444E+005 6.698E+004 6.425E+004 Eu-154 123.07 40.40 8.804E+004 8.80E+004 -2.167E+004 4.292E+004 723.30 20.06 1.694E+005 1.893E+005 7.900E+004 1274.43 34.80 9.301E+004 1.941E+004 4 .197E+004 Eu-155 86.55 30.70 1.519E+005 1.52E+005 2.152E+OOS 7.442E+004 105 .31 21.10 1.805E+005 1 .377E+005 8.812E+004 Tl-208 583.19 85.00 3.619E+004 3.62E+004 7.220E+003 1 .691E+004 Bi-212 727.33 6.67 4.768E+005 4.77E+005 3.982E+004 2.212E+005

+ Pb-212 238.63* 43 .60 4.039E+004 4.04E+004 2.250E+004 1.888E+004

+ Bi-214 609.32* 45.49 4.124E+004 4.12E+004 3.858E+004 1.835E+004 1120 .29 14 .92 2.082E+005 -5.364E+004 9.426E+004 1764.49 15.30 2.025E+005 5.045E+004 8.838E+004

+ Pb-214 295.22* 18.42 8.078E+004 4.31E+004 9.011E+004 3.685E+004 351.93* 35.60 4.314E+004 5.871E+004 1.952E+004 Ra-226 186.21 3.64 8.086E+005 8.09E+005 5.340E+005 3.906E+005 Ac-228 338.32 11. 27 2.317E+005 1.13E+OOS -1.084E+005 1.095E+005 911. 20 25.80 1.130E+005 5.363E+004 5.146E+004 968.97 15.80 1 .887E+005 6.586E+004 8.580E+004 Am-241 59. 54 35.90 l .475E+005 1 .48E+005 2.629E+004 7.205E+004

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[230]

- - - - GAMMA S P E C T R U M A N A L Y S I S *****

Filename: 6279 Report Generated On 6/5/2018 8:35:12 AM Sample Title B106201AFSWC037GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.027E+001 M"2 Sample Taken On 6/5/2018 8:25:00 AM Acquisition Started 6/5/2018 8:25:11 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 06 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP 1IN DATA VALIDATED DATE/3-4i /f.

4

~~

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Peak Analysis Report 6/5/2018 8:35:12 AM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSWC037GD Peak Analysis Performed on: 6/5/2018 8:35:12 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 181- 196 188.68 47.11 0 .64 2 .40E+001 33.59 8. 60E+001 M 2 247- 308 254.05 63.47 0 .82 3.64E+001 19. 00 7. 70E+001 m 3 247- 308 300.22 75.02 0 .83 9.23E+001 27.68 1. 25E+002 4 945- 962 953.03 238.38 0 .38 5.66E-001 30.63 6. 74E+001 5 1397- 1414 1405.74 351.64 0 .63 2.37E+001 2 1 .33 2. 73E+001 6 2427- 2444 2435.65 609.20 0 .35 2.87E+001 14.12 6.30E+OOO 7 4472- 4491 4481.95 112 0 .59 0 .30 8.03E+OOO 13.32 9.97E+OOO 8 5835- 5854 5844.67 146 0 .88 0 .48 7.80E+001 17.66 O.OOE+OOO 9 7051- 7070 7060.25 176 4 .25 1. 69 1 .80E+001 8.49 O.OOE+OOO M = Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2 . 000 sigma

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Sample

Title:

B106201AFSWC037GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1 .000 1460.82* 10.66 9.31519E+005 2.25925E+005 Pb-212 1.000 238.63* 43.60 5.49759E+002 2.97382E+004 Bi-214 1.000 609.32* 45.49 4.82111E+004 2.44219E+004 1120.29* 14. 92 5.84259E+004 9.70749E+004 1764.49* 15.30 1.70933E+005 8.17334E+004 Pb-214 0.434 295.22 18.42 351.93* 35.60 3.58995E+004 3.27141E+004 Am- 241 0.976 59.54* 35.90 4 .36180E+004 2.43874E+004

=Energy line found in the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2) Uncertainty K-40 1.000 9.315187E+005 2.259246E+005 Pb-212 1. 000 5.497594E+002 2.973821E+004 Bi-214 1. 000 5.827833E+004 2.274813E+00 4 Pb-214 0.434 3.589946E+004 3.271413E+004 Am-241 0.976 4.361797E+004 2.438743E+00 4

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

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

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

Peak Locate Performed on: 6/5/2018 8:35: 12 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 47.11 4 .0000E-002 139.95 m 3 75.02 1 .5386E-001 29.99 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[234]

Nuclide MDA Report 6/5/2018 8:35:12 AM Page 5

- - - - N U C L I D E MD A REPORT *****

Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC037GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 3.232E+004 3.23E+004 9.315E+005 O.OOOE+OOO Co-60 1173.23 99.85 2.793E+004 1. 99E+004 2.567E+004 1 .245E+004 1332.49 99.98 1 .991E+004 -3.153E+003 8.338E+003 Nb-94 702.65 99.81 3.072E+004 2.81E+004 2.847E+004 1 .423E+004 871.09 99.89 2.808E+004 -3.310E+004 l.277E+004 Ag-108m 433.90 90.50 3.093E+004 2.78E+004 l.671E+004 l.454E+004 614.30 89.80 3.SBSE+004 1.923E+004 1.677E+004 722.90 90.80 2.775E+004 -1.599E+004 1.262E+004 Cs-134 604.72 97.62 3.330E+004 2.76E+OD4 4.864E+004 l.559E+004 795.86 85.46 2.761E+004 1.651E+004 1 .239E+004 Cs-137 661.66 85.10 4.037E+004 4.04E+004 -1.116E+004 1. 891E+004 Eu-152 121.78 28.67 1. 258E+005 8.84E+004 -1. 968E+004 6.137E+004 344.28 26.60 1. 029E+005 -1. 938E+003 4.874E+004 1408. 01 21. 07 8.842E+004 -1. 977E+004 3.624E+004 Eu-154 123.07 40. 40 8.895E+004 8.70E+OD4 -4.676E+OD4 4.338E+004 723.30 20.06 l.290E+005 1.68SE+004 S.879E+004 1274.43 34.80 8.701E+004 4.808E+004 3.897E+004 Eu-155 86.55 30.70 1.550E+OOS 1.SSE+OOS 7.284E+004 7.599E+004 105.31 21.10 1.818E+OOS -2.594E+004 8.879E+004 Tl-208 583. 19 85.00 3.284E+004 3.28E+004 7.294E+003 1 .524E+004 Bi-212 727.33 6.67 3.989E+005 3.99E+OOS 3.535E+005 l.822E+OOS

+ Pb-212 238.63* 43.60 5.149E+004 S.15E+004 S.498E+002 2.443E+004

+ Bi-214 609.32* 45.49 2.997E+004 2.57E+004 4.821E+004 1.271E+004 1120.29* 14.92 l.640E+OOS 5.843E+004 7.218E+004 1764.49* 15. 30 2.570E+004 1.709E+005 O.OOOE+OOO

+ Pb-214 295.22 18. 42 1. 509E+005 5.13E+004 -l.032E+005 7.193E+004 351.93* 35.60 5.132E+004 3.590E+004 2.361E+004 Ra-226 186. 21 3.64 8.057E+005 8.06E+005 5.464E+005 3.891E+005 Ac-228 338.32 11. 27 2.161E+005 1.33E+005 1.026E+OOS l.017E+005 911. 2 0 25.80 1 .331E+OOS 4.315E+004 6.151E+004 968.97 15.80 2.056E+OOS 1.14SE+OOS 9.422E+004

+ Am-241 59.54* 35.90 5.214E+004 5.21E+004 4.362E+004 2.445E+004

+ - Nuclide identified during the nuclide identification

~Energy line found in the spectrum

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

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

[235]

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

Filename: 6279 Report Generated On 6/5/2018 8:06:35 AM Sample Title B106201AFSWC038GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.027E+001 MA2 Sample Taken On 6/5/2018 7:56:00 AM Acquisition Started 6/5/2018 7:56:33 AM Live Time 600.0 seconds Real Time 600. 4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP 1IN DATAVAUD,!\TED DATE/.J .. &> *IP GS4!:~~'-

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Detector Name: 6279 Sample

Title:

B106201AFSWC038GD Peak Analysis Performed on: 6/5/2018 8:06:34 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 286- 308 298.69 74.64 1.02 1.46E+002 68.98 2.66E+002 2 946- 963 954.87 238.84 0.65 4.03E+001 28.10 4.77E+001 3 1399- 1416 1407 .75 352.14 1 .18 4.68E+001 21.20 2.02E+001 4 2326- 2343 2334.27 583.85 0.69 2.90E+001 10.77 O.OOE+OOO 5 2429- 2446 2437.79 609.74 0.60 3.75E+001 1 4 .45 4.50E+OOO 6 2639- 2656 2647.69 662.22 0 .60 3.17E+001 18 . 83 l.73E+001 7 5839- 5859 5848.75 1461.90 0 .97 7.90E+001 17.78 O.OOE+OOO M == First peak in a multiplet region m "'- Other peak in a multiplet region F == Fi tted singlet Errors quoted at 2.000 sigma

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Sample

Title:

B106201AFSWC038GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/MA2 ) Uncertainty K-40 0.998 1460.82* 10 .66 9.43922E+005 2.27666E+005 Cs-137 1.000 661.66* 85.10 2.99971E+004 l.81554E+004 Tl-208 0.999 583.19* 85.00 2.53975E+004 9.91417E+003 Pb-212 1.000 238.63* 43.60 3.91835E+004 2.80422E+004 Bi-214 0.453 609.32* 45.49 6.30277E+004 2.54435E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.434 295.22 18.42 351.93* 35.60 7.09109E+004 3.3 8177E+004

~ Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0.998 9.439220E+005 2.276661E+005 Cs-137 1. 000 2.999714E+004 1.815540E+004 Tl-208 0.999 2.539751E+004 9.914168E+003 Pb-212 1 .000 3.918347E+004 2.804225E+004 Bi-214 0.453 6.302772E+004 2.544346E+004 Pb-214 0.434 7.091089E+004 3.381773E+00 4

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

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

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

Peak Locate Performed on: 6/5/2018 8:06:34 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 74.64 2.4361E-001 47 .19 M ::::- First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[239]

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Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC038GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M""2 ) (pCi/M""2 )

+ K-40 1460.82* 10.66 3.233E+004 3.23E+004 9.439E+005 O.OOOE+OOO Co-60 1173.23 99.85 2.793E+004 2 .40E+OD4 1 .121E+004 1.245E+004 1332.49 99.98 2.403E+004 1 .673E+004 1.040E+004 Nb-94 702.65 99. 81 2.644E+004 2.57E+004 -2.081E+003 1.209E+004 871. 09 99.89 2.572E+004 4.949E+003 1.159E+004 Ag-108rn 433.90 90.50 3.005E+004 2.99E+004 4.252E+003 1.410E+004 614.30 89.80 3.678E+004 2.951E+004 1.723E+004 722.90 90.80 2.989E+004 8.500E+003 1.369E+004 Cs-134 604.72 97.62 3.534E+004 2.90E+004 4.063E+004 1.661E+004 795.86 85.46 2.900E+004 3.029E+004 1.308E+004

+ Cs-137 661.66* 85. 10 2.601E+004 2.60E+004 3.000E+004 1.173E+004 Eu-152 121.78 28.67 1. 227E+005 1.15E+005 -l.736E+OOS 5.979E+004 344.28 26.60 1. 2 62E+O 05 4.281E+004 6.041E+004 1408.01 21. 07 1 .147E+OOS 1.676E+004 4.939E+004 Eu-154 123.07 40.40 8.746E+004 7.88E+004 -1.365E+003 4.263E+004 723.30 20.06 l.338E+005 3.531E+004 6.119E+004 1274.43 34.80 7.878E+004 -2.890E+004 3.486E+004 Eu-155 86.55 30.70 1.494E+005 1. 49E+005 5.917E+004 7.318E+004 105.31 21.10 1.825E+005 1. 226E+OOS 8.916E+D04

+ Tl-208 583.19* 85.00 2.370E+003 2.37E+003 2.540E+004 O.OOOE+OOO Bi-212 727.33 6.67 3.842E+OOS 3.84E+005 -3.914E+005 1.749E+005

+ Pb-212 238.63* 43.60 4 .272E+004 4.27E+004 3.918E+004 2.004E+004

+ Bi-214 609.32* 45.49 2.576E+004 2.58E+004 6.303E+004 1.060E+004 1120.29 14.92 2.200E+OOS l.845E+OOS 1.002E+005 1764.49 15.30 1 .968E+005 1.425E+005 8.557E+004

+ Pb-214 295.22 18.42 1 .584E+005 4 .44E+004 2.558E+005 7.569E+004 351. 93* 35.60 4.444E+004 7.091E+004 2.017E+004 Ra-226 186.21 3.64 8.665E+005 8.67E+005 8.615E+OD4 4.195E+005 Ac-228 338.32 11. 27 2.609E+005 1.lSE+OOS 7.167E+004 1 .241E+005 911. 20 25.80 1.145E+OOS 9.883E+004 5 . 219E+004 968.97 15.80 1.937E+005 -4 .111E+004 8.829E+004 Am-241 59.54 35.90 l.483E+005 l .48E+OOS 3.402E+004 7.241E+004

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[240]

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

Filename: 6279 Report Generated On 6/5/2018 8:23:44 AM Sample Title Bl06201AFSWC039GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Samp le Type Gamma Direct Samp le Geometry 4M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.027E+001 MA2 Sample Taken On 6/5/2018 8:13: 00 AM Acquisition Started 6/5/2018 8:13: 43 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP lIN DATA VALIDATED DATE/tl*,*LY TIME./.3.£0 Q,n?'=+

[241]

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Detector Name: 6279 Sample

Title:

B106201AFSWC039GD Peak Analysis Performed on: 6/5/2018 8:23:43 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 286- 347 300.22 75.02 1. 38 l. 88E+002 166.44 7.58E+002 2 946- 963 954.13 238.65 0.73 -2.07E+OOO 31. 22 7.0lE+OOl 3 1399- 1417 1407.09 35 1 .97 1. 42 4.58E+001 24 .80 3.12E+001 4 2326- 2343 2334.30 583.86 0. 40 1.93E+001 13.85 8.71E+OOO 5 2429- 2446 2437.21 609.59 0.57 2.85E+001 18.51 1.65E+001 6 2637- 2655 2646.54 66 1 .93 0.66 3.71E+001 17 . 71 1.19E+001 7 3639- 3656 3647.30 912.06 0.99 1.48E+001 1 1 .81 5.18E+OOO 8 5838- 5857 5847.23 146 1 .52 1.15 7.00E+OOl 18.72 5.00E+OOO M - Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

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Sample

Title:

Bl06201AFSWC039GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10 .66 8.36235E+005 2.35082E+005 Cs-137 1 .000 661.66* 85 .10 3.50768E+004 l .72559E+004 Tl- 208 0 .999 583.19* 85.00 1.68901E+004 1 .22975E+004 Pb-212 1 .000 238.63* 43.60 -2.01480E+003 3.03336E+004 Bi-214 0.453 609.32* 45.49 4. 78940E+004 3.16288E+004 1120.29 14.92 1764.49 15. 30 Pb-214 0 .434 295.22 18.42 351.93* 35.60 6.93025E+004 3.89500E+004

~ Energy line found in the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 } Uncertainty K-40 0 .999 8.362349E+005 2.350817E+005 Cs-137 1 .000 3.507677E+004 1.725586E+004 Tl-208 0. 999 1 .689009E+004 1.229755E+004 Pb-212 1.000 -2.014800E+003 3.033358E+004 Bi-214 0.453 4.789400E+004 3.162881E+004 Pb-214 0.434 6.930245E+OD4 3.894997E+00 4

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

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

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

Peak Locate Performed on: 6/5/2018 8:23:43 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV} Counts per Second % Uncertainty Type Nuclide 1 75.02 3.1314E-001 88.59 7 912.06 2.4708E-002 79.65 Tol. Ac-228 M . First peak in a mult iplet region m = Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC039GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA 2 )

+ K-40 1460.82* 10 .66 1 .971E+005 1 .97E+OOS 8.362E+OOS 8.238E+004 Co - 60 1173.23 99.85 3.194E+004 2.81E+004 2.326E+004 1 .446E+004 1332.49 99.98 2.809E+004 -2.688E+003 1 .243E+004 Nb-94 702.65 99.81 2.795E+004 2.44E+004 1 . 191E+004 1 .285E+004 871.09 99.89 2.444E+004 2.936E+003 1.095E+004 Ag-108m 433.90 90.50 2.914E+004 2.91E+004 -1 .879E+004 1.365E+004 614.30 89.80 3.922E+004 2.160E+004 1.845E+004 722.90 90.80 3.023E+004 -l .594E+003 1.386E+004 Cs-134 604.72 97.62 3.745E+004 3.03E+004 5.195E+004 1.767E+004 795.86 85.46 3.032E+004 -8.894E+002 1. 374E+004

+ Cs-137 661.66* 85.10 2.253E+004 2.25E+004 3.508E+004 9.987E+003 Eu-152 121 .78 28.67 1. 248E+005 1.23E+005 -1.160E+005 6.085E+004 344.28 26.60 1 .233E+OOS -2.076E+005 5.896E+004 1408.01 21.07 1. 289E+OOS -6.927E+002 5.648E+004 Eu-154 123.07 40 .40 8.846E+004 8.85E+004 -6. 014E+004 4.313E+004 723.30 20.06 1 .369E+005 -4 .838E+004 6.274E+004 1274.43 34.80 9.15SE+004 2.094E+004 4.124E+004 Eu-155 86.55 30.70 1.567E+OOS 1 .57E+005 -5.759E+003 7.684E+004 105. 31 21. 10 1.777E+005 -1. 056E+005 8.676E+004

+ Tl-208 583.19* 85. 00 1.780E+004 1 .78E+004 1 .689E+004 7.713E+003 Bi-212 727.33 6.67 4.221E+OOS 4.22E+005 4.134E+OOS 1.939E+OOS

+ Pb-212 238.63* 43.60 5.274E+004 5.27E+004 -2.01SE+003 2.505E+004

+ Bi-214 609.32* 45 .49 4 .633E+004 4.63E+004 4.789E+004 2.089E+004 1 1 20 .29 14.92 2.256E+005 -4.730E+004 1 .030E+OOS 1764.49 15. 30 2.233E+005 5.675E+004 9.881E+004

+ Pb-214 295.22 18.42 1 .613E+005 5.59E+004 6.860E+004 7.714E+004 351.93* 35.60 S.585E+004 6.930E+004 2.588E+004 Ra-226 186. 2 1 3.64 8.298E+OOS 8.30E+005 -7.305E+004 4.0llE+OOS Ac-228 338.32 11. 27 2.561E+OOS 1.23E+OOS 9.642E+004 1. 217E+OOS 911. 2 0 25.80 1.229E+OOS 7.946E+004 S.638E+004 968.97 15.80 1.912E+005 2.151E+004 8.705E+004 Am-241 59.54 35.90 1.463E+005 1. 46E+OOS 4.265E+004 7.144E+004

+=Nuclide identified during the nuclide identification

Energy line found in the spectrum

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

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

[245]

- - - - GAMM A SPECTRUM A N A L Y S I S *****

Filename: 6279 Report Generated On 6/6/20 11:l 9: 34 : 26 AM Sample Title B106201AFSWC040GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.030E+001 M"2 Sample Taken On 6/6/2018 9:24: 00 AM Acquisition Started 6/6/2018 9:24:25 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration used Done On 6/2/2018 Efficiency ID 4M90D CP lIN DATA VALIDATED DATE/3*,-/f.

TIME~"'°"

Oaz;<<4'

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Detector Name: 6279 Sample

Title:

Bl06201AFSWC040GD Peak Analysis Performed on: 6/6/2018 9:34:26 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts M 1 293- 354 300.59 75.12 0.83 -3.25E+001 111.01 2.34E+002 m 2 293- 354 341.59 85.38 0.84 -2.16E+001 7 4 .23 l. 33E+002 3 437- 452 444.56 111 .15 0.31 2.23E+001 38.16 1. 13E+O 02 4 945- 963 954.03 238.63 0.79 4.48E+001 28.81 4.62E+001 5 1397- 1414 1405.94 351.68 0.26 3.05E+001 20.37 2.25E+001 6 2322- 2339 2330.46 582.90 0.84 2.50E+001 16.39 l. 30E+001 7 2427- 2444 2435.33 609.12 0.52 4.22E+001 18.22 1. 18E+001 8 2636- 2653 2644.80 661.49 0.52 1.35E+001 15.15 l.35E+001 9 3635- 3652 3643.49 911.11 0.28 2.lOE+OOl 10 .48 2.04E+OOO 10 5833- 5852 5842.46 1460.33 1.48 7.00E+OOl 16 .73 O.OOE+OOO 11 7049- 7068 7058.70 1763.87 0.38 1.20E+001 6.93 O.OOE+OOO M : First peak in a multiplet region m Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 , 000 sigma

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Sample

Title:

B106201AFSWC040GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

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

I

I I ~ IDENTIFIED NUCLIDES . . .. ......... .... ... .

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 1.000 1460.82* 10. 66 8.35259E+005 2. 12 431E+005 Cs-137 1.000 661.66* 85.10 l .2745SE+004 1.43865E+004 Eu-155 0.977 86.55* 30.70 -2.42983E+004 8.34936E+004 105 .31* 21.10 3.47266E+004 5.98467E+004 Tl- 208 1. 000 583.19* 85.00 2.18938E+004 1. 4566SE+004 Pb-212 1. 000 238.63* 43.60 4.35099E+004 2.88433E+004 Bi-214 0.710 609.32* 45.49 7.08547E+004 3 .17507E+004 1120.29 14.92 1764.49* 15.30 l .13870E+OOS 6.63725E+004 Pb-214 0. 434 295.22 18.42 351.93* 35.60 4 .61267E+004 3.1575SE+004

= Energy line found in the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 8.352590E+005 2.124307E+OOS Cs-137 1. 000 1 .274545E+004 1.438650E+00 4 Eu-155 0 .977 3.472656E+004 5.984668E+00 4 Tl-208 1. 000 2.189382E+004 1. 4 5664 7E+O 0 4 Pb-212 1. 000 4.350986E+004 2.884331E+004 Bi-214 0 . 710 7.886518E+004 2.864215E+00 4 Pb-214 0 .434 4.612670E+004 3.157546E+004

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

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

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Peak Locate Performed on: 6/6/2018 9:34:26 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide M 1 75.12 -5.4084E-002 -342. 10 9 911.11 3.4928E-002 50. 01 Tol. Ac-228 M e First peak in a mult iplet region m = Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2 . 000 s igma

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Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B1062D1AFSWC040GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 3.229E+004 3.23E+004 8.353E+005 O.OOOE+OOO Co-60 1173.23 99.85 3.329E+004 2.33E+004 1.714E+003 1.513E+004 1332.49 99.98 2.326E+004 -1.104E+004 1 .002E+004 Nb-94 702.65 99.81 3.017E+004 2.84E+004 2.600E+004 1 .396E+004 871.09 99.89 2.843E+004 2.754E+003 1. 294E+004 Ag - 10 8rn 433.90 90.50 2.967E+004 2.97E+004 1.21DE+004 1. 391E+004 614.30 89.80 3.855E+004 1.902E+004 1.812E+004 722.90 90.80 3.121E+004 -4. 114E+004 1.435E+004 Cs-134 604.72 97.62 3.724E+004 3.58E+004 6.656E+004 l.757E+004 795.86 85.46 3.576E+004 4.697E+003 1.647E+004

+ Cs-137 661.66* 85. 1 0 2.313E+004 2.31E+004 1. 275E+004 1.029E+004 Eu-152 121. 7 8 28.67 1.240E+005 1. 13E+005 1. 426E+005 6.046E+004 344.28 26.60 1.125E+005 2.402E+004 5.356E+004 1408. 01 21.07 1.184E+005 -3.552E+004 5.122E+004 Eu-154 123.07 40.40 8.766E+004 8.38E+004 -9.456E+003 4.273E+004 723.30 20.06 1.457E+005 1.863E+004 6.713E+004 1274.43 34.80 8.378E+004 -3.334E+004 3.736E+004

+ Eu-155 86.55* 30.70 6.338E+004 6.34E+004 -2.430E+004 3.017E+004 105.31* 21.10 9.892E+004 3.473E+004 4.735E+004

+ Tl-208 583.19* 85.00 2.103E+004 2.10E+004 2.189E+004 9.330E+003 Bi-212 727.33 6.67 4.218E+005 4.22E+005 1. 493E+005 l.937E+005

+ Pb-212 238.63* 43.60 4.337E+004 4.34E+004 4.351E+004 2.037E+004

+ Bi-214 609.32* 45.49 3.982E+004 2.57E+004 7.085E+004 1.764E+004 1120.29 14.92 2.363E+005 2.982E+005 1.083E+OOS 1764.49* 15.30 2.568E+004 1.139E+005 O.OOOE+OOO

+ Pb-214 295.22 18.42 1 .632E+005 4.67E+004 2.072E+005 7.804E+004 351.93* 35.60 4.668E+004 4.613E+004 2.129E+004 Ra-226 186.21 3.64 8.634E+005 8.63E+005 -2.346E+005 4.179E+005 Ac-228 338.32 11. 27 2.136E+OOS 1.20E+005 -1. 099E+005 1.005E+005 911.20 25.80 1.201E+005 7.194E+004 5.498E+004 968.97 15.80 1.861E+005 3.592E+003 8.448E+004 Arn-241 59.54 35.90 1.533E+005 l .53E+OOS -1.280E+005 7.493E+004

+ =Nuclide identified during the nuclide identification

- Energy line found in the spectrum

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

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

[251]

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

Filename: 6279 Report Generated On 6/6/20 1 9 9: 51 :12 AM Sample Title B106201AFSWC041GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size Sample Taken On 6/6/2018 9: 41 : 00 AM Acquisition Started 6/6/2018 9: 41 : 11 AM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP 1IN DATA VALIDATED DATE41 .. , ../?

Tl~~!4-":..

~ ~ ~ , . c . , . _ .-

[252]

Peak Analysis Report 6/6/2018 9 :51 :13 AM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSWC041GD Peak Analysis Performed on: 6/6/2018 9:51:12 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 285- 347 297.92 74.45 0.80 5.31E+001 173.94 8.39E+002 2 945- 962 953.09 238.39 1. 27 1. 43E+001 27.32 5.07E+001 3 1172- 1189 1180 .67 295.33 0.57 6.83E+OOO 2 1. 48 3.32E+001 4 1398- 1415 1406.51 351.83 0.45 3.48E+OOO 23.87 4.25E+001 5 2031- 2048 2039.74 51 0 .20 0.39 2.29E+001 16.20 1. 31E+001 6 2324- 2341 2332.26 583.35 0.32 1.55E+001 1 0 .98 4.SOE+OOO 7 2427- 2444 2435.78 609.23 0.38 4.05E+001 1 4 .85 4.50E+OOO 8 5833- 5852 5842.17 1460.26 1. 33 7.60E+001 17.44 O.OOE+OOO M -=- First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[253]

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Sample

Title:

B106201AFSWC041GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"'2 ) Uncertainty K-40 0 .999 1460.82* 10 .66 9.06821E+005 2.22443E+005 Tl- 208 1 .000 583.19* 85. 00 1.35592E+004 9.74055E+003 Pb-212 1 .000 238.63* 43.60 1.38328E+004 2.66086E+004 Bi-214 0.453 609.32* 45.49 6.79947E+004 2.62373E+004 1120.29 14.92 1764.49 15. 30 Pb-214 1.000 295.22* 18.42 1. 78449E+004 5.61882E+004 351.93* 35.60 5.26175E+003 3.61178E+004

= Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0 .999 9. 06 8207E+OOS 2.224431E+OOS Tl-208 1 . 000 l.355921E+004 9.740550E+003 Pb-212 1 . 000 1.383277E+004 2.660858E+00 4 Bi-214 0 .453 6.799466E+004 2.623734E+00 4 Pb-214 1 .000 8.940840E+003 3.038229E+00 4

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

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

- - - - U N I D E N T I F I E D P E AK S **********

Peak Locate Performed on: 6/6/2018 9:5 1 :12 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak To l.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 74.45 8.8571E-002 327.30 5 510.20 3.8125E-002 70.83 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[255]

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Detector Name: 6279 Sample Geometry: 4M90D CP lIN Sample

Title:

B106201AFSWC041GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) (%) (pCi/M"2 ) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/M"'2 )

+ K-40 1460.82* 10 .66 3.229E+004 3.23E+004 9.068E+005 O.OOOE+OOO Co-60 1173.23 99.85 3.049E+004 2.74E+004 7.909E+003 1.373E+004 1332.49 99.98 2.745E+004 9.725E+003 1.211E+004 Nb-94 702.65 99.81 2.380E+004 2.38E+004 -1.847E+004 1.078E+004 871.09 99.89 2.651E+004 8.700E+003 l .198E+004 Ag-108m 433.90 90.50 2.558E+004 2.56E+004 -4.260E+004 l .187E+004 614.30 89.80 3.721E+004 4.851E+004 1.74SE+004 722.90 90.80 3.310E+004 -l.795E+004 l.529E+004 Cs-134 604.72 97.62 3.512E+004 3.50E+004 3.958E+004 1.651E+004 795.86 85.46 3.504E+004 -1. 905E+004 1.611E+004 Cs-137 661.66 85.10 3.136E+004 3. 14E+004 l.955E+004 1.440E+004 Eu-152 121.78 28.67 1.303E+005 9.34E+004 3.689E+004 6.360E+004 344.28 26.60 1.176E+005 8.213E+004 5.612E+004 1408.01 21.0 7 9.337E+004 -2.740E+004 3.872E+004 Eu-154 123.07 40 .40 9.045E+004 8.05E+004 -4 .712E+004 4.413E+004 723.30 20.06 1 .513E+OOS -2.414E+004 6.993E+004 1274.43 34.80 8.045E+004 - 2.511E+003 3.570E+004 Eu-155 86.55 30.70 1.529E+005 1 .53E+005 -2.938E+004 7.496E+004 105.31 21.10 1.853E+005 -1. 377E+005 9.057E+004

+ Tl-208 583.19* 85.00 1.337E+004 l.34E+004 1.356E+004 5.504E+003 Bi-212 727.33 6.67 4 .351E+005 4.35E+005 6.792E+004 2.004E+005

+ Pb-212 238.63* 43.60 4.454E+004 4.45E+004 1. 383E+004 2.096E+004

+ Bi-214 609.32* 45.49 2.567E+004 2.57E+004 6.799E+004 1. 056E+004 1120.29 14 .92 2. 111E+005 1 .696E+005 9.571E+004 1764.49 15.30 1.967E+005 4.160E+004 8.552E+004

+ Pb-214 295.22* 18.42 9.660E+004 6.28E+004 l.784E+004 4.477E+004 351.93* 35.60 6.276E+004 5.262E+003 2.933E+004 Ra-226 186.21 3.64 7.730E+005 7.73E+005 -5.929E+005 3.728E+OOS Ac-228 338.32 11. 27 2.559E+005 l.33E+005 -3.447E+005 1. 217E+005 911. 20 25.80 l.331E+005 l.498E+005 6.147E+004 968.97 15.80 1.835E+OOS 1. 3 58E+OOS 8.319E+004 Am-241 59.54 35.90 1.500E+OOS l. SOE+OOS 2.199E+004 7.327E+004

+= Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[256]

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

Filename: 6279 Report Generated On 6 / 6/20 l 8 10:19:13 AM Sample Title B106201AFSWC042GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.030E+001 MA2 Sample Taken On 6/6/2018 10:09:00 AM Acquisition Started 6/6/2018 10:09:12 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP lIN DATA VALIDATED DATE/2-~*IF TIME J,lia

~4

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Detector Name: 6279 Sample

Title:

Bl06201AFSWC042GD Peak Analysis Performed on: 6/6/2018 10: 19:13 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts 1 293- 348 300.66 75.13 0.48 -8.91E+OOO 166.50 8.68E+002 2 944- 961 952.68 238.29 0.54 8.57E+OOO 30.14 6.14E+001 3 1171- 1188 1179.94 295.15 0.33 1.44E+001 23.42 3.76E+001 4 1398- 1415 1406.86 351.92 1.45 4 .12E+001 19.25 1.58E+001 5 2033- 2050 2041.75 510.71 0.29 1 .38E+001 17.99 2.02E+001 6 2322- 2339 2330.14 582.82 0.56 1 .84E+001 15.24 1.16E+001 7 2426- 2443 2434.52 608.92 0.35 2.97E+001 16.49 1 .13E+001 8 4468- 4487 4477.94 1119 .59 0.25 l.15E+001 9.07 2.46E+OOO 9 5832- 5852 5842.22 146 0 .27 2.03 7.40E+001 17.20 O.OOE+OOO M = Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Sample

Title:

B106201AFSWC042GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

' ...... ..... ... .. . ... IDENTIFIED NUCLIDES ..... . . . . . . . . . ' .., * * * 'ti *

Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1 .000 1460.82* 10 .66 8.82963E+005 2.19136E+005 Tl- 208 1 .000 583.19* 85.00 1.60507E+004 1 .34669E+004 Pb- 212 1 . 000 238.63* 43.60 8.31611E+003 2.92779E+004 Bi-214 0 .743 609.32* 45.49 4.97773E+004 2.83184E+004 1120.29* 14.92 8.38637E+004 6.62544E+004 1764.49 15.30 Pb-214 1. 000 295.22* 18.42 3.76377E+004 6.14408E+004 351.93* 35.60 6.23779E+004 3.05843E+004

= Energy line found in t he spectrum.

@ = Energy line not used f or Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 .30 Errors quoted at 2 .000 sigma

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1.000 8.829632E+005 2.191360E+OOS Tl-208 1.000 1.605066E+004 1 .346693E+004 Pb-212 1.000 8.316111E+003 2.927785E+004 Bi-214 0.743 S.504255E+004 2.603959E+004 Pb-214 1.000 5.746493E+004 2.737964E+004

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

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

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

Peak Locate Performed on: 6/6/2018 10:19:13 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second % Uncertainty Type Nuclide 1 75.13 -1. 4854E-002 -1868.1 5 510. 71 2.2990E-002 13 0. 39 M ~

First peak in a mult iplet region m == Other peak in a mult iplet region F :;; Fitted singlet Errors quoted at 2 . 000 sigma

[260]

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Detector Name: 6279 Sample Geometry : 4M90D CP 1IN Sample

Title:

B106201AFSWC042GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10 .66 3.229E+004 3.23E+004 8.830E+005 O.OOOE+OOO Co-60 1173 .23 99.85 3.145E+004 2.40E+004 -7.112E+003 l.422E+004 1332.49 99.98 2.402E+004 1.672E+004 l .039E+004 Nb-94 702.65 99.81 2.643E+004 2.64E+004 -2.960E+003 l .209E+004 871 .09 99.89 2.880E+004 2.580E+004 1 .313E+D04 Ag-108m 433.90 90.50 2.875E+004 2.88E+004 2.215E+004 1.346E+004 614.30 89.80 3.676E+004 -1 .967E+004 1 .722E+004 722.90 90.80 3.021E+004 -1 .029E+004 1 .385E+004 Cs-134 604.72 97.62 3.551E+004 3.24E+004 4.345E+004 1 .670E+004 795.86 85.46 3.237E+004 1 .696E+004 l .477E+004 Cs-137 661.66 85.10 3.798E+004 3.80E+004 2.219E+004 l.771E+004 Eu - 152 121. 78 28.67 1 .241E+005 1. 12E+005 -5.405E+004 6.052E+004 344.28 26.60 1 .121E+005 2.632E+004 5.336E+004 1408. 01 21.07 1 .353E+005 1 .118E+OOS 5.967E+004 Eu-154 123.07 40 .40 8.874E+004 8.54E+OD4 1 .859E+004 4.327E+004 723.30 20.06 1 .398E+005 6.314E+OD3 6.421E+004 1274.43 34.80 8.538E+004 -2.860E+003 3.816E+004 Eu-155 86.55 30.70 1 .571E+005 1. 57E+005 3.362E+004 7.705E+004 105.31 21. 10 1 .898E+005 2.434E+005 9.279E+004

+ Tl-208 583.19* 85.00 2.050E+004 2.0SE+004 1 .605E+004 9.066E+003 Bi-212 727.33 6.67 4.395E+005 4.39E+005 2.410E+005 2.025E+005

+ Pb-212 238.63* 43.60 4.982E+004 4.98E+004 8.316E+003 2.360E+004

+ Bi-214 609.32* 45.49 3.873E+004 3.87E+004 4.978E+004 l.709E+004 1120.29* 14.92 9.149E+004 8.386E+004 3.591E+004 1764.49 15.30 1 .909E+005 1 .329E+OOS 8.262E+004

+ Pb-214 295.22* 18.42 1 .022E+005 3.98E+004 3.764E+004 4.757E+004 351.93* 35.60 3.978E+004 6.23BE+004 1 .785E+004 Ra-226 186. 21 3. 64 8.526E+005 8.53E+005 -2.585E+005 4.126E+005 Ac-228 338.32 11. 27 2.410E+005 1.21E+005 5.359E+004 l.142E+005 911. 20 25 . 80 J . 214E+005 1 .112E+005 5.567E+004 968.97 15.80 2.100E+005 3.161E+003 9.643E+004 Am-241 59.54 35.90 1 .646E+005 1.65E+005 1.330E+005 8.057E+004

+=Nuclide identified during the nuclide identification

~ Energy line found in the spectrum

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

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

[261]

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

Filename: 62 79 Report Generated On 6/5/2018 2:46 : 32 PM Sample Title B106201AFSWC043GD Sample Description Ul Diesel Fuel Oil Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 4M90D CP lIN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 5.027E+001 MA2 Samp le Taken On 6/5/2018 2:36: 00 PM Acquisition Started 6/5/20 1 8 2:36:30 PM Live Time 600 . 0 seconds Real Time 600.4 seconds Dead Time 0 . 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 4M90D CP 1IN DATA-VALIDATED DATE/a .. 6-Lf

{i)d;; ,.

TIME/~

[262]

Peak Analysis Report 6/5/2018 2:46:32 PM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSWC043GD Peak Analysis Performed on: 6/5/2018 2:46:31 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No . start end centroid (keV) (keV) Area Uncert. Counts M 1 284- 347 299.79 74.92 1. 21 1. 13E+002 33. 15 2.25E+002 m 2 284- 347 339.85 84.94 1. 22 3.02E+001 25.75 2.28E+002 3 653- 669 660.40 165.16 0.78 3.90E+001 29.34 5.60E+001 4 946- 963 954 .10 238.65 0.40 2.88E+001 28.97 5.42E+001 5 1172- 1189 1180 .51 295.29 0.87 2.62E+001 2 1 .40 2.68E+001 6 1400- 1417 1408.49 352.32 0.85 2.16E+001 22 . 28 3.14E+001 7 2429- 2446 2437.28 609.61 0.63 2.8SE+001 18.01 1.45E+001 8 2637- 2654 2645.79 661.74 0.73 3.08E+001 16.50 1.12E+001 9 3636- 3653 3644.82 911. 44 0.44 1. 53E+001 12.57 6.75E+OOO 10 5838- 5857 5847.06 1461. 48 1 .15 7.80E+001 17.66 O.OOE+OOO M ; First peak in a multiplet region m = Other peak in a multiplet region F Fitted singlet Errors quoted at 2.000 sigma

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Sample

Title:

B106201AFSWC043GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

. . .. . . .. . .. . . . . .. ........ IDENTIFIED NUCLIDES * *** ********* - ~*~** -

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/MA2 ) Uncertainty K-40 0 .999 1460 .82* 10.66 9.31786E+005 2.25989E+005 Cs-137 1.000 661.66* 85.10 2.91394E+004 1.59815E+004 Eu-155 0 .337 86.55* 30.70 3.39800E+004 2.97648E+004 105.31 21.10 Pb-212 1 . 000 238.63* 43.60 2.79907E+004 2.85096E+004 Bi-214 0 .453 6 0 9.32* 45.49 4.78166E+004 3.08045E+004 1120.29 14.92 1764.49 15.30 Pb -214 1 . 000 295.22* 18. 42 6.84960E+004 5.69913E+004 351.93* 35.60 3.26590E+004 3.41022E+004

: Energy line found in the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.999 9.317858E+005 2.259893E+005 Cs-137 1. 000 2.913936E+004 l.598151E+004 Eu-155 0.337 3.398004E+004 2.976484E+004 Pb-212 1. 000 2.799069E+004 2.850961E+004 Bi-214 0. 453 4.781665E+004 3.080453E+004 Pb-214 1. 000 4.210747E+004 2.926332E+004

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

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

[265]

Interference Corrected Activity Report 6/5/2018 2:46:32 PM Page 5

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Peak Locate Performed on: 6/5/2018 2:46: 31 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second % Uncertainty Type Nuclide M 1 74.92 1 .8765E-001 29 .44 3 165.16 6.5026E-002 75.19 Sum 9 911.44 2.5417E-002 82 .41 Sum M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 , 000 sigma

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Nuclide MDA Report 6/5/2018 2:46:32 PM Page 6

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Detector Name: 6279 Sample Geometry: 4M90D CP 1IN Sample

Title:

B106201AFSWC043GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yie ld Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/M"2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10 .66 3.233E+004 3.23E+004 9.318E+005 O.OOOE+OOO Co-60 1173.23 99.85 3.331E+004 2.08E+004 3.795E+004 1.514E+004 1332.49 99.98 2.081E+004 -5.245E+004 8.789E+003 Nb-94 702.65 99.81 3.124E+004 3.12E+004 5.460E+003 1.449E+004 871.09 99.89 3.126E+004 -4.636E+004 l.436E+004 Ag-108m 433.90 90.50 2.933E+004 2.88E+004 1.453E+004 1.374E+004 614.30 89.80 3.879E+004 4.052E+004 1.824E+004 722.90 90.80 2.884E+004 -1.911E+003 l.316E+004 Cs-134 604.72 97.62 3.573E+004 3.47E+004 1.682E+004 1.681E+004 795.86 85.46 3.469E+004 l.258E+004 1.593E+004

+ Cs-137 661.66* 85. 10 2.153E+004 2.15E+004 2.914E+004 9.487E+003 Eu-152 121.78 28.67 1.372E+005 1. 13E+005 -1.103E+005 6.706E+004 344.28 26.60 1.134E+005 -2.053E+004 5.399E+004 1408.01 21.07 l.385E+005 5.505E+004 6.126E+004 Eu-154 123.07 40. 40 9.698E+004 9.44E+004 6.014E+003 4 .739E+004 723.30 20.06 1.322E+005 2.278E+004 6.040E+004 1274.43 34.80 9.445E+004 1. 005E+OOS 4.269E+004

+ Eu-155 86.55* 30.70 8.202E+004 8.20E+004 3.398E+004 3.949E+004 105.31 21.10 1. 997E+005 -1.443E+005 9.775E+004 Tl-208 583.19 85.00 3.570E+004 3.57E+004 -1.216E+004 1 .666E+004 Bi-212 727.33 6.67 4.176E+005 4.18E+005 6.354E+003 1 .916E+005

+ Pb-212 238.63* 43.60 4.564E+004 4.56E+004 2.799E+004 2.150E+004

+ Bi-214 609.32* 45.49 4.465E+004 4.47E+004 4.782E+004 2.005E+004 1120.29 14.92 2.051E+005 2.183E+OOS 9.272E+004 1764.49 15. 30 1 .968E+005 1.42SE+005 8.557E+004

+ Pb-214 295.22* 18.42 8.786E+004 5.46E+004 6.850E+004 4.039E+004 351.93* 35.60 5.457E+004 3.266E+004 2.523E+004 Ra-226 186.21 3.64 8.408E+005 8.41E+005 -6.SOSE+004 4.067E+005 Ac-228 338.32 11. 27 2.522E+005 1 .31E+OOS 5.430E+004 1 .198E+005 911.20 25.80 1.307E+005 1.795E+OOS 6.027E+004 968.97 15.80 2.032E+005 -1.581E+004 9.307E+004 Am-241 59.54 35.90 1.692E+005 l .69E+OOS 1.077E+OOS 8.288E+004

+ =Nuclide identified during the nuclide identification

Energy line found in the spectrum

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

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

[267]

- - - - GAMM A SPECTRUM A N A L Y S I S *****

Filename: 6279 Report Generated On 6/11/20 18 1:26: 18 PM Samp le Title B106201AFSWC044GD Sample Description Ul Diesel Fuel Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 1.5M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/11/201 8 l: 1.6: 00 PM Acquisition Started 6/11/2016 1.: 16 :16 PM Live Time 600.0 seconds Real Time 601.0 seconds Dead Time 0.16 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/4/2018 Efficiency ID 1.5M90D CP 1IN DATAVAUDAlED DATE/ta7. Gi -If TIME/,;so G4r£):.i

[268]

Peak Analysis Report 6/11/2018 1:26 : 18 PM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSWC044GD Peak Analysis Performed on: 6/11/2018 1:26: 18 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 295- 306 300.87 75.34 0.88 3.31E+001 54.94 2.86E+002 2 951- 962 955.71 239.04 1. 00 2.84E+001 26.17 5.66E+001 3 2432- 2444 2437.68 609.52 0.76 2.59E+001 16. 40 l .51E+001 4 2642- 2656 2648.19 662.14 0.30 3.51E+001 16.73 1 .19E+001 5 5840- 5857 5847.98 1462. 04 0.69 8.31E+001 20 .12 5.87E+OOO M == Fi rst peak in a multiplet region m = Other peak in a multiplet region F == Fitted singlet Errors quoted at 2.000 sigma

[269]

Interference Corrected Activity Report 6/11/2018 1:26:18 PM Page 3

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Sample

Title:

B106201AFSWC044GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 0.998 1460.82* 10.66 9.80764E+005 2.52215E+005 Cs-137 1.000 661.66* 85.10 3.24217E+004 1.59239E+004 Pb-212 1. 000 238.63* 43.60 2.66883E+004 2.49309E+004 Bi-214 0.455 609.32* 45.49 4.25218E+004 2.73687E+004 1120.29 14.92 1764.49 15.30

=Energy line found i n the spectrum.

@ - Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold= 0 .30 Errors quoted at 2. 000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0.998 9.807643E+005 2.522155E+005 Cs-137 1. 000 3.242169E+004 1.592395E+004 Pb-212 1. 000 2.668834E+004 2.493087E+004 Bi-214 0 .455 4.252177E+004 2.736869E+004

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

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

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

Peak Locate Performed on: 6/11/2018 1:26:18 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.34 5.5225E-002 165 .81 M = First peak in a multiplet region m = Other peak in a multiplet region F : Fitted singlet Errors quoted at 2 . 000 sigma

[271]

Nuclide MDA Report 6/11/2018 1:26:18 PM Page 5

- - - - NUCLIDE MD A REPORT *****

Detector Name: 6279 Sample Geometry: 1.5M90D CP 1IN Sample

Title:

B106201AFSWC044GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL . NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/M"'2 ) (pCi/M"'2 )

+ K-40 1460.82* 10.66 1 .970E+005 l.97E+OD5 9.808E+005 8.255E+004 Co-60 1173.23 99.85 3.237E+004 2.22E+004 l .122E+004 1. 470E+004 1332.49 99.98 2.220E+004 -4.030E+003 9.505E+003 Nb-94 702.65 99.81 2.150E+004 1.91E+004 -3.980E+003 9.647E+003 871. 09 99.89 l .912E+004 7.258E+003 8.313E+003 Ag-108m 433.90 90.50 2.339E+004 2.34E+D04 4.202E+003 l .080E+004 614. 3 0 89.80 3.332E+004 1 .260E+004 l .553E+004 722.90 90.80 2.444E+004 6.785E+003 l .099E+D04 Cs-134 604.72 97.62 3.228E+004 2.93E+OD4 -1.890E+004 l .511E+004 795.86 85. 4 6 2.925E+004 -3.646E+OD4 1 .324E+004

+ Cs-137 661. 66* 85.10 2.042E+004 2.04E+004 3.242E+004 8.963E+D03 Eu-152 121. 78 28.67 9.172E+004 8.83E+004 -5.168E+004 4.438E+D04 344.28 26.60 8.828E+004 -1.208E+OOS 4.152E+004 1408.01 21.07 1.132E+005 1.990E+004 4.876E+D04 Eu-154 123.07 40. 4 0 6.591E+004 6.44E+004 3.544E+004 3.191E+004 723.30 20.06 1. 125E+O 05 6.072E+004 5.067E+004 1274.43 34.80 6 .439E+004 1.92DE+004 2.772E+D04 Eu-155 86.55 30.70 1. 166E+O 05 l .17E+005 1.029E+005 5.685E+004 105.31 21.10 1. 399E+005 8.604E+004 6.793E+004 Tl-208 583.19 85.00 3.011E+004 3.01E+004 1.60SE+004 l .390E+004 Bi-212 727.33 6.67 3.502E+005 3.50E+005 3.457E+004 1 .583E+005

+ Pb-212 238.63* 43.60 3.942E+004 3.94E+004 2.669E+004 l .844E+D04

+ Bi-214 609.32* 45.49 3.910E+004 3.91E+004 4.252E+004 1 .733E+D04 1120.29 14.92 2.079E+005 6.643E+004 9.428E+D04 1764.49 15. 30 1. 829E+005 1.220E+005 7.873E+004 Pb-214 295.22 18.42 1. 307E+005 7.29E+OD4 1.374E+005 6.195E+D04 351. 93 35.60 7.294E+004 5.302E+004 3.448E+D04 Ra-226 186.21 3.64 6.381E+005 6.38E+OOS -5.356E+005 3.058E+D05 Ac-228 338.32 11. 27 2.13BE+005 1.21E+005 1.208E+004 1 .0D8E+005 911. 2 0 25.80 1.205E+005 1.987E+004 5.531E+D04 968.97 15.80 1.613E+005 1.167E+005 7.226E+004 Am-241 59.54 35.90 1.051E+005 1.05E+OD5 -2.96BE+004 5.095E+004

+ =Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[272]

- - - - GAMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 6/11/2018 2:08:50 PM Sample Title B106201AFSWC045GD Sample Description Ul Diesel Fuel Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 1. SM90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) : 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/11/2018 1 :58::00 PM Acquisition Started 6/11/2018 1 :58:48 PM Live Time 600.0 seconds Real Time 600.9 seconds Dead Time 0 . 15 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/4/2018 Efficiency ID 1.SM90D CP lIN DATA VAUDAlED DATEJo? ... ~ *If wa(;r,.

TIME~

4

[273]

Peak Analysis Report 6/11/2018 2:08:50 PM Page 2

- - - - P E A K ANALYSIS R E P O R T *****

Detector Name: 6279 Sample

Title:

B106201AFSWC045GD Peak Analysis Performed on: 6/11/2018 2:08:50 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 281- 305 300.48 75.25 0.65 1.72E+002 87.82 4.26E+002 2 2429- 2444 2436.54 609.23 1. 04 4.37E+001 16.69 8.30E+OOO 3 2639- 2655 2646. 41 661.70 0.78 8.82E+001 27.91 3.28E+001 4 4687- 4700 4693.51 1173.44 0.28 1. 99E+001 1 1 .63 5.06E+OOO 5 5835- 5853 5844.26 1461.12 0.29 9.20E+001 19.18 O.OOE+OOO M First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[274]

Interference Corrected Activity Report 6/11/2018 2:08:50 PM Page 3

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Sample

Title:

B106201AFSWC045GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Ac tivity Name Confidence {keV) ( %) (pCi/M"'2 ) Uncertainty K-40 1.000 1460.82* 10. 66 1. 08497E+006 2.45066E+OOS Cs-137 1.000 661.66* 85.10 8.13376E+004 2.75298E+004 Bi-214 0.455 609.32* 45.49 7.16194E+004 2.86820E+004 1120.29 14. 92 1764.49 15.30

~ Energy line found in the spectrum.

@ - Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 .30 Errors quoted at 2. 000 sigma

[275]

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 1 .084972E+006 2.450663E+005 Cs-137 1. 000 8.133762E+004 2.752982E+004 Bi-214 0.455 7.161941E+004 2.868197E+004

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

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

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

Peak Locate Performed on: 6/11/2018 2:08:49 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % uncertainty Type Nuclide 1 75.25 2.8638E-001 51.11 4 1173.44 3.3233E-002 58. 31 M = First peak in a multip let region m = Other peak in a multip let region F - Fitted singlet Errors quoted at 2.000 sigma

[276]

Nuclide MDA Report 6/11/2018 2:08:50 PM Page 5

- - - - N U C L I D E MD A REPORT *****

Detector Name: 6279 Sample Geometry: l.5M90D CP 1IN Sample

Title:

B106201AFSWC045GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10 .66 3.191E+004 3.19E+004 1 .085E+006 O.OOOE+OOO Co-60 1173 .23 99.85 3.692E+004 3.69E+004 2.389E+004 1.697E+004 1332.49 99.98 3.959E+004 1 .465E+004 1.820E+004 Nb-94 702.65 99.81 2.112E+004 2.11E+004 -7.336E+003 9.460E+003 871.09 99.89 2.640E+004 3.229E+003 1 .19SE+004 Ag-108m 433.90 90.50 2.939E+004 2.36E+004 1 .194E+003 1 .380E+004 614.30 89.80 3.720E+004 -5.841E+003 1 .747E+004 722.90 90.80 2.361E+004 4.473E+003 1 .0SBE+004 Cs-134 604.72 97.62 3.289E+004 2.70E+004 -1.192E+004 1 .542E+004 795.86 85.46 2.702E+004 -1.140E+003 l .213E+004

+ Cs-137 661.66* 85. 10 3.381E+004 3.38E+004 8.134E+004 l .566E+004 Eu-152 121. 78 28.67 9.995E+004 9.49E+004 -5.956E+004 4.849E+004 344.28 26.60 9.486E+004 -8.487E+003 4.481E+004 1408.01 21.07 9.687E+004 -1. 776E+003 4.057E+004 Eu-154 123.07 40 .40 7.074E+004 6.65E+004 -7.816E+004 3.432E+004 723.30 20.06 1 .0SOE+OOS -3.688E+003 4.692E+004 1274.43 34.80 6.649E+004 4.627E+004 2.877E+004 Eu-155 86.55 30.70 1.229E+005 1.23E+005 7.547E+004 5.999E+004 105.31 21.10 1.562E+OOS 6.893E+004 7.607E+004 Tl-208 583.19 85.00 3.255E+004 3.26E+004 1.197E+004 l.512E+004 Bi-212 727.33 6.67 2.719E+005 2.72E+OOS -2.062E+005 1.191E+OOS Pb-212 238.63 43.60 6.234E+004 6.23E+004 6.147E+004 2.990E+004

+ Bi-214 609.32* 45.49 3.191E+004 3.19E+004 7.162E+004 1.374E+004 1120.29 14.92 2.166E+005 7.450E+004 9.860E+004 1764.49 15.30 1.564E+D05 -5.997E+003 6.551E+004 Pb-214 295.22 18.42 1.388E+005 7.33E+004 1. 366E+OOS 6.600E+004 351. 93 35.60 7.328E+004 4.327E+004 3.465E+004 Ra-226 186.21 3.64 6.931E+005 6.93E+005 -9.022E+003 3.333E+OOS Ac-228 338.32 11.27 2.336E+OOS 1 .18E+OOS 1. 810E+005 1. 107E+OOS 911.20 25.80 1.179E+005 1. 440E+004 5.398E+004 968.97 15.80 1.950E+OOS 1. 982E+004 8.909E+004 Am-241 59.54 35.90 1.158E+OOS 1 .16E+OOS 4.257E+004 5.625E+004

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[277]

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

Filename: 6279 Report Generated On 6/11/2018 1:40:35 PM Sample Title Bl06201AFSWC046GD Sample Description Ul Diesel Fuel Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry l.5M90D CP 1IN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range {in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/11/2018 1 :30:00 PM Acquisition Started 6/11/2018 1 :30:33 PM Live T ime 600.0 seconds Real Time 600.9 seconds Dead Time 0 . 14 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/4/2018 Efficiency ID 1. 5M90D CP lIN DATA VALIDATED DATEL;?-' *L?

+

TIMEas~

a"'""t?

[278]

,Peak Analysis Report 6/11/2018 1: 40 : 35 PM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSWC046GD Peak Analysis Performed on: 6/11/2018 1: 40: 35 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 285- 305 300.51 75.25 0.92 1.57E+002 75.73 3. 51E+002 2 949- 959 953.65 238.53 0.52 3.43E+001 2 1. 90 3. 58E+001 3 1402- 1414 1407 .82 352.07 0.57 2.30E+001 19.26 2. 60E+001 4 2326- 2337 2331.93 583.08 0.55 2.06E+001 9.83 1 . 42E+OOO 5 2431- 2443 2436.06 609.11 0.29 2.25E+001 14.63 1 . 15E+001 6 2641 - 2652 2646.54 661.73 0.50 3.40E+001 16. 01 1 . 20E+001 7 5836- 5855 5845.08 1 461.32 0.96 8.28E+001 20.76 7. 25E+OOO M = Fi rst peak in a multiplet region m ~ Other peak in a multiplet region F t.: Fitted singlet Errors quoted at 2 . 000 sigma

[279]

Interf erence Corrected Activity Report 6/11/2018 1 :40: 35 PM Page 3

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

Sample

Title:

Bl06201AFSWC046GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB I * * * * * * * * * * * *

I '"'" *

I '"'

IDENT IFIED NUCLIDES * * " * *

o, * * * * * 'I> *

M .. * * ..

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) uncertainty K-40 1. 000 1460.82* 10. 66 9.76015E+005 2.59131E+005 Cs-137 1. 000 661.66* 85.10 3.13605E+D04 l. 52368E+D04 Tl-208 1. 000 583.19* 85.00 l.75622E+D04 8.64892E+003 Pb-212 1 . 000 238.63* 43.60 3.20967E+D04 2. 11 650E+004 Bi-214 0.455 609.32* 45.49 3.68207E+D04 2.43827E+004 1120 .29 14.92 1764.49 15.30 Pb-214 0 .433 295.22 18.42 351.93* 35.60 3 . 37648E+004 2.87204E+004

= Energy line found i n the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"'2 ) Uncertainty K-40 1. 000 9. 7 60146E+OOS 2.591311E+005 Cs-137 1.000 3.136049E+004 1.523679E+004 Tl-208 1.000 1.756218E+004 8.648915E+003 Pb-212 1.000 3.209670E+004 2.116502E+004 Bi-214 0.455 3.682071E+004 2.438269E+004 Pb-214 0.433 3.376481E+004 2.872038E+004

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

@~Nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 2. 000 s igma

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

Peak Locate Performed on: 6/11/2018 1:4 0 :35 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.25 2.6125E-001 48. 31 M = First peak in a mult iplet region m "" Other peak in a mult iplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

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Nuclide MDA Report 6/11/2018 1: 40: 35 PM Page 5

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

Detector Name: 6279 Sample Geometry: 1.5M90D CP 1IN Sample

Title:

B106201AFSWC046GD Nuclide Library Used: C:\GE~~E2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (% ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 2.260E+005 2.26E+005 9.760E+005 9.704E+004 Co-60 1173.23 99.85 2.344E+004 2.34E+004 -l.450E+004 1.023E+004 1332.49 99.98 2.373E+004 6.993E+003 l.027E+004 Nb-94 702.65 99.81 1. 825E+004 1 .83E+004 -1.187E+004 8.027E+003 871.09 99.89 2.480E+004 -l.315E+004 1.11SE+004 Ag-108m 433.90 90.50 2.446E+004 2.36E+004 -8.918E+003 1.134E+004 614. 3 0 89.80 3.258E+004 -1.009E+004 1.516E+004 722.90 90.80 2.361E+004 1 .855E+003 1.058E+004 Cs-134 604.72 97.62 2.707E+004 2.71E+004 -3 .411E+004 1.250E+004 795.86 85.46 2.882E+004 2.233E+004 1.303E+004

+ Cs-137 661.66* 85.10 1.913E+004 1 .91E+004 3.136E+004 8.318E+003 Eu-152 121.78 28.67 9.627E+004 8.73E+004 4.392E+004 4.666E+004 344.28 26.60 8.925E+004 -7.992E+004 4.201E+004 1408.01 21. 07 8.728E+004 4.069E+004 3.578E+004 Eu-154 123.07 40.40 6.822E+004 6.82E+004 3.270E+004 3.306E+004 723.30 20.06 1 .069E+005 -5.137E+004 4.788E+004 1274.43 34.80 7.046E+004 9.916E+003 3.076E+004 Eu-155 86.55 30.70 1 .166E+005 l .17E+005 1 .789E+005 5.685E+004 105.31 21.10 1 .449E+005 l .152E+005 7.044E+004

+ Tl-208 583.19* 85.00 7.614E+003 7.61E+003 1 .756E+004 2.652E+003 Bi-212 727.33 6.67 3.047E+005 3.05E+005 -1. 354E+005 1.355E+005

+ Pb-212 238.63* 43.60 3.106E+004 3.11E+004 3.210E+004 1.426E+004

+ Bi-214 609.32* 45.49 3.448E+004 3.45E+004 3.682E+004 l.502E+004 1120 .29 14.92 1 .568E+005 1.254E+004 6.871E+004 1764.49 15.30 1 .945E+005 l.408E+OOS 8.457E+004

+ Pb-214 295.22 18 .42 l. 285E+005 4.43E+004 -1.0lBE+OOS 6.082E+004 351.93* 35.60 4.430E+004 3.376E+004 2.016E+004 Ra-226 186.21 3.64 6.993E+005 6.99E+005 7.909E+OOS 3.364E+005 Ac-228 ~38.32 11. 27 2.116E+005 1.15E+005 5.081E+004 9.968E+004 911.20 25.80 1.151E+005 8.394E+004 5.261E+004 968.97 15.80 1.751E+005 l.444E+OOS 7.915E+004 Am-241 59.54 35.90 1.104E+005 1.10E+005 -2.413E+004 5.356E+004

+=Nuclide identified during the nuclide identification

~ Energy line found in the spectrum

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

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

[282]

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

Filename: 6279 Report Generated On 6/11/2018 3:21:55 PM Sample Title B106201AFSWC047GD Sample Description Ul Diesel Fuel Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 1. 5M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO M"2 Sample Taken On 6/11/2018 3:11:00 PM Acquisition Started 6/11/2018 3:11:54 PM Live Time 600.0 seconds Real Time 601.0 seconds Dead Time 0 . 16 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/4/2018 Efficiency ID 1 .5M9DD CP lIN D,~TA VALIDATED DATE;;, . . ,-/Y, TIME~.sd

'ci~*

[283]

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* *** P E A K ANALYSIS R E P O R T *****

Detector Name: 6279 sample

Title:

B106201AFSWC047GD Peak Analysis Performed on: 6/11/2018 3:21:55 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Unc ert. Counts 1 208- 215 211 .29 52.95 0.58 -1. 63E+OOO 27.12 9.16E+001 2 283- 308 300.13 75.16 1. 03 2.05E+002 93.31 4.64E+002 3 949- 959 953.73 238.55 0.67 3.13E+001 23.90 4.68E+001 4 1402- 1414 1407.54 352.00 0.67 3.14E+001 21.04 2.96E+001 5 1796- 1808 1802.22 450.66 0.42 1.35E+OOO 16.76 2.56E+001 6 2431- 2445 2436.89 609.32 0.80 4.02E+001 16.78 9.82E+OOO 7 2635- 2654 2646.56 661.73 1. 30 2.41E+002 33.24 1.00E+OOl 8 4686- 4699 4692.99 1173.31 0.38 1.89E+001 11.62 5.06E+OOO 9 5834- 5855 5844.95 1461.29 0.62 8.52E+001 19.58 2.79E+OOO M First peak in a multiplet region m -; Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2 , 000 sigma

[284]

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

sample

Title:

B106201AFSWC047GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

~ .

. . . . . . . . ' . . . . . . . . .. IDENTI FIED NUCLIDES . . ... . . . . . . . . . ... . .. . .

'"' .... ~

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 1.000 1460.82* 10. 66 1.0049BE+006 2.46908E+005 Cs-137 1.000 661.66* 85.10 2.22291E+005 4.06534E+004 Pb-212 1.000 238.63* 43.60 2.92868E+004 2.28900E+004 Bi-214 0.455 609.32* 45. 49 6.58537E+004 2.8 6117E+004 1120 .29 14.92 1764.49 15.30 Pb-214 0.433 295.22 18.42 351.93* 35.60 4.60927E+004 3.16405E+004 Am- 241 0.933 59. 54* 35.90 -2.36340E+003 3.94480E+004

=Energy line found in the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold = 0 . 30 Errors quoted at 2. 000 sigma

[285]

Nuclide MDA Report 6/11/2018 3:21:55 PM Page 5

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

Detector Name: 6279 Sample Geometry: 1. 5M90D CP 1IN Sample

Title:

B106201AFSWC047GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M"'2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10 .66 1.587E+005 1.59E+005 1.00SE+006 6.337E+004 Co-60 1173.23 99.85 3.493E+004 3.42E+004 9.130E+003 1.598E+004 1332.49 99.98 3.424E+004 1.112E+004 1.552E+004 Nb-94 702.65 99.81 2.643E+004 2.22E+004 2.827E+004 1.211E+004 871. 0 9 99.89 2.217E+004 -1 .664E+004 9.836E+003 Ag-108m 433.90 90.50 2.869E+004 2.87E+004 -5.867E+002 1.345E+004 6 14 . 30 89.80 3.742E+004 -6.917E+003 1.758E+004 722.90 90.80 2.888E+004 5.245E+003 1.321E+004 Cs-134 6 04.72 97.62 3.428E+004 3.43E+004 -3.260E+004 1.611E+004 795.86 85. 4 6 3.503E+004 2.573E+004 1.613E+004

+ Cs-137 661. 66

85.10 2.051E+004 2.05E+004 2.223E+OOS 9.007E+003 Eu-152 121. 78 28.67 1 .077E+005 8.20E+004 2.617E+D04 5.235E+004 344.28 26.60 9.621E+004 -6.388E+004 4.548E+004 1408.01 21. 07 8.198E+004 2.422E+002 3.312E+004 Eu-154 123.07 40 .40 7.552E+004 6.44E+004 -4.223E+D04 3.671E+004 723.30 20.06 1 .276E+005 1 .416E+004 5.825E+004 1274.43 34.80 6.439E+004 - 7.437E+003 2.772E+004 Eu-155 86.55 30.70 1 .324E+005 1.32E+005 1 .551E+OOS 6.474E+004 105.31 21.10 1 .571E+005 -4 .399E+D04 7.654E+004 Tl-208 583.19 85.00 3.530E+004 3.53E+004 1 .110E+004 1.649E+004 Bi-212 727.33 6.67 3.656E+OOS 3.66E+005 -1. 506E+D03 1.660E+005

+ Pb-212 238.63* 43.60 3.510E+004 3.51E+004 2.929E+004 1.628E+004

+ Bi-214 609.32* 45.49 3.406E+004 3.41E+004 6.585E+004 1.481E+004 1120.29 14.92 2.109E+005 -l.424E+OOS 9.574E+004 1764.49 15.30 1.767E+005 1.126E+005 7.564E+004

+ Pb-214 295.22 18.42 1 . 547E+005 4.70E+004 1.266E+005 7.391E+004 351.93* 35.60 4. 696E+004 4 .609E+D04 2.149E+004 Ra-226 186.21 3.64 7.859E+OOS 7.86E+OOS -3.954E+005 3.797E+005 Ac-228 338.32 11. 27 2.265E+005 1.23E+OOS 9.004E+004 1.072E+OOS 911. 2 0 25.80 1.232E+005 4- .586E+003 5.661E+004 968.97 15.80 2.107E+005 1.025E+005 9.694E+004

+ Am-241 59.54* 35.90 6.911E+004 6.91E+004 -2.363E+003 3.259E+004

+ =Nuclide identified during the nuclide identification

- Energy line found in the spectrum

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

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

[286]

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

Filename: 6279 Report Generated On 6/11/2018 3:06:41 PM Sample Title Bl06201AFSWC048GD Sample Description Ul Diesel Fuel Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 1. 5M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/11/2018 2:56:00 PM Acquisition Started 6/11/2018 2:56:39 PM Live Time 600.0 seconds Real Time 600.8 seconds Dead Time 0 . 13 %

Energy Calibration Osed Done On 6/9/2018 Efficiency Calibration Used Done On 6/4/2018 Efficiency ID l.5M90D CP lIN DATA VALIDATED DATEll-&.-/Y TIME~

(i>,,~ <

[287]

Peak Analysis Report 6/11/2018 3:06:41 PM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFSWC048-GD Peak Analysis Performed on: 6/11/2018 3:06:40 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) {keV) Area Uncert. Counts 1 284- 305 300.87 75.34 0.84 1. 84E+002 79.55 3.72E+002 2 335- 344 339.25 84.94 0.39 4.57E+001 39.78 1. 54E+O 02 3 950- 960 954. 59 238.77 0.79 2.35E+001 24.74 5.05E+001 4 1400- 1416 1407.72 352.04 0.82 6.25E+001 18 .89 8.50E+OOO 5 2037- 2049 2043.63 511. 01 0.56 2.06E+001 13 .57 9.35E+OOO 6 5836- 5854 5845.53 1461.43 1.11 8.40E+001 18 .33 O.OOE+OOO M = Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[288]

Interference Corrected Activity Report 6/11/2018 3:06 :41 PM Page 3

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Sample

Title:

B106201AFSWC048GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

'"' ....... . . ,t *** t! ....... IDENTIFIED NUCLIDES * * * * * * * * * * * * "' I

I * * ~ \0 Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M~2 ) Uncertainty K-40 0.999 1460.82* 10 .66 9.90779E+005 2.32695E+005 Eu- 155 0.338 86.55* 30.70 4.87687E+004 4 .35922E+004 105.31 21. 10 Pb-212 1. 000 238.63* 43 .60 2.20676E+004 2.34675E+004 Pb-214 0.433 295.22 18.42 351.93* 35.60 9.17481E+004 3 . 09422E+004

= Energy line found in t he spectrum.

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

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Interference Corrected Activity Report 6/11/2018 3:06:41 PM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 0 .999 9.907789E+005 2.326950E+005 Eu-155 0 .338 4.876868E+004 4.359223E+004 Pb-212 1. 000 2.206756E+004 2.346753E+004 Pb-214 0.433 9. 1 74812E+004 3.094218E+004

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

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

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

Peak Locate Performed on: 6/11/2018 3:06:40 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second % Uncertainty Type Nuclide 1 75.34 3.0626E-001 43.29 5 511 .01 3.4417E-002 65.72 M = First peak in a multiplet region m - Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[290]

Nuclide MDA Report 6/11/2018 3:06:41 PM Page 5

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

Detector Name: 6279 Sample Geometry: 1. 5M90D CP 1IN Sample

Title:

B106201AFSWC048GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

K-40 1460.82* 10.66 3.192E+004 3.19E+OD4 9.908E+005 O.OOOE+OOO Co-60 1173 .23 99.85 2.957E+004 1 .87E+004 2.104E+004 1 .329E+004 1332.49 99.98 1 .871E+004 -6.266E+002 7.761E+003 Nb-94 702.65 99.81 2.186E+004 2.19E+004 2.718E+003 9.831E+003 871. 09 99.89 2.480E+004 1.936E+004 1 .115E+D04 Ag-108m 433.90 90.50 2.272E+004 2.27E+004 -6.631E+002 1 .D46E+004 614. 3 0 89.80 3.428E+OD4 9.768E+OD3 1.601E+004 722.90 90.80 2.601E+OD4 3.981E+003 1.178E+004 Cs-134 604.72 97.62 3.165E+OD4 2.56E+004 2.436E+OD4 1.480E+004 795.86 85.46 2.558E+004 -l .866E+OD4 1.141E+004 Cs-137 661.66 85.10 2.997E+OD4 3.00E+004 1 .128E+D04 1.374E+004 Eu-152 121.78 28.67 1.0D3E+005 7.79E+004 7.271E+D04 4.869E+004 344.28 26.60 7.786E+004 -4 .189E+D04 3.631E+004 1 4 0 8.01 21. 07 8.198E+004 9.688E+003 3.312E+004 Eu-154 123.07 40.40 6.998E+004 6.44E+D04 3.D92E+004 3.394E+004 723.30 20.06 l. 178E+005 1. 341E+004 5.332E+004 1274.43 34.80 6.439E+004 4. 297E+D04 2.772E+004

+ Eu-155 86.55* 30.70 6.862E+004 6.86E+004 4. 877E+004 3.287E+004 105. 31 21. 1 0 1.390E+005 1. 746E+004 6.749E+004 Tl-208 583.19 85. 0 0 3.149E+004 3.15E+004 2.432E+004 1.459E+004 Bi-212 727.33 6.67 3.448E+005 3.45E+005 1.185E+D05 1.556E+005

+ Pb-212 238.63* 43.60 3.764E+OD4 3.76E+004 2.207E+D04 1.755E+004 Bi-214 609.32 45.49 6.685E+004 6.69E+004 5.761E+004 3.121E+004 1120.29 14.92 2.194E+005 2.696E+004 9.999E+004 1764.49 15.30 1.888E+005 1. 314E+005 8.170E+004

+ Pb-214 295.22 18.42 1. 34DE+005 2.89E+OD4 1. 251E+O 05 6.360E+004 351. 93* 35.60 2.893E+004 9.175E+004 1.248E+004 Ra-226 186.21 3.64 6.978E+005 6.98E+005 5.921E+005 3.357E+005 Ac-228 338.32 11. 27 1.978E+005 l .D2E+005 1. 982E+005 9.280E+004 911. 20 25.80 1 .018E+005 -5.063E+004 4.596E+004 968.97 15.80 1 .642E+005 8.076E+004 7.369E+004 Am-241 59.54 35.90 1 .192E+005 1 .19E+005 -3.060E+004 5.796E+OD4

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[291]

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

Filename: 6279 Report Generated On 6/11/2018 2:23:15 PM Sample Title B106201AFSWC049GD Sample Description Ul Diesel Fuel Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 1. 5M90D CP lIN Peak Locate Threshold 3. 00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/11/2018 2:13:00 PM Acquisition Started 6/11/2018 2:13:13 PM Live Time 600.0 seconds Real Time 600.8 seconds Dead Time 0 . 14 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/4/2018 Efficiency ID 1.5M90D CP lIN DATA VALIDATED DATE/ef*&i--LP TIMELJ.5?>

a~.4

[292]

Peak Analysis Report 6/11/2018 2:23: 15 PM Page 2

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

Detector Name: 6279 Sample

Title:

Bl06201AFSWC049GD Peak Analysis Performed on: 6/11/2018 2:23: 14 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 296- 307 300.43 75.23 0.75 1.01E+002 55.51 2.63E+002 2 950- 964 954.70 238.79 0.99 3.09E+001 3 1 .51 7.41E+001 3 1400- 1414 1407.73 352 .04 0.39 4.58E+001 22. 04 2.63E+001 4 2328- 2340 2333.08 583.37 0.67 2.30E+001 1 4 .47 1 .lOE+OOl 5 2430- 2444 2436.85 609.31 0.82 5.93E+001 20. 14 1 .47E+001 6 3638- 3651 3644.61 911.23 0.56 2.42E+001 10.87 1 .85E+OOO 7 4476- 4489 4482.07 1120.59 0.70 1.12E+001 11 .97 8.82E+OOO 8 5836- 5856 5845.06 1461.32 1. 64 1.34E+002 23.15 O.OOE+OOO M "" First peak in a multiplet region m =- Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[293]

Interference Corrected Activity Report 6/11/2018 2 : 23:15 PM Page 3

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

Sample

Title:

B106201AFSWC049GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB I * * * * * * * * * *

t *

I * * * "

IDENTIFIED NUCLIDES Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"2 ) Uncertainty K-40 1.000 1460.82* 10.66 1 .58044E+006 3.05606E+005 Tl-208 1 .000 583.19* 85.00 1 .96275E+004 1. 25781E+004 Pb-212 1 .000 238.63* 43.60 2.90037E+004 2.99169E+004 Bi-214 0.744 609.32* 45.49 9.71741E+004 3.50215E+004 1120.29* 14.92 8.00681E+004 8.59706E+004 1764.49 15.30 Pb-214 0.433 295.22 18.42 351. 93* 35.60 6.71598E+004 3.38791E+004

= Energy line found in the spectrum.

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

[294]

Interference Corrected Activity Report 6/11/2018 2:23:15 PM Page 4

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 1. 000 1.580438E+006 3.056064E+005 Tl-208 1. 000 1.962750E+004 l.257805E+004 Pb-212 1. 000 2.900369E+004 2.991693E+004 Bi-214 0.744 9.473945E+004 3.243364E+004 Pb-214 0.433 6.715984E+004 3.387907E+004

? ~ Nuclide is part of an undetermined solution x ~ Nuclide rejected by the interference analysis

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

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

Peak Locate Performed on: 6/11/2018 2:23 :14 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.23 1. 6761E-001 55.20 6 911.23 4.0256E-002 45. 00 Tol. Ac-228 M = First peak in a multip let region m = Other peak in a multip let region F ~ Fitted singlet Errors quoted at 2 . 000 sigma

[295]

Nuclide MDA Report 6/11/2018 2:23: 15 PM Page s

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

Detector Name: 6279 Sample Geometry: 1 . SM9 0D CP 1IN Sample

Title:

B106201AFSWC049GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL .NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10 .66 3.192E+004 3.19E+004 1.580E+006 O.OOOE+OOO Co-60 1173.23 99.85 3.192E+004 2.83E+004 1.354E+004 1.447E+004 1332.49 99.98 2.834E+004 1.780E+004 1.257E+004 Nb-94 702.65 99.81 2.293E+004 2.29E+004 -1.262E+004 1.036E+004 8 71.09 99.89 2.998E+004 - 1. 526E+004 1.374E+004 Ag-108m 433.90 90.50 2.467E+004 2.47E+004 - l.549E+004 l.144E+004 614.30 89.80 4.166E+D04 - 2.798E+003 1. 970E+O 04 722.90 90.80 2.955E+004 -1.690E+004 1. 354E+004 Cs-134 604.72 97.62 4.031E+004 2.93E+004 8.295E+003 1. 913E+004 795.86 85.46 2.925E+D04 2.152E+003 1. 324E+004 Cs-137 661. 66 85.10 2.788E+004 2.79E+004 -9.249E+003 l. 269E+004 Eu-152 121.78 28.67 1.070E+005 9.39E+004 8.270E+004 5.204E+004 344.28 26.60 9.395E+D04 -4.707E+004 4 . 436E+004 1408 . 01 21. 07 9.687E+004 -1. 429E+OOS 4.057E+004 Eu-154 123.07 40.40 7.516E+004 7.52E+004 -3.130E+004 3.653E+004 723.30 20.06 1 .338E+005 -7.621E+004 6.132E+004 1274.43 34.80 8.584E+004 -6.191E+004 3.845E+004 Eu-155 86 . 55 30.70 l .233E+005 1.23E+OOS 7.744E+004 6.019E+004 105 .31 21.10 1 .585E+OOS l.865E+OOS 7.724E+004

+ Tl-208 583.19* 85.00 1 .753E+004 l .75E+004 1.963E+004 7.611E+003 Bi-212 727.33 6.67 3.899E+005 3.90E+OOS 2.240E+OOS 1.781E+005

+ Pb-212 238.63* 43.60 4.801E+004 4.BOE+004 2.900E+004 2.274E+004

+ Bi-214 609.32* 45.49 3.945E+004 3.94E+004 9.717E+004 1.751E+004 1120.29* 14 .92 1. 3 63E+O 05 8.007E+004 5.848E+004 1764.49 15 .30 2.158E+OOS l.783E+OOS 9.518E+004

+ Pb-214 295.22 18.42 1. 367E+OOS 4.60E+004 -9.721E+004 6.494E+004 351.93* 35.60 4.599E+004 6.716E+004 2.101E+004 Ra-226 186.21 3.64 7.054E+OOS 7.0SE+OOS -1. 335E+OOS 3.395E+005 Ac-228 338.32 11.27 2.306E+005 1.24E+OOS 1.575E+005 1 .092E+005 911. 2 0 25.80 1.244E+005 9.108E+004 5.725E+004 968.97 15.80 1.950E+OOS 1.018E+004 8.909E+D04 Am-241 59.54 35.90 1.159E+005 l.16E+OOS -2.881E+004 5.632E+D04

+ Nuclide identified during the nuc lide identification

=Energy line found in the spectrum

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

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

[296]

- - - - GAMMA S P E C T R U M A NA L Y S I S *****

Filename: 6279 Report Generated On 6/11/2018 12:56:39 PM Sample Title Bl06201AFSWCOSOGD sample Description Ul Diesel Fuel Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 1.SM90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/11/2018 12:46:00 PM Acquisition Started 6/11/2018 12: 46: 37 PM Live Time 600.0 seconds Real Time 600.9 seconds Dead Time 0 . 14 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/4/2018 Efficiency ID 1.SM90D CP 1IN DATA VAUDA1ED DATE;.7 .. , .. 1p 04.dT~ .J\

[297]

Peak Analysis Report 6/11/2018 12:56:39 PM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFSWC050GD Peak Analysis Performed on: 6/11/2018 12:56:38 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Ene rgy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area uncert. Counts 1 296- 306 300.46 75.24 1. 03 3.03E+001 47.45 2.19E+002 2 334- 354 340.42 85.23 0.34 6.17E+001 65.92 2.82E+002 3 950- 960 954.82 238.82 1. 17 3.82E+001 22. 14 3.48E+001 4 1402- 1414 1408.25 352.17 0.97 4.64E+001 2 1. 34 2.56E+001 5 2432- 2444 2437.45 609.46 1. 21 3.99E+001 14. 94 6.13E+OOO 6 5839- 5856 5847.44 1 461.91 0.59 7.85E+001 19.30 4.50E+OOO M e First peak in a multiplet region m ~ Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[298]

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

Sample

Title:

Bl06201AFSWC050GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertainty K-40 0.998 1460. 82* 10.66 9.26119E+005 2. 41 531E+005 Eu - 155 0.339 86.55* 30.70 6.58761E+004 7.15574E+004 105.31 21. 10 Pb-212 1. 000 238.63* 43.60 3.5785SE+004 2.15502E+004 Bi- 214 0.455 609.32* 45.49 6.53542E+004 2.57233E+004 1120.29 14.92 1764.49 15.30 Pb-214 0.433 295.22 18.42 351.93* 35.60 6.81245E+004 3.29439E+004

=Energy line found i n the spectrum.

@=Energy line not used for Weighted Mean Activity Energy Tolerance : 10.000 keV Nuclide confidence index threshold : 0 .30 Errors quoted at 2. 000 sigma

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0 .998 9.261193E+005 2.415313E+OOS Eu-155 0 .339 6.587613E+004 7.155737E+004 Pb-212 1 .000 3.578553E+004 2.155018E+004 Bi-214 0 .455 6.535422E+004 2.572330E+004 Pb-214 0 .433 6.812453E+004 3.294393E+004

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

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

- - - - U N I D E N T I F I E D PE AK S **********

Peak Locate Performed on: 6/11/2018 12 :56:38 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % uncertainty Type Nuclide 1 75.24 5.0579E-002 156.36 M First peak in a multiplet region m = Other peak in a multiplet region F ; Fitted singlet Errors quoted at 2 . 000 sigma

[300]

Nuclide MDA Report 6/11/2018 12:56:39 PM Page 5

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Detector Name: 6279 Sample Geometry: 1.SM90D CP 1IN Sample

Title:

B106201AFSWC050GD Nuclide Library used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 )

+ K-40 1460.82* 10.66 1.806E+005 1.81E+005 9.261E+005 7.432E+004 Co-60 1173.23 99.85 2.856E+004 2.37E+004 3.200E+003 1. 279E+004 1332.49 99.98 2.373E+004 -1. 432E+003 1.027E+004 Nb-94 702.65 99.8i 2.361E+004 2.07E+OD4 1. 566E+004 1.070E+004 871.09 99.89 2.071E+004 -9.483E+003 9.107E+003 Ag-108m 433.90 90.50 2.569E+004 2.57E+004 4.965E+003 1.195E+004 614. 3 0 89.80 3.520E+004 1.744E+004 1.647E+004 722.90 90.80 2.639E+004 2.389E+004 1.196E+004 Cs-134 604.72 97.62 3.122E+004 2.93E+004 -1. 781E+004 1.458E+004 795.86 85.46 2.925E+004 9.614E+003 1.324E+004 Cs-137 661. 66 85. 10 3.096E+004 3.10E+004 4.129E+003 1.423E+004 Eu-152 121. 78 28.67 8.920E+004 7.62E+004 2.887E+004 4.312E+004 344.28 26.60 8.680E+004 -5.014E+004 4.078E+004 1408.01 21.07 7.620E+004 2.906E+004 3.024E+004 Eu-154 123.07 40.40 6.146E+004 6.15E+004 -4.839E+004 2.968E+004 723.30 20.06 1.178E+005 8.100E+004 5.332E+004 1274.43 34.80 7.235E+004 -1.069E+003 3.170E+004

+ Eu-155 86.55* 30.70 1.153E+005 1.15E+005 6.588E+004 5.618E+004 105.31 21. 10 1.312E+005 2.824E+004 6.357E+004 Tl-208 583.19 85. 0 0 2.895E+004 2.89E+004 2.752E+004 1.332E+004 Bi-212 727.33 6.67 3.656E+005 3.66E+OD5 -6.963E+004 1.660E+OOS

+ Pb-212 238.63* 43.60 3.087E+004 3.09E+004 3.579E+004 1.417E+004

+ Bi-214 609.32* 45.49 2.598E+004 2.60E+004 6.535E+004 1.077E+004 1120.29 14.92 2.050E+005 -6.095E+004 9.279E+004 1764.49 15.30 1. 945E+005 1.408E+005 8.457E+004

+ Pb-214 295.22 18.42 1. 262E+005 4.36E+004 -6.934E+004 5.967E+004 351. 93

35.60 4.363E+004 6.812E+004 1.983E+004 Ra-226 186.21 3.64 6.694E+005 6.69E+005 4.934E+005 3.215E+005 Ac-228 338.32 11.27 2.094E+005 1.24E+005 1.761E+004 9.857E+004 911.20 25.80 1.244E+005 1.164E+005 5.725E+004 968.97 15.80 1.777E+005 1. 535E+005 8.046E+004 Am-241 59.54 35.90 1. 068E+O 05 l.07E+005 7.290E+004 5.178E+004

+ . Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[301]

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

Filename: 6279 Report Generated On 6/11/2018 1 : 09:54 PM Sample Title B106201AFSWC051GD Sample Description Ul Diesel Fuel Storage Wall Sample Identification Sample Type Gamma Direct Sample Geometry 1. 5M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO M... 2 Sample Taken On 6/11/2018 12:59: 00 PM Acquisition Started 6/11/2018 12:59:52 PM Live Time 600.0 seconds Real Time 601.0 seconds Dead Time 0 . 16 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/4/2018 Efficiency ID 1 .5M90D CP lIN DATA VALIDATED DATEa-, . . ,r TIME J:l,£r

@<<;Yi?

[302]

Peak .Analysis Report 6/11/2018 1: 09:54 PM Page 2

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

Detector Name: 6279 sample

Title:

B106201AFSWC051GD Peak Analysis Performed on: 6/11/2018 1 :09:54 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 201- 208 204.77 5 1 .32 0.41 5.49E+OOO 20.52 4.95E+001 2 283- 310 300.53 75.26 0.70 2.08E+002 82.47 3.31E+002 3 950- 960 955.34 238.95 0.75 4.33E+001 22.66 3.58E+001 4 1402- 1413 1407.33 351.94 0.92 3.54E+001 16.67 1.36E+001 5 2431- 2444 2436.56 609.24 1. 30 3.24E+001 15.89 9.64E+OOO 6 5837- 5857 5847.29 1461.87 1. 97 l. 06E+002 22.25 4.99E+OOO 7 7057- 7072 7064.92 1766.26 0. 33 1.70E+001 8.25 O.OOE+OOO M = Fi rst peak in a multiplet region m = Other peak in a multiplet region F = Fi tted singlet Errors quoted at 2 . 000 sigma

[303]

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sample

Title:

Bl06201AFSWC051GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

~ .. .. . . . . .. IDENTIFIED NUCLIDES .... . ..... . ........ . . ...

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M"'2 ) Uncertainty K-40 0.998 1460.82* 10 .66 l.25064E+006 2.84061E+005 Pb-212 1.000 238.63* 43.60 4.05747E+004 2.22506E+004 Bi-214 0.710 609.32* 45.49 5.30278E+004 2.68047E+004 1120.29 14 .92 1764.49* 15 .30 1.59681E+005 7.85054E+004 Pb-214 0.433 295.22 18 .42 351.93* 35.60 5.20284E+004 2.56776E+004 Am-241 0.898 59.54* 35.90 8.40497E+003 3.14896E+004

=Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2) uncertainty K-40 0.998 1. 250641E+006 2.840606E+005 Pb-212 1. 000 4.057471E+004 2.225060E+004 Bi-214 0.710 6.416318E+004 2.536683E+004 Pb-214 0.433 5.202839E+004 2.567764E+004 Am-241 0.898 8.404974E+003 3.148957E+004

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

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

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

Peak Locate Performed on: 6/11/2018 1:09:54 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 2 75.26 3.4610E-001 39.71 M == First peak in a multiplet region m == Other peak in a multiplet region F == Fitted singlet Errors quoted at 2 . 000 sigma

[305]

Nuc 1 i de MDA Report 6/11/2018 1: 09 ~ 54 PM Page 5

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

Detector Name: 6279 Sample Geometry: 1.5M90D CP lIN Sample

Title:

B106201AFSWC051GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2 ) (pCi/MA2)

+ K-40 1460.82* 10 .66 1.954E+005 1. 95E+O 05 1.251E+006 8.175E+004 Co-60 1173.23 99.85 3.281E+004 2.65E+004 3.946E+003 1.492E+004 1332.49 99.98 2.648E+004 4.882E+003 1.164E+004 Nb-94 702.65 99.81 2.035E+004 2.03E+004 -1. 795E+O 03 9.074E+003 871. 09 99.89 2.396E+004 1. 679E+004 1.073E+004 Ag-108m 433.90 90.50 2.446E+004 2.45E+004 1. 097E+004 1.134E+004 614.30 89.80 3.404E+004 -1. 773E+004 1.589E+004 722.90 90.80 2.563E+004 3.940E+003 1.158E+004 Cs-134 604.72 97.62 3 . 035E+004 2.97E+004 -2.308E+004 1.415E+004 795.86 85.46 2.968E+004 -2.908E+003 l.346E+004 Cs-137 661.66 85.10 2.860E+004 2.86E+004 1.656E+004 1 .305E+004 Eu-152 121 .78 28.67 9.445E+004 8.06E+004 -9.082E+004 4.574E+004 344.28 26.60 8.060E+004 -4.390E+004 3.768E+004 1408.01 21.07 1. 205E+005 -6.200E+003 5.237E+004 Eu-154 123.07 40.40 6.713E+004 6.71E+004 2.013E+002 3.251E+004 723.30 20.06 1.160E+005 1 .441E+004 5.245E+004 1274.43 34.80 8.428E+004 8.952E+002 3.767E+004 Eu-155 86.55 30.70 1.123E+005 1.12E+005 5.870E+004 5.472E+004 105.31 21. 10 1.409E+005 -4.881E+004 6.846E+004 Tl-208 583.19 85.00 3.307E+004 3.31E+004 2.376E+004 1.538E+004 Bi-212 727.33 6.67 3.851E+005 3.85E+005 2.9SOE+OOS l.758E+OOS

+ Pb-212 238.63* 43.60 3.102E+004 3.10E+004 4.057E+004 1.424E+004

+ Bi-214 609.32* 45.49 3.433E+004 2.54E+004 5.303E+004 1. 495E+004 1120.29 14.92 1 .860E+005 1.243E+OOS 8.333E+004 1764.49* 15.30 2.542E+004 1.597E+005 O.OOOE+OOO

+ Pb-214 295.22 18.42 1 .279E+005 3.21E+004 -3.067E+004 6.054E+004 351. 93

35.60 3.214E+004 5.203E+004 l. 409E+004 Ra-226 186.21 3.64 6.947E+005 6.95E+005 -2.217E+003 3.341E+OOS Ac-228 338.32 11. 27 1.893E+005 1.12E+005 -5.843E+004 8.854E+004 911. 20 25.80 1.123E+005 5.572E+004 5.121E+004 968.97 15.80 2.041E+005 1.234E+005 9.366E+004

+ Am-241 59.54* 35.90 5.445E+004 5.45E+004 8.405E+003 2.516E+004

+ =Nuclide identified during the nuclide identification

~ Energy line found in the spectrum

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

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

[306]

- - - - GAMMA S P E C T R U M ANALYSIS *****

Filename: 6279 Report Generated On 6/11/2018 1: 51: 23 PM Sample Title B106201AFQWC046GD Sample Description Ul Diesel Fuel Storage Wall QC Sample Identification QC Sample Type Gamma Direct Sample Geometry 1.5M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 7.070E+OOO MA2 Sample Taken On 6/11/2018 1:41:00 PM Acquisition Started 6/11/2018 1:41:21 PM Live Time 600.0 seconds Real Time 600.9 seconds Dead Time 0 . 14 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/4/2018 Efficiency ID 1 .5M90D CP lIN

[307]

~eak Analysis Report 6/11/2018 1 :51:23 PM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFQWC046GD Peak Analysis Performed on: 6/11/2018 1 :51:23 PM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 287- 306 300.33 75.21 0.64 2.46E+002 67.25 2.52E+002 2 1401- 1412 1406.85 351.82 0.29 2.85E+001 18.41 2.25E+001 3 2327- 2338 2332.29 583.17 0.69 2.20E+001 13.40 9.00E+OOO 4 2638- 2652 2645.50 661.47 0.33 3.86E+001 16.21 9.38E+OOO 5 5836- 5853 5844.47 146 1. 1 7 1. 76 6.64E+001 18.72 6.60E+OOO M = First peak in a multiplet region m - Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[308]

Interference Corrected Activity Report 6/11/2018 1 :5 1: 23 PM Page 3

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Sample

Title:

B106201AFQWC046GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB

~ . . . . . . . ......... .. . j

IDENTIFIED NUCLIDES * ~ * * * * * * * * * * * * .,. I * * *

Nuclide Id Energy Yield Activity Activity Name Confidence (keV) ( %) (pCi/M" 2 ) Uncertainty K-40 1.000 1460.82* 10.66 7.83135E+005 2.31062E+005 Cs-137 1.000 661.66* 85 .10 3.56133E+004 1.55468E+004 Tl-208 1.000 583.19* 85.00 1. 87762E+004 1.16582E+004 Pb-214 0.433 295.22 18.42 351.93* 35.60 4.18559E+004 2.77318E+004

= Energy line found in t he spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 7.831352E+005 2.310620E+005 Cs-137 1 . 000 3.561332E+004 l .554682E+004 Tl-208 1 . 000 l.877618E+004 l .165819E+004 Pb-214 0 .433 4 .18 5592E+004 2.773177E+004

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

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

- - - - U N I D E N T I F I E D P E AK S **********

Peak Locate Performed on: 6/11/2018 1:51 :23 PM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No . (keV) Counts per Second % Uncertainty Type Nuclide 1 75 .21 4.1039E-001 27.31 M "' First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[310]

Nuclide MDA Report 6/11/2018 1: 51: 23 PM Page 5

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Detector Name: 6279 Sample Geometry: 1.5M90D CP 1IN Sample

Title:

B106201AFQWC046GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec . Level Name (keV) ( %) (pCi/M ... 2 ) (pCi/M ... 2 ) (pCi/M"2 ) (pCi/M ... 2 )

+ K-40 1460.82* 10.66 2.108E+005 2.llE+OOS 7.831E+005 8.943E+004 Co-60 1173.23 99.85 2.856E+004 2.30E+004 2.750E+004 1.279E+004 1332.49 99.98 2.298E+004 4.922E+003 9.894E+003 Nb-94 702.65 99.81 2.222E+004 2.22E+004 1.307E+004 1.001E+004 871. 09 99.89 2.601E+004 -3.921E+003 1.176E+004 Ag-108m 433.90 90.50 2.446E+004 2.23E+004 5.513E+003 l.134E+004 614.30 89.80 3.233E+004 1.460E+004 1.504E+004 722.90 90.80 2.230E+004 3.244E+003 9.920E+003 Cs-134 604.72 97.62 2.829E+004 2.75E+004 1.902E+004 l.311E+004 795.86 85.46 2.749E+004 -5.765E+003 1.236E+004

+ Cs-137 661.66* 85.10 1.828E+004 1.83E+004 3.561E+004 7.891E+003 Eu-152 121. 78 28.67 l.014E+005 8.27E+004 8.496E+004 4.922E+004 344.28 26.60 8.272E+004 -9.039E+003 3.874E+004 1408.01 21. 07 l.054E+005 6.394E+004 4.4BSE+004 Eu-154 123.07 40.40 7.206E+004 6.44E+004 6.251E+004 3.498E+004 723.30 20.06 1.010E+005 3.602E+004 4.492E+004 1274.43 34.80 6.439E+004 -3.941E+003 2.772E+004 Eu-155 86.55 30.70 l.183E+005 1.18E+005 1.167E+005 5.771E+004 105.31 21.10 1.437E+005 1.961E+004 6.984E+004

+ Tl-208 583.19* 85.00 l.575E+004 1.57E+004 1.87BE+004 6.71BE+003 Bi-212 727.33 6.67 3.167E+005 3.17E+005 S.175E+002 l.416E+005 Pb-212 238.63 43.60 6.040E+004 6.04E+004 S.477E+004 2.893E+004 Bi-214 609.32 45.49 6.350E+004 6.3SE+004 3.729E+004 2.953E+004 1120.29 14.92 2.109E+OOS 7.175E+004 9.574E+004 1764.49 15.30 1.702E+005 1.032E+OOS 7.242E+004

+ Pb-214 295.22 18.42 l.324E+005 4.02E+004 3.222E+004 6.278E+004 351.93* 35.60 4.017E+004 4.186E+004 l.810E+004 Ra-226 186.21 3.64 6.900E+005 6.90E+OOS -1.906E+005 3.318E+OOS Ac-228 338.32 11. 27 l.880E+005 1.14E+OOS -3.952E+004 8.791E+004 911. 20 25.80 1.138E+005 7.987E+004 5.191E+004 968.97 15.80 1.725E+005 1.801E+OOS 7.782E+004 Am-241 59.54 35.90 l.139E+005 1.14E+OOS 1.163E+005 5.535E+004

+ ~ Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[311]

- - - - GAMMA S P E C T R U M A N A L Y S I S *****

Filename: 6279 Report Generated On 6/11/2018 10:32:54 AM Sample Title B106201AFQFC025GD Sample Description Ul Diesel Fuel Storage Floor QC Sample Identification QC Sample Type Gamma Direct Sample Geometry 3M90D CP 1IN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 MA2 Sample Taken On 6/11/2018 10:22:00 AM Acquisition Started 6/11/2018 10:22:52 AM Live Time 600. 0 seconds Real Time 600.9 seconds Dead Time 0. 15 %

Energy Calibration Used Done On 6/9/2018 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN DATA-VALIDATED DATE/.?... ~ .. /8" TIMEil,£.r C?,.w;L

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Peak Analysis Report 6/11/2018 10:32:54 AM Page 2

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

Detector Name: 6279 Sample

Title:

B106201AFQFC025GD Peak Analysis Performed on: 6/11/2018 10:32:54 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area uncert. Counts 1 296- 305 300.38 75.22 0.58 7.70E+001 48.83 2.27E+002 2 946- 958 953.29 238.44 0.83 3.91E+001 24 .41 4.09E+001 3 1399- 1414 1406. 33 351 . 69 1. 37 5.23E+001 23.27 2.77E+001 4 2429- 2445 2436.70 609.27 1. 40 6.12E+001 17.02 3.75E+OOO 5 2636- 2653 2645.54 661.48 1. 19 1 .76E+002 29.27 1. 15E+001 6 5324- 5337 5330.71 1332.73 0.96 2.lOE+OOl 10.40 1. 97E+OOO 7 5835 - 5851 5843.20 146 0. 85 1. 27 6.36E+001 18 .31 6.41E+OOO 8 7051- 7066 7058.85 1764.75 0.31 2.20E+001 9.38 O.OOE+OOO M = First peak in a multiplet region m = other peak in a multiplet region F Fitted singlet Errors quoted at 2 . 000 sigma

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

Sample

Title:

B106201AFQFC025GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M'"2 ) Uncertainty K-40 1.000 1460.82* 10.66 7.53312E+005 2.26545E+005 Cs-137 1.000 661.66* 85.10 l .63794E+005 3.36610E+004 Pb-212 1.000 238.63* 43.60 3.73745E+004 2.41246E+004 Bi-214 0.710 609.32* 45.49 l .01654E+005 3.07803E+004 1120.29 14.92 1764.49* 15.30 2.07343E+005 8.99575E+004 Pb-214 0.434 295.22 18.42 351.93* 35.60 7.81588E+004 3.66652E+004

=Energy line found in the spectrum.

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

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Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/M"2 ) Uncertainty K-40 1. 000 7.533124E+005 2.265448E+005 Cs-137 1. 000 1. 63 7 93 8E+005 3.366105E+004 Pb-212 1. 000 3.737454E+004 2.412462E+004 Bi-214 0.710 1 .127309E+005 2.912264E+004 Pb-214 0.434 7.815876E+004 3.666522E+00 4

? ~ Nuclide is part of an undetermined solution x ~ Nuclide rejected by the interference analysis

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

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

Peak Locate Performed on: 6/11/2018 10 :32:54 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % uncertainty Type Nuclide 1 75.22 1.2839E-001 63.38 6 1332.73 3.5054E-002 49.47 Sum M ~ First peak in a multiplet region m e Other peak in a multiplet region F = Fitted singlet Errors quoted at 2 . 000 sigma

[315]

Nucli de MDA Report 6/11/2018 10 :32:54 AM Page 5

- - - - NUCLIDE MD A R E P O R T *****

Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFQFC025GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) ( %) (pCi/MA2 ) (pCi/MA2 ) (pCi/M"2 ) (pCi/M"2 )

+ K-40 1460.82* 10.66 2.073E+005 2.07E+005 7.533E+005 8.761E+004 Co-60 1173.23 99.85 3.299E+004 3.30E+004 -2.220E+004 1.500E+004 1332.49 99.98 3.392E+004 1 .867E+004 1.536E+004 Nb-94 702.65 99.81 2.390E+004 2.37E+004 O.OOOE+OOO 1.084E+004 871.09 99.89 2.375E+004 -2.949E+003 1.061E+004 Ag-108m 433.90 90.50 2.878E+004 2.88E+004 -1 .345E+004 1.348E+004 614.30 89.80 3.875E+004 1 .866E+003 1.823E+004 722.90 90.80 2.888E+004 2.401E+004 1.320E+004 Cs-134 604.72 97.62 3.607E+004 2.73E+004 -2.059E+004 1.699E+004 795.86 85.46 2.731E+004 -4.590E+003 1.226E+004

+ Cs-137 661.66* 85.10 2.162E+004 2.16E+004 1 .638E+005 9.545E+003 Eu-152 121 .78 28.67 1.112E+005 9.52E+004 -7.927E+002 5.407E+004 344.28 26.60 9.520E+004 -2.024E+004 4.493E+004 1408.01 21.07 1.099E+005 1 .472E+004 4.707E+004 Eu-154 123.07 40.40 7.808E+004 7.46E+004 -3.865E+004 3.796E+004 723.30 20.06 1.308E+005 l .066E+005 5.975E+004 1274.43 34.80 7.457E+004 -2.326E+004 3.279E+004 Eu-155 86.55 30.70 1.276E+005 1.28E+OOS 1.557E+005 6.233E+004 105 . 31 21.10 l.498E+005 -4.569E+004 7.282E+004 Tl-208 583.19 85.00 3.271E+004 3.27E+004 2.199E+004 1.519E+004 Bi-212 727.33 6.67 4.040E+005 4.04E+005 1 .515E+005 1.850E+005

+ Pb-212 238.63* 43.60 3.559E+004 3.56E+004 3.737E+004 1.650E+004

+ Bi-214 609.32* 45.49 2.275E+004 2.28E+004 1. 017E+005 9.130E+003 1120.29 14.92 2.178E+005 1.423E+OOS 9.917E+004 1764.49* 15.30 2.550E+004 2.073E+005 O.OOOE+OOO

+ Pb-214 295.22 18.42 1.509E+005 4.88E+004 -7.590E+003 7.196E+004 351.93* 35.60 4.881E+004 7.816E+004 2.238E+004 Ra-226 186.21 3.64 7.383E+005 7.38E+005 9.237E+004 3.556E+OOS Ac-228 338.32 11. 27 2.276E+005 1.31E+005 7.397E+004 1.076E+OOS 911. 20 25 . 80 1.305E+OOS 1.055E+OOS 6.025E+004 968.97 15.80 1.917E+005 9.597E+004 8.737E+004 Am-241 59.54 35.90 1.261E+005 1.26E+005 -7.295E+004 6.138E+004

+ ~ Nuclide identified during the nuclide identification

; Energy line found in the spectrum

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

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

[316]

- - - - GAMM A SPECTRUM A N A L Y S I S *****

Filename: 6279 Report Generated On 6/5/2018 9:29:25 AM Samp le Title B106201AFQFC002GD Samp le Description Ul Diesel Fuel Oil Storage Floor Sample Identification QC Sample Type Gamma Direct Sample Geometry 3M90D CP lIN Peak Locate Threshold 3.00 Peak Locate Range (in channels) 85 - 8192 Peak Area Range (in channels) 85 - 8192 Identification Energy Tolerance 10.000 keV Sample Size 2.830E+001 M"2 Sample Taken On 6/5/2018 9:19: 00 AM Acquisition Started 6/5/2018 9:19:24 AM Live Time 600.0 seconds Real Time 600.4 seconds Dead Time 0 , 07 %

Energy Calibration Used Done On 12/28/2017 Efficiency Calibration Used Done On 6/2/2018 Efficiency ID 3M90D CP 1IN

[317]

Peak Analysis Report 6/5/2018 9:29:25 AM Page 2

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Detector Name: 6279 Sample

Title:

B106201AFQFC002GD Peak Analysis Performed on: 6/5/2018 9:29:24 AM Peak Analysis From Channel: 85 Peak Analysis To Channel: 8192 Peak ROI ROI Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 285- 309 300.30 75.04 0.48 l.72E+002 73.32 2.80E+002 2 945- 962 953. 11 238.40 0.74 2.18E+001 31. 77 6.72E+001 3 1171- 1188 1179.58 295.06 0.47 1.86E+001 19.67 2.34E+001 4 1397- 1414 1405.94 351.69 0.98 4.07E+001 23.88 3.13E+001 5 2031- 2048 2039.64 510.18 0.62 2.31E+001 18.07 1. 79E+O 01 6 2320- 2337 2328.99 582.53 2.38 1.35E+001 15.15 1. 3SE+O 01 7 2427- 2444 2435.31 609.12 0.53 4.81E+001 18.90 1 .19E+001 8 3866- 3883 3874. 44 968.82 0.32 1.15E+001 10.23 4.SOE+OOO 9 4609- 4628 4618.32 1154.66 0.36 1.43E+001 9.94 2.69E+OOO 10 5831- 5851 5840.97 1459.96 1. 36 8.18E+001 20.08 5.25E+OOO M First peak in a multiplet region m Other peak in a multiplet region F Fitted singlet Errors quoted at 2.000 sigma

[318]

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Sample

Title:

Bl06201AFQFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB IDENTIFIED NUCLIDES Nuc lide Id Energy Yield Activity Activity Name Confidence (keV) (%) (pCi/M"2 ) Uncertainty K-40 0.999 1460.82* 10 .66 9.68094E+005 2.52220E+005 Tl-208 0.999 583.19* 85.00 1 .16648E+004 1. 31 653E+004 Pb-212 1.000 238.63* 43.60 2.08075E+004 3.05760E+004 Bi-214 0.454 609.32* 45.49 7.98841E+004 3.27966E+004 1120.29 14 .92 1764.49 15.30 Pb-214 1.000 295.22* 18.42 4 .78227E+004 5.12463E+004 351.93* 35.60 6.07363E+004 3.67999E+004

: Energy line found in t he spectrum.

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

[319]

Interference Corrected Activity Report 6/5/2018 9:29:25 AM Page 4

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

Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (pCi/MA2 ) Uncertainty K-40 0 .999 9.680942E+005 2.522199E+OOS Tl-208 0 .999 1 .166480E+004 1.316527E+004 Pb-212 1.000 2.080746E+004 3.057595E+004 Bi-214 0.454 7.988414E+004 3.279656E+004 Pb-214 1.000 5.634276E+004 2.989133E+004

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

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

[320]

Interference Corrected Activity Report 6/5/2018 9:29:25 AM Page 5

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

Peak Locate Performed on: 6/5/2018 9:29:24 AM Peak Locate From Channel: 85 Peak Locate To Channel: 8192 Peak Energy Peak Size in Peak CPS Peak Tol.

No. (keV) Counts per Second % Uncertainty Type Nuclide 1 75.04 2.8657E-001 42.64 5 510.18 3.8496E-002 78.24 8 968.82 1. 9167E-002 88.94 Sum 9 1154.66 2.3848E-002 69.48 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 2.000 sigma

[321]

Nuclide MDA Report 6/5/2018 9:29:25 AM Page 6

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Detector Name: 6279 Sample Geometry: 3M90D CP 1IN Sample

Title:

B106201AFQFC002GD Nuclide Library Used: C:\GENIE2K\CAMFILES\Zion Lib-BNL.NLB Nuclide Energy Yield Line MDA Nuclide MDA Activity Dec. Level Name (keV) (%) (pCi/M"2 ) (pCi/M"2 ) (pCi/M"2 ) (pCi/MA2)

+ K-40 1460.82* 10.66 2.021E+005 2.02E+005 9.681E+005 8.504E+004 Co-60 1173.23 99.85 3.299E+004 2.91E+004 1 .008E+004 1.500E+004 1332 . 49 99.98 2.908E+004 1 .444E+004 1.294E+004 Nb-94 702.65 99.81 2.905E+004 2.91E+004 2.327E+004 1.341E+D04 871.09 99.89 3.026E+004 8.852E+003 1.387E+004 Ag-108m 433.90 90.50 2.968E+004 2.97E+004 -3.099E+004 1. 393E+004 614. 3 0 89.80 4.041E+004 2.223E+004 1.906E+004 722.90 90.80 3.277E+004 2.660E+004 1 .514E+OD4 Cs-134 604.72 97.62 3.879E+004 3.36E+004 4 .966E+004 1 .835E+004 795.86 85.46 3.358E+004 4 .237E+004 1 .539E+004 Cs-137 661.66 85. 10 3.672E+004 3.67E+004 5.787E+004 1 .710E+004 Eu-152 121.78 28.67 1.214E+005 1.21E+005 -1.996E+005 5.920E+004 344.28 26.60 1. 277E+005 8.035E+004 6.119E+004 1408.01 21. 07 1. 211E+005 2.083E+004 S.263E+004 Eu-154 123.07 40. 40 8.624E+004 8.47E+004 3.937E+004 4.204E+004 723.30 20.06 l.456E+005 2.622E+004 6.716E+004 1274.43 34.80 8.472E+004 3.845E+004 3.786E+004 Eu-155 86.55 30.70 1.507E+005 1.51E+005 -2.446E+005 7.389E+004 105.31 21.10 l.905E+005 -l.428E+005 9.317E+004

+ Tl-208 583. 19* 85.00 2.117E+004 2.12E+004 1.166E+004 9.415E+003 Bi-212 727.33 6.67 4 .220E+005 4 .22E+005 -3.446E+005 l .940E+005

+ Pb-212 238.63* 43.60 5.038E+004 5.04E+004 2.081E+004 2.389E+D04

+ Bi-214 609.32* 45.49 3.951E+004 3.95E+004 7.988E+004 1.751E+004 1120.29 14.92 2.493E+005 -5.626E+004 1.149E+OOS 1764.49 15. 30 2.063E+005 3.506E+004 9.039E+004

+ Pb-214 295.22* 18 .42 8.190E+004 5.36E+004 4.782E+004 3.746E+004 351.93* 35.60 5.363E+004 6.074E+004 2.479E+004 Ra-226 186.21 3.64 8.614E+005 8.61E+005 4.348E+004 4.172E+005 Ac-228 338.32 11 .27 2.593E+OOS 1.33E+005 1.691E+005 1 .234E+OOS 911. 20 25.80 1 .330E+005 1. 887E+005 6.147E+004 968.97 15.80 1 .965E+005 - 9.525E+004 8.976E+004 Am-241 59.54 35.90 1. 407E+OOS 1.41E+005 -1.615E+005 6.867E+004

+=Nuclide identified during the nuclide identification

=Energy line found in the spectrum

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

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

[322]

ATTACHMENT 5 EBERLINE REPORTS

[323]

l EBERLINE 0,1\I\ f(IIJGF,

~

EBS-OR-43977 July19,2018 Patricia Giza Zion Solutions, LLC 101 Shiloh Blvd Zion, IL 60099 CASE NARRATIVE Work Order# 18-06123-0R SAMPLE RECEIPT This work order contains four solid samples received 06/28/2018. Samples were analyzed for Total Strontium, Tritium, Nickel-63 and by Gamma Spectroscopy.

CLIENT ID LAB ID B l-06202A-FSFC-O 16CV 18-06123-04 B l-06202A-FSWC-035CV 18-06123-05 B 1-06201 AFSWC-027CV 18-06123-06 B 1-0620 I A-FSWC-024CV 18-06123-07 ANALYTICAL METHODS Total Strontium was analyzed using EIChroM Method SR WO 1 Modified. Tritium was performed using Method LANL ER-210 Modified. Nickel-63 was performed using Method ASTM 3500-Ni Modified.

Gamma Spectroscopy was performed using EPA Method 901.1 Modified.

Laboratory qualifiers are as follows:

U - Result is less than the MDA.

ANALYTICAL RESULTS Combined Standard Unce1tainty is reported at I-sigma value.

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

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

Page 1 of 3

[324]

ANALYTICAL RESULTS CONTINUED TOT AL STRONTIUM Samples were prepared by digesting with acids and diluting as appropriate. Aliquots were removed from dilution followed by adding Strontium recovery carriers to the samples. Chemical separations were conducted using selective extractions. Strontium precipitated was mounted on tared filter media.

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

Samples demonstrated acceptable results for all Total Strontium analyses. Strontium-90 results are repo1ied from Total Strontium assuming secular equilibrium. Chemical recovery was acceptable for all samples. The Total Strontium method blank demonstrated an acceptable result. Results for the Total Strontium duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Total Strontium laboratory control sample demonstrated an acceptable percent recovery.

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

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

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

NICKEL-63 Samples were prepared by digesting with acids and diluting as appropriate. Aliquots were removed from dilution and placed into appropriately sized beakers. Stable elemental Nickel carrier was added to each sample prior to digestion. After digestion, sample pH was adjusted and Nickel-63 was precipitated selectively with Dimethylglyoxime. Precipitates were selectively separated, redissolved, and residual acid was effectively neutralized. Sample residuals were placed into scintillation vials, scintillation cocktail was added and Nickel-63 activity was determined by beta liquid scintillation.

Samples demonstrated acceptable results for all Nickel-63 analyses. The Nickel-63 method blank demonstrated an acceptable result. Results for the Nickel-63 duplicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique. Results for the Nickel-63 laboratory control sample demonstrated an acceptable percent recovery.

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

Page 2 of 3

[325]

ANALYTICAL RESULTS CONTINUED GAMMA SPECTROSCOPY CONTINUED Samples demonstrated acceptable results for all gamma-emitting radionuclides as rep01ied. Some samples demonstrated results that are greater than the method detection limit. These results are reported from the Canberra Gamma Apex "Nuclide MDA Report" and are not positive. These results are qualified as non-detect (U). The method blank demonstrated acceptable results for all radionuclides as repo1ied. Results for the Bismuth-214 and Potassium-40 replicate demonstrated an acceptable relative percent difference and normalized difference. Results for the Cesium-137 replicate demonstrated a high relative percent difference; however, normalized difference is within acceptable limits for the analytical technique.

Results for the Cobalt-60 and Cesium-13 7 laboratory control sample demonstrated an acceptable percent recovery.

CERTIFICATION OF ACCURACY I ce1tify that this data rep01i is in compliance with the terms and conditions of the Purchase Order, both technically and for completeness, for other than the conditions detailed above. Release of the data contained in this hard copy data package has been authorized by the cognizant project manager or his/her

~.-==::-*-Knee to be accurarvcrified by the following signature.

j M. R-:*McIYouga1I Laboratory Manager /

7

~h:::,=,,, :'.,:'.:!::,~wee ts m~ ,>comoges yom fecdhack ,eganliog °"' 1,c,fonmmcc pnw idiog rndiosoalyticcl '"' ices I' lease visit http://eberlincanalytieal.com/ to provide us with foc.dbaek on our services.

Page 3 of 3

[326]

Printed: 7119/2018 9:05 AM Page 1 of 7 Report To: Work Order Details:

Patricia Giza 18-06123 Eberline Analytical Zion Solutions SDG:

Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category:_ ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report 10 Type 10 Date Date Date 10 Analyte Method Result cu CSU MOA Qualifier Units 18-06123-01 LCS KNOWN 06/28/18 00:00 6/28/2018 6/30/2018 18-06123 Tritium LANL ER-210 Modified 2.22E+02 18-06123-01 LCS SPIKE 06/28/18 00:00 6/28/2018 6/30/2018 18-06123 Tritium LANL ER-210 Modified 2.01E+02 18-06123-02 MBL BLANK 06/28/18 00:00 6/2812018 6/3012018 18-06123 Tritium LANL ER-210 Modified 7.50E-01 18-06123-03 DUP 81-06202A-FSFC-016CV 06118118 14:10 6/2812018 6/3012018 Tritium 1.12E+OO 86E-01

'm - - - - - " , - ~ ~ - - ~ - ' " ' -

18-06123-05 TRG 06118118 12:30 612812018 6/3012018 18-06123 Tritium LANL ER-210 Modified 9.13E-01 18-06123-06 TRG B1-06201AFSWC-027CV 06107118 13:30 6/2812018 6/3012018 18-06123 Tritium LANL ER-210 Modified 1-86E+OO 06107118 14:05 6/2812018 6/3012018 18-06123 Tritium LANL ER-210 Modified 9.48E-01 KNOWN 06128118 00:00 6/28/2018 71212018 18-06123 Nickel-63 ASTM 3500-Ni Modified 1.59E+03 4.76E+01 18-06123-01 LCS SPIKE 06128118 00:00 6/2812018 7/212018 18-06123 Nickel-63 ASTM 3500-Ni Modified 1.55E+03 8-94E+OO .18E+01 2.00E+OO 06128118 00:00 6/2812018 71212018 18-06123 Nickel-63 ASTM 3500-Ni Modified O.OOE+OO 1.22E+OO 1.22E+OO 2.08E+OO 18-06123-03 DUP B 1-06202A-FS F C-016CV 06118/18 14:10 6/2812018 71212018 18-06123 Nickel-63 ASTM 3500-Ni Modified 1.54E-01 1-14E+OO 1-14E+OO 1.95E+OO 18-06123-04 DO B1-06202A-FSFC-016CV 06118118 14:10 6/2812018 71212018 18-06123 88E-01 1.12E+OO 1.12E+OO 1.93E+OO 18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/1812:30 6128/2018 71212018 18-06123 -5.81E-01 1.22E+OO 1.22E+OO 2.10E+OO 18-06123-06 TRG 81-06201AFSWC-027CV 06107118 13:30 6/2812018 71212018 18-06123 Nickel-63 ASTM 3500-Ni Modified -8.63E-01 1.26E+OO 1.26E+OO 2.19E+OO 18-06123-07 TRG 81-06201 A-FSWC-024CV 06107118 14:05 6128/2018 71212018 18-06123 Nickel-63 ASTM 3500-Ni Modified 2.14E+02 3.30E+OO 1.30E+01 1.80E+OO 18-06123-01 KNOWN 06128118 00:00 6/2812018 71612018 18-06123 Strontium-90 EIChroM SRW01 Modified 4.98E+01 2.79E-01 18-06123-01 SPIKE 06128/18 00:00 6/2812018 71612018 4.49E+01 1.79E+OO 1.57E+01 7.44E-01 18-06123-02 MBL BLANK 06128118 00:00 6/2812018 71612018 1.30E-01 4.40E-01 4.42E-01 7.76E-01 18-06123-03 DUP B 1-06202A-FS FC-016CV 06118118 14:10 6/2812018 71612018 18-06123 Strontium-90 EIChroM SRW01 Modified 2.64E-01 4.92E-01 5.01E-01 8.47E-01 18-06123-04 DO 81-06202A-FSFC-016CV 06118118 14:10 612812018 71612018 18-06123 Strontium-90 EIChroM SRW01 Modified 5.45E-01 3.79E-01 4.24E-01 6.09E-01 18-06123-05 TRG B 1-06202A-FSWC-035CV 06118/18 12:30 6128/2018 71612018 18-06123 Strontium-90 EIChroM SRW01 Modified 1.93E-02 5.27E-01 5.27E-01 9.40E-01 18-06123-06 TRG 81-06201AFSWC-027CV 06107118 13:30 6128/2018 71612018 18-06123 Strontium-90 EIChroM SRW01 Modified 1.0SE-01 4.75E-01 4.76E-01 8.37E-01 18-06123-07 TRG 81-06201A-FSWC-024CV 06107/18 14:05 6/2812018 71612018 18-06123 Strontium-90 EIChroM SRW01 Modified -3.19E-02 4.19E-01 4.19E-01 7.55E-01 18-06123-01 LCS KNOWN 06128118 00:00 6/2812018 612812018 18-06123 Cobalt-60 EPA 901.1 Modified 2.71E+02 1.06E+01 18-06123-01 LCS KNOWN 06128118 00:00 6/2812018 6/2812018 18-06123 Cesium-137 EPA901.1 Modified 1.69E+02 6.75E+OO pCilg 18-06123-01 LCS 06128118 00:00 6/2812018 6/2812018 18-06123 Cobalt-60 EPA 901.1 Modified 2.68E+02 1.58E+01 2.10E+01 1.85E+OO 06128118 00:00 6/2812018 6/2812018 18-06123 Cesium-137 EPA 901.1 Modified 1.93E+02 2.02E+01 2.25E+01 2.16E+OO pCilg CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;OUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect EBERLINE

[327]

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~ **-~-*'*'-'-~- 865/481-0683 FAX 865/483-4621

Printed: 7/19/2018 9:05 AM Page 2 of 7 Report To Work Order Details:

Patricia Giza 18-06123 Eberline Analytical Zion Solutions SDG:

Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd _Analysis Category: ENVIRONMENTAL

-- --+ ..

so Zion, IL 60099 Sample Matrix:

Lab Sample Client Sample Receipt Analysis Batch Report ID Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 18-06123-02 MBL 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 18-06123-02 MBL 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 4.72E-02 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Bismuth-214 1.09E-01 18-06123-02 MBL BLANK 06/28118 00:00 6/28/2018 6/28/2018 18-06123 Cobalt-60 EPA 901.1 Modified 9.34E-04 2.45E-02 2.45E-02 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Cesium-134 EPA 901.1 Modified 3.06E-03 2.21E-02 2.21E-02 u pCi/g

, ". ""'-------~-----

18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Cesium-137 EPA 901.1 Modified 3.10E-02 5.82E-02 18-06123-02 MBL BLANK 06128/18 00:00 6/28/2018 6/28/2018 18-06123 Europium-152 1.16E-01 1.16E-01 8.97E-02

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

18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Europium-154

'"'" ______ 5.74E-02 5.74E-02 4.39E-02 18-06123-02 MBL BLANK 6/28/2018 18-06123 Europium-155 EPA 901.1 Modified 1.17E-02 4.81E-02 4.81E-02 6.66E-02

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

18-06123-02 MBL BLANK 6/28/2018 18-06123 Holmium-166m EPA 901.1 Modified 9.64E-03 4.01E-02 4.01E-02 3.25E-02 18-06123-02 MBL BLANK 6/28/2018 18-06123 lodine-129 EPA 901.1 Modified -5.23E-04 6.89E-02 6.89E-02 9.03E-02 u pCi/g 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Potassium-40 EPA 901.1 Modified 2.65E-01 2.20E-01 2.21E-01 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Manganese-54 EPA 901.1 Modified 6.25E-03 1.36E-02 1.36E-02 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Niobium-94 2.60E-02 2.60E-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Lead-210 4.01E-01 4.02E-01 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Lead-212 EPA 901.1 Modified 3.88E-02 3.88E-02 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Lead-214 EPA 901.1 Modified 5.74E-02

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

18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Promethium-145 EPA 901.1 Modified 7.28E-02 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Radium-226 EPA901.1 Modified 3.61E-02 6.44E-02 6.44E-02 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Antimony-125 EPA 901.1 Modified -1.97E-02 5.93E-02 5.93E-02 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Thorium-234 EPA 901.1 Modified 2.24E-01 4.43E-01 4.44E-01 18-06123-02 MBL BLANK 06/28/18 00:00 6/28/2018 6/28/2018 18-06123 Thallium-208 EPA 901.1 Modified -5.42E-03 6.57E-02 6.57E-02 1.15E-01 u pCi/g

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

18-06123-02 MBL BLANK 06/28/18 00:00 6/2812018 6/28/2018 18-06123 Uranium-235 EPA 901.1 Modified -4.49E-02 3.13E-01 3.13E-01 1.85E-01 u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE P,NALYT:C,L.L 601 SCARBORO ROAD OAK RIDGE, CAL CORPORATION

[328]TN 37830 865/481-0683 FAX 865/483-4621

Printed: 7/19/2018 9:05 AM Page 3 of 7 Report To Work Order Details:

Patricia Giza 18-06123 Eberline Analytical Zion Solutions SOG:

Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd _ll_naty~is Catef!ory: ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report ID Type ID Date Date Date Analyte Method Result cu CSU MDA Qualifier ID Units 18-06123-03 DUP B1-06202A-FSFC-016CV 06118118 14:10 6128/2018 6/2812018 18-06123 Actinium-228 EPA 901.1 Modified 9.14E-01 3.27E-01 .31E-01 5.06E-01 18-06123-03 DUP 81-06202A-FSFC-016CV 06118/18 14:10 6/2812018 6/2812018 18-06123 Silver-108m EPA901.1 Modified 2.49E-02 9.35E-02 .35E-02 1.07E-01 u pCilg 18-06123-03 DUP 81-06202A-FSFC-016CV 06/18118 14:10 6/2812018 6/2812018 18-06123 Americium-241 EPA 901.1 Modified -4.60E-03 6.88E-02 18-06123-03 B 1-06202A-FSFC-016CV 06118/18 14:10 6/2812018 6/2812018 18-06123 Barium-133 EPA901.1 Modified O.OOE+OO 3.90E-02 w ""

18-06123-03 81-06202A-FSFC-016CV 06/18/1814:10 6/2812018 6/2812018 18-06123 Bismuth-214 EPA901.1 Modified 7.17E-01 2.45E-01 18-06123-03 DUP 81-06202A-FSFC-016CV 06118/1814:10 6/2812018 6/2812018 18-06123 Cobalt-60 EPA 901.1 Modified 1.79E-02 7.72E-02 18-06123-03 DUP 81-06202A-FSFC-016CV 06/18118 14:10 6128/2018 6/2812018 18-06123 Cesium-134 EPA 901.1 Modified 9.49E-04 4.02E-02 18-06123-03 DUP B 1-06202A-FSFC-016CV 06118/18 14:10 6/28/2018 6/28/2018 18-06123 Cesium-137 EPA 901.1 Modified 2.15E-01 1.26E-01 .27E-01 18-06123-03 DUP B 1-06202A-FSFC-016CV 06118/18 14:10 6128/2018 6/28/2018 18-06123 Europium-152 EPA 901.1 Modified 5.33E-02 1.34E-01 .34E-01 u

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

18-06123-03 DUP 81-06202A-FSFC-016CV Europium-154 -1.52E-01 2.64E-01 .64E-01

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

18-06123-03 B1-06202A-FSFC-016CV 06118118 14:10 6/2812018 6/2812018 18-06123 Europium-155 EPA 901.1 Modified 8.24E-02 1.45E-01 1.45E-01 2.45E-01 u pCilg

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

18-06123-03 81-06202A-FSFC-016CV 06/18118 14:10 6/2812018 6/2812018 18-06123 Holmium-166m EPA 901.1 Modified -4.16E-02 1.56E-01 1.56E-01 18-06123-03 B1-06202A-FSFC-016CV 06118118 14:10 6128/2018 6/2812018 18-06123 lodine-129 EPA 901.1 Modified -7.08E-02 1.23E-01 1.23E-01 18-06123-03 81-06202A-FSFC-016CV 06/18/1814:10 Potassium-40 EPA 901.1 Modified 6.29E+OO 1.83E+OO 1.85E+OO 2.12E+OO 18-06123-03 DUP 81-06202A-FSFC-016CV 06118/1814:10 6/2812018 6/2812018 18-06123 Manganese-54

' '"". . --~--~*--*" " ' ' ___ '

18-06123-03 DUP 81-06202A-FSFC-016CV 06/18118 14:10 6/2812018 6/2812018 18-06123 Niobium-94 18-06123-03 DUP B 1-06202A-FSFC-016CV 06118/18 14:10 6/28/2018 6/28/2018 18-06123 Lead-210 EPA 901.1 Modified 2.40E+OO 06118118 14:10 6/28/2018 6/28/2018 18-06123 Lead-212 4.60E-01 1.66E-01 DUP 81-06202A-FSFC-016CV 06118/18 14:10 6128/2018 6/2812018 18-06123 Lead-214 6.03E-01 2.03E-01 18-06123-03 DUP 81-06202A-FSFC-016CV 06/18118 14:10 6/2812018 6/2812018 18-06123 Promethium-145 EPA 901.1 Modified -4.29E-02 1.68E-01

-~----------- --------

18-06123-03 DUP 81-06202A-FSFC-016CV 06118/18 14:10 6/2812018 6/2812018 18-06123 Radium-226 EPA901.1 Modified 7.17E-01 2.45E-01 18-06123-03 DUP 81-06202A-FSFC-016CV 06118118 14:10 6/2812018 6/2812018 18-06123 Antimony-125 EPA 901.1 Modified -1.19E-01

- W""'"'"*-"'"'*---o*-""'

18-06123-03 DUP B 1-06202A-FSFC-016CV 06/18/1814:10 6/2812018 6/2812018 18-06123 Thorium-234 EPA 901.1 Modified 18-06123-03 B 1-06202A-FSFC-016CV 06/18/1814:10 6128/2018 6/2812018 18-06123 Thallium-208 EPA901.1 Modified 4.14E-01 2.50E-01 18-06123-03 B1-06202A-FSFC-016CV 06118/18 14:10 6/2812018 6/28/2018 18-06123 Uranium-235 EPA 901.1 Modified -3.10E-01 8.71E-01 CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma); MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect 601 SCARBORO ROAD OAK RIDGE, [329]TN 37830 865/481-0683 FAX 865/ 483-4621

Printed: 7/19/2018 9:05 AM Page 4 of 7 Report To: Work Order Details:

Patricia Giza 18-06123 Eberline Analytical Zion Solutions SDG.

Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category: ENVIRONMENTAL w,._.__,,_, __ *,--,u-~--,-v A Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report ID Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Actinium-228 EPA901.1 Modified 6.10E-01 2.58E-01 2.59E-01 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Silver-108m EPA901.1 Modified 1.55E-02 9.16E-02 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Americium-241 EPA901.1 Modified -2.57E-01 1.67E-01 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Barium-133 EPA901.1 Modified -2.50E-02 5.88E-02 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/1814:10 6/28/2018 6/28/2018 18-06123 Bismuth-214 EPA901.1 Modified 7.39E-01 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/1814:10 6/28/2018 6/28/2018 18-06123 Cobalt-60 EPA901.1 Modified 9.14E-03 18-06123-04 DO B 1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 -2.29E-02 4.78E-02 4.78E-02 1.40E-01 u 18-06123-04 DO B 1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Cesium-137 EPA 901.1 Modified 3.58E-01 1.21E-01 1.23E-01 1.48E-01 18-06123-04 DO B1-06202A-FSFC-016CV -6.97E-02 2.43E-01 2.43E-01 2.72E-01 u 18-06123-04 DO B 1-06202A-FSFC-016CV 6.99E-02 2.21E-01 2.21E-01 1.44E-01 u 18-06123-04 DO B1-06202A-FSFC-016CV 6/28/2018 EPA901.1 Modified 1.78E-02 1.50E-01 1.SOE-01 2.49E-01 u 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Holmium-166m EPA 901.1 Modified ""_" 3.81E-02

_______ 1.32E-01 1.32E-01 1.24E-01 u 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 lodine-129 EPA 901.1 Modified -5.22E-02 1.22E-01 1.22E-01 1.53E-01 u 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Potassium-40 EPA 901 .1 Modified 7.38E+OO 1.86E+OO 18-06123-04 DO B 1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Manganese-54 EPA 901.1 Modified 1.67E-02 7.88E-02 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/1814:10 6/28/2018 6/28/2018 18-06123 Niobium-94 EPA901.1 Modified -6.74E-03 7.30E-02 1.16E-01 u 18-06123-04 DO B 1-06202A-FSFC-016CV 06/18/1814:10 6/28/2018 6/28/2018 18-06123 Lead-210 EPA 901.1 Modified 2.23E+OO 1.24E+OO 1.25E+OO 2.22E+OO u 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/1814:10 6/28/2018 6/28/2018 18-06123 Lead-212 EPA 901.1 Modified 4.09E-01 1.53E-01 1.55E-01 5.73E-01 u 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Lead-214 EPA 901.1 Modified 8.34E-01 2.60E-01 2.64E-01 3.14E-01 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Promethium-145 EPA901.1 Modified 7.15E-02 1.54E-01 1.54E-01 2.14E-01 u 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Radium-226 EPA 901.1 Modified 7.39E-01 2.58E-01 2.60E-01 3.54E-01 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Antimony-125 EPA 901.1 Modified 1.12E-01 2.07E-01 2.07E-01 3.48E-01 u 18-06123-04 DO B 1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Thorium-234 EPA 901.1 Modified 2.27E+OO 1.98E+OO 1.99E+OO 18-06123-04 DO B1-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Thallium-208 EPA 901.1 Modified 5.49E-01 3.17E-01 3.19E-01 18-06123-04 DO 81-06202A-FSFC-016CV 06/18/18 14:10 6/28/2018 6/28/2018 18-06123 Uranium-235 EPA901.1 Modified 5.61E-01 9.30E-01 9.31E-01 6.59E-01 pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE /\ ,

1 v : 1 r- .,, i rsi'cA~***'-'~- 601 SCARBORO ROAD OAK RIDGE, [330]TN 37830 865/481-0683 FAX 865/ 483-4621

Printed: 7/19/2018 9:05 AM Page 5 of 7 Report To Work Order Details:

Patricia Giza 18-06123 Eberline Analytical Zion Solutions SDG.

Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Category. ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report ID Type ID Date Date Analyte Method Result cu CSU MDA Qualifier Date ID Units 18-06123-05 TRG B1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 u 18-06123-05 TRG B 1-06202A-FSWC-035CV u 18-06123-05 TRG B 1-06202A-FSWC-035CV 18-06123-05 TRG 81-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 18-06123 Barium-133 18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Bismuth-214 18-06123-05 TRG B 1-06202A-FSWC-035CV 06118/18 12:30 6/28/2018 6/2812018 18-06123 Cobalt-60 18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/1812:30 6/28/2018 6/28/2018 18-06123 Cesium-134 18-06123-05 TRG B1-06202A-FSWC-035CV 06/18/1812:30 6/28/2018 6/28/2018 18-06123 Cesium-137 18-06123-05 TRG 81-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Europium-152 EPA901.1 Modified w '""',__.,,,_-,_"

18-06123-05 TRG B1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Europium-154 EPA 901.1 Modified

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18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Europium-155 EPA 901.1 Modified 18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Holmium-166m EPA901.1 Modified u 18-06123-05 TRG B1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 lodine-129 EPA 901.1 Modified u 18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Potassium-40 EPA 901.1 Modified u 18-06123-05 TRG 81-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Manganese-54 EPA 901.1 Modified u

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18-06123-05 TRG B1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Niobium-94 EPA 901.1 Modified u 18-06123-05 TRG B1-06202A-FSWC-035CV u 18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Lead-212 EPA 901.1 Modified 18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/1812:30 6/28/2018 6/28/2018 18-06123 Lead-214 EPA 901.1 Modified 5.88E-01 u

-05 TRG B 1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Promethium-145 EPA 901.1 Modified 1.71E-01 u

-05 TRG B1-06202A-FSWC-035CV 06/18/18 6/28/2018 6/28/2018 18-06123 Radium-226 EPA 901.1 Modified 5.86E-01 18-06123-05 TRG B1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Antimony-125 EPA 901.1 Modified 5.36E-02 u 18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Thorium-234 EPA 901.1 Modified 1.88E+OO 18-06123-05 TRG B 1-06202A-FSWC-035CV 06/18/1812:30 6/28/2018 6/28/2018 18-06123 Thallium-208 EPA 901.1 Modified 2.43E-01 2.18E-01 18-06123-05 TRG 81-06202A-FSWC-035CV 06/18/18 12:30 6/28/2018 6/28/2018 18-06123 Uranium-235 EPA 901.1 Modified 6.23E-01 1.13E+OO CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE AN LYT,CA [331] 865/481-0683 FAX 865/483-4621

Printed: 711912018 9:05 AM Page 6 of 7 Report To Work Order Details:

Patricia Giza 18-06123 Eberline Analytical Zion Solutions SDG:

Purchase Order.- 677118 Final Report of Analysis 101 Shiloh Blvd Analysis Cateqory: ENVIRONMENTAL c,------f-ss,,

Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report ID Analyte Method Result cu CSU MDA Qualifier Type ID Date Date Date ID Units 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Actinium-228 EPA 901.1 Modified 4.49E-01 4.91E-01 4.92E-01 8.84E-01 u pCi/g 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Silver-108m EPA901.1 Modified 2.23E-02 1.14E-01 1.14E-01 1.13E-01 u pCi/g

~*A,_""."'" A- se 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/1813:30 6/28/2018 6/28/2018 18-06123 Americium-241 EPA 901.1 Modified 8.21E-02 18-06123-06 TRG B 1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Barium-133 EPA901.1 Modified 5.55E-02 1.13E-01 1.13E-01 1.81E-01 pCi/g 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Bismuth-214 EPA 901.1 Modified 1.08E+OO 3.08E-01 3.13E-01 3.50E-01 pCi/g 18-06123-06 TRG B 1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Cobalt-60 EPA901.1 Modified 4.12E-02 8.87E-02 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Cesium-134 EPA901.1 Modified -3.21E-02 6.38E-02 18-06123-06 TRG B 1-06201 AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Cesium-137 EPA 901.1 Modified 1.98E-01 1.41E-01 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Europium-152 EPA901.1 Modified -7.84E-02 4.64E-01 4.64E-01 18-06123-06 TRG B 1-06201 AFSWC-027CV 2.77E-02 2.49E-01 2.49E-01 18-06123-06 TRG 81-06201AFSWC-027CV 6/28/2018 Europium-155 EPA 901.1 Modified 2.61E-01 2.34E-01 2.34E-01 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Holmium-166m EPA901.1 Modified 2.92E-02 2.05E-01 2.05E-01 18-06123-06 TRG 81-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 lodine-129 EPA901.1 Modified -3.55E-02 2.70E-01 2.70E-01 18-06123-06 TRG 81-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Potassium-40 EPA901.1 Modified 7.81E+OO 2.25E+OO 2.29E+OO 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Manganese-54 EPA 901.1 Modified -2.73E-02 1.22E-01 1.22E-01 1.88E-01 18-06123-06 TRG B 1-06201 AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Niobium-94 EPA 901.1 Modified 7.19E-03 1.04E-01 1.04E-01 1.61E-01 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Lead-210 EPA 901.1 Modified 2.21E+OO 2.20E+OO .21E+OO 3.66E+OO u pCi/g

"""~-c--*

18-06123-06 TRG B1-06201AFSWC-027CV 06/07/1813:30 6/28/2018 6/28/2018 18-06123 Lead-212 EPA 901.1 Modified 3.76E-01 2.31E-01 2.32E-01 3.52E-01 u 18-06123-06 B1-06201AFSWC-027CV 06/07/1813:30 6/28/2018 6/28/2018 18-06123 Lead-214 EPA901.1 Modified 7.43E-01 2.53E-01 2.56E-01 4.47E-01 18-06123-06 B 1-06201 AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Promethium-145 EPA901.1 Modified 2.25E-01 3.00E-01 3.00E-01 4.71E-01 u 18-06123-06 TRG B 1-06201 AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Radium-226 EPA901.1 Modified 1.08E+OO 3.08E-01 3.13E-01 3.50E-01 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Antimony-125 EPA 901.1 Modified 4.44E-02 2.46E-01 2.46E-01 4.35E-01 u 18-06123-06 TRG B1-06201AFSWC-027CV 06/07/18 13:30 6/28/2018 6/28/2018 18-06123 Thorium-234 EPA 901.1 Modified 2.95E+OO 2.02E+OO

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18-06123-06 TRG 81-06201AFSWC-027CV 06/07/1813:30 6/28/2018 6/28/2018 18-06123 Thallium-208 EPA 901.1 Modified 7.84E-02 3.25E-01 18-06123-06 TRG 81-06201AFSWC-027CV 06/07 /18 13:30 6/28/2018 6/28/2018 18-06123 Uranium-235 EPA 901.1 Modified -6.67E-01 1.74E+OO 1.74E+OO u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank;DUP=Duplicate;TRG=Nonmal Sample;DO=Duplicate Original;U=Non-detect

( ~

EBERLINE 1\ ! A.? VT' Al

,-,Nr*.'-* .,C~~ 601 SCARBORO ROAD OAK RIDGE, [332]TN 37830 865/481-0683 FAX 865/ 483-4621

Printed: 7/19/2018 9:05 AM Page 7 of 7 Report To: Work Order Details Patricia Giza 18-06123 Eberline Analytical Zion Solutions SDG:

Purchase Order: 677118 Final Report of Analysis 101 Shiloh Blvd An~ly_sis Catef!CJf)L_ ENVIRONMENTAL Zion, IL 60099 Sample Matrix: so Lab Sample Client Sample Receipt Analysis Batch Report ID Type ID Date Date Date ID Analyte Method Result cu CSU MDA Qualifier Units 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Actinium-228 EPA901.1 Modified 7.61E-01 7.10E-01 7.11E-01 1.29E+OO u 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Silver-108m EPA 901.1 Modified m, ' " '""

9.83E-02

, _ . _ . _ , __ * - - , , , , - - , ~ ,

1.91E-01 1.91E-01 2.22E-01 u 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Americium-241 EPA901.1 Modified -2.00E-02 2.07E-01 2.07E-01 3.00E-01 u pCi/g 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Barium-133 EPA 901.1 Modified 4.55E-01 2.77E-01 2.78E-01 3.54E-01 u 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Bismuth-214 EPA 901.1 Modified 6.48E-01 4.69E-01 4.70E-01 8.01E-01 u 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Cobalt-60 EPA 901.1 Modified 5.00E-02 1.58E-01 1.58E-01 2.87E-01 u pCi/g 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Cesium-134 EPA901.1 Modified 7.29E-02 1.19E-01 1.19E-01 3.17E-01 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/1814:05 6/28/2018 18-06123 Cesium-137 EPA 901.1 Modified 5.59E-02 2.21E-01 2.21E-01 3.21E-01 18-06123-07 TRG 81-06201A-FSWC-024CV EPA 901.1 Modified -1.61E-01 4.84E-01 4.84E-01 4.20E-01 18-06123-07 TRG 81-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Europium-154 EPA901.1 Modified -5.41E-02 1.90E-01 1.90E-01 2.15E-01 18-06123-07 TRG 81-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Europium-155 EPA 901.1 Modified 1.73E-01 2.62E-01 2.62E-01 3.93E-01 18-06123-07 TRG 81-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Holmium-166m EPA 901.1 Modified -1.07E-01 3.30E-01 3.30E-01 1.81E-01 18-06123-07 TRG 81-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 lodine-129 EPA 901.1 Modified -1.03E-01 8.75E-02 8.76E-02 1.17E-01 18-06123-07 TRG 81-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Potassium-40 EPA901.1 Modified 5.40E+OO 3.15E+OO 3.16E+OO 4.70E+OO 18-06123-07 TRG 81-06201 A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Manganese-54 EPA 901.1 Modified 1.15E-01 1.62E-01 1.62E-01 2.98E-01

""'rn--***

18-06123-07 TRG ---*-*----- ____________________

81-06201A-FSWC-024CV, _______________ 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Niobium-94 EPA 901.1 Modified 1.43E-01 1.65E-01 1.65E-01 2.88E-01 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 1.61E+OO 1.61E+OO 2.54E+OO 18-06123-07 TRG 81-06201 A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 3.24E-01 3.24E-01 5.31E-01 18-06123-07 TRG B 1-06201 A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Lead-214 EPA 901.1 Modified 4.95E-01 4.97E-01 7.20E-01 18-06123-07 TRG B 1-06201A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Promethium-145 EPA 901.1 Modified 1.49E-01 1.49E-01 2.07E-01 18-06123-07 TRG B 1-06201 A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Radium-226 EPA 901.1 Modified 6.48E-01 4.69E-01 4.70E-01 8.01E-01 18-06123-07 TRG B 1-06201 A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 -1.04E-01 5.29E-01 5.29E-01 7.18E-01 18-06123-07 TRG B1-06201A-FSWC-024CV 06/07/1814:05 6/28/2018 6/28/2018 18-06123 Thorium-234 EPA 901.1 Modified 2.22E+OO 1.99E+OO 2.00E+OO 3.12E+OO 18-06123-07 TRG B 1-06201 A-FSWC-024CV 06/07/1814:05 6/28/2018 6/28/2018 18-06123 Thallium-208 EPA 901.1 Modified 5.20E-01 5.53E-01 5.54E-01 9.04E-01 18-06123-07 TRG 81-06201 A-FSWC-024CV 06/07/18 14:05 6/28/2018 6/28/2018 18-06123 Uranium-235 EPA 901.1 Modified -3.29E-01 1.78E+OO 1.78E+OO 9.06E-01 u pCi/g CU=Counting Uncertainty;CSU=Combined Standard Uncertainty (1-sigma);MDA=Minimal Detected Activity;LCS=Laboratory Control Sample;MBL=Blank; DUP=Duplicate;TRG=Normal Sample;DO=Duplicate Original;U=Non-detect

( _@

EBERLINE

,A, NAL YT! CA

[333] 865/481-0683 FAX 865/483-4621

~

ZS-WM-131 Revision 0 ZIONSOLUTIONSiu: 18-06123 Information Use Attachment 1 - Chain-of-Custody Form REC'D JUN 2 8 2018 Sample ID Sample Matrix Sample Sample Container Sample Date Sample Time Analysis Type Preservative Remarks Log Type Vol Unit Type Qty 136.46g B1-06202A-FSFC-Ol6CV NIA Concrete Concrete 57.94 cm3 Puck ! 6118/2018 1410 5ROC-H3 None 0.0-0.5" 141.92g G B1-06202A-FSWC-035CV NIA Concrete Concrete 57.94 cm3 Puck 1 6/18/2018 1230 5 ROC-H3 None 0.0-0.5" 113.80g B1-06201AFSWC-027CV NIA Concrete Concrete 57.94 cm3 Puck 1 6/0712018 1330 5ROC-H3 None 0.0-0.5" lQ 127.63g

~

v B1-06201A-FSWC-024CV NIA Concrete Concrete 57.94 cm3 Puck ! 6107/2018 1405 5 ROC-H3 None 0.0-0.5" Laboratmy: Date Submitted To Lab: Ship Container No.: Cooler Temperature:

r~'fi?xeGff/.tSS Eberline Labs NIA NIA 8tl5 '!51? 61!0 Relinquished by: Date Time: Received by: Date: (mmldd/yyyy): Time:

Jack Mucia 0612712018

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~; vhci trt f ft,~ f O(u/)7/ ZDJ 'l !3'./0 Relinquished by: Date Time: { {,30 Received by: Date: (mmldd/yyyy): Time:

(mmlddlyyyy):

~tr hcu-J ~- fliicko1 orc/11/1.on /jf fJ'o,z!IW r f<J [i.. ti-J>rf 9f!J 06/J.7 }J-Clrt 1630 Relinquished by: Date Time: Received by: V 6~lik-.f) Time:

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Relinquished by:

c;~rJ!l!rR Date o~:~ ~Tu~ ~\vh'ot/

Time: Received by: _) I Da;; ; ; ; ; ~ {~

Date: (mmldd/yyyy):

~30 Time:

(mmldd/yyyy):

Comments ANALYSIS 5 ROC HTD-H 3 PRIORITY 7 day turnaround PO# 677118

[334]

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